Codes and Standards and Other Guidance Cited in ...

I NUREG/CR-5973PNL-8462Rev. 3

MMMOMMMMMMEM

Codes and Standards and OtherGuidance Cited in RegulatoryDocuments

Prepared by3. R. Nickolaus, K. L. Bohlander .4

Pacific Northwest National Laboratory

Irepared forJ.S. Nuclear Regulatory Commission

AVAILABIUTY NOTICE

AvailAbility of Reference Materials Cited in NRC Publications

Most documents cited In NRC publicatlons wit be available from one of the following sources:1. The NRC Public Document Room, 2120 L Street, NW., Lower Level, Washington. DC 20555-0001

2. The Superintendent of Documents, U.S. Govermnent Printing Office, P. 0. Box 37082, Washington, DC20402-9328

3. The National Technical Information Service. Springfield, VA 22161-0002

Although the listing that follows represents the majority of documents cited in NRC publications, it is not in-tended to be exhaustive.

Referenced documents available for inspection and copying for a fee from the NRC Public Document Roominclude NRC correspondence and internal NRC memoranda; NRC bulletins, circulars, information notices. in-spection and investigation notices; licensee event reports: vendor reports and correspondence: Commissionpapers; and applicant and licensee documents and correspondence.

The following documents In the NUREG series are available for purchase from the Government Printing Office:formal NRC staff and contractor reports. NRC-sponsored conference proceedings, international agreementreports, grantee reports, and NRC booklets and brochures. Also available are regulatory guides, NRC regula-tions In the Code of Federal Regulations, and Nuclear Regulatory Commission Issuances.

Documents available from the National Technical Information Service Include NUREG-series reports and tech-nical reports prepared by other Federal agencies and reports prepared by the Atomic Energy Commission,forerunner agency to the Nuclear Regulatory Commission.

Documents available from public and special technical libraries include all open literature items, such as books,journal articles, and transactions. Federal Register notices. Federal and State legislation, and congressionalreports can usually be obtained from these libraries.

Documents such as theses, dissertations. foreign reports and translations, and non-NRC conference pro-ceedings are available for purchase from the organization sponsoring the publication cited.

Single copies of NRC draft reports are available free. to the extent of supply, upon written request to the Officeof Administration, Distribution and Mail Services Section. U.S. Nuclear Regulatory Commission, Washington,DC 20555-0001.

Copies of industry codes and standards used in a substantive manner in the NRC regulatory process are main-tained at the NRC Library. Two White Flint North. 11545 Rockville Pike, Rockville. MD 20852-2738. for use bythe public. Codes and standards are usually copyrighted and may be purchased from the originating organiza-tion or, If they are American National Standards. from the American National Standards Institute, 1430 Broad-way, New York, NY 1001 6-3308.

DISCLAIMER NOTICE

This report was prepared as an account of work sponsored by an agency of the United States Government.Neitherthe UnitedStates Government noranyagencythereof, noranyof theiremployees, makes anywarranty,expressed or implied, or assumes any legal liability or responsibility for any third party's use, or the results ofsuch use, of any information, apparatus, product, or process disclosed in this report, or represents that its useby such third party would not infringe privately owned rights.

NUREG/CR-5973PNL-8462Rev. 3

Codes and Standards and OtherGuidance Cited in RegulatoryDocuments

Manuscript Completed: July 1996Date Published: August 1996

Prepared byJ. R. Nickolaus, K. L. Bohlander

Pacific Northwest National LaboratoryBattelle BoulevardRichland, WA 99352

Prepared forDivision of Inspection and Support ProgramsOffice of Nuclear Reactor RegulationU.S. Nuclear Regulatory CommissionWashington, DC 20555-0001NRC Job Code J2328

Abstract

As part of the U.S. Nuclear Regulatory Commission (NRC) Standard Review Plan Update and DevelopmentProgram (SRP-UDP), Pacific Northwest National Laboratory developed a listing of industry consensus codesand standards and other government and industry guidance referred to in regulatory documents. The SRP-UDPhas been completed and the SRP-Maintenance Program (SRP-MP) is now maintaining this listing. Besidesupdating previous information, Revision 3 adds approximately 80 citations. This listing identifies the version ofthe code or standard cited in the regulatory document, the regulatory document, and the current version of thecode or standard. It also provides a summary characterization of the nature of the citation. This listing was

developed from electronic searches of the Code of Federal Regulations and the NRC's Bulletins, InformationNotices, Circulars, Enforcement Manual, Generic Letters, Inspection Manual, Policy Statements, RegulatoryGuides, Standard Technical Specifications and the Standard Review Plan (NUREG-0800).

. . NUREG/CR-5973 Rev. 3

Contents

Section

Abstract ..........................

Summary .........................

Acronyms and Abbreviations .............

Definitions ........................

Part A - Industry Consensus Codes and Standards

Part B - Other Guidance ............. ...

A

A Summation of Code and Standard Citation

B Summation of Other Government and Indt

. . . . . . . . . . . . . . . . . . . . . . . . .

. . . . . . . . . . . . . . . . . . . . . . . . .

. . . . . . . . . . . . . . . . . . . . . . . . .

. . . . . . . . . . . . . . . . . . . . . . . . .

. . . . . . . . . . . . . . . . . . . . . . . . .

. . . . . . . . . . . . . . . . . . . . . . . . .

Page

. iii

. vii

ix

. . xi

.4.

463

Appendices

s in Regulatory Documents ..... ............ A-1

istry Guidance Citations in Regulatory Documents . . B-i

v NUREG/CR-5973 Rev. 3

Summary

For a study sponsored by the U.S. Nuclear Regulatory Commission (NRC), Pacific Northwest National

Laboratory' developed a listing of industry consensus codes and standards and other government and industry

guidance referred to in regulatory documents, identified the most current version, and developed a summary

characterization of the reference. This listing was developed from electronic searches of the Code of Federal

Regulations and the NRC's Bulletins, Information Notices, Circulars, Enforcement Manual, Generic Letters,

Inspection Manual, Policy Statements, Regulatory Guides, Standard Technical Specifications, and the Standard

Review Plan (NUREG-0800). Therefore, this is not an exhaustive listing of all code and standard citations in

all NRC documents.

This work was initially conducted for the Standard Review Plan Update and Development Program (SRP-UDP)

under JCN L-2013 (formerly FIN L-2013) and is continued for the SRP-Maintenance Program (SRP-MP) under

JCN J-2328. The users of this listing may find errors or omissions. They should refer these items to Armand

Masciantonio, the NRC Lead Engineer for the SRP-UDP. He may be contacted by telephone at (301) 415-1290

or by mail at the following address:

U.S. Nuclear Regulatory CommissionOffice of Nuclear Reactor RegulationMailstop 0-12 E4Washington, D.C. 20555-0001

Besides updating previous information, Revision 3 adds approximately 80 citations. This listing comprises

nearly five thousand two hundred records divided into two parts. Part A lists industry consensus codes and

standards cited in NRC regulatory documents. Part B lists other government and industry guidance and

requirements found in NRC regulatory documents that are not codes or standards that provide information.

The listings are organized alphabetically by code group and include such information as a unique record

number, code group and code or standard number, title, date of referenced code or standard edition, and the

latest standard version and version date. The listings also include a comment section and the NRC document in

which the citation was found and its date. A column is also provided that indicates the degree to which the

NRC document finds the specific code or standard acceptable for the specific application.

Pacific Northwest National Laboratory is operated for the U.S. Department of Energy by Battelle Memorial Institute.

vii NUREG/CR-5973 Rev. 3

Acronyms and Abbreviations

ACI American Concrete InstituteACS American Chemical SocietyAEC Atomic Energy CommissionAICHE American Institute of Chemical EngineersAISC American Institute of Steel ConstructionANS American Nuclear SocietyANSI American National Standards InstituteAPHA American Public Health AssociationAPI American Petroleum InstituteASA Acoustical Society of AmericaASCE American Society of Civil EngineersASHRAE American Society of Heating, Refrigerating and Air-Conditioning EngineersASME American Society of Mechanical EngineersASNT American Society for Nondestructive TestingASQC American Society for Quality ControlATC Applied Technology CouncilASTM American Society for Testing and MaterialsAWS American Welding SocietyAWWA American Water Works Associationbul NRC Bulletincfr Code of Federal Regulationscir NRC CircularCMAA Crane Manufacturers Association of AmericaDEMA Diesel Engine Manufacturers AssociationDOE US Department of Energydrg Draft Regulatory GuideDOT US Department of TransportationEPA US Environmental Protection AgencyERDA US Energy Research and Development AdministrationFFPR Federal SpecificationFWPCA Federal Water Pollution Control ActFM Factory Mutualglt NRC Generic LetterGS of A Geological Society of AmericaHEI Heat Exchanger InstituteHHS US Department of Health and Human ServicesHPS Health Physics SocietyHPSSC Health Physics Society Standards CommitteeICBO International Conference of Building OfficialsICEA Insulated Cable Engineers AssociationICRP International Commission on Radiological ProtectionICRU International Commission on Radiological Units and MeasurementsIEC International Electrotechnical CommissionIEEE Institute of Electrical and Electronics Engineers

ix NUREG/CR-5973 Rev. 3

Acronyms and Abbreviations (Cont'd)

inm-toc NRC Inspection Manual Table of Contentsimn..... NRC Inspection Manual with Chapter referenceISA Instrument Society of AmericaISO International Standards OrganizationMIL Military StandardMSS Manufacturers Standards SocietyNACE National Association of Corrosion EngineersNBS National Bureau of StandardsNCMA National Concrete and Masonry AssociationNCRP National Council on Radiation ProtectionNEA Nuclear Energy AgencyNEI Nuclear Energy InstituteNEMA National Electrical Manufacturers AssociationNETA National Electrical Testing AssociationNIOSH National Institute for Occupational Health and SafetyNIST National Institute of Standards and TechnologyNFPA National Fire Protection AssociationNOAA National Oceanic and Atmospheric Administrationnot NRC Information Noticenureg A formal NRC Staff PublicationNRA National Rifle AssociationNSF National Science FoundationN/S in the "Standard Version" column shows they did not specify the version date in the citation.OSHA Occupational Safety and Health Administrationpol NRC Policy StatementR in the "Current Version Date" column shows the date the issuing body reaffirmed the Code or

Standardreg NRC Regulatory Guidesrp Standard Review Plan (NUREG-0800)sts Standard Technical Specificationssts4-ge... Standard Technical Specifications for the General Electric Model 4 with paragraph reference

sts6-ge... Standard Technical Specifications for the General Electric Model 6 with paragraph reference

stsb&w... Standard Technical Specifications for Babcock & Wilcox with paragraph referencestsce... Standard Technical Specifications for Combustion Engineering with paragraph reference

stswst... Standard Technical Specifications for Westinghouse Electric with paragraph reference

UL Underwriters LaboratoryUSGS United States Geological Survey

NUREGICR-5973 Rev. 3 x

Definitions

Disclaimer: These definitions were developed for, and only pertain to, the Standard Review Plan Update and

Development Program that the Pacific Northwest National Laboratory is conducting for the NRC.

The following acceptability codes are used in the 'Acceptability' column. These acceptability codes have been

assigned to each standard listing based on review of the associated regulatory citations. The assignment of these

acceptability codes often requires some level of judgement. These codes are provided to give the user a general

idea of the acceptability of the standard to the NRC and are not intended to imply any level of formal

endorsement. The actual regulatory citation of the standard should be reviewed for applicability and

acceptability prior to any application of the standard.

A - denotes that the document is acceptable to the NRC. The regulatory document does not state

the need for any limitations, exceptions, or modifications to the provisions of the code or

standard.

P - denotes partial acceptance; this means that the regulatory document showed acceptability of the

code or standard but also stated the need for limitations, exceptions, or modifications to the

provisions of the code or standard. If the regulatory document indicates acceptability of only

part of the code or standard (e.g., Section 18.18 of ACI 318-77), the acceptability code is "P"'

instead of "A.."

R - denotes that the citation is used as a reference for definition purposes or to provide background

information. The regulatory document does not provide an indication of acceptability orunacceptability of the code or standard.

N - denotes that the regulatory document indicated that the code or standard was unacceptable for a

given application and has no indication of acceptability of any portion of the code or standard.

Standard: A set of rules that is based upon proven practices that are mutually agreed upon through an

industry-consensus process.

Industry-consensus process: The process by which the participating members of a standard writing group,

who represent the various interests of that industry (e.g., product manufacturers, material manufacturers,

product users, utilities, insurers, designers, constructors, consultants, and regulators, whether local, regional, or

national), develop a standard. An industry-consensus process does not approve, recommend, or endorse any

specific or proprietary design or manufacturing process. The standards writing group members meet regularly

on a formal basis to consider revisions of the current requirements, requests for interpretation of current

requirements, and new requirements as dictated by technological development. The industry-consensus process

satisfies the separate and distinct needs, requirements, and interest of its participants through a process of

arriving at mutually agreed upon rules.

Code: A standard that a regulatory organization or a governing body mandates, for example, a State.

xi NUREG/CR-5973 Rev. 3

Part A

Industry Consensus Codes and Standards

1 NUREG/CR-5973 Rev. 3

Codes and Standards and Other Guidance Cited in Regulatory Documents


RecodSord rd-De cet atest, Stendad Lates Vesion

co 'Stanhdard Version Til cmn Dt bliy Cmmns 'erso NOte

0001 ACI ACI NiS American Concrete Institute Code gt79 79 R ACt 34 0359 _ _ _ _ _

0002 ACI ACI N/S Building Code Requirements for glt80-032 1980 r Proposed ACl 530 1992

Masonry Structures Standard

0003 ACI ACI 201 N/S Guide for Making a Condition reg1.127.rO1 1978 P .. R 1992Survey of Concrete in Service

0004 ACI ACI 201 1968 Guide for Making a Condition regl.35.rO3 1990 R Cited for ACI 201.1 R 1992

Survey of Concrete in Service definitions

0005 ACI ACI 201 N/S Guide for Making a Condition regl.90.rOl 1977 R ACI 201.1R 1992

Committee Survey of Concrete in Service

0006 ACI ACI 212 N/S Chemical Admixtures for Concrete reg1.107.rOl 1977 R A-I 212.3R 1991

Committee _________1983_______212_1 __1981_R86

0007 ACI ACI 212.1 N/S Admixtures for Concrete inm46051 1983 R ACI 212.1R 1981 R86

0008 ACI ACI 212.2 N/S Guide for Use of Admixtures in inm46051 1983 R ACI 212.2R 1981 R86

Concrete

0009 ACI ACI 214 N/S Recommended Practice for inm46051 1983 R ACI 214 1977 R89

Evaluation of Strength TestResults of Concrete

0010 ACI ACI 214 N/S Recommended Practice for inm46055 1983 R ACI 214 1977 889

Evaluation of Strength TestResults of Concrete .

0011 ACI ACI 221 N/S Guide for Use of Normal Weight inm46051 1983 R ACI 221 R 1989

Aggregates in Concrete

0012 ACI ACI 301 N/S Specifications for Structural inm46051 1983 R ACI 301 1989

Concrete for Buildings --------

0013 ACi ACi 301 N/S Specifications for Structural inm46053 1983 R ACI 301 1989

Concrete for Buildings

0014 ACI ACI 301 1972 Specifications for Structural regl.107.rOt 1977 R ACI 301 1989

Committee Concrete for Buildings

0015 ACI ACi 304 N/S Guide for Measuring, Mixing, inm46051 1983 R ACI 304R 1989

Transporting, and PlacingConcrete

C

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4.

Codes and Standards and Other Guidance Cited in Regulatory DocumentsPart A - Industry Consensus Codes and Standards

Recorad Stotid:d Doe. :Accdept-. I Laitest Standard Lateast Ver.lo

No. : 1:Code Standard Verslon Title Docun et Date l y C m t V;i Da;t

0016 ACI ACI 304.2 N/S Recommended Practice for inm46051 1983 R ACI 304 1991Measuring, Mixing, Transportingand Placing Concrete

0017 ACI ACI 305 N/S Hot Weather Concreting inm46051 1983 R _ ACI 305R 1991

0018 ACI ACI 306 N/S Cold Weather Concreting inm46051 1983 R ACI 306R 1988

0019 ACl ACI 308 N/S Standard Practice for Curing inm46051 1983 R ACI 308 1992Concrete

0020 ACI ACI 308 1971 Standard Practice for Curing reg1.136.rO2 1981 A ACI 308 1992Concrete

0021 ACI ACI 309 NIS Guide for Consolidation of inm46051 1983 R ACI 309R 1987Concrete

0022 ACI ACI 309 1972 Guide for Consolidation of regl.94.rOl 1976 R ACI 309R 1987Concrete

0023 ACI ACI 311 NIS Guide for Concrete Inspection inm46051 1983 R ACI 311.4R 1995

0024 ACI ACI 311.1 N/S ACI Manual of Concrete inm46051 1983 R ACI 311.1 R 1992Inspection

0025 ACI ACI 311.2 N/S Guide for Concrete Inspection inm46051 1983 R ACI 311.4R 1995

0026 ACI ACI 311.3 N/S Guide for Concrete Inspection inm46051 1983 R ACI 311.4R 1995

0027 ACI ACI 315 N/S Details and Detailing of Concrete inm46051 1983 R ACI 315 1992Reinforcement

0028 ACI ACI 318 1989 Building Code Requirements for 10cfr36 1994 R ACI 318 1995Structural Concrete

0029 ACI ACI 318 1989 Building Code Requirements for drgOO03.rOO 1994 R ACI 318 1995Structural Concrete

0030 ACI ACI 318 1971 Building Code Requirements for gIt79-005 1979 R ACI318M 1995Structural Plain Concrete

0031 ACI ACI 318 N/S Building Code Requirements for inm46051 1983 R ACI 31 8M 1995Structural Plain Concrete

0032 ACI ACI 318 N/S Building Code Requirements for inm46053 1983 R ACI 318M 1995Structural Plain Concrete



R ecord Cotde -.. A cpt L S d te Verion

-NoCde Sadr VrsoTil Documen Daa aiiy Cmet eson D:~ ate


0035 ACI ACI 318 1977 Building Code Requirements for regl.36 rO2 1981 P ACI 318M 1995Structural Plain Concrete

0036 ACI ACI 318 1971 Building Code Requirements for regl.142.rOl 1981 _ ACI 318M 1995Structural Plain Concrete

0037 ACI ACI 318 1977 Building Code Requirements for regl.142.rOl 1981 P ACI 318M 1995Structural Plain Concrete

0038 ACI ACI 318 1977 Building Code Requirements for regl.143.rOl 1979 A ACI 318M 1995

Structural Plain Concrete

0039 ACI ACI 318 N/S Building Code Requirements for reg1.35.1.rOO 1990 R ACI 31 8M 1995Structural Plain Concrete

0040 ACI ACi 318 N/S Building Code Requirements for srp3.8.3 1981 P ACI 318M 1995Structural Plain Concrete

0041 ACI ACI 318 N/S Building Code Requirements for srp3.8.4 1981 P ACI 318M 1995Structural Plain Concrete

0042 ACI ACI 347 NIS Formwork for Concrete inm46051 1983 R A-I 347 1989

0043 ACI ACI 349 1976 Code Requirements for Nuclear bui79-002.rO2 1979 N Use of reduced ACI 349 1990Safety Related Concrete factors notStructures accepted

0044 ACI ACI 349 N/S Code Requirements for Nuclear git79-005 1979 P ACI 349 1990Safety Related ConcreteStructures

0045 ACI ACI 349 N/S Code Requirements for Nuclear glt87-002.sOl 1992 N anchorage ACI 349 1990Safety Related Concrete outliers is notStructures acceptable to

the staff.

0046 ACI ACI 349 N/S Code Requirements for Nuclear inm46051 1983 R ACI 349 1990Safety Related ConcreteStructures

0047 ACI ACI 349 N/S Code Requirements for Nuclear inm47051 1983 R ACI 349 1990Safety Related ConcreteStructures

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Record D A SSta da D c Accept- s n a aes Vet lon

N&o, Code Standard , Version T itle ocument Date ability Comrments Version Dte0048 ACI ACI 349 N/S Code Requirements for Nuclear inm48051 1986 R ACI 349 1990

Safety Related ConcreteStructures

0049 ACI ACI 349 NIS Code Requirements for Nuclear inm48053 1986 R ACI 349 1990

Safety Related ConcreteStructures

0050 ACI ACI 349 N/S Code Requirements for Nuclear reg1.70.rO3 1978 P ACI 349 1990Safety Related ConcreteStructures

0051 ACI ACI 349 1976 Code Requirements for Nuclear regl.136.rO2 1981 P ACI 349 1990Safety Related ConcreteStructures

0052 ACI ACI 349 1976 Code Requirements for Nuclear regl.142.rOl 1981 P ACI 349 1990Safety Related ConcreteStructures

0053 ACI ACl 349 1979 Code Requirements for Nuclear reg1.142.rO1 1981 P ACI 349 1990Safety Related ConcreteStructures

0054 ACI ACI 349 1976 Code Requirements for Nuclear srp3.8.3 1981 P ACI 349 1990Safety Related ConcreteStructures

0055 ACI ACI 349 N/S Code Requirements for Nuclear srp3.8.4 1981 P ACI 349 1990Safety Related ConcreteStructures

0056 ACI ACI 349 N/S Code Requirements for Nuclear srp3.8.5 1981 P A-I 349 1990Safety Related ConcreteStructures

0057 ACI ACI 359 N/S Code for Concrete Reactor git79-005 1979 R ASME Section 1995

Vessels and Containments III, Division 2

0058 ACI ACI 359 N/S Code for Concrete Reactor inm46051 1983 R ASME Section 1995Vessels and Containments Ill, Division 2

0059 ACI ACI 359 N/S Code for Concrete Reactor inm47051 1983 R ASME Section 1995Vessels and Containments Ill, Division 2


Rco Sta.dard Doc Accept- Latest St a.ard Latest Version

No Code.: Standard Version Title :ocument Date amet e n Dt

0060 ACI Aci 359 N/S Code for Concrete Reactor inm47053 1983 R ASME Section 1995

Vessels and Containments IlIl, Division 2

0061 ACI ACi 359 NIS Code for Concrete Reactor inm48051 1986 R. ASME Section 1995

Vessels and Containments Ill, Division 2

0062 ACi ACI 359 N/S Code for Concrete Reactor inm48053 1986 R ASME Section 1995


0063 AC! ACi 359 N/S Code for Concrete Reactor inm63050 1983 R ASME Section 1995


0064 ACI ACi 359 1980 Code for Concrete Reactor regl.136.r02 1981 P ASME Section 1995


0065 ACI ACI 359 1980 Code for Concrete Reactor regl.142.rOl 1981 P ASME Section 1995


0066 ACI ACI 359 1986 Code for Concrete Reactor regl.35.1.rOO 1990 P ASME Section 1995

Vessels and Containments i!!, Division 2

0067 ACI AC! 359 N/S Code for Concrete Reactor srp3.9.3 1981 P ASME Section 1995

Vessels and Containments III1 Division 2

0068 ACI ACI 359 1975 Code for Concrete Reactor reg1.107.r01 1977 P ASME Section 1995

Committee Vessels and Containments Il, Division 2

0069 AC ACI 359 1980 Code for Concrete Reactor regl.142.rOl 1981 R ASME Section 1995

Committee Vessels and Containments lli, Division 2

0070 ACI ACI 359 1975 Code for Concrete Reactor regl.90.rOl 1977 P ASME Section 1995

Committee Vessels and Containments III, Division 2

0071 ACI AC! 503 N/S Use of Epoxy Compounds with inm46051 1983 ACi 503R 1993

_ _ Concrete _I_

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Record Standard De Standard Latest Ve..ion

0072 ACI ACI 503.4 NIS Standard Specification for inm46051 1983 R ACI 503.4 1992

Repairing Concrete with EpoxyMortars

0073 AC! ACI 504 N/S Guide to Sealing Joints in inm46051 1983 R ACI 504R 1990

Concrete Structures _ _ _ _ _ _ _ __ _ _ _

0074 ACI ACI 506 N/S Guide to Shotcrete inm46051 1983 R ACI 506R 1990

0075 ACI ACI 506.2 N/S Specifications for Materials, inm46051 1983 R ACI 506.2 1990

Proportioning, and Application ofShotcrete

0076 ACI ACI 531 1979 Building Code Requirements for bul80-01 1 1980 R Used as a ACi 530 1992

Masonry Structures definitionreference

0077 ACI ACI 531 N/S Building Code Requirements for inm46051 1983 R ACI 530 1992Masonry Structures

0078 AC! AC 531 1979 Building Code Requirements for inm46061 1986 R ACI 530 1992

Masonry Structures

0079 ACI ACI 531 1979 Building Code Requirements for srp3.8.4 1981 P ACI 530 1992Masonry Structures

0080 AC! AC! 5318 1979 Building Code Requirements for inm46061 1986 R AC! 530 1992

Masonry Structures Commentary .

0081 ACI ACI SP-2 N/S ACI Manual of Concrete inm46053 1983 R ACI 311.1 R 1992

Inspection

0082 AISC AISC N/S Design, Fabrication, and Erection glt78-01 1 1978 A AISC N690 1984

of Steel Safety Related Structuresfor Nuclear Facilities,Specifications for the

0083 AiSC AISC N/S Design, Fabrication, and Erection git79-004 1979 P AISC N690 1984


0084 AISC AISC N/S Manual of Steel Construction git97-002.sOl 1992 P AISC M016 1989

_ _ Allowable Stress Design . _


Record SnddDo. Acp-L test standard Latet Viersiono. Cd. Stnad Vrsion * *> hs Documenht..~ Date..abiiy . omns Vrin Date

-t~ fr 0 fi -;.: :: -: i- iiiyif i~i~E 7:~ii ;fX::00. .;-i tSifi i.i Om .r Oftit:it-:t0 .i:

0085 AISC AISC N/S Design, Fabrication, and Erection inm48051 1986 R AISC N690 1984


0086 AISC AiSC N/S Design, Fabrication, and Erection inm48053 1986 R AISC N690 1984

of Steel Safety Related Structuresfor Nuclear Facilities,Sprcifications for the

0087 AlSC AISC N/S Design, Fabrication, and Erection regl.124.rO1 1978 R AISC N690 1984


0088 AISC AISC 1969 Design, Fabrication, and Erection regl.143.rO1 1979 P AISC N690 1984


0089 AISC AISC N/S Design, Fabrication, and Erection regl.70.r03 1978 P AISC N690 1984


0090 AISC AISC N/S Design, Fabrication, and Erection srp3.8.3 1981 P AiSC N690 1984


0091 AISC AISC N/S Design, Fabrication, and Erection srp3.8.4 1981 P AISC N690 1984


z

(1)

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-ecor Standar Do,. AcceptL Sta dard Latest Ver';on

No. Code Standard Version: i _tit_ Document Dote .bility Comments Versin Date0092 AISC AISC N/S Design, Fabrication, and Erection srp3.8.5 1981 P AISC N690 1984


0093 AISC AISC N/S Manual of Steel Construction glt89-0 0 9 1989 P AISC M016 1989

Allowable Stress Design

0094 AISC AISC NIS Design, Fabrication, and Erection glt87-002.sO1 1992 R AISC N690 1984

Specification of Steel Safety Related Structuresfor Nuclear Facilities,Specifications for the

0095 ANS ANS 2.2 1978 Earthquake Instrumentation drgms140-5.rOO 1981 P ANS 2.2 1988Criteria for Nuclear Power Plants

0096 ANS ANS 2.3 1983 Estimating Tornado and Extreme nuregO933, 1992 R ANS 2.3 1983Wind Characteristics at Nuclear 3.156Power Sites

0097 ANS ANS 2.5 1984 Determining Meteorological drges926-4.rOO 1986 P Proposed ANS 2.5 1984 R90

Information at Nuclear Power regl.23.rOlSites

0098 ANS ANS 2.5 NiS Determining Meteorological inmi245 App. B 1991 R ANS 2.5 1984 R90

Information at Nuclear PowerSites

0099 ANS ANS 2.5 1984 Determining Meteorological inm92207 1993 R ANS 2.5 1984 R90Information at Nuclear PowerSites

0100 ANS ANS 2.5 1984 Determining Meteorological reg3.63.rOO 1988 R ANS 2.5 1984 R90Information at Nuclear PowerSites

0101 ANS ANS 2.8 1981 Determining Design Basis Flooding reg3.48.rOl 1989 P Implied ANS 2.8 1992

at Power Reactor Sites endorsement.Procedures canbe used.


Recor Stadad Doe. cct- Ltet 6.Standr L V iNo. Code Standard -Version .11 I Title i :; Document Date bt C m V ion ate

0102 ANS ANS 2.8 1981 Determining Design Basis Flooding reg3.44.rO2 1989 P Implied ANS 2.8 1992at Power Reactor Sites endorsement.

Guidanceshould befollowed.

0103 ANS ANS 2.8 1981 Determining Design Basis Flooding reg4.17.rOl 1987 R Referred to as ANS 2.8 1992at Power Reactor Sites ANSI/ANS 2.8

N170

0104 ANS ANS 2.19 1981 Guidelines for Establishing Site- reg3.49.rOO 1981 R ANS 2.19 1981 R90Related Parameters for SiteSelection and Design of anIndependent Spent Fuel StorageInstallation (Water-Pool Type)

0105 ANS ANS 2.19 1981 Guidelines for Establishing Site- reg3.60.rOO 1987 R ANS 2.19 1981 R90Related Parameters for SiteSelection and Design of anIndependent Spent Fuel StorageInstallation (Water-Pool Type)

0106 ANS ANS 3.1 1978 Selection, Qualification, and cir80-21 1980 P Must meet ANS 3.1 1993Training of Personnel for Nuclear training andPower Plants qualification

requirements

0107 ANS ANS 3.1 N/S Selection, Qualification and drg1O43.r00 1995 R ANS 3.1 1993Training of Personnel for NuclearPower Plants

0108 ANS ANS 3.1 N/S Selection, Qualification and glt83-012.A 1983 R Must meet ANS 3.1 1993Training of Personnel for Nuclear training andPower Plants qualification

requirements

0109 ANS ANS 3.1 N/S 5election, Qualification and inml245 App. B 1991 R ANS 3.1 1993Training of Personnel for NuclearPower Plants

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4.,



.Re ord to r Doc A e. Lat si St.ndaid Lats-t Veision

No, co e Stanid ard Ver$i Tit' Doc'u ment D te a ilt C o m mntn sf Ve sW O-D t

0110 ANS ANS 3.1 1981 Selection, Qualification, and inm2525/11 7 1992 R ANS 3.1 1993

Training of Personnel for NuclearPower Plants

0111 ANS ANS 3.1 1978 Selection, Qualification, and inm35701 1992 R ANS 3.1 1993




0113 ANS ANS 3.1 1978 Selection, Qualification, and inm40703 1992 R ANS3.11993Training of Personnel for NuclearPower Plants



0115 ANS ANS 3.1 1981 Selection, Qualification, and inm4l500 1995 R ANS 3.1 1993

Training of Personnel for NuclearPower Plants --_____3_1_1993

0116 ANS ANS 3.1 1978 Selection, Qualification, and inm6n1700 1983 R ANS3.11993Training of Personnel for NuclearPower Plants




Training of Personnel for Nuclear

Power Plants ANS_3_1_1993

0119 ANS ANS 3.1 1981 Selection, Qualification, and inm7l001 1995 R ANS 3.1 1993Training of Personnel for NuclearPower Plants

0120 ANS ANS 3.1 1981 Selection, Qualification, and inm82102 1993 _ ANS 3.1 1993




Codes and Standards, and Other Guidance Cited in Regulatory Documents


Record d o Aep Latest S Lveta Veision

o. Code, Standard VeIo il ouet Dae bity Cm ns Vers io Dat



0123 ANS ANS 3.1 1981 Selection, Qualification and nm83522 1991 R ANS 3.1 1993


0124 ANS ANS 3.1 1981 Selection, Qualification and inm83523 1984 R ANS 3.1 1993






0127 ANS ANS 3.1 N/S Selection, Qualification and inm99100 1992 R ANS 3.1 1993


0128 ANS ANS 3.1 1981 Selection, Qualification and nuregO933, 1987 R ANS 3.1 1993

Training of Personnel for Nuclear 1.l.A.2Power Plants

0129 ANS ANS 3.1 1978 Selection, Qualification and reg1.8.r02 1987 R ANS 3.1 1993


0130 ANS ANS 3.1 1981 Selection, Qualification and regl.8.r02 1987 P With ANS 3.1 1993

Training of Personnel for Nuclear exceptions and

Power Plants conditions

0131 ANS ANS 3.1 1979 Selection, Qualification and regl1.8.r02 1987 R ANS 3.1 1993


0132 ANS ANS 3.1 1978 Selection, Qualification and regl.149.rOO 1981 R ANS 3.1 1993

Training of Personnel for NuclearPower Plants ___

zC-�

0W(!A�10-4

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Re o dSO dad DC ., A ce t Latet Si dard Latest V ersionpoorcd ,0000i ;t; :t ..~y fm ;.; L; -i. 0 .0 ar po Accep .t s _

: :iN o. t I : C od e Standard V rs o Ttle Do c en t D e ab l . C - m n s e s o D te

0133 ANS ANS 3.1 1978 Selection, Qualification and srpl2.5 1981 p As related to ANS 3.1 1993

Training of Personnel for Nuclear selection,

Power Plants qualification,and trainingcriteria

0134 ANS ANS 3.1 1978 Selection, Qualification and srpl3.2.1 1981 R ANS 3. 1993


0135 ANS ANS 3.1 N/S Selection, Qualification and srpl3.2.2 1981 P Sections 5.1, ANS 3.1 1993

Training of Personnel for Nuclear 5.3, 5.4, and

Power Plants

0136 ANS ANS 3.1 1978 Selection, Qualification and srpl 3.4 1981 p iSection 4.7 ANS 3.1 1993


0137 ANS ANS 3.1 1979 Selection, Qualification and srpl 3.5.1 1981 P Section 4.4.6 ANS 3.1 1993

Training of Personnel for Nuclear of ANS 3.1

Power Plants Draft Revision

0138 ANS ANS 3.1 1978 Selection, Qualification and srpl 7.1 1981 P Section 4.4.5 ANS 3.1 1993

Training of Personnel for Nuclear as endorsed by

Power Plants Reg. Guide 1.8

0139 ANS ANS 3.1 1981 Selection, Qualification and sts4-ge5.5 1992 P ANS 3.1 1993


0140 ANS ANS 3.1 1981 Selection, Qualification, and sts4-geB3.8.7 1992 A ANS 3.1 1993


0141 ANS ANS 3.1 1981 Selection, Qualification, and sts6-ge5.5 1992 A ANS 3.1 1993


0142 ANS ANS 3.1 1981 Selection, Qualification, and stsb&w5.5 1992 A ANS 3.1 1993

Training of Personnel for NuclearPower- Plants



Recod Sandrd cc. Accpt-Latst Standard Latest Version

t-RcordX a~oet d:-<\i0

No. CoSandrd Version il Dcmn D afte ably Cmmns VerinDt

0143 ANS ANS 3.1 1981 Selection, Qualification, and stsce5.5 1992 A ANS 3.1 1993


0144 ANS ANS 3.1 1981 Selection, Qualification, and stswst5.5 1992 A ANS 3.1 1993


0145 ANS ANS 3.2 .1988 Administrative Controls and drg1010.rOO 1992 R ANS 3.2 1994

Quality Assurance for theOperational Phase of NuclearPower Plants _

0146 ANS ANS 3.2 1980 Administrative Controls and drgrs902-4.r00 1980 P Proposed ANS 3.2 1994

Quality Assurance for the reg1.3.r03

Operational Phase of NuclearPower Plants

0147 ANS ANS 3.2 N/S Administrative Controls and glt82-012 1982 R ANS 3.2 1994

Quality Assurance for theOperational Phase of NuclearPower Plants

0148 ANS ANS 3.2 N/S Administrative Controls and inm1245 App. B 1991 R ANS 3.2 1994

Quality Assurance for theOperational Phase of NuclearPower Plants _______

0149 ANS ANS 3.2 N/S Administrative Controls and inm37001 1992 R ANS 3.2 1994


0150 ANS ANS 3.2 1982 Administrative Controls and inm4O5OO 1995 R ANS 3.2 1994


0151 ANS ANS 3.2 1982 Administrative Controls and inm81022 1984 R ANS 3.2 1994

Quality Assurance for theOperational Phase of NuclearPower Plants _ _ _ _

z

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.Reaord St0andar. D0o. Accept Lae t Stan dard t i;it Ve ion.No. Code Standar Dat. ability W f. CjMrM"int version - Da .te

0152 ANS ANS 3.2 1982 Administrative Controls and inm83522 1991 R ANS 3.2 1994Quality Assurance for theOperational Phase of NuclearPower Plants

0153 ANS ANS 3.2 1982 Administrative Controls and inm83722 1984 R ANS 3.2 1994Quality Assurance for theOperational Phase of NuclearPower Plants

0154 ANS ANS 3.2 1982 Administrative Controls and inm9900IN18.7 1986 R ANS 3.2 1994Quality Assurance for theOperational Phase of NuclearPower Plants

0155 ANs ANS 3.2 1982 Administrative Controls and inm9900/OPS 1991 R ANS 3.2 1994Quality Assurance for theOperational Phase of NuclearPower Plants

0166 ANS ANS 3.2 1988 Administrative Controls and inm9900/OPS 1991 - ANS 3.2 1994Quality Assurance for theOperational Phase of NuclearPower Plants

0157 ANS ANS 3.2 NIS Administrative Controls and not82-03 1982 R ANS 3.2 1994Quality Assurance for theOperational Phase of NuclearPower Plants

0158 ANS ANS 3.2 N/S Administrative Controls and not84-51 1984 R Reg. 1.33 Rev. ANS 3.2 1994Quality Assurance for the 2. EndorsesOperational Phase of Nuclear draft revisionPower Plants

0159 ANS ANS 3.2 1982 Administrative Controls and not85-90 1985 R ANS 3.2 1994Quality Assurance for theOperational Phase of NuclearPower Plants

0160 ANS ANS 3.2 N/S Administrative Controls and not86-64.sOl 1987 R ANS 3.2 1994Quality Assurance for theOperational Phase of NuclearPower Plants



RorSafidbkd EZocv Ace:t-; Latest Stfidard La Vetson

0161 ANS ANS 3.2 1976 Administrative Controls and not86-75 1986 R ANS 3.2 1994


0162 ANS ANS 3.2 1982 Administrative Controls and not86-75 1986 R ANS 3.2 1994


0163 ANS ANS 3.2 N/S Administrative Controls and nuregO737 1980 P ANS 3.2 1994


0164 ANS ANS 3.2 N/S Administrative Controls and nuregO933, 3.75 1990 R ANS 3.2 1994


0165 ANS ANS 3.2 1982 Administrative Controls and regl.28.rO3 1985 R Expected to be ANS 3.2 1994

Quality Assurance for the endorsed by

Operational Phase of Nuclear Reg. Guide

Power Plants 1.33, Rev. 3

0166 ANS ANS 3.2 1976 Administrative Controls and reg1.33.r02 1978 P Subject to ANS 3.2 1994

Quality Assurance for the conditions


0167 ANS ANS 3.2 N/S Administrative Controls and srpl 3.4 1981 P Implied ANS 3.2 1994

Quality Assurance for the endorsement -

Operational Phase of Nuclear cited in SRP as

Power Plants both ANSI andANS 3.2

0168 ANS ANS 3.2 N/S Administrative Controls and srpl3.5.1 1981 P Section 5.2 ANS 3.2 1994

Quality Assurance for theOperational Phase of NuclearPower Plants --- - - _ - -- - -

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its


R odStandard D e. A ce Latest'Staindard Watet VersionO'd Dbcurnbn ;0t : 00 d Xt- ;; tt00 tX; - S -- V

No. : code.0 Standard : iVersio ; -Tit D u Da6ta: ability Co .entsVer'ion Date

0169 ANS ANS 3.2 1982 Administrative Controls and srp13.5.2 1985 P Section 5.3 ANS 3.2 1994


0170 ANS ANS 3.3 1982 Security for Nuclear Power Plants inm81018 1984 R ANS 3.3 Withdrawn n/awithdrawn1992

0171 ANS ANS 3.3 1982 Security for Nuclear Power Plants inm81501 1984 R ANS 3.3 Withdrawn n/awithdrawn1992

0172 ANS ANS 3.3 N/S Security for Nuclear Power Plants not86-83 1986 R ANS 3.3 Withdrawn n/awithdrawn1992

0173 ANS ANS 3.3 1982 Security for Nuclear Power Plants not88-91 1988 R ANS 3.3 Withdrawn n/awithdrawn1992

0174 ANS ANS 3.4 N/S Medical Certification and glt82-013 1982 P Incorrectly ANS 3.4 1 983 R88

Monitoring of Personnel Requiring typed as ANS

Operator Licenses for Nuclear 546

Power Plants

0175 ANS ANS 3.4 1983 Medical Certification and not84-03 1984 R ANS 3.4 1983 R88

Monitoring of Personnel RequiringOperator Licenses for NuclearPower Plants

0176 ANS ANS 3.4 1983 Medical Certification and not9l-08 1991 R ANS 3.4 1983 R88


0177 ANS ANS 3.4 1983 Medical Certification and not94-14 1994 R ANS 3.4 1983 R88


0178 ANS ANS 3.4 1983 Medical Certification and reg1.134.rO2 1987 R ANS 3.4 1983 R88




Record tdr.. ceptat Stndad Lttst Vetsol-

No Code Standard Version Tie D ocuent t a'bilit : Date

0179 ANS ANS 3.5 1993 Nuclear Power Plant Simulators drg1043.rO0 1995 P ANS 3.5 1993

for Use in Operator Training andExamination

0180 ANS ANS 3.5 1979 Nuclear Power Plant Simulators nuregO933, 1987 R ANS 3.5 1993

for Use in Operator Training and 1.1.A.4Examination

0181 ANS ANS 3.5 1981 Nuclear Power Plant Simulators nureg0933, 1987 R ANS 3.5 1993

for Use in Operator Training and 1.1.A.4Examination

0182 ANS ANS 3.5 1985 Nuclear Power Plant Simulators regl.149.r0l 1987 P Subject to ANS 3.5 1993

for Use in Operator Training and conditions

Examination

0183 ANS ANS 3,7.1 N/S Facilities and Medical Care for On- inm1245 App. B 1991 R ANS 3.7.1 1979 R86

Site Nuclear Power PlantRadiological Emergencies

0184 ANS ANS 3.7.2 N/S Criteria for Emergency Response nmi1 245 App. 8 1991 R ANS 3.8.2 1987

Functions and Organizations

0185 ANS ANS 3.7.3 N/S Criteria for Functional and inm1245 App. B 1991 R ANS 3.8.3 1987

Physical Characteristics ofEmergency Response Facilities

0186 ANS ANS 4.5 N/S Criteria for Accident Monitoring inm1245 App. B 1991 R ANS 4.5 1980 R88

Functions in Light Water CooledReactors

0187 ANS ANS 4.5 1980 Criteria for Accident Monitoring reg1 .97.r03 1983 P Subject to ANS 4.5 1980 R88

Functions in Light Water Cooled conditions

Reactors

0188 ANS ANS 4.5 1980 Criteria for Accident Monitoring srp7.5 1984 P ANS 4.5 1980 R88

Functions in Light Water CooledReactors _______

0189 ANS ANS 5.1 1971 Decay Heat Power in Light Water 1 Ocfr5O App. K 1994 P Proposed ANS 5,1 1994

Reactors standard

0190 ANS ANS 5.1 1979 Decay Heat Power in Light Water nureg0933, 2.C- 1986 R ANS 5.1 1994

Reactors __

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90

M

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R r Stan ard . cLatest Stotan d L atest - IVe.*lNo c deSt n ard Ver&siloin T~l ocum en t Dat Jeabilitfy , -, C o m m ntsVe sio Date;

0191 ANS ANS 5.1 1979 Decay Heat Power in Light Water reg1.157.rOO 1989 R ANS 5.1 1994

Reactors


Reactors


Reactors

0194 ANS ANS 5.1 N/S Decay Heat Power in Light Water srp6.2.5 1981 R ANS 5.1 1994

Reactors

0195 ANS ANS 6.3.1 NIS Program for Testing Radiation ini 245 App. B 1991 R Cited as ANSI ANS 6.3.1 1987

Shields in Light Water Reactors in inm 245

(LWR)0196 ANS ANS 6.3.1 1980 Program for Testing Radiation inm83521 1984 R ANS 6.3.1 1987

Shields in Light Water Reactors(LWR)

0197 ANS ANS 6.4 1977 Guidelines on Nuclear Analysis drgem805-5.r00 1979 P ANS 6.4 1985

and Design of Concrete RadiationShielding for Nuclear Power Plants

0198 ANS ANS 6.4 1977 Guidelines on Nuclear Analysis regl.142.rOl 1981 P Applicable to ANS 6.4 1985

and Design of Concrete Radiation extent of

Shielding for Nuclear Power Plants enhancingradiationshieldingfunction

0199 ANS ANS 6.7.1 1981 Radiation Zoning for Design of drgop618-4.rOO 1982 R Proposed n/a nta

Nuclear Power Plants reg8.8.rO4 -draft standardnot issued

0200 ANS ANS 7-4.3.2 NIS Standard Criteria for Digital drg1010.rOO 1992 R IEEE 7-4.3.2 1993

Computer Systems in Safety

Systems of Nuclear Power

Generating Stations



Record Standard . Ac eipt - Latest Standard Latest Version

No."1 ~ codei~ Standard Veso xl ouen ae aiiy Cmmns VrinDt

0201 ANS ANS 7-4.3.2 1982 Standard Criteria for Digital drg1039.r00 1995 R IEEE 7-4.3.2 1993

Computer Systems in SafetySystems of Nuclear PowerGenerating Stations

0202 ANS ANS 7-4.3.2 1993 Standard Criteria for Digital drglO39.rOO 1995 R IEEE 7-4.3.2 1993


0203 ANS ANS 7-4.3.2 1993 Standard Criteria for Digital drgl 039.rOO 1995 R IEEE 7-4.3.2 1993


0204 ANS ANS 7-4.3.2 1982 Standard Criteria for Digital drg39.rOO 199 R7-4.3.2 1993


0205 ANS ANS 7-4.3.2 1982 Standard Criteria for Digital drg1039.rOO 1995 R IEEE 7-4.3.2 1993


0206 ANS ANS 7-4.3.2 1982 Standard Criteria for Digital drg1039.rOO 1995 R IEEE 7-4.3.2 1993


0207 ANS ANS 7.60 NIS drgms2-5r 1986 R ANS 56.8 1994

Testing Requirements

0208 ANS ANS 8.1 1983 Nuclear Criticality Safety in bul9l-001 1991 R ANS 8.1 1983 R88

Operations with FissionableMaterials Outside Reactors

0209 ANS ANS 8.1 1983 Nuclear Criticality Safety in bul9l -001.sOl 1993 R ANS 8.1 1983 R88


0210 ANS ANS 8.1 1983 Nuclear Criticality Safety in not89-24 1989 R ANS 8.1 1983 R88


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R ec ordl. S tan d r of DAC-C ptL te t t nd d Lo t es e s o

No. Code Standard. rsi Date abili Comments: ,VnDat

0211 ANS ANS 8.1 1983 Nuclear Criticality Safety in not90-63 1990 R ANS 8.1 1983 R88


0212 ANS ANS 8.1 1983 Nuclear Criticality Safety in drg3004.rOO 1990 R Proposed ANS 8.1 1983 R88

Operations with Fissionable reg3.58.rO1

Materials Outside Reactors

0213 ANS ANS 8.1 1983 Nuclear Criticality Safety in reg3.4.rO2 1986 A Certain ANS 8.1 1983 R88

Operations with Fissionable procedures

Materials Outside Reactors acceptable toNRC

0214 ANS ANS 8.1 1983 Nuclear Criticality Safety in reg3.58.rOO 1986 R ANS 8.1 1983 R88


0215 ANS ANS 8.3 1986 Criticality Accident Alarm System drg3004.rOO 1990 R Proposed ANS 8.3 1986reg3.58.rOl

0216 ANS ANS 8.3 1979 Criticality Accident Alarm System inm83100 1991 R ANS 8.3 1986

0217 ANS ANS 8.3 1979 Criticality Accident Alarm System _nm83526 1984 R ANS 8.3 1986

0218 ANS ANS 8.3 1979 Criticality Accident Alarm System inm83726 1991 R ANS 8.3 1986

0219 ANS ANS 8.3 1979 Criticality Accident Alarm System regM8.roo 1986 R ANS 8.3 1986

0220 ANS ANS 8.3 1986 Criticality Accident Alarm System reg8.12.rO2 1988 P With ANS 8.3 1986conditions

0221 ANS ANS 8.5 1986 Use of Borosilicate Glass Raschig reg3.1.rO2 1987 A ANS 8.5 1986

Rings as a Neutron Absorber inSolutions of Fissile Material

0222 ANS ANS 8.9 NIS Nuclear Criticality Safety Criteria inm1245 App. B 1991 R Cited as ANSI ANS 8.9 1987

for Steel-Pipe Intersections in inm 1245

Containing Aqueous Solutions ofFissile Material


RcodStanddd D Accep La Standard Latest Version

No Cod stand ard ersion Titl D81en ee blty Cmmns Veso Date~0223 ANS ANS 8.9 1987 Nuclear Criticality Safety Criteria reg3.45.rO1 1989 A ANS 8.9 1987

for Steel-Pipe IntersectionsContaining Aqueous Solutions ofFissile Material

0224 ANS ANS 8.11 N/S Nuclear Criticality Safety in reg3.4,r02 1986 R Withdrawn and ANS 8.1 1983 R88

Operations with Fissionable incorporated

Materials Outside Reactors into anotherANS standard

0225 ANS ANS 8.12 N/S Nuclear Criticality Control and inm1245 App. B 1991 R Cited as ANSI ANS 8.12 1987 R93

Safety of Homogeneous Plutonium in inr 1245Uranium Fuel Mixtures OutsideReactors__ _ _ _ _ _ __ _ _ _ _ _

0226 ANS ANS 8.12 1978 Nuclear Criticality Control and reg3.47.r00 1981 P ANS 8.12 1987 R93

Safety of Homogeneous PlutoniumUranium Fuel Mixtures OutsideReactors

0227 ANS ANS 8.17 1984 Criticality Safety Criteria for the drg3004.rOO 1990 R Proposed ANS 8.17 1984 R89

Handling, Storage, and reg3.58.rO1Transportation of LWR FuelOutside Reactors

0228 ANS ANS 8.17 1984 Criticality Safety Criteria for the reg3.58.r00 1986 P ANS 8.17 1984 R89

Handling, Storage, andTransportation of LWR FuelOutside Reactors

0229 ANS ANS 8.19 1984 Administrative Practices for reg3.57.rOO 1986 A ANS 8.19 1984 R89

Nuclear Criticality Safety _

0230 ANS ANS 8,20 1991 Nuclear Criticality Safety Training reg3.68.rO0 N/S P ANS 8.20 1991

0231 ANS ANS 13.8 N/S Fuel Assembly Identification reg5.1.rOO 1972 R A standard for ANS 57.8 1995fuel assemblyidentification

z

-- I


Reo)adaDo A ccet Latest Standard Latest, ers io

tie Spcfctin o RsacN .C dSt a n a d e ~ o T t eD o c M en t D a t e a b ilit C o m e t Se s o D a t

0232 ANS ANS 15.1 1982 Development of Technical inm39745 1992 R ANS 15.1 1990

Specifications for ResearchReactors



0234 ANS ANS 15.1 1982 Development of Technical inm46750 1995 R ANS 15.1 1990Specifications for ResearchReactors



0236 ANS ANS 15.2 1974 Quality Control for Plate-Type inm40750 1995 R ANS 15.2 1990Uranium-Aluminum Fuel Elements

0237 ANS ANS 15.2 1974 Quality Control for Plate-Type inm60745 1994 R ANS 15.2 1990Uranium-Aluminum Fuel Elements

0238 ANS ANS 15.2 1974 Quality Control for Plate-Type inm6O745B 1992 R ANS 15.2 1990

Uranium-Aluminum Fuel Elements

0239 ANS ANS 15.3 1974 Development of Technical inm40750 1995 R Incorporated ANS 15.1 1990

Specifications for Research into ANS 15.1Reactors

0240 ANS ANS 15.4 1977 Selection and Training of glt83-012.a 1983 P ANS 15.4 1988

Personnel for Research Reactors

0241 ANS ANS 15.4 1987 Selection and Training of inm40745 1992 R ANS 15.4 1988


0242 ANS ANS 15.4 1977 Selection and Training of inm4O75O 1995 R ANS 15.4 1988


0243 ANS ANS 15.4 1977 Selection and Training of not91-08 1991 R ANS 15.4 1988



RoSn RDoc. dp L Standard LWtest Versiont

No. CodeD Sbndard Version Ttle iDocumnt iDate :biit Comiients Veation Date

0244 ANS ANS 15.4 1988 Selection and Training of not94-1 4 1994 R ANS 15.4 1988Personnel for Research Reactors

0245 ANS ANS 15.6 1974 Development of Technical inm40750 1995 R Incorporated ANS 15.1 1990Specifications for Research into ANS 15.1Reactors

0246 ANS ANS 15.6 1974 Development of Technical inm69745 1994 R Incorporated ANS 15.1 1990Specifications for Research into ANS 15.1Reactors

0247 ANS ANS 15.6 N/S Development of Technical reg2.4.rOR 1977 P Incorporated ANS 15.1 1990Specifications for Research into ANS 15.1Reactors

0248 ANS ANS 15.7 1977 Research Reactor Site Evaluation inm40750 1995 R ANS 15.7 1977 R86

0249 ANS ANS 15.8 1976 Quality Assurance Program inm40750 1995 R ANSI N402/ 1976 R87Requirements for Research ANS 15.8Reactors _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

0250 ANS ANS 15.11 1993 Radiation Protection at Research inm40750 1995 R ANS 15.11 1993Reactor Facilities

0251 ANS ANS 15.11 1993 Radiation Protection at Research inm60745 1994 R ANS 15.11 1993

Reactor Facilities




0255 ANS ANS 15.12 1977 Radiation Protection at Research inm40750 1995 R Incorporated ANS 15.11 1993Reactor Facilities into ANS

15.11

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0

c



Rec-rd Stand doO. Aci ep t- tipt t gc St ndard ILat t Vers on

0256 ANS ANS 15.15 1978 Criteria for the Reactor Safety inm40750 1995 R ANS 15.15 1978 R86

Systems for Research Reactors

0257 ANS ANS 15.16 1978 Emergency Planning for Research glt79-01O 1979 R ANS 15.16 1982 R88

Reactors

0258 ANS ANS 15.16 N/S Emergency Planning for Research inml245 App. B 1991 R ANS 15.16 1982 R88

Reactors

0259 ANS ANS 15.16 1982 Emergency Planning for Research inm40750 1995 R ANS 15.16 1982 R88

Reactors

0260 ANS ANS 15.16 1982 Emergency Planning for Research inm82745 1992 R ANS 15.16 1982 R88

Reactors

0261 ANS ANS 15.16 1982 Emergency Planning for Research reg2.6.rOl 1983 P Subject to ANS 15.16 1982 R88

Reactors conditions

0262 ANS ANS 15.17 1981 Fire Protection Program Criteria inm4O750 1995 R ANS 15.17 1981 R87

for Research Reactors

0263 ANS ANS 15.18 1979 Development of Technical inm40750 1995 R Incorporated ANS 15.1 1990

Specifications for Research into ANS 15.1

Reactors

0264 ANS ANS 15.19 N/S Shipment and Receipt of Special inm40750 1995 R ANS 15.19 1991

Nuclear Material (SNM) byResearch Reactor Facilities

0265 ANS ANS 15.20 N/S Criteria for the Reactor Safety inm40750 1995 R ANS 15.15 1978 R86

Systems for Research Reactors

0266 ANS ANS 18.1 1976 Radioactive Source Term for drgop618-4.rOO 1982 R Proposed ANS 18.1 1984

Normal Operation of Light Water reg8.8.rO4

Reactors

0267 ANS ANS 19.6.1 1984 Reload Startup Physics Tests for inm6l708 N/S R ANS 19.6.1 1985

Pressurized Water Reactors

0268 ANS ANS 19.6.1 1985 Reload Startup Physics Tests for inm61709 1986 R ANS 19.6.1 1985

Pressurized Water Reactors


Record SAn dard Do'. Aoptj* Latest Stindard La tes Vesi _i

No.od Standad Vrsio t Do t D ability Conderd' Vesion Date

0269 ANS ANS 19,6.1 1985 Reload Startup Physics Tests for inm61710 1985 R ANS 19.6.1 1985Pressurized Water Reactors

0270 ANS ANS 19.6.1 1985 Reload Startup Physics Tests for stsb&wB3.1.8 1992 P ANS 19.6.1 1985Pressurized Water Reactors

0271 ANS ANS 19.6.1 1985 Reload Startup Physics Tests for stsb&wB3.1.9 1992 P ANS 19.6.1 1985Pressurized Water Reactors

0272 ANS ANS 19.6.1 1985 Reload Startup Physics Tests for stsceB3.1.10 1992 P ANS 19.6.1 1985Pressurized Water Reactors

0273 ANS ANS 19.6.1 1985 Reload Startup Physics Tests for stsceB3.1.8 1992 P ANS 19,6,1 1985Pressurized Water Reactors

0274 ANS ANS 19.6.1 1985 Reload Startup Physics Tests for stsceB3.1.9(a) 1992 P ANS 19.6.1 1985Pressurized Water Reactors

0275 ANS ANS 19.6.1 1985 Reload Startup Physics Tests for stsceB3.1.91d) 1992 P ANS 19.6.1 1985Pressurized Water Reactors

0276 ANS ANS 19.6.1 1985 Reload Startup Physics Tests for stswstB3.1.10 1992 P ANS 19.6.1 1985Pressurized Water Reactors

0277 ANS ANS 19.6.1 1985 Reload Startup Physics Tests for stswstB3.1.1 1 1992 P ANS 19.6.1 1985Pressurized Water Reactors

0278 ANS ANS 19.6.1 1985 Reload Startup Physics Tests for stswstB3.1.9 1992 P ANS 19.6.1 1985Pressurized Water Reactors

0279 ANS ANS 40.35 N/S Volume Reduction of Low-Level inm1245 App. B 1991 R Cited as ANSI ANS 40.35 1991Radioactive Waste or Mixed in inm1245Waste _ _ _

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W'

t(.)PO



Record Standard Doc.: Acc t L S

-No. Code: ! . Standiard : Vesionw Tit Docume t Dat t C Vter on D ate.

0280 ANS ANS 51.10 N/S Auxiliary Feedwater System for nuregO933, 1986 R ANS 51.10 is ANS 51.10 1991

Pressurized Water Reactors 1.11.E.1 assumed viceANS 51.00

0281 ANS ANS 52.00 N/S Not Found nuregO933, 1986 R Not found n/a

1 .ll.E .1 l_ _ _ _ _ _

0282 ANS ANS 55.1 1979 Solid Radioactive Waste drgop618-4.rfO 1982 R ANS 55.1 1992

Processing System for Light-WaterCooled Reactor Plants

0283 ANS ANS 55.1 1979 Solid Radioactive Waste glt8O-009 1980 R ANS 55.1 1992


0284 ANS ANS 55.1 N/S Solid Radioactive Waste inml245 App. B 1991 R Cited as ANSI ANS 55.1 1992

Processing System for Light-Water in inm 245

Cooled Reactor Plants

0285 ANS ANS 55.1 1979 Solid Radioactive Waste inm84101 1991 R ANS 55.1 1992






0288 ANS ANS 55.1 1979 Solid Radioactive Waste regl.143.rOl 1979 R ANS 65.1 1992


0289 ANS ANS 55.1 N/S Solid Radioactive Waste reg8.8.rO3 1978 R ANS 55.1 1992


0290 ANS ANS 55.2 1976 Liquid Radioactive Waste regl.143.rOl 1979 P ANS 55.2 Withdrawn n/a

Processing System for Pressurized withdrawn

Water Reactor Plants 1980



6=Racord Stada . Accp- Latest Standard Latest ersi on

N. code 'Standardai Vefrsion: Title Document Dae aiiy Comm t Verio Datea'.

0291 ANS ANS 55.4 N/S Gaseous Radioactive Waste inml 245 App. B 1991 R Cited as ANSI ANS 55.4 1993

Processing Systems for Light in inm 1245

Water Reactor Plants

0292 ANS ANS 55.4 1979 Gaseous Radioactive Waste inm84524 1984 R ANS 55.4 1993

Processing Systems for LightWater Reactor Plants

0293 ANS ANS 55.4 1979 Gaseous Radioactive Waste inm84724 1991 R ANS 55.4 1993


0294 ANS ANS 55.4 1979 Gaseous Radioactive Waste regl.143.rOl 1979 R ANS 55.4 1993


0295 ANS ANS 55.6 1979 Liquid Radioactive Waste drgop618-4.rOO 1982 R ANS 55.6 1993


0296 ANS ANS 55.6 N/S Liquid Radioactive Waste inm1245 App. B 1991 R Cited as ANSI ANS 55.6 1993

Processing Systems for Light in inm1 245


0297 ANS ANS 56.2 1976 Containment Isolation Provisions inm70307 1986 R ANS 56.2 1984 R89

for Fluid Systems After a LOCA

0298 ANS ANS 56.2 1976 Containment Isolation Provisions inm70313 1985 R ANS 56.2 1984 R89


0299 ANS ANS 56.2 1976 Containment Isolation Provisions inm70323 1985 R Cited as ANSI ANS 56.2 1984 R89

for Fluid Systems After a LOCA 56.2

0300 ANS ANS 56.5 1979 PWR and BWR Containment Spray inm2515/065 1990 R ANS 56.5 1979 R87

System Design Criteria

0301 ANS ANS 56.5 1979 PWR and BWR Containment Spray nuregO933, 2.C- 1983 R ANS 56.5 1979 R87

System Design Criteria 10

0302 ANS ANS 56.5 1979 PWR and BWR Containment Spray srp6.5.2 1988 R ANS 56.5 1979 R87

System Design Criteria

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ReoDoe. Accp LatetStndrd Latest Versi on

No. c dSt dad %V ersio T tDocu meint!, 0D ae b Clm.ents Version Date

0303 ANS ANS 56.8 1987 Containment System Leakage 1 Ocfr5O App. J 1994 R Describes mass ANS 56.8 1994

Testing Requirements point methodto calculateleak rates

0304 ANS ANS 56.8 1981 Containment System Leakage drgms021-5.r00 1986 P ANS 56.8 1994


0305 ANS ANS 56.8 1981 Containment System Leakage inm61720 1985 R ANS 66.8 1994

03 ,Testing Requirements__ _ _ _ _ __ _ _ _ _ _ _

036 ANS AN$ 56.8 1981 Containment System Leakage inmn70307 1986 R ANs 56.8 1994Testing Requirements

0307 ANS ANS 56.8 1981 Containment System Leakage inm70303 1985 R ANS 56.8 1994

Testing Requirements0308 ANS ANS 66.8 1981 Containment System Leakage inm70323 1985 R ANS 56.8 1994


0309 ANS ANS 56.8 1981 Containment System Leakage nureg0933, 2.A- 1983 R ANS 56.8 1994

Testing Requirements 23

0310 ANS ANS 56.8 1994 Containment System Leakage regl.163.rOO 1995 R ANS 56.8 1994


0311 ANS ANS 57.1 N/S Design Requirements for Light srp9.1.1 1981 P ANS 57.1 1992

Water Reactor Fuel HandlingSystems

0312 ANS ANS 57.1 N/S Design Requirements for Light srp9.1.4 1981 A ANS 57.1 1992


0313 ANS ANS 57.1 N/S Design Requirements for Light srp9.1.5 1981 A ANS 57.1 1992


0314 ANS ANS 57.2 1976 Requirements for Light Water drgce913-5.rOO 1981 P Proposed reg ANS 57.2 1983

Reactor Spent Fuel Storage 1.13.rO2

Facilities at Nuclear Power Plants,Design

0315 ANS ANS 57.2 N/S Requirements for Light Water inm50095 1994 R ANS 57.2 1983

Reactor Spent Fuel Storage

Facilities at Nuclear Power Plants,Design



Reod tndr e. A"4cbl-; Laes Sndrd Latst Version' ol-.<; ; t-.S-- tinod < . -i- f..'.. .

t oNo. Cid Stndr Verio T ,tl o D--¢ 2 .ilit. Co.men Verson Date

0316 ANS ANS 57.2 N/S Requirements for Light Water inm50095 1994 R ANS 57.2 1983

Reactor Spent Fuel StorageFacilities at Nuclear Power Plants,Design

0317 ANS ANS 57.2 1976 Requirements for Light Water srp9.1.2 1981 P Implied ANS 57.2 1983

Reactor Spent Fuel Storage endorsements

Facilities at Nuclear Power Plants, & 5.1, 5.3, 5.4

Design specifically

0318 ANS ANS 57.2 N/S Requirements for Light Water srp9.1.5 1981 A ANS 57.2 1983

Reactor Spent Fuel StorageFacilities at Nuclear Power Plants,

__________ Design ____

0319 ANS ANS 57.3 N/S Design Requirements for New srp9.1.1 1981 P Proposed ANS 57.3 1983

Fuel Storage Facilities at Light standard


0320 ANS ANS 57.7 1981 Design Criteria for an Independent reg3.44.rO2 1989 R may be used ANS 57.7 1988

Spent Fuel Storage Installation as guidance

(Water Pool Type)

0321 ANS ANS 57.7 1981 Design Criteria for an Independent reg3.49.rOO 1981 P Subject to ANS 57.7 1988

Spent Fuel Storage Installation conditions(Water Pool Type)

0322 ANS ANS 57.7 1981 Design Criteria for an Independent reg3.53.rOO 1982 R Endorsed by ANS 57.7 1988

Spent Fuel Storage Installation Reg. Guide

(Water Pool Type) 3.49

0323 ANS ANS 57.9 1984 Design Criteria for an Independent reg3.48.rO1 1989 R ANS 57.9 1992

Spent Fuel Storage Installation(Dry Type)

0324 ANS ANS 57.9 1984 Design Criteria for an Independent reg3.60.rOO 1987 P Subject to ANS 57.9 1992

Spent Fuel Storage Installation conditions

(Dry Type)

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NO. Code Standard _Version.- Title Document Do Date

0325 ANS ANS 57.9 1984 Design Criteria for an Independent reg3.61.r00 1989 R Endorsed by ANS 57.9 1992


(Dry Type) 3.60

0326 ANS ANS 57.9 1984 Design Criteria for an Independent reg3.62.rO0 1989 R Endorsed by ANS 57.9 1992


(Dry Type) 3.60

0327 ANS ANS 58.2 1980 Design Basis for Protection of not93-55 1993 R ANS 58.2 1988

Light Water Nuclear Power PlantsAgainst Effects of Postulated PipeRupture

0328 ANS ANS 58.8 1984 Time Response Design Criteria for drg1040.rOO 1995 R ANS 58.8 1994

Safety Related Operator Actions

0329 ANS ANS 58.8 1994 Time Response Design Criteria for drg1040.rOO 1995 A ANS 58.8 1994

Safety Related Operator Actions

0330 ANS ANS 59.51 1989 Fuel Oil Systems for Emergency not9t-04 1991 R ANS 59.51 1989

Diesel Generators

0331 ANS ANS 59.51 1989 Fuel Oil Systems for Emergency not91-46 1991 P ANS 59.51 1989

Diesel Generators

0332 ANS ANS Draft 2 N/S Evaluation of Radionuclide srp2.4.13 1981 R ANS 2.17 1980 R89

Transport in Ground Water forNuclear Power Sites

0333 ANS ANS N2.3 1979 Criticality Accident Alarm System reg8.5.rOl 1981 A Incorporated ANS 8.3 1986into ANS 8.3

0334 ANS ANS N2.3 1979 Criticality Accident Alarm System reg8.5.r01 1981 A Incorporated ANS 8.3 1986into ANS 8.3

0335 ANS ANS N55.4 1979 Gaseous Radioactive Waste inm84101 1991 R ANS 55.4 1993

Processing Systems for Light-



:0 MRecor StendardOP D Accet- LatestiStandard t Vrion

No. Code Standard Verslon, i Document D et ability;;: Comments Veision D

0336 ANS ANS N55.6 1979 Liquid Radioactive Waste inm84101 1991 R ANS 55.6 1993

Processing System for Light Water

Cooled Reactor Plants


Processing System for Light WaterCooled Reactor Plants


Processing System for Light WaterCooled Reactor Plants

0339 ANS ANS N199 N/S Liquid Radioactive Waste reg8.8.rO3 1978 R ANS 55.2 Withdrawn n/a

Processing System for Light Water withdrawn

Reactor Plants 1980

0340 ANS ANS N212 1974 Nuclear Safety Criteria for the srpi5.2.1 1981 R ANS 52.1 1983 R99

Design of Stationary Boiling WaterReactor Plants

0341 ANS ANS N212 1974 Nuclear Safety Criteria for the srpl5.2.6 1981 R ANS 52.1 1983 R88


0342 ANS ANS N212 1974 Nuclear Safety Criteria for the srpl5.2.7 1981 R ANS 52.1 1983 R88


0343 ANS ANS N212 1974 Nuclear Safety Criteria for the srpl 5.3.1 1981 R ANS 52.1 1983 R88






0346 ANS ANS 1973 Decay Heat Power in Light Water srp9.2.5 1981 R ANS 5.1 1994

Proposed Reactors

Standard . .__ _ _

0347 ANSI ANSI 56.2 N/S Containment Isolation Provisions inm2515/128 1995 R ANS 56.2 1984 R89


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Record Standard DoA.-Accept- Late: Stanidar Latest Version

:0X ood; :it000-04:0 0 $ t - 0;i;i0 t en 'd 00 i; f. d0 Let ;t'Veiit ~tf.:~No. aCod Standard Version T.tle Document Dbte aV

0348 ANSI ANSI 7.4-3- 1993 Standard Criteria for Digital drglO39.rOO 1995 R IEEE 7-4.3.2 1993

2 Computer Systems in SafetySystems of Nuclear PowerGenerating Stations

0349 ANSI ANSI A2.1 1972 Standard Test Methods for Fire drgrs809-5.rOO 1979 R ASTM El 19 1995

Tests of Building Construction and Rev. A

Materials

0350 ANSI ANSI A2.1 .1972 Standard Test Methods for Fire reg3.16.rOO 1974 R ASTM El 19 1995


Materials

0351 ANSI ANSI A11.1 1973 industrial Lighting reg5.14.rOl 1980 R ANSI RP-7 1991

0352 ANSI ANSI A58.1 1972 Minimum Design Loads for srp2.3.1 1981 R ASCE 7 1993

Buildings and Other Structures

0353 ANSI ANSI A58.1 N/S Minimum Design Loads for srp3.3.1 1981 P ASCE 7 1993


0354 ANSI ANSI A58.1 N/S Minimum Design Loads for srp3.3.2 1981 P ASCE 7 1993


0355 ANSI ANSI A89.1 1972 Building Code Requirements for regl.142.rOl 1981 R ACI 318M 1995

Structural Plain Concrete

0356 ANSI ANSI B16.5 1973 Pipe Flanges and Flanged Fittings cir77-05 1977 R ASME B16.5 1988

0357 ANSI ANSI B16.5 N/S Pipe Flanges and Flanged Fittings not92-68 1992 R Flanges ASME B16.5 1988

0358 ANSI ANSI B16.5 N/S Pipe Flanges and Flanged Fittings srp3.9.4 1984 A ASME B16.5 1988

0359 ANSI ANSI B16.9 N/S Factory-Made Wrought Steel srp3.9.4 1984 A ASME B16.9 1993

Buttwelding Fittings

0360 ANSI ANSI N/S Forged Fittings, Socket-Welding srp3.9.4 1984 A ASME B16.11 1991

B16.11 and Threaded

0361 ANSI ANSI N/S Buttwelding Ends srp3.9.4 1984 A ASME 316.25 1992

B16.25 I I


Reor Standard.Do. Acp'Latest Standard Late.t Vrion*No. Code Staindard~" .' Vrsio .. Titleocument Dae-, abl.CoIet V Iers on *. .Dt.

0362 ANSI ANSI N/S Valves-Flanged, Threaded and srp3.2.2 1981 R ASME 816.34 1988

B16.34 Welding End

0363 ANSI ANSI N/S Valves-Flanged, Threaded and srp3.9.4 1984 A ASME B16.34 1988

B16.34 Welding End0364 ANSI ANSI N/S Functional Qualification srp3.10 1981 R ANSI 316.41 1983 R89

816.41 Requirements for Power OperatedDraft Active Valve Assemblies for

Nuclear Power Plants

0365 ANSI ANSI B30.2 1976 Overhead and Gantry Cranes (Top glt8O-013 1980 P ASME B30.2 1990Running Bridge, Single or MultipleGirder Top Running Trolley Hoist)

0366 ANSI ANSI B30.2 1976 Overhead and Gantry Cranes (Top git8l-007 1981 P Chapters 2-1 ASME B30.2 1990Running Bridge, Single or Multiple and 2-2Girder Top Running Trolley Hoist)

0367 ANSI ANSI B30.2 N/S Overhead and Gantry Cranes (Top gIt89-021 1989 P ASME B30.2 1990Running Bridge, Single or MultipleGirder Top Running Trolley Hoist)

0368 ANSI ANSI B30.2 1976 Overhead and Gantry Cranes (Top not85-12 1985 R ASME 830.2 1990Running Bridge, Single or MultipleGirder Top Running Trolley Hoist)

0369 ANSI ANSI B30.2 1976 Overhead and Gantry Cranes (Top srpl3.5.1 1981 P Chapters 2-3 ASME 830.2 1990Running Bridge, Single or MultipleGirder Top Running Trolley Hoist)

0370 ANSI ANSI B30.9 1971 Slings gIt80-013 1980 P ASME B30.9 1990

0371 ANSI ANSI B30.9 1971 Slings gIt81-007 1981 P Alternate to ASME 0.9 990ANSI 14.6-

.1 1978

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(I)

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R ecord St.ndard e. A cept-~ iL atst .Standard L ae ist Ver i on

N o. Code Standard V'e sion T' D c e D't ait Comments Version :,':Date

0372 ANSI ANSI B30.9 N/S Slings glt89-021 1989 P For lifting ASME 830.9 1990devices thatare notspeciallydesigned

0373 ANSI ANSI 831.1 1973 Power Piping cir77-05 1977 R ASME B31.1 1995

0374 ANSI ANSI B31.1 N/S Power Piping drg1010.r00 1992 P Endorsed by ASME B31.1 1995regl.26

0375 ANSI ANSI B31.1 NIS Power Piping gIt80-088 1980 R ASME B31.1 1995

0 A AS _ N/S P10376 ANSI ANSI 831.1 N/S Power Piping glt86-010 1986 P ASME B31.1 1995

0377 ANSI ANSI B31.1 NIS Power Piping glt87-011 1987 P conition ASME B31.1 1995conditions

0378 ANSI ANSI 831.1 NIS Power Piping git89-013.sO1 1990 R ASME B31.1 1995

0379 ANSI ANSI 831.1 1977 Power Piping not82-39 1982 P ASME 831.1 1995

0380 ANSI ANSI B31.1 N/S Power Piping not86-106.sOl 1987 P ASME B31.1 1995

0381 ANSI ANSI B31.1 N/S Power Piping not88-17 1988 R ASME B31.1 1995

0382 ANSI ANSI 831.1 1973 Power Piping regl.120.rOl 1977 P ASME B31.1 1995

0383 ANSI ANSI831.1- N/S Power Piping regl_143.rOl 1979 R ASME 831.1 1995

0384 ANSI ANSI B31.1 N/S Power Piping regl.148.rOO 1981 P ASME B31.1 1995

383 ANSI ANSI B31.1 NIS Power Piping reg1.26.r03 1976 P Implied ASME 831.1 1995endorsement

0386 ANSI ANSI 831.1 1973 Power Piping srp3.2.2 1981 P Paragraph ASME 831.1 1995136.4

0387 ANSI ANSI B31.1 1980 Power Piping srp3.2.2 1981 R ASME B31.1 1995

Codes and Standards and Other Guidance. Cited in Regulatory DocumentsPart A - Industry Consensus Codes and Standards

RecordStandird De. Acp-LaetSndd Lats eso

NCode Standard V 196e oouen Daping flte 0sbi~ty Cona3monts VeStio | ate io

0388 ANSI ANSI B31.1 1967 Power Piping srp3.6.2 1990 R ASME B31.1 1995

0389 ANSI ANSI 831.1 N/S Power Piping srp3.6.2 1981 P With ASME B31.1 1995conditions

0390 ANSI ANSI 831.1 N/S Power Piping srp3.9.4 1984 A ASME 831.1 1995

0391 ANSI ANSI 831.1 1973 Power Piping srp9.5.1 1981 PASEB1195

0392 ANSI ANSI 831.7 N/S Rules for Construction of Nuclear gIt80-088 1980 R ASME B&PV 1995Power Plant Components Section III

0393 ANSI ANSI B31.7 N/S Rules for Construction of Nuclear git89-008 1989 R ASME B&PV 1995Power Plant Components Section IlIl

0394 ANSI ANSI B31.7 NIS Rules for Construction of Nuclear inm49055 1982 R ASME B&PV 1995Power Plant Components Section III

0395 ANSI ANSI 831.7 N/S Rules for Construction of Nuclear not87-3 6 1987 - ASME 5&PV 1995

Power Plant Components Section HIl

0396 ANSI ANSI 831.7 N/S Rules for Construction of Nuclear not88-17 1988 R ASME B&PV 1995Power Plant Components Section III

0397 ANSI ANSI B31.7 1970 Rules for Construction of Nuclear reg1.84.r30 1994 R Use of 1970 ASME B&PV 1995Power Plant Components Addenda of Section III

831.7 SectionIll annulled

z 1978

0398 ANSI ANSI B95.1 1972 Terminology for Pressure Relief srpl 5.6.1 1981 R Not found n/a

_____ __ _ Devices _ _ _

x 0399 ANSI ANSI B96.1 N/S Welded Aluminum-Alloy Storage drgl010.r00 1992 P Endorsed by ASME B96.1 1993

MD Ta k _ _ _ regl.26_ _ _ _ _ _

q4cJ

z

~0l.A

-I

00


AReord S Dcc, Accep...- t an... fst:Ohdard Latest Vroion

$ No. ": Code -- D tStandard V s Tt tte : biiity en Versio Date

0400 ANSI ANSI B96.1 NIS Welded Aluminum-Alloy Storage regl.26.rO3 1976 P Implied ASME B96.1 1993

Tanks endorsement(Table 1,QualityStandards)

0401 ANSI ANSI B96.1 1980 Welded Aluminum-Alloy Storage srp3.2.2 1981 R ASME B96.1 1993

Tanks

0402 ANSI ANSI 1971 UL Standard for Safety Air Filter regl.52.rO2 1978 A UL 900 1994

B124.1 Units

0403 ANSI ANSI N/S UL Standard for Safety High- inm88O55 1991 R UL 586 1990

B132.1 Efficiency, Particulate, Air FilterUnits

0404 ANSI ANSI 1971 UL Standard for Safety High- reg3.12.rOO 1973 R UL 586 1990


0405 ANSI ANSI N3.1 N/S Bases for GM Counter Tubes inm1 245 App. B 1991 R IEEE N42.5 1965 R91

0406 ANSI ANSI N3.2 NIS Interrelationship of Quartz-Fiber inrn 245 App. B 1991 R IEEE N42.6 1980 R91Electrometer Type ExposureMeters and Companion ExposureMeter Charges

0407 ANSI ANSI N7.2 NIS Radiation Protection for Nuclear inml 245 App. B 1991 R Typo in Withdrawn n/a

Reactor Fuel Fabrication Plants inm 1245 -

Natural (or Normal) and Enriched ANSI N7.2 vs

Uranium, Thorium and Plutonium 7.2 -Withdrawn in'86

0408 ANSI ANSI 1971 UL Standard for Safety High- reg3.32.rOO 1975 R UL 586 1990


0409 ANSI ANSI N/S Standard Rating Structure for AC srp8.2 1983 A IEEE C37.04 1979 R89

C37.04 High-Voltage Circuit BreakersRated on a Symmetrical CurrentBasis


tRecord Standard Docd:.y Aco- Latest Standard Latest Vers onNo oa Stnad Verse Til oumn aa blt Comments Vekaior Date

0410 ANSI ANSI N/S Switchgear-AC High-Voltage srp8.2 1983 A ANSI C37.06 1987 S89

C37.06 Circuit Breakers Rated on aSymmetrical Current Basis-Preferred Ratings and RelatedRequired Capabilities

0411 ANSI ANSI N/S Standard Test Procedure for AC srp8.2 1983 A IEEE C37.09 1979 R89

C37.09 High-Voltage Circuit BreakersRated on a Symmetrical CurrentBasis

0412 ANSI ANSI 1978 Standard for Relays and Relay not83-63.sO1 1984 R IEEE C37.90 1989 R94

C37.90 Systems Associated with ElectricPower Apparatus

0413 ANSI ANSI 1977 Polyphase Induction Motors for not91-07 1991 R Withdrawn nWa

C50.41 Power Generating Stations

0414 ANSI ANSI 1977 Polyphase Induction Motors for not91-57 1991 R Withdrawn n/a

C50.41 Power Generating Stations0415 ANSI ANSI C62.1 1975 Standard for Gapped-Silicon Surge drgrs705-4.rOO 1979 P IEEE C62.1 1989 R94

Arresters for AC Power Circuits

0416 ANSI ANSI C62.2 1969 Guide for Application of Gapped drgrs705-4.rOO 1979 IEEE C62.2 1987 R94Silicon-Carbide Surge Arresters forAlternating Current Systems

0417 ANSI ANSI C84.1 1982 Electric Power Systems and sts4-geB3.8.1 1992 R ANSI C84.1 1989Equipment - Voltage Ratings (60Hertz)

0418 ANSI ANSI C84.1 1982 Electric Power Systems and sts6-geB3.8.1 1992 R ANSI C84.1 1989Equipment - Voltage Ratings (60Hertz)

0419 ANSI ANSI C84.1 1982 Electric Power Systems and stsb&wB3.8.1 1992 R ANSI C84.1 1989Equipment - Voltage Ratings (60Hertz)

0420 ANSI ANSI C84.1 1982 Electric Power Systems and stsceB3.8.1 1992 R ANSI C84.1 1989Equipment - Voltage Ratings (60Hertz)

z

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(5

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Record Standard IDc AcWpOOats Standard Latet VersIio

Nob :::Coda Standard i i -Verson Titl D ocumen Date biNSiit o m.nts Verion ate9

0421 ANSI ANSI C84.1 1982 Electric Power Systems and stswstB3.8.1 1992 R ANSI C84.1 1989Equipment - Voltage Ratings (60Hertz)

0422 ANSI ANSI MC 1976 Quality Standard for Instrument srp9.3.1 1981 P Supplements ISA S7.3 1975 R81

11.1 Air Reg. Guide1.68.3 _ _ _ _ _

0423 ANSI ANSI MH5.1 N/S Cargo Container Chassis - Basic inm81370 1986 R ANSI MH5.6 1990

Interface Requirements ANSI______19_9

0424 ANSI ANSI N2.1 1969 Warning Symbols - Radiation reg8.1.rOO 1973 PANSI N2.1 199

Symbol _ _

0425 ANSI ANSI N2.3 1979 Criticality Accident Alarm System reg8.5.rOl 1981 A ANS 8.3 1986

0426 ANSI ANSI N4.1 1973 Classification System for regl.70.rO3 1978 P ASTM 02953 discontinued n/a

Polymeric Materials for Services in discontinued

Ionizing Radiation

0427 ANSI ANSI N8.1 1967 Quality Control for Plate-Type reg2.3,rOl 1976 R ANS 15.2 1990


0428 ANSI ANSI N13.1 1969 Guide for Sampling Airborne drg3003.rOO 1990 A ANSI N13.1 1969 R93

Radioactive Materials in NuclearFacilities

0429 ANSI ANSI N13.1 1969 Guide for Sampling Airborne drgop618-4.rOO 1982 R Proposed ANSI N13.1 1969 R93

Radioactive Materials in Nuclear reg8.8.r04

Facilities

0430 ANSI ANSI N 13.1 N/S Guide for Sampling Airborne inm1245 App. B 1991 R ANSI N13.1 1969 R93


0431 ANSI ANSI N13.1 1969 Guide for Sampling Airborne inm2515/065 1990 R ANSI N13.1 1969 R93


0432 ANSI ANSI N13.1 1982 Guide for Sampling Airborne inm2515/065 1990 - ANSI N13.1 1969 R93

Radioactive Materials in Nuclear

Facilities I_3_1_1969_R93

0433 ANSI ANSI N13.1 1969 Guide for Sampling Airborne inm83lOO 1991 R ANSI N13.1 1969 R93Radioactive Materials in NuclearFacilities


........dad' . Dck Acept- . .. atests tadrd Lates Veln1o - oe: tandad Vrion Title Docu t Date abi Comments ero Dati

0434 ANSI ANSI N13.1 1969 Guide for Sampling Airborne inm83525 1984 R ANSI N13.1 1969 R93




0436 ANSI ANSI N13.1 1982 Guide for Sampling Airborne inm83525 1984 R ANSI N1 3.1 1969 R93







Radioactive Materials in NuclearFacilities __._ _




Radioactive Materials in NuclearFacilities _ _ _



0443 ANSI ANSI N13.1 NIS Guide for Sampling Airborne inm83729 1991 R ANSI N13.1 1969 R93


0444 ANSI ANSI N 13.1 NIS Guide for Sampling Airborne inm83750 1994 R ANSI N13.1 1969 R93




z

ttl

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(b

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i.;N o. C da stanCda rd:o T itle Docum entS. D;ate ability Co me tsVe si n at



Facilities



Facilities







Facilities

0451 ANSI ANSI N13.1 1969 Guide for Sampling Airborne nuregO737 1980 P Typo N131 ANSI N13.1 1969 R93


Facilities

0452 ANSI ANSI N13.1 1969 Guide for Sampling Airborne regl.21.rOl 1976 P ANSI N13.1 1969 R93


Facilities _

0453 ANSI ANSI N13.1 1969 Guide for Sampling Airborne regl.70.rO3 1978 R ANSI N13.1 1969 R93


0454 ANSI ANSI N13.1 1969 Guide for Sampling Airborne regl.97.rO3 1983 P As applicable ANSI N13.1 1969 R93

Radioactive Materials in Nuclear to gases

Facilities

0455 ANSI ANSI N13.1 1969 Guide for Sampling Airborne reg3.3.rOl 1974 R Draft standard ANSI N13.1 1969 R93


0456 ANSI ANSI N13.1 1969 Guide for Sampling Airborne reg3.39.rOO 1976 P Implied ANSI N13.1 1969 R93

Radioactive Materials in Nuclear endorsement

Facilities

0457 ANSI 969 Guide for Sampling Airborne reg4.14.rOl 1980 R ANSIN13.1 1969 R93


Facilities _ _


Record Sta nda rd Dec A c ep Latest Standard Latest Version

No, Code Standard Version Title Do e Dat abili*f Co mments Ven ion Date0458 ANSI ANSI N13.1 1969 Guide for Sampling Airborne reg4.15.rOI 1979 R ANSI N13.1 1969 R93


0459 ANSI ANSI N 13.1 1982 Guide for Sampling Airborne reg4.16.rO1 1985 R ANSI N13.1 1969 R93Radioactive Materials in NuclearFacilities

0460 ANSI ANSI N13.1 1969 Guide for Sampling Airborne reg8.37.r00 1993 P ANSI N13.1 1969 R93

. Radioactive Materials in NuclearFacilities

0461 ANSI ANSI N13.1 1969 Guide for Sampling Airborne srpl1.5 1981 P Implied in ANSI N13.1 1969 R93Radioactive Materials in Nuclear acceptanceFacilities criteria

0462 ANSI ANSI N13.1 1969 Guide for Sampling Airborne srpl2.3 1981 P Implied in ANSI N13.1 1969 R93Radioactive Materials in Nuclear acceptanceFacilities criteria

0463 ANSI ANSI N13.1 1969 Guide for Sampling Airborne srp9.3.2 1981 P ANSI N13.1 1969 R93Radioactive Materials in NuclearFacilities

0464 ANSI ANSI N13.2 N/S Guide to Administrative Practices inm1245 App. B 1991 R ANSI N13.2 1969 R88in Radiation Monitoring

0465 ANSI ANSI N13.2 1969 Guide to Administrative Practices inm93100 1991 R ANSI N13.2 1969 R88in Radiation Monitoring




0469 ANSI ANSI N13.2 1982 Guide to Administrative Practices inm83725 1991 R ASI N13.2 1969 R88in Radiation Monitoring

z

Ci

z

U.)


Re o dSta nd ard D o c. ;A cc e t L t s St n ard L atest Version

N o .C o d S t n d a d V r s i n T tl eD o c m e n D a e a ili y o m m e n t s V r s io n D to0 0i .;' ' co~.' .0.: l :',': i,~ Stan '. ,,- ...... ........ ai . 6 Data: I ... -: 'i'-:_

0470 ANSI ANSI N13.2 1969 Guide to Administrative Practices regl0.8.rO2 1987 R ANSI N13.2 1969 R88

in Radiation Monitoring

0471 ANSI ANSI N13.2 1969 Guide to Administrative Practices reg8.2.rOO 1973 P Subject to ANSI N13.2 1969 R88

in Radiation Monitoring conditions

0472 ANSI ANSI N13.2 1969 Guide to Administrative Practices srp12.5 1981 P As relates to ANSI N13.2 1969 R88

in Radiation Monitoring administrativepractices

0473 ANSI ANSI N13.3 N/S Dosimetry for Criticality Accidents inml 245 App. B 1991 R ANSI N1 3.3 1969 R88

0474 ANSI ANSI N13.4 N/S Performance Specifications for inm1245 App. B 1991 R iEEE N42.17A, 1989

Health Physics Instrumentation N42.17B, &N42.17C

0475 ANSI ANSI N13.4 1971 Performance Specifications for reg10.8.r02 1987 R IEEE N42.17A, 1989

Health Physics Instrumentation N42.17B, &N42.17C

0476 ANSI ANSI N13.5 N/S Performance Specifications for inm 245 App. B 1991 R ANSI N13.5 1972 R89

Direct-Reading and Indirect-Reading Pocket Dosimeters for X-and Gamma Radiation

0477 ANSI ANSI N13.5 1972 Performance Specifications for inm83100 1991 R ANSI N13.5 1972 R89





a Reco Sa r Doe. Ae Latest Standard Lates Ve rion$ Nt ;:d i 0ttd rdEjrit 0;0-Ti $ 0:iii: t;}No.:1C4de Standaird Versiot TteDumn Dte aity onihients, Version Date



0480 ANSI ANSI N13.5 1972 Performance Specifications for reg8.4.r00 1981 P ANSI N13.5 1972 R89


0481 ANSI ANSI N13.5 1972 Performance Specifications for srp12.5 1981 P As applicable ANSI N13.5 1972 R89

Direct-Reading and Indirect- in acceptanceReading Pocket Dosimeters for X- criteriaand Gamma Radiation

0482 ANSI ANSI N13.6 1982 Practice for Occupational drg8004.rOO 1991 R ANSI N13.6 1966 R89

Radiation Exposure RecordsSystems

0483 ANSI ANSI N13.6 N/S Practice for Occupational inm1245 App. B 1991 R ANSI N13.6 1966 R89


0484 ANSI ANSI N13.6 1966 Practice for Occupational inm83100 1991 R ANSI N13.6 1966 R89


0485 ANSI ANSI N13.6 1972 Practice for Occupational inm83100 1991 R ANSI N 13.6 1966 R89








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Record StAndavd DOl. 0Latest Sandard LaetVersion

No. Code o Standard rsion Title Doc umnt i Date ability C ut Version Date











0494 ANSI ANSI N13.6 1966 Practice for Occupational reg10.8.r02 1987 R ANSI N13.6 1966 R89Radiation Exposure RecordsSystems

0495 ANSI ANSI N13.6 1966 Practice for Occupational reg6.5.r00 1974 R ANSI N13.6 1966 A89


0496 ANSI ANSI N1 3.6 1966 Practice for Occupational reg8.4.rOO 1991 R Draft Reg ANSI N1 3.6 1966 R89

Radiation Exposure Records GuideSystems

0497 ANSI ANSI N13.6 1972 Practice for Occupational srpl 2.5 1981 P As applicable ANSI N13.6 1966 R89

Radiation Exposure Records in acceptanceSystems criteria

0498 ANSI ANSI N13.7 N/S Radiation Protection - inmi245 App. B 1991 R ANSI N13.7 1983 R89Photographic Film Dosimeters -Criteria for Performance

0499 ANSI ANSI N13.7 1983 Radiation Protection - inm83100 1991 R ANSI N 13.7 1983 R89Photographic Film Dosimeters -Criteria for Performance



t nard Latest Standard Latest V.rsion

NO. Cod o Standard Version Title Documnt D ate: abity Comments Veirsion Date

0500 ANSI ANSI N13.7 1972 Radiation Protection - inm83524 1984 R ANSI N13.7 1983 R89

Photographic Film Dosimeters-Criteria for Performance

0501 ANSI ANSI N13.7 1983 Radiation Protection- inm83524 1984 R ANSI N13.7 1983 R89

Photographic Film Dosimeters -Criteria for Performance

0502 ANSI ANSI N13.7 1983 Radiation Protection - inm83724 1991 R ANSI N1 3.7 1983 R89


0503 ANSI ANSI N13.7 1972 Radiation Protection - reg8.3.rOO 1973 P ANSI N13.7 1983 R89


0504 ANSI ANSI N13.7 1972 Radiation Protection - srpl2.5 1981 P As applicable ANSI N13.7 1983 R89

Photographic Film Dosimeters - in acceptance

Criteria for Performance criteria

0505 ANSI ANSI N13.8 N/S Radiation Protection in Uranium inm1245 App. B 1991 R ANSI N13.8 1973 R89

Mines

0506 ANSI ANSI N13.8 1973 Radiation Protection in Uranium reg4.14.rO1 1980 R Redesignation ANSI N13.8 1973 R89

Mines of N7.1 andN7.1A

0507 ANSI ANSI N13.8 1973 Radiation Protection in Uranium reg8.3.rOO 1973 R Redesignation ANSI N13.8 1973 R89

Mines of N7.1 andN7.1A

0508 ANSI ANSI Ni13.9 N/S Guide to Environmental inm1245 App. B 1991 R Proposed Not issued n/a

Surveillance Around Nuclear standardFacilities

0509 ANSI ANSI N/S Specification and Performance of inm1 245 App. B 1991 R IEEE N42.18 1980 R91

N1 3.10 On-Site Instrumentation forContinuously MonitoringRadioactivity in Effluents

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tJA

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Record Standard D Ltest StaEdard Lat.es Version

No. Code Standard Vrsione Titl D D bit C m nt Veso Date

0510 ANSI ANSI 1974 Specification and Performance of inm84101 1991 R ANSI N13.10 IEEE N42.18 1980 R91

N13.10 On-Site Instrumentation for redesignatedContinuously MonitoringRadioactivity in Effluents




N1 3.10 On-Site Instrumentation for redesignatedContinuously MonitoringRadioactivity in Effluents


N1 3.10 On-Site Instrumentation for redesignatedContinuously MonitoringRadioactivity in Effluents



0515 ANSI ANSI 1974 Specification and Performance of reg4.14.rOl 1980 R Typo in IEEE N42.18 1980 R91

N13.10 On-site Instrumentation for reg4.14.rOl -

Continuously Monitoring ANSI N14.10Radioactivity in Effluents not a valid

designation.Title cited isfor ANSIN1 3.10



-R cot Standard A'c- Acet L St L Version

N ce Staindar VeioTtl Dument Data abillity Cmet erinDt

0516 ANSI ANSI 1974 Specification and Performance of reg4.15.r01 1979 R ANSI N13.10 IEEE N42.18 1980 R91

N13.10 On-Site Instrumentation for redesignated

Continuously MonitoringRadioactivity in Effluents

0517 ANSI ANSI 1974 Specification and Performance of srpl1.5 1981 P ANSI N13.10 IEEE N42.18 1980 R91



0518 ANSI ANSI N/S Dosimetry - Personnel Dosimetry inm 124 App. B 1991 R ANSI N 13.11 1993

N1 3.11 Performance, Criteria for Testing

0519 ANSI ANSI 1983 Dosimetry - Personnel Dosimetry inm83100 1991 R ANSI N13.11 1993


0520 ANSI ANSI 1983 Dosimetry - Personnel Dosimetry inm83524 1984 R ANSI N 13.11 1993


0521 ANSI ANSI 1983 Dosimetry - Personnel Dosimetry inm83724 1991 R ANSI N13.11 1993

N13.1 1 Performance, Criteria for Testing

0522 ANSI ANSI NIS Dosimetry - Personnel Dosimetry inm83750 1994 R ANSI N1 3.11 1993


0523 ANSI ANSI N/S Dosimetry - Personnel Dosimetry nureg0933, 1987 R ANSI N1 3.11 1993

N1 3.11 Performance, Criteria for Testing 1.11I.D.3

0524 ANSI ANSI N/S Surface Radioactivity Guides for inm 1245 App. B 1991 R Proposed Not issued n/a

N13.12 Materials, Equipment, and standardFacilities to be Released forUncontrolled Use

0525 ANSI ANSI 1978 Surface Radioactivity Guides for cir81-07 1981 R Standard ANSI N 13.12 not issued

N13.12 Materials, Equipment, and development in

Draft Facilities to be Released for process

Uncontrolled Use

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,R c od . , t n d r " ' 'D e . A e p -"L e t Set ah d a d L at est Ve reio nC de Stindard | ers io tn 0 ' i D u D t a t C - V erso |ate.

0526 ANSI ANSI N/S NotFound ini 245 App. B 1991 .Notfound n/aN i 3 .1 3 _ _ _ _ _ _ _ _ _ _ _ _

0527 ANSI ANSI N/S Internal Dosimetry Programs for inml245 App. B 1991 R ANSI N1 3.14 1994

N1 3.14 Tritium Exposure - MinimumRequirements

0528 ANSI ANSI 1983 Internal Dosimetry Programs for reg8.32.rOO 1988 R ANSI N13.14 1994

N1 3.14 Tritium Exposure - MinimumRequirements

0529 ANSI ANSI N/S Radiation Detectors - Personnel inml 245 App. B 1991 R ANSI N13.15 1985

Ni 3.15 Thermoluminescence DosimetrySystems - Performance

0530 ANSI ANSI 1981 Radiation Detectors - Personnel inm83100 1991 R ANSI Ni 3.15 1985

N13.15 Thermoluminescence DosimetrySystems - Performance

0531 ANSI ANSI 1981 Radiation Detectors - Personnel inm83524 1984 R ANSI N1 3.15 1985

N 13.15 Thermoluminescence DosimetrySystems - Performance

0532 ANSI ANSI 1981 Radiation Detectors - Personnel inm83724 1991 R ANSI N1 3.15 1985

N 13.15 Thermoluminescence DosimetrySystems - Performance

0533 ANSI ANSI N/S Performance Requirements for inm1245 App. B 1991 R ANSI N13.27 1981 R92

N1 3.27 Pocket Sized Alarm Dosimetersand Alarm Ratemeters

0534 ANSI ANSI 1981 Performance Requirements for inmB3100 1991 R ANSI N1 3.27 1981 R92

N13.27 Pocket Sized Alarm Dosimetersand Alarm Ratemeters


Rcrd td Doc Accept- La'test Standard ILatst Version

No. Code Standard Version Tit -Dolcument Date: abili C met0 Verision t Date

0535 ANSI ANSI 1981 Performance Requirements for inm83524 1984 R ANSI N13.27 1981 R92

N1 3.27 Pocket Sized Alarm Dosimetersand Alarm Ratemeters

0536 ANSI ANSI 1981 Performance Requirements for inm83724 1991 R ANSI N13.27 1981 R92

N13.27 Pocket Sized Alarm Dosimetersand Alarm Ratemeters

0537 ANSI ANSI 1981 Performance Requirements for reg8.28.rO0 1981 P One exception ANSI N13.27 1981 R92

Ni 3.27 Pocket Sized Alarm Dosimetersand Alarm Ratemeters

0538 ANSI ANSI N14.1 1982 Nuclear Materials-Uranium not87-26 1987 R DOT requires ANSI N14.1 1995

Hexafluoride-Packaging for UFG shippingTransport containers to

meet ANSI

0539 ANSI ANSI N14.1 1987 Nuclear Materials-Uranium not89-78 1989 R Provides ANSI N14.1 1995

Hexafluoride-Packaging for criteria for

Transport transport

0540 ANSI ANSI N14.1 1987 Nuclear Materials-Uranium not90-27 1990 R ANSI N14.1 1995Hexafluoride-Packaging forTransport

0541 ANSI ANSI N14.1 1971 Nuclear Materials-Uranium not92-58 1992 R ANSI N14.1 1995Hexafluoride-Packaging forTransport

0542 ANSI ANSI N14.2 1986 Tiedowns for Transport of Fissile not87-31 1987 R Standard under nWa n/a

and Radioactive Containers development -

Greater than One-Ton Truck standard has

Transport not beenpublished

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Riecordll Standard Doe. A c p Latest Standard Latest Version

-.00No. ; - i .Code f Standa d Versio t Do t 0 D ate bil;ity IR Vin t Version Dae

0543 ANSI ANSI N14.3 1973 Packaging and Transportation of reg7.2.rOO 1974 P Subject to Withdrawn n/a

Radioactively Contaminated conditions

Biological Materials

0544 ANSI ANSI N14.4 N/S ANSI N14.4 Subcommittee reg7.10.r01 1986 R Refers to the n/a n/aANSI N14.4Subcommittee

0545 ANSI ANSI N14.5 1977 Radioactive Materials - Leakage reg10.8.r02 1987 R ANSI N14.5 1987

Tests on Packages for Shipment

0546 ANSI ANSI N14.5 N/S Radioactive Materials - Leakage reg7.4.rOO 1975 A ANSI N14.5 1987

Tests on Packages for Shipment

0547 ANSI ANSI N14.6 1978 Radioactive Materials - Special gIt80-013 1980 P ANSI N14.6 1993

Lifting Devices for ShippingContainers Weighing 10 000Pounds (4500 kg) or More

0548 ANSI ANSI N14.6 1978 Radioactive Materials-Special gIt81 -007 1981 P For lifting ANSI N14.6 1993

Lifting Devices for Shipping devicesContainers Weighing 10,000pounds (4500 kg) or More

0549 ANSI ANSI N14.6 N/S Radioactive Materials-Special g1t89-021 1989 P Typo - was ANSI N14.6 1993

Lifting Devices for Shipping ANSI N14.6.6

Containers Weighing 10,000pounds (4500 kg) or More

0550 ANSI ANSI N14.6 N/S Radioactive Materials-Special not83-71 1983 P ANSI N14.6 1993

Lifting Devices for ShippingContainers Weighing 10,000pounds 14500 kg) or More

0551 ANSI ANSI N/S Administrative Guide for the inm1245 App. B 1991 R Proposed Not issued n/a

N14.10 Liability and Property Insuance standardAspects of Shipping NuclearMaterials


Record Sna . t- Lete | Standard Latest nVerion

No. Code Standard iVers ion Tit Docu ment 0:Date abilit Cm nsront

0552 ANSI ANSI 1973 Administrative Guide for reg7.1.rOO 1974 A Withdrawn n/a

N14.10.1 Packaging and Transporting

Radioactive Materials

0553 ANSI ANSI 1973 Administrative Guide for Obtaining reg7.5.rOR 1977 P Withdrawn n/a

N14.10.2 Department of TransportationSpecial Permits for RadioactiveMaterial Shipments

0554 ANSI ANSI 1986 Administrative Guide for Verifying reg7.7.rOO 1977 P Withdrawn n/a

N 14.10.3 Compliance with PackagingRequirements for Shipments of

Radioactive Material

0555 ANSI ANSI N15.1 N/S Classification of Unirradiated inmi 245 App. B 1991 R Typo in Not issued n/a

Uranium Scrap inm1245 -ANSI N 15.1 vs15.1. ANSIN15.1 waswithdrawn in1978, AnewANSI N 15. 1 isin process.

0556 ANSI ANSI Ni 5.2 N/S Record and Reporting Units for inm 245 App. 1991 R Typo in Withdrawn n/a

Nuclear Material Control inml 245 -ANSI N1 5.2 vs15.2

0557 ANSI ANSINi 5S Guide to Practice Nuclear Material inm 245 App. B 1991 R Typo in Withdrawn n/a

Control Systems for Conversion inm 1245 -

Facilities ANSI N15.4 vs15.4

0558 ANSI ANSI N15.5 N/S Statistical Terminology and inm1245 App. B 1991 R Withdrawn n/a

Notation for Nuclear Materials

Management ___ -

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Rcord Stadard D ALtst Standard Lat st Version

N .C od ae ': S a dar eso Tilao u en ~ ablility Co mnm ents ~ Version Date4

0559 ANSI ANSI Ni 5.5 1972 Statistical Terminology and reg5.3.rOO 1974 P With Withdrawn n/a

Notation for Nuclear Materials clarification

Management

0560 ANSI ANSI N1 5.6 1972 Analytical Procedures for reg5.4.rOO 1973 A Standard was Not found n/a

Accountability of Uranium transferred to

Tetraflouride ASTM in 1975

0561 ANSI ANSI N 15.7 N/S Analytical Procedures for inm1245 App. B 1991 R Typo in Not found n/a

Accountability of Uranium inm 245 -

Hexaflouride ANSI N15.7 vs15.7.Standard wastransferred toASTM in 1975

0562 ANSI ANSI N15.7 1972 Analytical Procedures for reg5.4.rOO 1973 P Standard was Not found n/a

Accountability of Uranium transferred to

Hexaflouride ASTM in 1975

0563 ANSI ANSI N15.8 N/S NuclearMaterialControlSystems ini1245 App. B 1991 R Typo in Withdrawn n/a

for Nuclear Power Plants inm 245 -ANSI N15.8 vs15.8 _

0564 ANSI ANSI N15.8 1974 Nuclear Material Control Systems reg5.29.rOl 1975 A Withdrawn n/a

for Nuclear Power Plants

0565 ANSI ANSI N/S Nuclear Materials - Unirradiated inm1245 App. B 1991 R Typo in ANSI N15.10 1987

N15,10 Plutonium Scrap - Classification inm1245 -ANSI N15,10vs 15.10

Codes and Standards- and Other Guidance Cited in Regulatory Documents


ReodStandatd ic. Acp~Latet Standard Ltkes Versio

No. Code" Standi f Veisrlo Ttle Document Date. ailit o vment Vero Date

0566 ANSI ANSI N/S Assessment of the Assumption of inm1245 App. B 1991 R Typo in ANSI N1 5.15 1974 R81

N1 5.15 Normality (Employing Individual inm1245 -

Observed Values) ANSI N1 5.15vs 15.15

0567 ANSI ANSI 1974 Assessment of the Assumption of regl.126.rOl 1978 R ANSI Ni5.15 1974 R81

N15.15 Normality (Employing Individual

Observed Values)

0568 ANSI ANSI 1973 Assessment of the Assumption of reg5.22.r00 1974 P ANSI N15.15 1974 R81

N15,15 Normality (Employing IndividualObserved Values)

0569 ANSI ANSI N/S Limit of Error Concepts and inm1 245 App. B 1991 R Withdrawn n/a

N1 5.16 Principles of Calculation in Nuclear

Materials Control

0570 ANSI ANSI N/S Limit of Error Concepts and reg5.18.rO0 1974 P With Withdrawn n/a

N15.16 Principles of Calculation in Nuclear exceptions

Materials Control

0571 ANSI ANSI 1974 Limit of Error Concepts and reg5.28.r00 1974 R Withdrawn n/a

N15.16 Principles of Calculation in NuclearMaterials Control

0572 ANSI ANSI N/S Concepts and Principles for the inm1245 App. B 1991 R Withdrawn n/a

N1 5.17 Statistical Evaluation of Shipper-Receiver Differences in theTransfer of Special NuclearMaterials

0573 ANSI ANSI 1974 Concepts and Principles for the reg5.28.rO0 1974 P With Withdrawn n/a

N1 5.17 Statistical Evaluation of Shipper- exceptionsReceiver Differences in theTransfer of Special NuclearMaterials

0574 ANSI ANSI N/S Nuclear Materials - Mass inm 245 App. B 1991 R ANSI N15.18 1988

N1 5.18 Calibration Techniques for Control

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Recddard D A 'st Stindard LaDest ;ersiDt

N o o eS ta~n d ard ~ . V er si o n l- i leD o u m n D a t e . ab l t C m e t sV s o nD t

0575 ANSI ANSI NIS Nuclear Materials - Mass reg5.48.rOO 1975 R ANSI Ni5.18 1988

Ni 5.18 Calibration Techniques forControl

0576 ANSI ANSI 1975 Nuclear Materials - Mass reg5.58.rOl 1980 R ANSI Ni5.18 1988

N15.18 Calibration Techniques forControl

0577 ANSI ANSI N/S Nuclear Materials Control - inm1245 App. B 1991 R Typo in ANSI N15.19 1989

N1 5.1 9 Volume Calibration Techniques inm 245 -ANSI N15.19vs 15.19

0578 ANSI ANSI N/S Nuclear Materials Control - reg5.48.rOO 1975 R ANSI N1 5.19 1989

N1 5.19 Volume Calibration Techniques

0579 ANSI ANSI 1975 Nuclear Materials Control - reg5.58.rOl 1980 R ANSI N15.19 1989

N15.19 Volume Calibration Techniques

0580 ANSI ANSI N/S Guide to Calibrating inm1245 App. B 1991 R ANSI N15.20 1975 R87

Ni15.20 Nondestructive Assay Systems

0581 ANSI ANSI 1975 Guide to Calibrating reg5.11.rO1 1984 R Endorsed by ANSI N15.20 1975 R87

N1 5.20 Nondestructive Assay Systems Reg Guide5.53

0582 ANSI ANSI 1975 Guide to Calibrating reg5.34.rOl 1984 R Endorsed by ANSI Ni 5.20 1975 R87

N1 5.20 Nondestructive Assay Systems Reg Guide5.53

0583 ANSI ANSI 1975 Guide to Calibrating reg5.38.rOl 1983 - A N SI N15.20 1975 R87

N15.20 Nondestructive Assay Systems

0584 ANSI ANSI 1975 Guide to Calibrating reg5.53.rOl 1984 P With ANSI N15.20 1975 R87

N15.20 Nondestructive Assay Systems supplementalconditions

0585 ANSI ANSI 1975 Guide to Calibrating reg5.58.rO1 1980 R ANSI Ni5,20 1975 887

N1 5.20 Nondestructive Assay Systems



Record Sta ndrd b Doe. Aiept Lates Siandard Latett dersionNo coda Standard V .rVersion> Trtl Dcmn Dt a.lt C e Ve-o iate'

0586 ANSI ANSI 1975 Guide to Calibrating reg5.9.rO2 1983 R Endorsed by ANSI N 65.20 1975 R87

N15.20 Nondestructive Assay Systems Reg Guide5.53

0587 ANSI ANSI N/S Nuclear Materials Management - inml245 App. B 1991 R ANSI N1 5.51 1990

N15.51 Measurement Control Program -Nuclear Materials AnalyticalChemistry Laboratory

0588 ANSI ANSI N16.1 1975 Nuclear Criticality Safety in inm88020 N/S R ANS 8.1 1983 R88


0589 ANSI ANSI N16.1 1969 Nuclear Criticality Safety in reg3.33.rOO 1977 R ANS 8.1 1983 R88


0590 ANSI ANS1 N16.1 1975 Nuclear Criticality Safety in reg3.34.rOl 1979 R ANS 8.1 1983 R88


0591 ANSI ANSI N16.1 1975 Nuclear Criticality Safety in reg3.35.rOl 1979 R ANS 8.1 1983 R88


0592 ANSI ANSI N16.1 1975 Nuclear Criticality Safety in reg3.4.rO2 1986 R ANS 8.1 1983 R88


0593 ANSI ANSI N16.1 1975 Nuclear Criticality Safety in reg3.47.rOO 1981 R ANS 8.1 1983 R88


0594 ANSI ANSI N16.1 1975 Nuclear Criticality Safety in stswstB3.7.16 1992 R ANS 8.1 1983 R88


0595 ANSI ANSI N16.1 1975 Nuclear Criticality Safety in stswstB3.7.17 1992 R ANS 8.1 1983 R88

operations with FissionableMaterials Outside Reactors _

0596 ANSI ANSI Ni 6.2 1969 Criticality Accident Alarm System srpl 2.3 1981 P AN- 8.3 1986

_ ___

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Rec stadrdDo. A L-tet tStahdard Latest Version

No. Code Standard VeIrsio Document Date Aity ts Vrsion ... Dcte

0597 ANSI ANSI N16.5 1975 Guide for Nuclear Criticality reg3.43.rO1 1979 P Subject to ANS 8.7 1975 R87

Safety in the Storage of Fissile conditions

Material

0598 ANSI ANSI N16.9 1975 Nuclear Criticality Safety in drgce913-5.rO0 1981 R ANS 8.11 - ANS 8.1 1983 R88

Operations with Fissionable withdrawn and

Materials Outside Reactors incorporatedinto ANS 8.1

0599 ANSI ANSI N16.9 1975 Nuclear Criticality Safety in inm88015 N/S R ANS 8.11 - ANS 8.1 1983 R88



0600 ANSI ANSI N`16.9 1975 Nuclear Criticality Safety in reg3.4.r02 1986 R ANS 8.11 - ANS 8.1 1983 R88



0601 ANSI ANSI N16.9 1975 Nuclear Criticality Safety in reg3.47.rOO 1981 R ANS 8.11 - ANS 8.1 1983 R88



0602 ANSI ANSI N16.9 1975 Nuclear Criticality Safety in reg3.53.rOO 1982 R ANS 8.11 - ANS 8.1 1983 R88



0603 ANSI ANSI N18.1 1971 Selection, Qualification, and cir80-21 1980 P General ANS 3.1 1993

Training of Personnel for Nuclear endorsement

Power Plants

0604 ANSI ANSI N18.1 1971 Selection, Qualification and cir81-07 1981 A Endorsed by ANS 3.1 1993

Training of Personnel for Nuclear Reg Guide 1.8

Power Plants Rev 1



No oditadr Vrld itODcuiht Dt Abdi..t.. .Commnts VerionDat

0605 ANI ANSI N 18.1 Nis Selection, Qualification and drgrs902-4.r00 1980 R Proposed ANS 3.1 1993

Training of Personnel for Nuclear regil.3.r03

Power Plants

0606 ANS ANSI N 18.1 -N/S Selection, Qualification and g1t79-025 1979 R ANS 3.1 1993


Power Plants _________

0607 ANSI AN S-I N1 ST 1971 Selection, Qualification and inm 1245 App. B 1991 R ANS 3.1 19


Power Plants -- 19

00 ANI ASN8. 191 Selection, Qualification and n371 19 ANS 3.1 19

0608 ANSI ANI N18.1 1 01 Training of Personnel for Nuclear 371 92 R

Power Plants n 331 1 6 R------A S3193

0-6609 ANI AS N`18.1 N/S Selection, Qualification and in301 196 BAS3193Training of Personnel for Nuclear

--- Power Plants _______19 2_____3_1199

0610 ANI ANSI N1 8.1 1971 Selection, Qualification and im70 92 RAS3119Training of Personnel for Nuclear

Power Plants 1992____1993

0611 ANI ANSI Ni 8.1 1971 Seeton, Qualification and im00 92 RAS3119Training of Personnel for NuclearPower Plants ______

0612 ANI AS 1. / eetoQualification and inm56700 N/S BAS3119Training of Personnel for Nuclear

Power Plants I_____-___

_____ .. 4 I,.A7flA I hI *R1 R ANS 3.1 1993

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03 131 4

ANSI

ANSI

ANSI N10.1 N/5Training of Personnel for Nuclear

I --

____ __ I 11-owerr rian s I------ , t-A -N- 3.1 T1 1 i993- -- -.. ~ I n m oa- - -v IoANSI N18.1 1971

Training of Personnel for NuclearInmol/vI i UV. I I

-- I -rw r t n - -..A T i I ' RR It A N S 3.1 1 9 9 3515

M

ANSI ANSI N18.1 1 9 11Training of Personnel for Nuclear

P__ _ _ _ Iow er Plan ts I:tO~ A ) I i Q I A S 3 1 9 31, - - II - ... 1- - - . .... 1 i4- -- T -I A0 3 3 A

3b e l e c ti o n , if : -aQiri

IA

ANSI ANSI N18.1 1977Training of Personnel for Nuclear

111111V�'V- I -- -

I

L I I__ _ _ _ _ _ I _ _ _ _ _ _ _ P o w e r F l a n ts J- - I__ _ _ _ _ _ _ - a_ _ _ __I_ _I

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Reeord St ndad .- . D. . Aecpt L e -Standa d Latest Version

- No. Code i Standard.: Version . Tite m *.. Dete abtlity; Vea

0617 ANSI ANSI N18.1 1971 Selection, Qualification and inm82102 1993 R ANS 3.1 1993Training of Personnel for NuclearPower Plants





0622 ANSI ANSI N18.1 1971 Selection, Qualification and inm83522 1991 - ANS 3.1 1993Training of Personnel for NuclearPower Plants

0623 ANSI ANSI N18.1 1977 Selection, Qualification and inm83522 1991 _ ANS 3.1 1993Training of Personnel for NuclearPower Plants

0624 ANSI ANSI N18.1 1971 Selection, Qualification and inm83523 1984 - ANS 3.1 1993Training of Personnel for NuclearPower Plants




0628 ANSI ANSI N18.1 1977 Selection, Qualification and inm83723 1991 R ANS 3.1 1993Training of Personnel for NuclearPower Plants _ _ _



Record tedrd Do. Acp~Lbteit Standard Lates: VersionX o. Code Standard Vrs TItle Dc nt ae ily omments'.. Ve.o Dat MO

0629 ANSI ANSI N18.1 N/S Selection, Qualification and inm88025 N/S R ANS 3.1 1993


0630 ANSI ANSI N1 8.1 1971 Selection, Qualification and reg1.8.r02 1987 P Revised as ANS 3.1 1993

Training of Personnel for Nuclear ANS-3.1-1981

Power Plants someendorsements

0631 ANSI ANSI N18.1 N/S Selection, Qualification and srpl3.1.1 1981 P Section 4.6.1 ANS 3.1 1993


0632 ANSI ANSI N18.1 N/S Selection, Qualification and srpl 3.1.2 1989 P Section 3.2, 4, ANS 3.1 1993

Training of Personnel for Nuclear and some

Power Plants exceptions,

0633 ANSI ANSI N18.1 1971 Selection, Qualification and srp 3.2.1 1981 P Endorsement ANS 3.1 1993

Training of Personnel for Nuclear implied

Power Plants

0634 ANSI ANSI N18.1 N/S Selection, Qualification and srpl 3.4 1981 P Section 4.4 ANS 3.1 1993


0635 ANSI ANSI N18.2 N/S Nuclear Safety Criteria for the pol57FR22495 1987 R ANS 51.1 1983 R88

Design of Stationary PressurizedWater Reactor Plants

0636 ANSI ANSI N18.2 N/S Nuclear Safety Criteria for the pol52FR3788 1987 R ANS 61.1 1983 R88


0637 ANSI ANSI N18.2 N/S Nuclear Safety Criteria for the polpr390 1993 R ANS 51.1 1983 R88


0638 ANSI ANSI N1 8.2 1974 Nuclear Safety Criteria for the srpl 5 .2.1 1981 R ANS 51.1 1983 R88


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i R ec o rd et a n d a r d D o c . A ceit- L a t e s t S t a ndt. a t e sti;e rto

No. Code Standard rsich Ti. Documen D ilIt Comfents Vatsin Dite

0639 ANSI ANSI N18.2 1974 Nuclear Safety Criteria for the srpl 5.2.6 1981 R ANS 51.1 1983 R88


0640 ANSI ANSI N18.2 1974 Nuclear Safety Criteria for the srpl 5.2.7 1981 R ANS 51.1 1983 R88


0641 ANSI ANSI N18.2 1974 Nuclear Safety Criteria for the srpl5.3.1 1981 R ANS 51.1 1983 R88


0642 ANSI ANSI N18.2 1974 Nuclear Safety Criteria for the srpl5.5.1 1981 R ANS 51.1 1983 R88


0643 ANSI ANSI N18.2 1974 Nuclear Safety Criteria for the srp15.6.1 1981 R ANS 51.1 1983 188


0644 ANSI ANSI N18.2 1973 Nuclear Safety Criteria for the stsb&wB3.2.4 1992 R ANS 51.1 1983 R88


0645 ANSI ANSI N18.3 1972 Fuel Assembly Identification reg5.1.rOO 1972 P Special ANS 57.8 1995conditionsrequire furtheridentificationmeasures

0646 ANSI ANSI N18.5 1974 Earthquake Instrumentation drgms140-5.r00 1981 P Proposed ANS 2.2 1988

Criteria for Nuclear Power Plants regi1.1 2.rO2

0647 ANSI ANSI N1 8.5 NIS Earthquake Instrumentation reg1.1 2.rOl 1974 P Subject to ANS 2.2 1988

Criteria for Nuclear Power Plants conditions



- .D .e .

S Latest Vrs ion

0No. Cod, Standard V ors:o Titl fiDocment D a .il ity Commenis io Dte

0648 ANSI ANSI N18.7 N/S Administrative Controls and admin95-06 1995 R ANS 3.2 1994


0649 ANSI ANSI N18.7 N/S Administrative Controls and cir80-O2 1980 R ANS 3.2 1994


0650 ANSI ANSI N1 8.7 1976 Administrative Controls and drgrs902-4.rOO 1980 P Proposed ANS 3.2 1994

Quality Assurance for the regl.3.rO3


0651 ANSI ANSI N18.7 1972 Administrative Controls and drgrs9O2-4.rOO 1980 R Proposed ANS 3.2 1994

Quality Assurance for the regl.3.rO3


0652 ANSI ANSI N1 8.7 1976 Administrative Controls and git83-028 1983 R ANS 3.2 1994


0653 ANSI ANSI N18.7 1972 Administrative Controls and inm-toc 1995 R ANS 3.2 1994


0654 ANSI N18.7 1977 Administrative Controls and inm-too 1995 R ANS 3.2 1994


0655 ANSI ANSI N18.7 1976 Administrative Controls and inml 245 App. B 1991 R ANS 3.2 1994


0656 ANS ANSI N18.7 1972 Administrative Controls and inm2515106 5 1990 R ANS 3.2 1994


Ch

z

C-)

~V

-IVi

z

\0-1

W



Record St Andeid -. . SL e St andard L t a Version

N o o eS a d a rd ' V a st j K i le' ,o u m t D t ' a b it . C m m en ts V e s o n D a t e :

0657 ANSI ANSI N18.7 1976 Administrative Controls and inm35701 1992 R ANS 3.2 1994

Quality Assurance for the


0658 ANSI ANSI N1 8.7 1976 Administrative Controls and inm35740B 1979 R ANS 3.2 1994


0659 ANSI ANSI N18.7 1976 Administrative Controls and inm35741 B 1979 R ANS 3.2 1994






0661 ANSI ANSI N18.7 1976 Administrative Controls and inm35743B 1982 R ANS 3.2 1994













Operational Phase of Nuclear

Power Plants



ReodStan'dadD Accet Laet Standard Lates Versionicod St. V n .D..ument Dat 0 X ' n 'e: ablt C n Ve_,ion Date

0666 ANSI ANSI N18.7 N/S Administrative Controls and inm37001 1992 R ANS 3.2 1994




0668 ANSI ANSI N18.7 1976 Admninistrative Controls and inm37551 1994 R Typo in ANS 3.2 1994

Quality Assurance for the inm37551 -

Operational Phase of Nuclear ANSI vs. ANS

Power Plants



0670 ANSI ANSI N18.7 1976 Administrative Controls and inm37702 1987 R AN$ 3.2 1994


0671 ANiS ANSI N18.7 1976 Administrative Controls and inm37703 1992 R ANS 3.2 1994


0672 ANSI N8.7 1976 Administrative Controls and inm37828 1988 R ANS 3.2 1994






zC)

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z

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Codes and Standards and Other Guidance Cited in RegulatoryDocumentsPart A - Industry Consensus Codes and Standards

.. t . _

R e c r dS t n d r dD o . c c e p t- L a te t S a d a d L e t V e i n

RNo i. Code t lgE Standa -dA tVerIon; Titlet .Dou et Date blity C m t VDo D e .

0675 ANSI ANSI N18.7 1976 Administrative Controls and inm40500 1995 A ANS 3.2 1994


0676 ANSI ANSI N18.7 1976 Administrative Controls and inm40702 1992 _ ANS 3.2 1994




0678 ANSI ANSI N1 8.7 1976 Administrative Controls and inm40704 1992 ANS 3.2 1994








0682 ANSI ANSI N18.7 N/S Administrative Controls and inm42451 B 1975 _ ANS 3.2 1994


0683 ANSI ANSI N18.7 N/S Administrative Controls and inm42452B 1975 R ANS 3.2 1994



Part A - Industry Consensus Codes and Standardsr71777 7 I

I IS I . . ..I - .. . . f. .

I':Record-L, .. . ., r r

iNo.0684

WiStanrdard. .' � L , � L '' ' ., r 1 , , � � , " , � � � � � � ! ,� 4 r p . __, ,i ; � : � " , ". � � i � � � � � i � � � � � >' � L , � ,ED Aceebt--.X . A i ;, . S .E

t , r , t , ,r � r ' d tdlLa "est S an a��: �'::: V611 Inii �' ,

atst Verslo, :.1 . ...at ;X~i::.

CodIANSI

r' ,j L

Ir I nitl _ _ _ _ _ _I tD, I ' __IE V j _ -_..__..______Ljr rS--ta- ard erio-n o . ---- -- IANS 3.2 1 1 9 4

Adminisrativ otrANSI N18.7 1976 Administrative Controls and


Operational Phase of Nuclearn .t --t

inun-+2700 I ;Q y ; I .

I____I_ F1ower aMU --- l = R | ANS 3.2 - 1994Administrativ _on

0685 1 ANSI ANSI N18.7 1976 Administrative Controls andQuality Assurance for theOperational Phase of Nuclear

InmTsOVrVU 1 ... 9 I �

_____ Power P-lants I . -+-i 1 *,tN4 19 1 19

0686 I ANSI -ANSI N18.7 N/S Administrative Controls andQuality Assurance for the


inm61700U i 1 Yo n rwlsv w. . _ _ .

______nowro I t"t ANS -1.2 i -- 1994_

0687 t ANSI FANSI N18.7 1976 Administrative Controls andQuality Assurance for the


mrno I /253 a Z0.5 n ... -- - - _

I________ j jPower Plants . 7 A 3. 1994_ I .. -. _1ANS 3.2

0688 1 ANSI ANSI N18.7 1976 Administrative Controls and

Quality Assurance for theOperational Phase of Nuclear

Inmoz0 1 U4 1-c> I I

I I 1~Power Plants -I_ ._ _.______ p'ow itS -. - . ITmi 1987 I ANS 3.2 1 1994

Admini~tratI~e v.orros a0689 ANSI ANSI N18.7 N/S Administranive konlrols anou


Operational Phase of Nuclearn_._ _*

irllv I - I F

I rower riants .1 I. lANS 3.2 | 1994m.... 9 I 071._

0690 I ANSI IANSI N18.7 N/S Administrative Controls andQuality Assurance for theOperational Phase of Nuclear

mnmoz 203 1.7p / I I - - - - - -

z

ci

-4Wk

I Irowrr rtams -Aown rt . II A 32 1994Administrative Controls an2d Inm,4134 I

OA9 1 ANSI ANS NI 8.7 1976 Administrative Controls andQuality Assurance for theOperational Phase of Nuclear

nAAA l 0n.A

Jnm 1V0 I I -0

I --- o -----96 A inist aive C 1ot 3rs2 i 1oIn TX uu Z I AN 32 19

0692 'ANSI ANSI N18.7 1 976 Administrative Controls andQuality Assurance for theOperational Phase of Nuclear

If If I I I V';lxj 4 I - I .

I

._I I_ JPower Plants A I j 1II

Wj

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00

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6i Mc " R,! , C .nar : a st e lo.=.::.:i0 0 ; 7:~.5i: :aRecord -St adatd Doc. ept La Stand rdM L Ves.ion

No. Code Standard Version T:TlM Document Datelability Commnent Vs Date0693 ANSI ANSI N18.7 1976 Administrative Controls and inm70370 1987 R ANS 3.2 1994


0694 ANSI ANSI N18.7 1976 Administrative Controls and inm71302 1983 R ANS 3.2 1994Quality Assurance for theOperational Phase of NuclearPower Plants

0695 ANSI ANSI N18.7 N/S Administrative Controls and inm72300 1982 R ANS 3.2 1994Quality Assurance for theOperational Phase of NuclearPower Plants

0696 ANSI ANSI N18.7 N/S Administrative Controls and inm72400B 1976 R ANS 3.2 1994Quality Assurance for theOperational Phase of NuclearPower Plants

0697 ANSI ANSI N18.7 N/S Administrative Controls and inm72502B 1975 R ANS 3.2 1994Quality Assurance for theOperational Phase of NuclearPower Plants

0698 ANSI ANSI N18.7 N/S Administrative Controls and inm725708 1975 R ANS 3.2 1994Quality Assurance for theOperational Phase of NuclearPower Plants






RcoLrd Satestandard L Version

N. code Standald VssurancTite Drouent DttV Dat


Quality Assurance for theOperational Phase of NuclearPower Plants_______

0703 ANSI ANSI N18.7 1972 Administrative Controls and inm990015.1.5 1986 R ANS 3.2 1994


0704 ANSI ANSI Ni 8,7 1976 Administrative Controls and inm9900/5.2. 7 1977 R ANS 3.2 1994


0705 ANSI ANSI N18.7 1976 Administrative Controls and inm9900/6,5.1 1980 R ANS 3.2 1994Quality Assurance for theOperational Phase of NuclearPower Plants

0706 ANSI AN N18.7 1972 Administrative Controls and inm9900/B 1977 R ANS 3.2 1994




0708 ANSI ANSI N18.7 1976 Administrative Controls and inm9900/OPS 1991 R ANS 3.2 1994


070 ANSI ANSI N18.7 1976 Administrative Controls and not79- 5 1979 R Endorsed by ANS 3.2 1994

Quality Assurance for the Reg. Guide

Operational Phase of Nuclear 1.33

Power Plants

0710 ANSI ANSI N1 8.7 1972 Administrative controls and not84-51 1984 R Partial ANS 3.2 1994

Quality Assurance for the endorsement

Operational Phase of Nuclear by Reg Guide

Power Plants ______ 1.33 _____

z

(!h

CD

W

z

q)

(Ith

~0


R e c rd. S t da i;. A cce t- t.....t . Stand a d IL te VersioC

eNo. Code . tndr rs or it ocment I Date a t C

0711 ANSI ANSI N18.7 1976 Administrative Controls and not85-66 1985 P Typo - ANSI ANS 3.2 1994

Quality Assurance for the N8.7 is not a

Operational Phase of Nuclear valid ANSI

Power Plants standard.ANSI N18.7assumed.

0712 ANSI ANSI N18.7 N/S Administrative Controls and nureg0737 1980 _ ANS 3.2 1994

Quality Assurance for theOperational Phase of NuclearPoWer Plants

0713 ANSI ANSI N18.7 1972 Administrative Controls and regl.33.r02 1978 R ANS 3.2 1994


0714 ANSI ANSI N18.7 1976 Administrative Controls and regl.33.r02 1978 P Subject to ANS 3.2 1994

Quality Assurance for the conditionsOperational Phase of NuclearPower Plants

0715 ANSI ANSI N18.7 N/S Administrative Controls and srpl3.1.2 1989 P Sections 3.4, ANS 3.2 1994

Quality Assurance for the 4.4, and 5.2

Operational Phase of Nuclear endorsed by

Power Plants Reg Guide1.33

0716 ANSI ANSI N1 8.7 N/S Administrative Controls and srpl 3.4 1981 P Section 4,3, ANS 3.2 1994

Quality Assurance for the 4.4


0717 ANSI ANSI N1 8.9 1972 Program of Testing Biological reg2.1.rOM 1973 P Subject to ANS 6.3.1 1987

Shielding in Nuclear Reactor conditions

Plants0718 ANSI ANSI N/S Security for Nuclear Power Plants bu179-016 1979 P ANSI N1 8.17 Withdrawn n/a

N18,17 withdrawn1992



ReodSanaDC. A'ccept' Latesit Stanidatd LatestVersion

No oe standard VriniteDocUment: iDatiei: biit ComnS Vesoata

0719 ANSI ANSI 1973 Security for Nuclear Power Plants cir78-1 7 1978 R ANSI N18.17 Withdrawn n|a

N18.17 withdrawn1992

0720 ANSI ANSI 1973 Security for Nuclear Power Plants cir79-03 1979 8 ANSI N1 8.17 Withdrawn n/a

N 18.17 withdrawn1992

0721 ANSI ANSI N/S Security for Nuclear Power Plants drgrs9O2-4.rOO 1980 P ANSI N18.17 Withdrawn nia


0722 ANSI ANSI N/S Security for Nuclear Power Plants glt79-016 1979 R ANSI N18.17 Withdrawn n/a


0723 ANSI ANSI N/S Security for Nuclear Power Plants not83-t 5 1983 - ANSI N18.17 Withdrawn n/a

N 18.17 withdrawn1992

0724 ANSi ANSI N/S Security for Nuclear Power Plants not88-91 1988 R ANSI N18.17 Withdrawn n/a


0725 ANSI ANSI 1973 Security for Nuclear Power Plants regl.70.rO3 1978 P ANSI N18.17 Withdrawn n/a

N1 8.17 withdrawn1992

0726 ANSI ANSI N/S Security for Nuclear Power Plants srpl 3.6 1981 P ANSI N18.17 Withdrawn n/a


0727 ANSI ANSI N41.2 N/S Standard Application of the Single reg .53.rOO 1973 R Alternate title IEEE 379 1994

Failure Criterion to Nuclear Power for IEEE 379

Generating Station Safety

Systems _ ___ _

zrC1

U)

~0

-4



Re odSa d r Oc Acept- L altest Standard Latest V ersion

No'. co eSld r e so n"~l D o cuM ent Da e ability co e tsV r i nD e

0728 ANSI ANSI N41.6 1972 Standard for Qualification of reg.73.rOO 1974 A Subject to IEEE 382 1985

Actuators for Power Operated conditions

Valve Assemblies With Safety-Related Functions for Nuclear

Power Plants ------

0729 ANSI ANI tandard for Qualification of srp3.1 0 1981 _ . IEEE 382 1985

Draft Actuators for Power OperatedValve Assemblies With Safety-Related Functions for NuclearPower Plants _ _ _ _ _ _

ANSI ANSI 1975 St for T T f drgrsO5O-2.rOO 1979 R Proposed IEEE 383 1974 R92

N41.10 1 E Electric Cables, Field Splices, regl.131.rOland Connections for NuclearPower Generating Stations

0731 ANSI ANSI 1975 Standard for Type Test of Class reg1.131.rOO 1977 R Historical IEEE 383 1974 R92

N41.10 1 E Electric Cables, Field Splices, development

and Connections for Nuclear cited

Power Generating Stations

ANSI ANSI N/S Standard Criteria for regl.75.r02 1978 P With IEEE 384 1992

N41.14 independence of Class 1 E exceptionsEquipment and Circuits

0733 ANSI ANSI 1976 IEEE Recommended Practice for reg1.129.rO1 1978 R Historical IEEE 450 1995

N41.15 Maintenance, Testing, and development

Replacement of Vented Lead-Acid cited

Batteries for Stationary

A pplications ------__ ____ _ __ _ __ _

_.,-.i _., e _l i 1 Q7A R 1 Historical IEEE 484 19871 9 / b ~ ~~~ .ic m m n e .c u ~0734 ANSI ANSI

N41.241976 Recommended Practice lor

Installation Design and Installation

of Large Lead Storage Batteries

for Generating Stations andSubstations

,.WI .I .1, . v , v . .

developmentcited

I I I I I I _ _ _ I I_ _ E ---

__ _ __ _ _ . . ~ ... t.... i - I-I IE 309- -19/ -t- -I 1_ 0 . .__. C T _n__ .. l 2 l A n 1,fiARa 1 7 r I .Q _ IlEEE 309 19r HYJ/ 1il -1 9 6 9 ~ ~ ~~~~ _e s _rc a r _o e g r - v u I

------0735

1

At�ISI ANSI N42.3 1969 i est Procedure Tor Geiger-Muelle, I ego.,U.l Vu , A} I - ,5

- I I j u o u i u e rs I I . . . . . . ~ - I.1 _ _ _ _ _ _ _ .



.no d - . .. ... :Cd. .. . . ....... r. .- A- , n..*.:. k.R'c-dSt nad - cc "Acept LtsStdadLesVrio

0736 ANSI ANSI N42.3 1969 Test Procedure for Geiger-Mueller srpl2.5 1981 P As relates in IEEE 309 1970 R91

Counters acceptancecriteria

0737 ANSI ANSI N42.7 1972 Criteria for Safety Systems for drg1042,rOO 1995 R IEEE 603 1991

Nuclear Power GeneratingStations

0738 ANSI ANSI N42.7 1972 Criteria for Safety Systems for inm1245 App. B 1991 R IEEE 603 1991

Nuclear Power GeneratingStations____

___

0739 ANSI ANSI N42.7 1972 Criteria for Safety Systems for nuregO933, 1992 R ANSI N42.7 IEEE 603 1991

Nuclear Power Generating 3.156 also designated

Stations IEEE 279

0740 ANSI ANSI N42.7 1972 Criteria for Safety Systems for nuregO933, 3.50 1984 R ANSI N42.7 IEEE 603 1991

Nuclear Power Generating also designated

Stations IEEE 279

0741 ANSI ANSI N42.7 1972 Criteria for Safety Systems for nuregO933, 3.64 1983 R ANSI N42.7 IEEE 603 1991

Nuclear Power Generating also designated

Stations IEEE 279

0742 ANSI ANSI N42.7 1972 Criteria for Safety Systems for reg1.153.rOO 1985 P Implies IEEE 603 1991

Nuclear Power Generating endorsement

Stations by1 OCFR50.55a

0743 ANSI ANSI N42.7 1972 Criteria for Safety Systems for reg1.47.rOO 1973 R IEEE 603 1991

Nuclear Power GeneratingStations _ _ _ _ _ _ _

0744 ANSI ANSI N42.7 1972 Criteria for Safety Systems for regl.53.rOO 1973 R IEEE 603 1991


0745 ANSI ANSI N42.7 1972 Criteria for Safety Systems for regl .75.rO2 1 978 Alternate title IEEE 603 1991

Nuclear Power Generating of IEEE 279-

Stations 1971 _ _

zci

U'

Z

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-4



0746 ANSI ANSI N42.7 N/S Criteria for Safety Systems for reg2.2.rOO 1973 R IEEE 603 1991


0747 ANSI ANSI N42.7 1972 Criteria for Safety Systems for srp3.121 1981 R IEEE 603 1991


0748 ANSI ANSI N/S Calibration and Usage of Sodium inm1245 App. B 1991 R Typo in IEEE N42.12 1994

N42.12 Iodide Detector Systems for inm1245 -

Assay of Radionuclides ANSI N42.12vs 42.12

0749 ANS ANSI 1980 Calibration and Usage of Sodium reg13.8.r02 1987 R IEEE N42.12 1994

N42.12 Iodide Detector Systems forAssay of Radionuclides

0750 ANSI ANSI 1978 Calibration and Usage of Dose drgfc410-4.rOO 1985 R IEEE N42.13 1986 R93

N42.13 Calibrator Ionization Chambers forthe Assay of Radionuclides

0751 ANSI ANSI 1985 Calibration and Usage of Dose reg1O.8.r02 1987 R IEEE N42.13 1986 R93

N42.13 Calibrator Ionization Chambers forthe Assay of Radionuclides

0752 ANSI ANSI N/S Calibration and Use of Germanium inm1245 App. B 1991 R Typo in IEEE N42.14 1991

N42.14 Spectrometers for the inm1245 -

Measurement of Gamma-Ray ANSI N42.14

Emission Rates of Radionuclides vs 42.14

0753 ANSI ANSI 1978 Calibration and Use of Germanium reg4.15.rOl 1979 R IEEE N42.14 1991

N42.14 Spectrometers for theMeasurement of Gamma-RayEmission Rates of Radionuclides



ReodStandrd o. Acp aetSadard Latest VesL

No- Cod . Standard TVerWin Title Document D iae ability -Comment| Verion | D

0754 ANSI ANSI N/S Performance Verification of Liquid- inm1 245 App. B 1991 R Typo in IEEE N42.1 5 1990

N42.15 Scintillation Counting Systems inm 245 -ANSI N42.15vs 42.15

0755 ANSI ANSI 1980 Performance Verification of Liquid- reg1 0.8.r02 1987 R IEEE N42.15 1990

N42.15 Scintillation Counting Systems

0756 ANSI ANSI N/s Performance Specifications for inm 245 App. B 1991 R IEEE N42.17A 1989

N42.17 Health Physics Instrumentation-Portable Instrumentation for Use

in Normal EnvironmentalConditions

0757 ANSI ANSI N/S Performance Specifications for nuregO933, 1987 R IEEE N42.17A 1989

N42.1 7 Health Physics Instrumentation- 1.111.D.3

Portable Instrumentation for Usein Normal EnvironmentalConditions

0758 ANSI ANSI N/S Performance Specifications for not90-44 1990 R IEEE N42.1 7A 1989

N42.17A Health Physics Instrumentation-Portable Instrumentation for Use

in Normal EnvironmentalConditions

0759 ANSI ANSI N/S Specification and Performance of inmi 245 App. B 1991 R IEEE N42.18 1980 R91

N42.18 On-Site Instrumentation forContinuously MonitoringRadioactivity in Effluents


N42. 18 On-Site Instrumentation for redesignated


z

0�v(�h\0-4w

�vI

w

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'0

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R ec o rd t D o d.,." AC C L t t S L a es V ersio n

No. Code Standarid e Tit Dat l Version Datei

0761 ANSI ANSI 1980 Specification and Performance of inm84523 1984 R ANSI N1 3.10 IEEE N42.18 1980 R91




N42,18 On-Site Instrumentation for redesignatedContinuously MonitoringRadioactivity in Effluents





0765 ANSI ANSi 1980 Specification and Performance of reg4.16.rOl 1985 R ANSI N13.10 IEEE N42.18 1980 R91


0766 ANSI ANSI N/S Specification and Performance of reg8.37.rOO 1993 P ANSI N13.10 IEEE N42.18 1980 R91


0767 ANSI ANSI N/S Safe Design and Use Panoramic, reglO.10.rOO 1987 R ANSI N43.10 1984

N43.10 Wet Source Storage GammaIrradiators (Category IV)



Recrd tanardDoc Aeep t Laes Stndr Les Vrso

No Cd Standard erio Title:: ~ Document Dite abliy om:et Version. Oat.

0768 ANSI ANSI N/S Safe Design and Use Panoramic, reg 1 0 1 .rmi 1987 R ANSI N43.10 1984

N43.10 Wet Source Storage GammaIrradiators (Category IV)

0769 ANSI ANSI N44.1 1973 Integrity and Test Specifications reg10.1 1.rOO 1987 R ANSI N44.1 1973 R84

for Selected BrachytherapySources

0770 ANSI ANSI N44.1 1973 Integrity and Test Specitications reg10.8.r02 1987 R ANSI N44.1 1973 R84

for Selected BrachytherapySources

0771 ANSI ANSI N44.1 1973 Integrity and Test Specifications reg6.2.rOl 1974 P Subject to ANSI N44.1 1973 R84

for Selected Brachytherapy conditions

Sources__ _ _ _ _ _ ___ _ _ _ _ _

0772 ANSI ANSI N44.2 1979 Leak Testing Radioactive reg10.8.r02 1987 R ANSI N44.2 1973 R84

Brachytherapy Sources

0773 ANSI ANSI N44:2 1973 Leak Testing Radioactive reg6.1.rO1 1974 P Subject to ANSI N44.2 1973 R84

Brachytherapy Sources ____conditions _______

0774 ANSI ANSI N44.3 1973 Thyroid Radioiodine ptake regl0.8.r02 1987 R ANSI N44.3 1973 R84

Measurements Using a NeckPhantom____

___

0775 ANSi ANSI N44.3 1973 Thyroid Radioiodine Uptake reg8.20.r01 1979 R ANSI N44.3 1973 R84

Measurements Using a NeckPhantom

0776 ANSI ANSI N45.2 1971 Quality Assurance Program drgl'O1 O.rOO 1992 R ASME NQA-1 1994Requirements for Nuclear FacilityApplications

0777 ANSI ANSI N45.2 1977 Quality Assurance Program drgl1lO.rOO 1992 R ASME NQA-1 1994Requirements for Nuclear FacilityApplications

0778 ANSI ANSI N45.2 N/S Quality Assurance Program drgce902-5.rOO 1981 R Proposed ASME NQA-1 1994

Requirements for Nuclear Facility reg1.1 3.rO2

Applications ___ _Reureet foula ailt ei..0

C)~

z

'0

-.4

-400



N.o Standar ero T Document Date bii C e V o aVrtie n

-R

ASMr Nucea 199

0780 ANSi ANSI N45.2 N/S Qal~ity Assurance Program inmls 245Ap.rOB 19791 RASEN -194Requirements for Nuclear FacilityA p p l i c a t i o n s _ _ _ _ _ _ _ _ _ _ _ _ _ _

0782 ANSNS I SI N45.2 NiS Quality Assurance Program minm3245.00 B 1979 R ASME NQA-1 1994

Requirements for Nuclear FacilityApplications inm_25_____19 1______Q --- 99

0782 ANSI ANSI N45.2 N/S Quality Assurance Program Inm3500 19 R ASME NQA-1 1994

Requirements for Nuclear Facility

--- Ap- Applications m501B 198 -ASME NQA-1 19940783 ANSI ANSI N45.2 N/S Quality Assurance Program inm3500B 15 RASENA194Requirements for Nuclear FacilityApplications ________

_____-- -inm1.5018B 1975 R ASME NQA-1 1994

0784

0785

0786

0787

I

ANSI AN51 N45.Z N/zv

Requirements for Nuclear Facility..... ------.

I I pplications I__---_______

ANSI ANSI N45.2 N/S for Nuclar inm35020 119::91 R -ASME NOA-19 94


_ _...,,DAAppl;ricaions 18 ASME NQA-1 1994

ANSI IANSI N45.2 NIS euairty Assurance NrogramRequirements for Nuclear Facility

M,11lOD- I . ---

_I __I_-__ _ -. _ .___. I I Cq i R i 1ASME NQA;-1 1994ANSI ANSI N45.2 NIS Quality Assurance Nroura ci

Requirements for Nuclear FacilityII II II O v I- -V-

I_ _ jApplicatons _ . ASME NQA-1 1 1994nmA V ' .o.

0788 1 ANSI IANSI N45.2 N/S Quality Assurance ProgramRequirements for Nuclear Facility

inm,5 /4vvB I :Y I v In

_ __ Applications .I- -A1 1994L~~~~ ~ ~ ~ ~ _. _-

. - iIi.mr n 1 1 9

0789 i ANSI AN-SIN45T2 Quality Assuranc u ProgramRequirements for Nuclear Facility

inm37v51 7Yo/1 n A V } v I i. I w 5,A A .

I I . _ IAppiications I 7 1 IASME NQA-1 9 1994

0790 ANSI ANSI N45.2 N/S Quality Assurance t rrogra cRequirements for Nuclear Facility

1nm 1113 1 vv I ,

. _ - Applications j I ioroI -_ ASME NQA-1 1 994- ~ ~ ~ ~ ~ / Q u ._ a lity A ssurance rrogra mE N b A -j F - -- 19 9

0791 ANSI 1 ANSi N45.2 N/S Quality Assurance ProgramRequirements for Nuclear Facility

Al -- A-r.

IF111101040

1

I---O I I

I .. IjAppllud1u flls -


.V.

Record aStadard l Do0 A Latest Stanida-d Latest V ion

o. code standard ;Version TMitd otmh Dat blt omns VrinDt

0792 ANSI ANSI N45.2 1977 Quality Assurance Program inm38703 1993 R ASME NQA-1 1994

Requirements for Nuclear FacilityApplications

0793 ANSI ANSI N45.2 N/S Quality Assurance Program inm42400B 1976 R ASME NQA-1 1994


Applications ____192_______

0794 ANSI ANSI N45.2 N/S Quality Assurance Program inm49051 1982 R ASME NQA-1 1994Requirements for Nuclear Facility

Applications

0795 ANSI ANSI N45.2 N/S Quality Assurance Program inm50090 1985 R ASME NQA-1 1994


Applications _

0796 ANSI ANSI N45.2 N/S Quality Assurance Program inm51051 1984 R ASME NQA-1 1994Requirements for Nuclear FacilityApplications ________

______

0797 ANSI ANSI N45.2 N/S Quality Assurance Program inm51053 1984 R ASME NQA-1 1994Requirements for Nuclear FacilityApplications

0798 ANSI ANSI N45.2 N/S Quality Assurance Program inm51055 1984 R ASME NQA-1 1994Requirements for Nuclear FacilityApplications _______


__________ Applications

0800 ANSI ANSI N45.2 N/S Quality Assurance Program inm52053 1984 R ASME NOA-1 1994Requirements for Nuclear FacilityApplications


Applications .

0802 ANSI ANSI N45.2 1977 Quality Assurance Program inm700P 1983 R ASME NQA-1 1994


Applications

0803 ANSI ANSI N45.2 1971 Quality Assurance Program inm9900/OPS 1991 R ASENA194Requirements for Nuclear FacilityApplications___________ _____

w

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. .. ......

R cor St ndd Do. A c p-L atestStandard Latest Version

No.- code i Standard erson itle Document Date bilnr0804 ANSI ANSI N45.2 N/S Quality Assurance Program not87-66 1987 R ASME NQA-1 1994


0805 ANSI ANSI N45.2 N/S Quality Assurance Program not88-95 1988 R ASME NQA-1 1994


0806 ANSI ANSI N45.2 1977 Quality Assurance Program not85-66 1985 P ASME NQA-1 1994


0807 ANSI ANSI N45.2 N/S Quality Assurance Program pol52FR38077 1987 R ASME NQA-1 1994


0808 ANSI ANSI N45.2 1977 Quality Assurance Program regl.137.rOl 1979 P implied, ASME NQA-1 1994

Requirements for Nuclear Facility endorsed by

Applications Reg. Guide1.28

0809 ANSI ANSI N45.2 1977 Quality Assurance Program regl.142.rOl 1981 R ASME NQA-1 1994

Requirements for Nuclear Facility____9_Applications

0810 ANSI ANSI N45.2 1971 Quality Assurance Program regl.28.rO3 1985 6 Referenced ASME NQA-1 1994

Requirements for Nuclear Facility previous

Applications endorsements

0811 ANSI ANSI N45.2 1 971 Quality Assurance Program regl. 0.rOO 1972 P Implied ASME NQA-1 1994

Requirements for Nuclear Facility endorsementApplications _

0812 ANSI ANSI N45.2 1971 Quality Assurance Program regl.33.r02 1978 R ASME NQA-1 1994


0813 ANSI ANSI N45.2 1971 Quality Assurance Program regl.54.rOO 1973 P In conjunction ASME NQA-1 1994

Requirements for Nuclear Facility with ANSI

Applications N101.4-1972

_ _ . _ _I



.Record.. tada Do ALatest Stand L Version

No. Code Sta r Vsioni Tttitle Do.-I-nnt Date abili C t Vrs Dt

0814 ANSI ANSI N45.2 1972 Quality Assurance Program reg3.21.rOO 1974 R ASME NQA-1 1994


Applications --_yows______19

0815 ANSI ANSI N45.2 1971 Quality Assurance Program reg3.3.r01 1974 P Typo - was ASME NQA-1 1994

Requirements for Nuclear Facility regO30

Applications ____12Edsb____9

0816 ANSI ANSI N45.2 1977 Quality Assurance Program reg3.53.rOO 1982 R Endorsed by ASME NQA-1 1994

Requirements for Nuclear Facility Reg Guide

Applications Pgm___19 1.28.r02 __________199

0817 ANSI ANSI N45.2 N/S Quality Assurance Program drg1010.rOO 1992 P ASME NQA-1 1994

Series Requirements for Nuclear Facility

Applications ____19______9

0818 ANSI ANSI N45.2 N/S Quality Assurance Program inm2512/13 1984 R ASME NQA-1 1994

Series Requirements for Nuclear Facility

Applications

0819 ANSI N ANSI N45.2 N/S Quality Assurance Program inm35002B 1980 R ASME NQA-1 1994

Series Requirements for Nuclear FacilityApplications ASME_______1994

0820 ANSI ANSI N45.2 NIS Quality Assurance Program inm92720 1992 R ASME NQA-1 1994

Series Requirements for Nuclear FacilityApplications

0821 ANSI ANSI N/S Quality Assurance Program drg1010.rOO 1992 P Endorsed by ASME NQA-1 1994

N45.2.1 Requirements for Nuclear Facility reg1.37

Applications

0822 ANSI ANSI N/S Quality Assurance Program inm350168 1975 R ASME NQA-1 1994

N45.2.1 Requirements for Nuclear FacilityApplications ---- _1994

0823 ANSI ANSI N/S Quality Assurance Program inm35018B 1975 R ASME NQA-1 1994

N45.2.1 Requirements for Nuclear FacilityApplications I

_ ____ ASME NQA-1 1994II

00

z

t-j~

08.

24 ANSI ANSIN45.2.1

N/S euality Assurance lrogra itRequirements for Nuclear FacilityA -- I:o -ti1-

111111OW-. I - I

_ M plvlvalutlo ._ -- -- _

25 -ANSI 1973 Quality Assurance Program inm35743B 1982 R ASME NQA-1 1994

N45.2.1 Requirements for Nuclear FacilityApplications _ I I

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Reco.d tndd daDeC. A e| L atet Standard LatstVsn

N o o e S tan d ard V e s o i l o cu m e t D t a i iC o m n sV erso D ato


N45.2.1 Requirements for Nuclear FacilityApplications



0828 ANSI ANSI 1976 Quality Assurance Program inm62702 1987 R ASME NQA-1 1994


0829 ANSI ANSI N/S Quality Assurance Program regl.33.rO2 1978 R ASME NQA-1 1994

N45.2.1 Requirements for Nuclear FacilityA pplications __ _ _ _ _ _ _ _ _ _ _ _ _ _

0830 ANSI ANSI 1973 Quality Assurance Program reg1.37.rOO 1973 P Subject to six ASME NQA-1 1994

N45.2.1 Requirements for Nuclear Facility supplemental

Applications statements

0831 ANSI ANSI 1973 Quality Assurance Program reg1.70.r03 1978 P Implied ASME NOA-1 1994

N45.2.1 Requirements for Nuclear Facility endorsement

Applications

0832 ANSI ANSI 1973 Quality Assurance Program reg3.37.rOO 1975 A ASME NQA-11994


0833 ANSI ANSI 1973 Quality Assurance Program srp10.3.6 1981 P Implied ASME NOA-1 1994

N45.2.1 Requirements for Nuclear Facility endorsement in

Applications acceptancecriteria

aKll AMKI 171 ualOitv A iuran Proaram isrD4.51 1981 P Implied ASME NQA-1 1994



Recoid 1tndrdDo. "Acice Lats Sgtandard LatestVersion

d No. c . Standard ; V.ri Tit. Document Dte lityi :Cae n ommentse Dat

0837 ANSI ANSI N/S Quality Assurance Program drgce913-5.r00 1981 R Proposed ASME NQA-1 1994

N45.2.2 Requirements for Nuclear Facility reg1.13.rO2

Applications________

0838 ANSI ANSI N/S Quality Assurance Program drgrs9O2-4.rOO 1980 R Proposed ASME NQA-1 1994

N45.2.2 Requirements for Nuclear Facility regl.3.rO3

Applications _______________

0839 ANSI ANSI N/S Quality Assurance Program drgrs908-5.rOO 1979 RF ASME NQA-1 1994


0840 ANSI ANSI N/S Quality Assurance Program inm1245 App. B 1991 R ASME NQA-1 1994

N45.2.2 Requirements for Nuclear Facility__________Applications




N45.2.2 Requirements for Nuclear FacilityApplications_______ - -ASENA194




N45.2.2 Requirements for Nuclear FacilityApplications_____






N45.2.2 Requirements for Nuclear FacilityApplications ________

______

0848 ANSI ANSI N/S alit Assurance Program inm38703 1993 R ASME NQA-1 1994

N45.2.2 Requirements for Nuclear FacilityApplications _

Co

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Recorid Standard ctat Standard Iatest VeXsion

N .c d aS a d r V e s o . T tl Do c u m e ht ' D t b l ty C m e t V e ri o n D at




















N45.2.2 Requirements for Nuclear FacilityApplications__ _ _ _ _ _ _


N45.2.2 Requirements for Nuclear Facility

Applications _

0860 ANSI ANSI N/S Quality Assurance Program inm53051 1984 R ASME NQA-11994



R o rd~~~~~~~~~~~~~.- : .. ... -.....................::..ecr tendirf De Accept' LttSandard Motst Vetslh

9-NHo.' co:.:. . '.Standard E T:iAa s; . - ntle - ? - ;.Document . . .t biity.- Comme.. . ...

0861 ANSI ANSI N/S Quality Assurance Program inm60501 B 1975 R ASME NQA-1 1994

N45.2.2 Requirements for Nuclear FacilityApplications ___ _



0863 ANSI ANSI N/S Quality Assurance Program inm9900/d.E 1982 R ASME NQA-1 1994

N45.2.2 Requirements for Nuclear FacilityApplications _ . .

0864 ANSI ANSI 1972 Quality Assurance Program regl.142.rOl 1981 R ASME NQA-1 1994


0865 ANSI ANSI N/S Quality Assurance Program reg1.33.r02 1978 R ASME NQA-1 1994

N45.2.2 Requirements for Nuclear Facility___.___.___ Applications

0866 ANSI ANSI 1972 Quality Assurance Program regl.38.r02 1977 A Subject to ASME NQA-1 1994

N45.2.2 Requirements for Nuclear Facility conditionsApplications

0867 ANSI ANSI NIS Quality Assurance Program drg1010.r00 1992 P Endorsed by ASME NQA-1 1994

N45.2.3 Requirements for Nuclear Facility regl.39Applications


N45.2.3 Requirements for Nuclear Facility reg1.3.r03Applications

0869 ANSI ANSI N/S Quality Assurance Program drgrs9O8-5.rOO 1979 . ASME NQA-1 1994


0870 ANSI ANSI N/S Quality Assurance Program inm35016B 1975 - ASME NQA-1 1994






00

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0873 ANSi ANSI NIS Quality Assurance Program inm3506t 1985 R ASME NQA-1 1994






Applications


N45.2.3 Requirements for Nuclear FacilityApplications _______



Applications



Applications ____1 8_____19

0879 ANSI ANSI N/S Quality Assurance Program1984 R E NQA-1 1994

N45.2.3 Requirements for Nuclear FacilityApplicatio~ns ---__ _ __ _ _ _ __ _ __ _ _


N45.2.3 Requirements for Nuclear FacilityApplications _______________


N45.2.3 Requirements for Nuclear FacilityApplications ___________199



0883 ANSI ANSI 1976 Quality Assurance Program inm62702 1987 R ASME NOA-1 1994


ApplicationsI___ . .:1tv1 1983 ASME NQA-1 1994

0884 ANSI ANSIN45.2.3

WMb UU611ty /Aziuranmc rroswfa -swev-- { v . .

Requirements for Nuclear FacilityA ---_sr

I I 1 M/ p p iltud iu 1 1 I _ _ _ _ _ _ _ _ _ _ _ _ _ _ I



Record tandar -Doe. Accept- LatstSndard LatestVerslon

oVrso TietorNulear Facilmtn Date atmet erso

0885 ANSI ANSI N/S Quality Assurance Program not82-03 1982 R ASME NQA-1 1994


- __________ ~Applications ______

0886 ANSI ANSI 1973 Quality Assurance Program - reg 1 I42.rO1 1981 R ASME NQA-1 1994

N45.2.3 Requirements for Nuclear FacilityApplications ________

0887 ANSI ANSI NIS Quality Assurance Program regl .33.r02 1978 R ASME NQA-1 1994

N46.2.3 Requirements for Nuclear Facility__________ Applications _______

088 ANSI -ANSI - 1973 Quality Assurance Program regi1.39.r02 1977 P Subject to ASME NQA-1 1994

N45.2.3 Requirements for Nuclear Facility conditions

___ ___ ___ Applications _ _ _ _ _ _ _ _ _ _ _ _

0889 ANSI ANSI N/S Standard Installation, Inspection, drgce913-5.r00 1981 R Proposed IEEE 336 1985 R91

N45.2.4 and Testing Requirements for regi .1 3.r02

Power, Instrumentation, andControl Equipment at NuclearFacilities

0890 ANSI ANSI N/S Standard Installation, Inspection, drgrs902-4.r00 1980 R Proposed IEEE 336 1985 R91

N45.2.4 and Testing Requirements for reg1.3.r03


0891 ANSI ANSI N/S Standard Installation, Inspection, inm1245 App. B 1991 R IEEE 336 1985 R91

N45.2.4 and Testing Requirements forPower, Instrumentation, and

Control Equipment at NuclearFacilities

0892 ANSI ANSI N/S Standard Installation, Inspection, inm35016B 1975 R IEEE 336 1985 R91

N45.2.4 and Testing Requirements forPower, Instrumentation, andControl Equipment at NuclearFacilities

00,-4

z

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t~l-40

z

5X

W

(!A

o9

0000



= i C de .. A. .; ......

Nd o e Sa dad V rin '..q e " ite D c me t ae bliy o me t Ver osio "Ptatee

0893 ANSI ANSI N/S Standard Installation, Inspection, inm35018B 1975 R IEEE 336 1985 R91


0894 ANSI ANSI N/S Standard Installation, Inspection, inm35061 1985 R IEEE 336 1985 R91


0895 ANSI ANSI NIS Standard Installation, Inspection, inm51051 1984 R IEEE 336 1985 R91


0896 ANSI ANSI N/S Standard installation,. Inspection, inm51053 1984 R IEEE 336 1985 R91







Re'or Stbndard DoU ccp- at Stanhdard Latest Vets onNoc~d.. Code . Stndr Veio - Tit Docmnt Date N/S y * .ai .Xta Ver sion ate






N45.2.4 and Testing Requirements forPower Instrumentation andControl Equipment at NuclearFacilities

0902 ANSI ANSI 1972 Standard Installation, Inspection, inm72701 1992 R IEEE 336 1985 R91


0903 ANSI ANSI 1972 Standard Installation, Inspection, regl.30.rOO 1972 P With IEEE 336 1985 R91

N45.2.4 and Testing Requirements for exceptionsPower, Instrumentation, andControl Equipment at NuclearFacilities

0904 ANSI ANSI N/S Standard Installation, Inspection, reg1.33.r02 1978 R IEEE 336 1985 R91


00

zCs

C)!t!n:aUvD~

~0

\0


Record St n D Accept' L atest.Stondard L tet Vrsion

No. CodeSt nda d Versio Tite. Doum ent Datel: bili ents er sion bate

0906 ANSI ANSI NIS Quality Assurance Program drg1010.rOO 1992 P Endorsed by ASME NQA-1 1994

N45.2.5 Requirements for Nuclear Facility reg1.94

Applications

06 NSI A NSi N/S Quality Assurance Program drgce913 -5.rOO 1981 R Proposed ASME NQA-1 1994

N45.2.5 Requirements for Nuclear Facility regl .1 3.rO2Applications _

0907 ANSI ANSI N/S Quality Assurance Program drgrs902-4.rOO 1980 R Proposed ASME NQA-1 1994


0908 ANSI ANSI 1974 Quality Assurance Program drs908-5.rOO 1979 R ASME NQA-1 1994


0909 ANSI ANSI 1978 Quality Assurance Program drgrs908-5.rOO 1979 R ASME NQA-1 1994

N45,2.5 Requirements for Nuclear FacilityApplications

0910 ANSI ANSI N/S Quality Assurance Program in 1245 App. B 1991 R ASME NQA-1 1994


0911 ANSI ANSI N/S Quality Assurance Program inm35018B 1975 R AsME NQA-1 1994


0912 ANSI ANSI NIS Quality Assurance Program inm45051 1984 R ASME NQA-1 1994






0915 ANSI ANSI N/S Quality Assurance Program inm72701 1992 R AsME NQA-1 1994


0916 ANSI ANSI 1974 Quality Assurance Program reg1.142.rOl 1981 P ASME NQA-1 1994




ROOF ..... d.id DCc. Accept' Latent Mtidied Latest Versiont

No. x:N Code tandd V n f T leauent at Fcalbt Coment V on:

0917 ANSI ANSI N/S Quality Assurance Program reg1 .33.r02 1978 R ASME NQA-1 1994


0918 ANSI ANSI N/S Quality Assurance Program reg1.70.rO3 1978 P Implied ASME NQA-1 1994

N45.2.5 Requirements for Nuclear Facility endorsementApplications

0919 ANSI ANSI 1974 Quality Assurance Program regl.94.rOl 1976 P Subject to ASME NQA-1 1994


0920 ANSI ANSI NIS Quality Assurance Program srpl 7.1 1981 R ASME NQA-1 1994

N45.2.5 Requirements for Nuclear FacilityApplications_____________

0921 ANSI ANSI NIS Quality Assurance Program srp3.8.3 1981 P ASME NQA-1 1994


S922 ANSI ANSI N/S Quality Assurance Program drgce13.rOO 1992 P Endorsed by ASME NQA-1 1994

N45.2.6 Requirements for Nuclear Facility regl.58Applications________

0924 ANSI ANSI N/S Quality Assurance Program drgce903-5.rOO 1981 R Proposed ASME NQA-1 1994

N45.2.6 Requirements for Nuclear Facility regl.13.r02

Applications


N45.2.6 Requirements for Nuclear Facility reg1.3.r03

Applications__ _____

0925 ANSI ANSI NIS Quality Assurance Program drgrs9O8-5.rOO 1979 R ASME NQA-1 1994


0926 ANSI ANSI N/S Quality Assurance Program glt8l-001 1981 P Reg. Guide ASME NQA-1 1994

N45.2.6 Requirements for Nuclear Facility 1 .58 endorses

Applications withexceptions

0927 ANSI ANSI N/S Quality Assurance Program inmOO40 1995 R ASME NQA-1 1994


____._______ Applications __ _ _

'.4

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z

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4vt

w



Rec |-d Standard K- Doc4 Acicet-. Lates SrXttdrtersteon

No. ---S-a dar -- rin ~ - ~ Ttl K Dcu~n ae blt o m n VetAl - Date

0928 ANSI ANSI NIS Quality Assurance Program inm 245 App. 8 1991 R ASME NQA-1 1994


0929 Applications inm3901 _ dd 1975_R_____ 1994

0929 ANSI ANSI NIS Quality Assurance Program inm350168B 1975 R ASME NQA-1 1994


Applications im58 17 R. AS___i9

0930 ANSI ANSI NIS Quality Assurance Program inm3501 88 1975 R ASME NQA-1 1994


0931 ANSI ANSI N1/S Quality Assurance Program inm35028B 1975 Ft ASME N(A-1 1994


_ _ _ _ _ _ _ _ __ ____ ___ A p p lic atio n s _ _ _ _ _ _

093 ANSI ANSI N/S Quality Assurance Program inm3063018- 1985 R- ASME NQA-1 1994


Applications ___ __ __ __

0933 ANSI ANSI 1976 Quality Assurance-Program inm35743B 1982 R ASME NQA-1 1994


0939 ANSIANiN/Applications _ inm493 R ASME NQA- 19

0934 ANSI ANSI NIS Quality Assurance Program inm36301 8 197 ASME NQA-1 1994


- -pliaiosASME

NQA-1 1994

0938 ANSI ANSI N/S Quality Assurance Program inm49051 1982 R -N45.2.6 Requirements for Nuclear Facility

Applications _ _ _ _ _ _ _



Applications

0937 ANSI ANSI N/S Quality Assurance Program inm_0l 00 1985 R ASME NQA-1 1994

N45.2.6 Requirements for Nuclear FacilityApplications__ _ _ _ _ _ _

0938 ANSI ANSI N/S Q6uality Assurance Program inm5 1051 1984 Ft ASME NQA-1 1994


0939 ANSI ANSI N/S Quality Assurance Program inm51053 I1984 FtAMN -194


_ _ _ _ _ _ _ _ _ _ A p p lic a tio n s_ _ _ _ _ _ _ _ __ _ _ _ _ _ _



ecord . Standard DOe. Accept- La dar t

;;jNo. Codeto Standard Version Tdtle Dc e Date -bilit Conlont V i Date



0941 ANSI ANSI N/S Quality Assurance Program !nm5105t 1984 R ASME NQA-1 1994




0943 ANSI ANSI N/S Quality Assurance Program inmS 1065 1984 R ASME NQA-1 1994



N45.2.6 Requirements for Nuclear FacilityApplications ___ _





0947 ANSI ANSI N/S Quality Assurance Program inm57050 1983 - ASME NQA- 1 1994



N45.2.6 Requirements for Nuclear FacilityApplications _ ___________199




N45,2.6 Requirements for Nuclear FacilityApplications



'IO

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0956 ANSI ANSI 1978 Quality Assurance Program inm70462 1983 R AsME NQA-1 1994






0959 ANSI ANSI 1978 Quality Assurance Program regl.142.rOl 1981 R Reg Guide ASME NQA-1 1994

N45.2,6 Requirements for Nuclear Facility 1.58Applications

0960 ANSI ANSI 1975 Quality Assurance Program regl.28.rO3 1985 R ASME NQA-1 1994

N45.2.6 Requirements for Nuclear FacilityApplications . _ _ ___

0961 ANSI ANSI N/S Quality Assurance Program regl.33.rO2 1978 R ASME NQA-1 1994

N45.2.6 Requirements for Nuclear FacilityApplications ._._ __

0962 ANSI ANSI N/S Quality Assurance Program drg1010.r00 1992 P Endorsed by ASME NQA-1 1994

N45.2.8 Requirements for Nuclear Facility reg1.116Applications

0963 ANSI ANSI N/S Quality Assurance Program drgce913-5.rOO 1981 R Proposed ASME NQA-11994

N45.2.8 Requirements for Nuclear Facility reg1 .1 3.rO2Applications


-i..i: ....... -.-i. .. ... .................... ..... ......- E:- .X . :i................. .- -. ;.

andd Do. ACcd Latest Stindard Latet r

14, Coa- S oUomntandArd Veao Title ocumen Date~ bIity omet VeloDate:



0965 ANSI ANSI N/S Quality Assurance Program inm1 246 App. B 1991 R ASME NQA-1 1994N45.2.8 Requirements for Nuclear Facility

Applications


N45.2.8. Requirements for Nuclear FacilityApplications





0969 ANSI ANSI . N/S Quality Assurance Program inm49053 1985 R ASME NQA-1 1994


0970 ANSI ANSI 1975 Quality Assurance Program inm72701 1992 R ASME NiA-1 1994


0971 ANSI ANSi 1975 Quality Assurance Program regl .11 6.rOO 1976 P Subject to ASME NQA-1 1994


0972 ANSI ANSI N/S Quality Assurance Program regl.33.r02 1978 R ASME NQA-1 1994



N45.2.9 Requirements for Nuclear Facility regl.88Applications

0974 ANSI ANSI N/S Quality Assurance Program drgce913-5.rOO 1981 R Proposed ASME NtA-1 1994

N45.2.9 Requirements for Nuclear Facility regl.13.rO2

Applications0975 ANSI ANSI N/S Quality Assurance Program drgrs902-4.rOO 1980 R Proposed ASMENQA-1 1994

N45.2.9 Requirements for Nuclear Facility regl.3.rO3| _Applications _ ;

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0976 ANSI ANSI N/S Quality Assurance Program drgrs908-5.rOO 1979 R ASME NQA-1 1994


Applications

0977 ANSI ANSI 1974 Quality Assurance Program gIt79-050 1979 R ASME NQA-1 1994


Applications

0978 ANSI ANSI 1974 Quality Assurance Program g1t88-01 8 1988 P Endorsed by ASME NQA-1 1994

N45.2.9 Requirements for Nuclear Facility Reg. Guide

Applications 1 88

0979 ANSI ANSI 1982 Quality Assurance Program inm-toc 1995 R ANS 3.2 1994


Applications

0980 ANSI ANSI N/S Quality Assurance Program inm1 245 App. B 1991 R ASME NQA-1 1994




Applications



Applications

0983 ANSI ANSi NIS Quality Assurance Program inm35 8B 1975 R ASME NQA-1 1994


Applications



Applications



Applications



Applications

0987 ANSi ANSI 1974 Qualy Assurance Program inm35743B 1982 R ASMENQA-1 1994


Applications

Codes and Standards, and Other Guidance Cited in Regulatory Documents


Record St rdd|rd97oe= Accept| Letest StandardLaetVersion|

No Code Standr s erol iteDcuet Dte bliy Cmet Veion Dt

0988 ANSI ANS 1974 Quality Assurance Program inm35748B 1976 8 ASME NQA-1 1994


Applications _


N45.2,9 Requirements for Nuclear Facility

Applications_____________

0990 ANSI ANSI 1974 Quality Assurance Program inm39301B 1975 _ ASME NQA-1 1994


Applications ________ _______



Applications _______

0992 ANSI ANSI N/S Quality Assurance Program inm4905 3 1985 R ASME NQA-1 1994


Applications i 982A E -9




N45.2.9 Requirements for Nuclear FacilityApplications___ _____



Applications ________ ______






Applications

0998 ANSi ANSI N/S Quality Assurance Program inm51063 1985 R AsME NQA-1 1994


Applications ____


N45.2.9 Requiremenits for Nuclear FacilityApplications___________

_____

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N45.2.9 Requirements for Nuclear FacilityApplications;

1003 ANSI ANSI N/S Quality Assurance Program inm57070 1983 R ASME NQA-1 1994N45.2.9 Requirements for Nuclear Facility

Applications



1005 ANSI ANSi N/S Quality Assurance Program inm57090 1993 R ASME NQA-1 1994N45.2.9 Requirements for Nuclear Facility

Applications

1006 ANSI ANSI 1974 Quality Assurance Program inm62702 1987 R ASME NQA-1 1994N45.2.9 Requirements for Nuclear Facility

Applications

1007 ANSI ANSI N/S Quality Assurance Program inm70301 1983 R ASME N(A-1 1994N45.2.9 Requirements for Nuclear Facility

Applications

1008 ANSI ANSI N/S Quality Assurance Program inm73051 1986 ASME NQA-1 1994

N45.2.9 Requirements for Nuclear Facility_______Applications

1009 ANSI ANSI N/S Quality Assurance Program inm9900/5.5 1982 R ASME NQA-1 1994N45.2.9 Requirements for Nuclear Facility

Applications

1010 ANSI ANSI 1974 Quality Assurance Program inm9900/5.6 1980 R ASME NQA-1 1994N45.2.9 Requirements for Nuclear Facility

Applications

1011 ANSI ANSI 1974 Quality Assurance Program reg1.142.r01 1981 R ASME NQA-1 1994N45.2.9 Requirements for Nuclear Facility

Applications


Re'ord Stadaat:e Accept Ltea Stnard Lts esoNo oe tnad V rdio fll ouet Dte aiiy Cmet VeStond DatesVeao

1012 ANSI ANSI N/S Quality Assurance Program regi.28.rO3 1985 R ASME NQA-1 1994


1013 ANSI ANSI N/S Quality Assurance Program regl .33.r02 1978 R ASME NQA-1 1994


1014 ANSI ANSI N/S Quality Assurance Program srpl 7.1 1981 R ASME NQA-1 1994


1015 ANSI ANSI N/S Quality Assurance Program drgl 010.rOO 1992 R ASME NQA-1 1994

N45.2.10 Requirements for Nuclear FacilityApplications________



Applications I__ _ _ _ _ _ _ _ _ _ _ _ _

1017 , ANSI ANSI N/S Quality Assurance Program drgrs902-4.rOO 1980 R Proposed ASME NQA-1 1994


Applications _ _ _ _ _ _ _ __ _ _ _ _ _ _

1018 ANSI ANSI N/S Quality Assurance Program drgrs908-5.rOO 1979 R ASME NQA-1 1994

N45.2.10 Requirements for Nuclear FacilityApplications________



1020 ANSI ANSI 1975 Quality Assurance Program reg1.28.rO3 1985 R ASME NQA-1 1994

N45.2.10 Requirements for Nuclear FacilityApplications_______

1021 ANSI ANSI N/S Quality Assurance Program reg1.33.r02 1978 R ASME NQA-1 1994


1022 ANSI ANSI N/S Quality Assurance Program drg1010.r00 1992 P Endorsed by ASME NQA-1 1994

N45.2.1 1 Requirements for Nuclear Facility reg1.64

Applications : _:_:

1023 A ANSI N/S Quality Assurance Program drgce9l3-5.r00 1981 R Proposed ASME NQA-1 1994

N45.2. 1 Requirements for Nuclear Facility reg1.13.r02

Applications ____________ _ _

z

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Reoid Sts; an aDoe. Acc_''- aest Ve -rio

N . ' Codeii .. Stand d . ' ' .Ver s I on, te Document Dete ility Comment a Date



.____._____ Applications _


N45.2.1 1 Requirements for Nuclear FacilityApplications



1027 ANSi ANSI N/S Quality Assurance Program inm35018B 1975 R ASME NQA-1 1994







N45.2.1 1 Requirements for Nuclear Facility__0_0___Applications





1033 ANSI ANSI 1974 Quality Assurance Program inm37551 1994 R Typo in ASME NQA-1 1994

N45.2.11 Requirements for Nuclear Facility inm37551 -Applications ANSI vs. ANS

1034 ANSi ANSI 1974 Quality Assurance Program inm37702 1987 R Typo - was ASME NQA-1 1994

N45.2.1 1 Requirements for Nuclear Facility ANSI N45.11Applications



ecd :Stadard D. Acp td L Vers ion

No , Code S rd Vri , TDcument Dt i Veron Date


N45.2.11 Requirements for Nuclear FacilityApplications -




N45.2.1 I Requirements for Nuclear FacilityApplications

1038 ANSI NIS Quality Assurance Program inm501 00 1985 R ASME NQA-1 1994








1042 ANSI ANSI N/S Quality Assurance Program inm70301 1983 R ASME NQA-11994



N45.2.1 1 Requirements for Nuclear FacilityApplications _

1044 ANSI ANSI 1974 Quality Assurance Program not84-54 1984 P Endorsed by ASME NQA-1 1994

N45.2.11 Requirements for Nuclear Facility Reg. Guide

Applications 1.64

1045 ANSI ANSI 1974 Quality Assurance Program regl.142.rOl 1981 R Reg Guide ASME NQA-1 1994

N45.2.1 I Requirements for Nuclear Facility 1.64Applications _

1046 ANS Quality Assurance Program regl.28.rO3 1985 A ASME NQA-1 1994

N45.2.1 1 Requirements for Nuclear FacilityApplications - _______MEN_

0

zCi

LA

(5

LA

zCI1

~0



~Ro otdSt nda d oe. Ac ep L testS tanhdard Lat egst V e rtsion.Std ' Vri,- TIocumet- Dat, at Cm, -.. V i Datei

1047 ANSI ANSI N/S Quality Assurance Program regl .33.r02 1978 R ASME NOA-1 1994


Applications Enosdb______19

1048 ANSi ANSI N/S Quality Assurance Program drg1010.rOO 1992 P Endorsed by ASME NQA-1 1994

N45.2.12 Requirements for Nuclear Facility reg1.144Applications

1049 ANSI ANSI N/S Quality Assurance Program drgrs902"4.rOO 1980 R Proposed ASME NQA-1 1994


Applications


N4S.2.12 Requirements for Nuclear Facility

Applications __18 ___9

1051 ANSI ANSI N/S Quality Assurance Program inm35002 B 1980 R ASME NQA-i 1994




Applications _ASME______1994



1054 ANSI ANSI N/S Quality Assurance Program inm 35020 1983 R ASME NQA-1 1994.

N45.2.12 Requirements for Nuclear FacilityA pplications am_____ ______ ____________1 9

1055 ANSI ANSI N/S Quality Assurance Program inm350dO 1983 R AAME NQA-1 1994


Applications 1994

1056 ANSI ANSI 1973 Quality Assurance Program inm35741B 1979 R Typo - was ASME NQA-1 1994

N45.2,12 Requirements for Nuclear Facility ANSI N45.12


-plcton --- ASME NQA-1 1994

1057 ANSI ANSI N Quality Assurance Program inm37055 1983 R


Applications ---



Applications _-___ _

a0

z

tTIC)

tjA

~0


Record t d d D ., A te;t t da t V ersion

1059 ANSI ANSI 1977 Quality Assurance Program inrn40702 1992 R ASME NQA-1 1994

N45.2.12 Requirements for Nuclear Facility.Appli.c..on _L_ _ _ i__nd_

1060 ANSI ANSi 1977 Quality Assurance Program inm40704 1992 R ASME NQA-1 1994

N45.2.12 Requirements for Nuclear FacilityApplications I



c

1062 ANSI ANSI N/S Quality Assurance Program inm49051 1982 R ASME NQA^1 1994


____ ____ _ __ ____ ___ A pplications

1063 ANSI ANSI NIS Quality Assurance Program inmr50075 1983 R ASME NQA-1 1994




1065 ANSI ANSI NIS Quality Assurance Program inm5 1065 1984 R ASME NQA-1 1994




1067 ANSI ANSI 1977 Quality Assurance Program not8-21 1986 R States ASME NQA-1 1994


Applications by RG 1.441068 ANSI ANSI N/S Quality Assurance Program regi.28.r03 1985 R ASME NQA-1 1994


1069 ANSI ANSI N/S Quality Assurance Program srp187.2 1981 P Implied ASME NQA-1 1994


_______Applications by______1__44

Applications

1070 ANSI ANSI N/S Quality Assurance Program drglO10.rOO 1992 P Endorsed by ASME NQA-1 1994

N45.2.13 Requirements for Nuclear Facility regl.1 23Applications

~0ar~


..ec..d Sto'nd ar D c A e tLate st: S tand ard L atet V es io

No.dode *. St'andard "Versio TItle Doc um ent . a e abillity: Corrm ments Ve so Oats


N45.2.13 Requirements for Nuclear Facility reg1.13,r02Applications

1072 ANSI ANSI N/S Quality Assurance Program drgrs902-4.roo 1980 R Proposed ASME NQA-1 1994

N45.2.13 Requirements for Nuclear Facility reg1.3.r03Applications --- ._ _ _ _

1073 ANSI ANSI N/S Quality Assurance Program inm1245 App. B 1991 R ASME NQA-1 1994N45.2.13 Requirements for Nuclear Facility

Applications


Applications1075 ANSI ANSI N/S Quality Assurance Program inm35016B 1975 - ASME NQA-1 1994





Applications1078 ANSI ANSI N/S Quality Assurance Program inm350288 1975 R ASME NQA-1 1994


1079 ANSI ANSI 1976 Quality Assurance Program inm35060 1983 R ASME NQA-1 1994N45.2.1 3 Requirements for Nuclear Facility

Applications


Applications

1081 ANSI ANSI N/S Quality Assurance Program 1inm35065 1983 R ASME NQA-1 1994N45.2,13 Requirements for Nuclear Facility

Applications _ _ _ _ _ _ _ _

1082 ANSI ANSI 1976 Quality Assurance Program inm35746B 1979 R ASME NQA-1 1994N45.2.13 Requirements for Nuclear Facility

Applications L



R Stanhd D... A Latest standard L0tet Vern

No. Codn Sa r V ilear D nt t Co ent Vatei

1083 ANSI ANSI 1976 Quality Assurance Program inm35747B 1976 R ASME NQA-1 1994


______


N45.2.13 Requirements for Nuclear FacilityApplications__

_____


N45,2.13 Requirements for Nuclear Facility

Applications ANSI vs._ANS

1086 ANS ANSI 1976 Quality Assurance Program inm37551 1994 R Typo in ASME NQA-1 1994

N46.2.13 Requirements for Nuclear Facility inm37551 -

Applications ANSI vs. ANS





Applications _ _ _ _ _ _ _ __ _ _ _ _ _

1089 ANSI ANSI. N/S Quality Assurance Program inm51051 1984 R Typo- was ASME NQA-1 1994

N45.2.13 Requirements for Nuclear Facility ANSI

Applications ________N45.2.1 .3

1090 ANSI ANSI N/S QualityAssurance Program inm51053 1984 R ASME NQA-1 1994




1092 ANSI ANSI N/S Quality Assurance Program inm5106l 1984 R ASME NQA-1 1994


1093 AUNSI ANSI N/S Quality Assurance Program inm51065 1984 A ASME NQA-1 1994

N45.2113 Requirements for Nuclear Facility

Applications ______________

0

C)

-3tw

z

C)qi

0

0

r



Ne XC d e S tan ard ': 'V er sion T tl eo nl n D ata b l t o i en sV r i nD t


N45.2.13 Requirements for Nuclear FacilityApplicati


N45.2.13 Requirements for Nuclear Facility__ Applications

1096 ANSI ANSI 1976 Quality Assurance Program inm9900/BVII 1980 R ASME NQA-1 1994


1097 ANSI ANSI 1976 Quality Assurance Program regl.142.rOl 1981 R ASME NQA-1 1994

N45.2.13 Requirements for Nuclear FacilityApplications _ _

1098 ANSI ANSI 1975 Quality Assurance Program regl.28.rO3 1985 R ASME NQA-1 1994

N45.2.13 Requirements for Nuclear Facility_ _ _ Applications __ _

1099 ANSI ANSI N/S Quality Assurance Program reg1 .33,rO2 1978 R ASME NQA-1 1994

N45.2.1 3 Requirements for Nuclear FacilityApplications ___


N45.2.23 Requirements for Nuclear Facility regl.146Applications __

1101 ANSI ANSI NIS Quality Assurance Program git82-020 1982 P Implied ASME NQA-1 1994

N45.2.23 Requirements for Nuclear Facility endorsementApplications

1102 ANSI ANSI N/S Quality Assurance Program g0t82^021 1982 P ASME NQA-1 1994

N45.2.23 Requirements for Nuclear FacilityApplications __

1103 ANSI ANSI N/S Quality Assurance Program inm 245 App. B 1991 R ASME NQA-1 1994





N45.2.23 Requirements for Nuclear FacilityApplications ___



PM. .. t _iiiir L

Reor :.tende-r: Do1 Accept: Laes Stndr LateL::|tt Version::d::0 : '''i't'"i:si'sxttE2"":ki'S i-^ '

de ocument Date a'bili' tComment Ver . Date'






N45.2.23 Requirements for Nuclear Facility________-ANS__ANSI Applications













1115 ANSI ANSI 1975 Quality Assurance Program regl .28.rO3 1985 R ASME NQA-1 1994


1116 ANSI ANSI N45.4 1972 Containment System Leakage 1Ocfr5O App. J 1994 A In conjunction ANS 56.8 1994

Testing Requirements with ANS 56,8

1117 ANSI ANSI N45.4 1972 Containment System Leakage drgmsO21^5.rOO 1986 R ANS 56.8 1994


0

-4wk

Cs

z

Mi'0

%000


R e ord S:tandard D o . A. c cept- L- te st S tand ard L atest V ersion

No. Code D Standard ;Verson Tt o w e D t e Version Date1118 ANSI ANSI N45.4 NIS Containment System Leakage inml 245 App. B 1991 R ANS 58.8 1994


1119 ANSI ANSI N45.4 1972 Containment System Leakage inm61720 1985 R ANS 56.8 1994Testing Requirements




1123 ANSI ANSI N45.4 1972 Containment System Leakage not85-71 1985 R Endorsed by ANS 56.8 1994Testing Requirements 1 OCFR.J

1124 ANSI ANSI N46.2 1978 Quality Assurance Program drg1010.rOO 1992 R ANSI N46.2 ASME NQA-1 1994Requirements for Nuclear Facility obsolete withApplications approval of

ASME NQA-1

1125 ANSI ANSI N46.2 1978 Quality Assurance Program regl.28.rO3 1985 R ANSI N46.2 ASMENQA1 1994Requirements for Nuclear Facility obsolete withApplications approval of

ASME NQA-1

1126 ANSI ANSI N55.1 1979 Solid Radioactive Waste inm84522 1984 R ANS 55.1 1992Processing System for Light-WaterCooled Reactor Plants

1127 ANSI ANSI 1972 Nuclear Power Plant Air-Cleaning reg3.2.rOO 1973 A Errata issued ASME N509 1989N101.1 Units and Components July '93



Rcor Stadad' Dc. A.ept- . . . :..:DLate Stand ard Let Vrionh

8 ANSI ANSI 17 Protective Coatings (Paints) for drgop6l8-4.root n

NI1l .2 Light Water Nuclear Reactor regs8. r4 -

Containment Facilities ANSI N101.2withdrawn.Incorporatedinto variousASTM

.standards

1129 ANSI ANSI N/S Protective Coatings (Paints) for reg8.8.r03 1978 R ANSI Ni01 .2 Withdrawn n/a

N101.2 Light Water Nuclear Reactor withdrawn

Containment Facilities

113 ANSI ANSI 1972 Protetv Coate uings (Paintsfor srp6.1 .2 1981 A ANSI NiOl .2 Withdrawn n/a

Ni~l.2 ightWatr Nulea Reatorwithdrawn.

Containment Facilities

113 ANSI ANSI N/S Standard Practice for Quality drglfO&0 1992 P Endorsed by ASTx34319

Ni01.4 Assurance for Protective Coatings regpora

Applied to Nuclear Facilities

1132 ANSI ANSI N/S Standard Practice for Quality drgrs924.rOO 1980 R P 3ro s ASTM 03843 1993

NSI0.4 Assurance for Protective Coatings regI .3.r W r

Applied to Nuclear Facilities

1 1 _ -S N *AN Pcic for ruality drg1f1(7r8B 1975 R - ASTM D3843 1993

N1 01.4 Assurancer frProtectu iv Coating rgl6

0

Ct~

1 134 ANSI ANSIN 101.4

N/b standard Prauxcnc 1or UU-IltyAssurance for Protective CoatingsApplied to Nuclear Facilities

-IIVVsV . [

ANSI ANSI 1972 Standard Practice for Quality re .54,rOO 1973 P Subject to ASTM D3843 1993

N101.4 Assurance for Protective Coatings conditions

Applied to Nuclear FacilitiesNs r e.

z

thi

'-4

tj0

~0


Recod Standard Doe. iAccept-a LLts V ers io

Noc d e Standard, V ersion T itle11 ~ ` D ocum enit : Dat abliyaon m nt V r onD to

1135 ANSI ANSI 1972 Standard Practice for Quality reg3.21.rOO 1974 P Subject to ASTM D3843 1993

N101.4 Assurance for Protective Coatings conditionsApplied to Nuclear Facilities

1136 ANSI ANSI 1977 Code Requirements for Nuclear drgemBO5-5.rOO 1979 P Typo - reg ACI 349/ANS 1990! 1985

N101.6 Safety Related Concrete states 101.76. 6.4

Structures Incorporatedinto ACI349/ANS 6.4

1137 ANSI ANSI 1972 Code Requirements for Nuclear drgem8O5-5.rOO 1979 R Incorporated ACI 349/ANS 1990/ 1985

N101.6 Safety Related Concrete intoACI 6.4

Structures 349/ANS 6.4

1138 ANSI ANSI 1977 Code Requirements for Nuclear drgrs908-5.r0O 1979 P Incorporated ACI 349/ANS 1990/ 1985

N101.6 Safety Related Concrete into ACI 6.4

Structures 349/ANS 6,4

1139 ANSI ANSI 1972 Code Requirements for Nuclear regl.142.rOl 1981 R Incorporated ACI 349/ANS 1990/ 1985



1140 ANSI ANSI 1972 Code Requirements for Nuclear regl.69.rOO 1973 P Incorporated ACI 349/ANS 1990/ 1985



1141 ANSI ANSI 1972 Code Requirements for Nuclear reg3.53.rOO 1982 R Incorporated ACI 349/ANS 1990/ 1985



1 142 ANSI ANSI 1972 Code Requirements for Nuclear reg3.9.r00 1973 P Incorporated ACI 349/ANS 1990/ 1985





. Code. Standird 1972 'it Dte& abiit Co nts. Vrsion Date

1143 ANSI ANSI 1972 Code Requirements for Nuclear srpl 2.3 1981 P3 Incorporated ACI 349/ANS 19901 1985



1144 ANSI ANSI N170 1976 Determining Design Basis Flooding nuregO933, 1989 R ANS 2.8 1992

at Power Reactor Sites 3.103

1145 ANSI ANSI N170 1976 Determining Design Basis Flooding regl.59.rO2 1977 P One exception ANS 2.8 1992

at Power Reactor Sites in App. A ofReg. Guide1.59

1146 ANSI ANSI N170 1976 Determining Design Basis Flooding reg3.40.rOl 1977 P Subject to ANS 2.8 1992

at Power Reactor Sites conditions

1147 ANSI ANSI N170 N/S DeterminingDesign Basis Flooding srp2.4.10 1981 R ANS 2.8 1992

at Power Reactor Sites

148 ANSI ANSI N170 1976 Determining Design Basis Flooding srp2.4.14 1981 R ANS 2.8 1992at Power Reactor Sites

1149 ANSI ANSI N1 70 N/S Determining Design Basis Flooding srp2.4.2 1989 RANS 2.8 1992at Power Reactor Sites

116 ANSI ANSI Ni70 N/S Determining Design Basis Flooding srp2.4.3 1989 P ANS 2.8 1992


1151 ANSI ANSI N170 N/S Determining Design Basis Flooding srp2.4.4 1981 P ANS 2.8 1992at Power Reactor Sites

1152 AANSIN170 1976 Determining Design Basis Flooding srp2.4.5 1981 R ANS 2.8 1992at Power Reactor Sites

1153 ANSI ANSI N170 1976 Determining Design Basis Flooding srp2.4.7 1981 R ANS 2.8 1992


;4M0

Q(�A'IO

aW

�v:i

LO

z

'0



RS n d D Latst S dard Latik version

N o' C o eS a d rd V e s o nT tl o u m n D t b il it C o r mno a s o nD t

1154 ANSI ANSI N170 N/S Determining Design Basis Flooding srp2.4.8 1981 R ANS2.8 1992


1155 ANSI ANSI N1 95 N/S Fuel Oil Systems for Emergency git83-026 1983 R ANS 59.51 1989

Diesel Generators ... _

1156 ANSI ANSI N195 1976 Fuel Oil Systems for Emergency regl.137.rOl 1979 P ANS 59.51 1989

Diesel Generators

1157 ANSI ANSI N195 N/S Fuel Oil Systems for Emergency srp9.5.4 1981 P ANS 59.51 1989

Diesel Generators _ - -

1158 ANSI ANSI N195 1976 Fuel Oil Systems for Emergency sts4-geB3.8.3 1992 P ANS 59.51 1989

IDiesel Generators _ _ _ _ _ _ _ __ _ _ _ _ _ _

1159 ANSI ANSI N195 1976 Fuel Oil Systems for Emergency sts6-geB3.8.3 1992 P ANS 59.51 1989

Diesel Generators _ _ _ _ _ _ _ _ _ _ _ _ _

1160 ANSI ANSI N 195 1976 Fuel Oil Systems for Emergency stsb&wB3.8.3 1992 P ANS 59.51 1989

Diesel Generators

1161 ANSI ANSI N195 1976 Fuel Oil Systems for Emergency stsceB3.8.3 1992 P ANS 59.51 1989

Diesel Generators

1162 ANSI ANSI N195 1976 Fuel Oil Systems for Emergency stswstB3.8.3 1992 P ANS 59.51 1989

Diesel Generators__ _ _ _ _ _ -- A S 5 .19 2

1163 ANSI ANSI N197 1976 Solid Radioactive Waste regl.143.rOl 1979 R ANS 55.1 1992

Processing System for Light-WaterCooled Reactor Plants_______

1164 ANSI ANSI N199 1976 Liquid Radioactive Waste regl.143.rOl 1979 P ANS 55.6 1993

Processing System for Light WaterReactor Plants _

1165 ANSI ANSI N208 N/S Design Requirements for Light srp9.1.5 1981 A ANS 57.1 1992

Water Reactor Fuel HandlingSystems__

_ _ _ _ _

1166 ANSI ANSI N210 1976 Requirements for Light Water drgce913-5.rOO 1981 P Proposed ANS 57.2 1983

Reactor Spent Fuel Storage regl .13.rO2

Facilities at Nuclear Power Plants,D e s ig n _ _ _ _ _ _ _ __ _ _ _ _ _ _

1167 ANSI ANSi N210 1976 Requirements for Light Water srp3.8.4 1981 R ANS 57.2 1983

Reactor Spent Fuel StorageFacilities at Nuclear Power Plants,Design __ = __ _



Record Standrd Datet Standar Leta't eVersion

No oe Stned Vrsion Ti ouet: Data eiit omnt esinDt

1168 ANSI ANSI N210 1976 Requirements for Light Water srp9.1.2 1981 R ANS 57.2 1983

Reactor Spent Fuel StorageFacilities at Nuclear Power Plants,Design

1169 ANSI ANSI N210 N/S Requirements for Light Water srp9.1.5 1981 R ANS 57.2 1983

Reactor Spent Fuel StorageFacilities at Nuclear Power Plants,

___ ___ ___ Design

1170 ANSI ANSIer Plants - Source reg1.70.r03 1978 R ANS 18.1 1984

_________Term Specification-

1171 ANSI ANSI N237 1976 Radioactive Source Term for reg8.8.rO3 1978 R Implied ANS 18.1 1984

Normal Operation of Light Water endorsement

Reactors

1172 ANSI ANSI N237 1976 Radioactive Source Term for srpl 2.2 1981 P As relates to ANS 18.1 1984

Normal Operation of Light Water radionuclide

Reactors concentrations

1173 ANSI ANSI N237 1976 Radioactive Source Term for drgop61 8-4.rOO 1982 R Proposed ANS 18.1 1984

Normal Operation of Light Water reg8.8.rO4

Reactors

1174 ANSI ANSI N271 1976 Nuclear Power Plants - inm2515/1 2 8 1995 R ANS 56.2 1984 R89

Containment Isolation Provisionsfor Fluid Systems After a LOCA

1175 ANSI ANSI N271 1976 Containment Isolation Provisions inm70307 1986 R ANS 56.2 1984 R89






1178 ANSI ANSI N271 1976 Containment Isolation Provisions regl.141.rOO 1978 P With ANS 56.2 1984 R89

for Fluid Systems After a LOCA exceptions

z

tJI

t0

z

Q,

tj



F nt a Scpt fitctStndaord LatestV rio

1179 ANSI ANSI 1975 Self-Operated and Power regip3.148rO 1981 P Excptonsedb ASME N278.1 1975 R92

N278.1 Operated Safety-Related Valves Reg Guide

.Functional Specification Standard 1.148 as.Supplemental

1181 ANSI ANSI N299 1976 Administrative and Managerial reg3.50.rOl 1989 P Provides Withdrawn n/a

Controls for the Operation of guidance.

Nuclear Fuel Reprocessing Plants Impliedacceptance

1182 ANSI ANSI N303 N/S Guide for Control of Gasborne inm1245 App. B 1991 R Typo in Withdrawn n/a

Radioactive Materials at Nuclear minm 245 -

Fuel Reprocessing Facilities ANSI N303 vs303

1183 ANSI ANSI N309 N/S Standard Test Procedures for inm 245 App. B 1991 R Typo in IEEE 309 1970 R91

Geiger-Muller Counters inm 245 -ANSI N309 vs309

1184 ANSI ANSI N319 1976 Personnel Neutron Dosimeters drgoh940-4 1980 P Proposed reg ANSI N319 1976 R84

(Neutron Energies Less than 20 8.14.rO2

1185 ANSI ANSI N319 N/S Personnel Neutron Dosimeters inm1245 App. B 1991 R Typo in ANSI N319 1976 R84

(Neutron Energies Less than 20 inm 1245 -

MeV) ANSI N319 vs319

1186 ANSI ANSI N319 1976 Personnel Neutron Dosimeters inm83524 1984 R ANSI N319 1976 R84

(Neutron Energies Less than 20M eV ) _ _ _ _ _ __ _ _ _ _

1187 ANSI ANSI N319 1976 Personnel Neutron Dosimeters inm83724 1991 R ANSI N319(Neutron Energies Less than 20MeV)



.cr -. r :.~' Dec.3 'Acce - Q tW2Lbtes=t Staa a

N Code Stanidard ;Vrin

il>. . ouln ae: blty Cnmna VrinDt

1188 ANSI ANSI N319 1976 Personnel Neutron Dosimeters reg8.14.r01 1977 P Typo - was ANSI N319 1976 R84

(Neutron Energies Less than 20 Reg 6.14

MeV) IEEN30_979R9

1189 AN-SI [ANSI N320 1978 Performae s for git79-050 1979 R IEEE N320 7

Reactor Emergency RadiologicalMonitoring Instrumentation

1190 ANSI ANSI N322 N/S inspection and Test Specifications inml 245 App. 8 1991 R Typo in IEEE N322 1977 R91

for Direct and Indirect Reading inmi 245 -

Quartz Fiber Pocket Dosimeters ANSI N322 vs322

1191 ANSI ANSI N322 1975 Inspection and Test Specifications inm831 00 1991 R IEEE N322 17g

for Direct and Indirect ReadingQuartz Fiber Pocket Dosimeters

1192 ANSI ANSI N322 1975 Inspection and Test Specifications inm83524 1984 R IEEE N322 1977 R91


119 ANSI ANSI N322 1975 Inspection and Test Specifications inm83724 1991 R IEEE N322 1977 R91


1194 ANSI TANSI N323 1978 Radiation Protection drgfc401-4.rOO 1984 R Proposed IEEE N323 1978 R93

Instrumentation Test and regi 0.6.r02

Calibration _________ _ _ _

1195 ANSI ANSI N323 1978 Radiation Protection drgfc403-4.rOO 1985 R IEEE N323 1978 893

Instrumentation Test andCalibration_ ___18_-EE__98_

V4o-unrriuiuA =,.AnAA nOl 1qRr, R IEEE N323 1978 R93

f-A

tVi

-I

Cs

196 ANSI ANSI N323 1978j RaInatron ProtectionInstrumentation Test and

Us -" -V-.lV { EVA

I I__ __ --- d~ ,Qr~ I R I 1EEE.N323 j 9 8 93

1197 ANSI ANSI N323 Iadiation Protectioninstrumentation Test and

UlglC;�'vU�7wWVp - ---

I I_ I calibration I __ _ _ _ _ _ I I - ___ _

�4

1

VLA\0

.1w

,I,

w

C7%


R or d St n d r D oc=_-. , f .S iS, : U z i f . ~Dt Q . - S . A c e t L a es St n d r L a es V ersion: ..; i! it-

No.R Code S0000:; : 0tand-; tard Version.000 T .. . ... 0:itle0 Doumn Dta bility Comment Vrion Dat

1198 ANSI ANSI N323 1978 Radiation Protetction drgfc410-4.rOO 1985 R IEEE N323 1978 R93Instrumentation Test andCalibration _ _ _ _ _ _ _

1199 ANSI ANSI N323 1978 Radfition Protctin drgfc4l3"4.r00 1985 R IEEE N323 1978 R93

Instrumentation Test andCalibration _ _ _ _ _ _ _

1200 ANSi ANSI N323 1978 iRadiation Protection drgfc4l4-4.r00 1985 R . IEEE N323 1978 R93

Instrumentation Test andCalibration _ _ _ _ _ _ _

1201 ANSI ANSI N323 1978 Radiation Protection drgopO32-S.rOO 1984 PIEEE N323 1978 R93

lnstrumentation Test andCalibration

1202 ANSI ANSI N323 1978 Radiation Protection drgop618-4.rOO 1982 P Proposed IEee N323 1978 R93

Instrumentation Test and reg8.8.rO4

Calibration1203 ANSI ANSIN323 1978 Radiation Protection minml230 1983 R IEEE N323 1978 R93

Instrumentation Test andCalibration IEEEN_23_1978_R93_---

1204 ANSI ANSIN323 N/S Radiation Protection inmld245 App. 8 1991 R Typo in IEEE N323 1978 R93

Instrumentation Test and im 1245 -

Calibration ANSI N323 vs323

1205 ANSI ANSI N323 1978 Radiation Protection inm40750 1995 R IEEE N323 1978 R93

Instrumentation Test andCalibration IE E_______9 8_9

1208 ANSI ANSI N323 1978 Radiation Protection inm8310O 1991 R IEEE N323 1978 R93Instrumentation Test and

Calibration drgop618______ 1982__Propsed _EEEN23_198 _R9

1207 ANSI ANSI N323 1978 Radiation Protection inm83526 1984 R IEEE N323 1978 R93Instrumentation Test and

Calibration _ _ _

1208 ANSI ANSI N323 1978 Radiation Protection inm83726 1991 R IEEE N323 1978 R93Instrumentation Test and

Calibration

124 AS _ NI33 NS RdainPoeto _ n _ 24 p..B19 yoi IE 3317 9



I .. . L. at e S ndad: -; .-.-. i L.s .t I . Ves...i

t Record... No '.'.1209

1210

1211

1212

1213

1214

Steodard -.- no'� :�:. � " � ' :' o�::z !I Ea 1 .1 ....li .P no :x

-cc0t..~AP,60P-n :~ -man i d iStandar DatesiVia

00-40.,..I Q:L, . ,:! a .....7

, ,, ; , I i i: . VE . I4

iauoumen uu' 1. _____Code I~~iA VVSIfl -. itl I.W~7~i~ f194I -"~' rIEEN33 ~ 1978 893

---ANSI

ANSI

ANSI

ANSI

ANSI

ANSI

ANSI N323

ANSI N323

ANSI N323

ANSI N323

ANSI N323

ANSI N328

1978 Intaimnation TsroteandInstrumentation Test and

.... -{ -

IEEE N323I Calibration I .. ...

Rda - tion it P eitt forn --------------- 197 R93__

1978 Radiiation ProtectionInstrumentation Test andCalibration

not 1 -410 I 70 1

8definitionpurpose

J. _._=3_AA 1993_1978

1978

Radiation ProtectionInstrumentation Test andCalibrationRadiation ProtectionInstrumentation Test andCalibration

not93-30

regl 0.8.rO

1993

1987

IR

IEEE N323

IEEE N323

IEEE N323

IEEE N323

FA-NSIN13.12

. _ . :i .- -

1978

1978

Radiation ProtectionInstrumentation Test andCalibration

rega .-ouar . -s

1978 R93

1978 R93

1978 9not issued

1978 R84

.1

I i - t-7 %rT n I

-4

z

C)4

(,Jh'.0

Cs

_ = _ _ . . A

Surface Radioactivity Guides forMaterials, Equipment, andFacilities to be Released forUncontrolled UseInternal Dosimetry for MixedFission and Activation Products

inm697/45 1 YY4 I n

min. 24 App B Typo in ANSI N343

1215 ANSI IANSI N343 Q N/S in m ~12 45 -App. B 1991s - --

E R

R

L_

Typo ininml 245 -ANSI N343 vs343

IANSI N343

ANSI N343

ANSl N343

I L- t inm83lOO 1991

1216 ANSI ~N-SI N34:3

1 117 ANSI IANSI N343

1978

1978

1978

;ntera simeiry;or MixedFission and Activation Products

Internal Dosimetry for MixedFission and Activation Products

Internal Dosimetry for MixedFission and Activation Products

;

inm83525

I 1991

1984

I

1218

1219

ANSI

ANSI

ANSI N343

ANS N34

InIiIB372b ANSI N343 1978 R84inm8372b luul )1 ANSI N343

Endorsed by ANSI N343Reg. Guide8.26 ___ _

I __7 __8.

1978 R84

197 R8I I t - I I = --I

.

_

1978 nternal Dosimetry for MixedFission and Activation Products

reg3.b3.rw I ::10L n

...... . _ .

z

00



R e c lo r d S t.......c c p - - a e s ta d r Datet V e s o

N Co de Standard | Ves T1itl 0Doc m n Date ability Co ntV rioi Date

1220 ANSI ANSI N343 1978 Internal Dosimetry for Mixed exceprO 18 P WthiNons3 98 8

Fission and Activation Products exceptions

1221 ANSI ANSI N398 N/S Quality Control for Plate-Type inm607 4 5B 1992 R ANS 15.2 1990


1222 ANSI ANSIN398 1974 Quality Control for Plate-Type reg2.3.rOl 1976 P Subjedt to ANS 15.2 1990

Uranium-Aluminum Fuel Elements conditions

1223 ANSI ANSI N401 1974 Development of Technical reg2.4.rOR 1977 ANS 15.6 ANS 15.1 1990

Specifications for Research withdrawn

.Reactors incorporated

into ANS 15.1

1224 ANSI ANSI N402 N/S Quality Assurance Program reg2.3.rOl 1976 R ANSI 11976 R87

Requirements for Research ANS 15.8

Reactors 17 8

1225 ANSI ANSI N402 1976 Quality Assurance Program reg2.4.rOR 1977 A Acceptable ANSI N402/ 1976 R87

Requirements for Research means of ANS 15.8

Reactors complying with1 OCFR50.34

1226 ANSI ANSIN402 1976 Quality Assurance Program reg2.5.rOR 1977 A ANSI N402 1976 R87

Requirements for Research ANS 15.8

R eactors _ _ _ _ _ _ _ _ _ _ _ _ _ _

1227 ANSI ANSIN403 1977 Guidelines on Nuclear Analysis drgem8O5-5.rOO 1979 P ANS 6.4 1985

and Design of Concrete RadiationShielding for Nuclear Power Plants

_____ 1 _ .-. A1A 1 in7q I R -ANS 10.3. 1995

1228 _ ANSI ANSI N413 1974 Documentation of 1-U111PULUJ 16V_. IV.-V

I 1��I I I ______ '_I --- ______ _____________________ I ---



eo S 0-. |- Standard o Accep Stadaid Lt Vei oI

N o .a a r si . .._. ..._ [

MCI- Staf__4_1-n1994 A JANSI N43.9 ANSI N43.9 1991

I 1229 ANSI IANSI N432 I 9ud I amma nuaovigraviy -Specifications for Design and Testof Apparatus

1-1-z WIalso designatedas NBSHandbook 136

I I a _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ 4 _ ANSI N43,9 199119�U

1230 ----ANSI ANSI N432 I 1980 G5amma Radiography -

Specifications for Design and Testof Apparatus

1-1- --nnt9Q5-RR I I1 Y95 I K

l reg iu.I'J.I-'.

1231 1 ANSI JANS1N432 N/S Gamma Radiography -


reg I v. I W~vv I -0,�1^ StE on I 1QS47 I H,1 ANSI N43.9

also designatedas NBSHandbook 136

ANSI N43.9 1991

.I I - 4 A IANSI N43.9 1ANSI N43.991'.0

z

'0

(.!

i 2321 ANSI ANSI N43A

ANSIN433.1

2 N/S Gamma Radiography - reg XIv. I 1' -,U , ;Ru, ..


also designatedas NBSHandbook 136

_______- it . f---- ,. t1AWSl N4:3.7 T 1977 R89 I

1233 t ANSI__

N/S Safe Design and Use of Selt-Contained, Dry Source StorageGamma Irradiators (Category I)

reg 1u.-i.rWv ndesignatedNBS 127

...... _..

1977 R89I I .------ I -- ATVZic KIAA7----

1234 ANSI ANSIN433.1

N/S Safe Design and Use of Self-Contained, Dry Source StorageGamma Irradiators (Category I)

reg I v.1 7 .ruu 1170 I I1___1 n s e Mn( I 1 SIR 7 I H IAISO lblv7 *5S- S.;MU

7.... _....

designatedNBS 127

I I II. lo

I rno

I D IAk|n Alo.ANSI N43.7 1 1977 R89Safev Desig and _s ot... .e.

1.235 | ANSI ANSIN433.1

N/S Safe Design and Use of tielt-Contained, Dry Source StorageGamma Irradiators (Category I)

reg I . 9.rU I , voo I r

designatedNBS 127

I_____I I I II ~I ~ IjNI49 17 8....... n - - '.ovuISI

N449

1236 ANSI ANSI N449 19 /4

L��maintainig Coubmt-60 anuld o137 Teletherapy Equipment,Guidelines for

a,, v- - .

JI ________ I________

()I

;v

%0

c4


d SA1ild Dos.AScildArd LOOSl4'

Code Standard ~ ~ 13 Teleterap EqipmencuetDtellt omnt ealnDt1237 ANSI ANSI N449 1974 Maintaining Cobalt-es and Cesium dtgfc414-4.r02 1985 R ANSI N449 1974 R84

137 Teletherapy Equipment,

- ~~~~Guidelines for_______

1238 ANSI- ANSI N449 1974 Maintaining Cobalt-tO and Cesium regCei.8.m13 1987 R ANSIN449 1974 R84

137 Teletherapy Equipment,

Guidelines for --___ ----_

1239 ANSI ANSI 1978 Procedures for Periodic Inspection cir80-24 1980 R IEEE N449.1 1978 R84

N449.1 of Cobalt-60 and Cesium-137Teletherapy Equipment

1240 ANSI ANSI 1978 Procedures for Periodic Inspection drgfc4n48-4.r3 1985 R IEEE N449.1 17RN449.1 of Cobalt-60 and Cesium-1 37

Teletherapy Equipment

124 ANSI ANSI 1978 Procedures for Periodic Inspection notg0-33 1980 P IEEE N449.1 1978 R84

N449.1 of Cobalt-60 and Cesium-1 37Teletherapy Equipment

1242 ANSI ANSI 1978 Procedures for Periodic Inspection regn1.8.r02 1987 9 IEEE N449.1 1978 R84

N449.1 of Cobalt-GO and Cesium-137Teletherapy Equipment

1243 ANS i ANSI N509 N9S Nuclear Power Plant Air-Cleaning in-1245App.B 1991 R ASME N5O9 1989

Units and Components

1244 ANSI ANSI N509 1976 Nuclear Power Plant Air-Cleaning inm847 2 4 1991 R ASME N509 1989


5 ANSI NSI N509 1976 Nuclear Power Plant Air-Cleaning not83-25 1983 P Sets ASME N509 1989

Units and Components appropriate'setpoints

_ __ - = - ;. 1Q79 P Several ASME N509 1989

C3

1246 ANSi ANSI N509 1976j Nuclear rower mP on e An s-C a ,1111Units and Components

I vt3 1. I--

I

sectionssupplementedby Peg. Guide1 929 I

I I__ _ J _ _ _ _ I _ _ _ _ _ _ _ _ _ _ I _ _ _I_ I . J _ _ U . - -_ _ _ _ _ _ _



r Stndard Do. AEpt -. Ltt St da Le V.rsion

_o oe Stand ''d: Veso TteDouet ate ability omns VrinDt

1247 ANSI ANSI N509 1976 Nuclear Power Plant Air-Cleaning regl .52.rO2 1978 P ASME N509 1989


1248 ANSI ANSI N509 1980 Nuclear Power Plant Air-Cleaning srp6.5.1 1981 P ASME N509 1989


1249 ANSI ANSI N510 1975 Testing of Nuclear Air Treatment bul8O-003 1980 R ASME N510 1989 R95

Systems _WS_______99_9

1250 ANSI ANSI N510 1975 Testing of Nuclear Air Treatment git83-013 1983 P Several ASME N510 1989 R95

Systems sectionsendorsed

1251 ANSI ANSI N510 1975 Testing of Nuclear Air Treatment glt83-036 1983 P ASME NS10 1989 R95

Systems

1252 ANSI ANSI N510 N/S Testing of Nuclear Air Treatment inm1245 App. B 1991 R ASME N510 1989 R95

Systems _______________

1253 ANSI ANSI N510 1975 Testing of Nuclear Air Treatment inm84724 1991 R AS-ME N510 1989 R95

Systems

1254 ANSI ANSI N510 1975 Testing of Nuclear Air Treatment regl.140.rOl 1979 P Several ASME N510 1989 R95

Systems ________Sections

1255 ANSI ANSi N51O 1975 Testing of Nuclear Air Treatment regl.52.rO2 1978 P Several ASME N510 1989 R95

Systems sectionsendorsed

1256 ANSI ANSI N510 1980 Testing of Nuclear Air Treatment srp6.5.1 1981 P Implied ASME N510 1989 R95

Systems endorsement _

1257 ANSI ANSI N512 1974 Protective Coatings (Paints) for reg3.3.rOl 1974 P ANSI N51 2 Withdrawn n/a

the Nuclear Industry withdrawn1988

1258 ANSI ANSI N538 1979 Classification of Industrial Ionizing drgtplo2-5.rOO 1980 A Also ANSI N43.8 1979 R88

Radiation Gaging Devices designatedNBS 129

1259 ANS A N538 N/S Classification of Industrial Ionizing reg1 .10.rOO 1987 Also


1260 ANSI ANSI N538 N/S Classification of Industrial Ionizing regl0.1 1.rOO 1987 R Also ANSI N43.8 1979 R88


t'-

t71C)

eU)

U)

z4

w~

,.!h


R ec rd ta n ar . D c. cce t ~L at s Sta d ard L atest V et o n

NO. Cod . Standard. k V o T0tle Dc metE Date bifit:y oon Da :; te _

1261 ANSI ANSI N538 N/S Classification of Industrial Ionizing SECY94-275 1995 R Also ANSI N43.8 1979 R88


1262 ANSI ANSI N538 N/S Classification of Industrial Ionizing SECY95-083 1995 R Also ANSI N43.8 --- 1979 R88


1263 ANSI ANSI N540 N/S Classification of Radioactive or reg10.10.rOO 1987 R Also ANSI N43.4 1975 R89

Self-Luminous Light Sources designatedNBS 116

1264 ANSI ANSI N540 N/S Classification of Radioactive or reg 1o.11 .rOO 1987 R Also ANSI N43.4 1975 R89

Self-Luminous Light Sources designatedNBS 116 _ . ..

1265 ANSI ANSI N540 1975 Classification of Radioactive or reg6.4.rO2 1980 P Also ANSi N43.4 1975 R89

Self-Luminous Light Sources designatedINBS 116

1266 ANSI ANSI N542 N/S Classification of Sealed not85-29 1985 R Also ANSI N43.6 1977 R89

Radioactive Sources designated ISO2919 and NBS

Handbook 126

1267 ANSI ANSI N542 N/S Classification of Sealed regl0.10.rOO 1987 R Also ANSI N43.6 1977 R89

Radioactive Sources designated ISO2919 and NBSHandbook 126

1268 ANSI ANSIN542 N/S Classification of Sealed reg10.11.rOO 1987 F Also ANSI N43.6 1977 889




Record tnr D Accpt ttst 0tandard e Ersio

1269 ANSI ANSI N542 1977 Classification of Sealed reg6.4.r2 10 P Also ANSI N43.6 977 R89


1270 ANSI N543 1974 General Radiation Safety Standard reg6.5.rOO 1974 P ANSI N43.3 1993

for Installations Using Non-Medical X-Ray and Sealed GammaRay Sources, Energies up to 10MeV

1271 ANSI ANSIN545 N/S Thermoluminescence Dosimetry: inmi 245 App. 8 1991 R Typo in ANSI N545 1975 R93

Environmental Applications, inml 245 -

Performance, Testing, and ANSI N545 vs

Specification for 5456..i~7R3

1272 ANSI ANSIN545 .1979 Performance, Testing, and reg3.53.rOO 1982 R Endorsed by ANSI N545 1975 893

Specification for Reg. Guide

Thermoluminescence Dosimetry: 4.13.rOl

Environmental Applications

1273 ANSI ANSI N545 1975 Performance, Testing, and reg4.13.rOl 1977 P Additional ANSI N545 1975 893

Specification for provision and

Thermoluminescence Dosimetry: qualifications

Environmental Applications

1274 ANSI ANSI N546 1976 Medical Certification and not84-03 1984 R ANS 3.4 1983 R88


1275 ANSI ANSI N546 1976 Medical Certification and 608-4.rOO 1982 P ANS 3.4 1983 R888


1276 ANSI IN58 N/S PWR and BWR Containment Spray nuregO933, 2.C- 1983 R ANS 56.5 1979 R87

System Design Criteria 1 0 ___

'0

(b

zC)

PoI'0A


Part A - Industry Consensus Codes and Standards* ... ...

HecrdE ,i. .i: : -i: :. . .-; .

" ", ,, -. . . Z :

.... �;. I

:: � -�-11��:�:--- " ,II I �4�% - - i

S...;d.dOW rt.... .... -. E-Document. I ' Date

bAccep-.. ability

Comm-, t-;; I-g~, .s<Ux , isis iss tl

,.- I . .; S L~'

LAtest 5Standad

ANS 58.9i-iDateia

fi No joe j~tarldardj v"r , ....... Li~ 1-9841I- R f- -i '

1277 ANSI ANSI N658b N/S wItgl r Safelu ty RelatedWater Reactor Safety-Related

F .: ^.,-

V- F. .

tFlUlo v~yssems_ _ _ _ I a-. .

Nib- I,- . .: . .

1278 ANSI ANSI N660 N/S Time iResponse Design Criteria forSafety Related Operator Actions

nuregO933 ,1.11.E.6

1984 R - ANS 58.8 1994

-

I --.-- 4 -.. e. .. -. t1,~Al 198311279 ANSI ANSI N660

DraftNib Sime Hesponse Uerator Actions

Safety Related Operator Actionsytvv-v . v -- . _ _ _

R

R

.1ANS 58.8 1994

___ 1ANS 58,8 1994N _ m .esp nse-Atri h {r u i3i 1983

1280 : ANSI ANSI N660Draft

NIS lime Response dOerat An sSafety Related Operator Actions

tp-o-v , v-

ANS 58.8 1994I/ I Ime nepns eiy'-.i1281 ANSI ANSI N660

DraftN/S aime RespOnste Ouesra AUt-io nsU

Safety Related Operator ActionsU1v-v - v.v . _ _ _

v~- I _ _ _ _ _ L -I...I 6.. . -- - f M...~ * wi -A l A (I I 19-83 1 R |ANS 58.8 1994

1282 ANSI ANSI N660Draft

NIS I ime elaspoted Ope rator I lA t I Ion

Safety Related Operator ActionsUv.-v-v I v-v

II _ I_ _ _ _ 1 ' . 4.. .-, -- r. ,, -' , n t q - A 1 A iI t T I~ ANS 58.8 19941283 ANSI ANSI N660

DraftN/S ISam e Resplat ds U e rtog r Acti on.. s

SaFety Related Operator ActionsvltV- .I

N/b ime nepw~se----yI - . .. .1111,1,111.1 .....I - ---

1284 ANSI ANSI N660Draft

N/IS I ISa e espR latSed Oue r l a Ito A i

Safety Related Operator Actionsztvv- . .S

1ANS R 1 1994tI .--- I - *t .-.-

| .

1285' ANSI ANSI N660Draft

NIS Time Response Design Criteria forSafety Related Operator Actions

qltoa-v I'v.l

I I I I- R. . I1286 ANSI

18 ANSI

ANSI N665

ANSI N665

19850_ - - Nuclear Fuel Facilities forFabricating Fuel for Light WaterReactors (LWR) Fire Protection

}|Wl{wWvVvvinm880551 I ?vZ-1 ANSI N665

has beenwithdrawn

Referenced infootnote

_ r0 RNucea Ful aclitesfo Withdrawn

Withdrawn n/a

1985 Nuclear Fuel Facilities forFabricating Fuel for Light WaterReactors (LWR) Fire Protection

reg3.52.r0 I I Ovo n

n/a

II I _______I ----________________a_________



Recrd Standard Doc. Accept- Latest Standard Laest U e|itonNo oe Sanad Vrin TWoneuet Dae aiiy Cmens VrinDt

1288 ANSI ANSI N719 1979 Setpoints for Nuclear Safety- nuregO933, 3.3 1986 R ISA S67.04 1994

Related Instrumentation ______

1289 ANSI ANSI NQA-1 N/S Quality Assurance Program drgrs9O2-4.rOO 1980 R Proposed ASME NQA-1 1994

Requirements for Nuclear Facility regl.3.rO3

Applications _______________ ______

1290 ANSI ANSI NQA-1 N/S Quality Assurance Program inm37700 1990 R ASME NQA-1 1994

Requirements for Nuclear FacilityApplications____ ____-

1291 ANSI ANSI NQA-1 N/S Quality Assurance Program inm39701 1992 R ASME NQA-1 1994


- _ _ _~ Applications _

1292 ANSI ANSI NQA-1 N/S Quality Assurance Program inm40O74 1992 R ASME NQA-1 1994

Requirements for Nuclear FacilityApplications_______

1293 ANSI ANSI NQA-1 1979 Quality Assurance Program inm73051 1986 R ASME NQA-1 1994

Requirements for Nuclear FacilityApplications ________

1294 ANSI ANSI S3.6 1973 Specifications for Audiometers 10cfr73 1995 A ASA S3.6 1989

1295 ANSI ANSI X3.39 1973 Information Systems - Recorded drg3003.rOO 1990 A ANSI X3.39 1986 R92

Magnetic Tape for InformationInterchange (1600 cpi, PhaseEncoded)

1296 ANSI ANSI X3.39 1973 Information Systems - Recorded reg3.3.rOl 1974 R Draft standard ANSI X3.39 1986 R92

Magnetic Tape for InformationInterchange (1600 cpi, Phase

Encoded) _______________

1297 ANSI ANSI Z9.2 1979 Fundamentals Governing the reg3.56.rOO 1986 R ANSI Z9.2 1979 R91

Design and Operation of LocalExhaust Systems -

1298 -- ANSI A-NSI1- -1976 Standard Method of Gaging reg 1. 137.rOl 1979 R Cited in ASTM D1085 1965 ROO

Z1 1.33 Sampling Petroleum and footnote (also

Petroleum Products ASTM D270)

t1j(A

za

0

0�0

110I

w

'IO:1-,

w

z

C-)

(bh

%J.

t1)

Codes gmid Standards and Other re Lance Cited in Regulatory DocumentsPart A - Industry Constenswus Codes and Standards

'r, R ecord Sta nd ard Doe......... Ac e pt La test t d ard La es i

N o C d aS ta n d a rd V r i nT dD o m n t D t , b l t ' C h e nt s V e rs o a te~1299 ANSI ANSI Z88.2 1980 Respiratory Protection 1 Ocfr73 1995 R ANSI Z88.2 1992

1300 ANSI ANSI Z88.2 1980 Respiratory Protection drgop618-4.rOO 1982 P Proposed ANSI Z88.2 1992reg8.8.r04

1301 ANSI ANSI Z88.2 1969 Respiratory Protection reg8.8.rO3 1978 P For ANSI Z88.2 1992consideration

1302 ANSI ANSI Z88.5 1981 Practices for Respiratory not86-24 1986 P ANSI Z88.5 1981Protection for the Fire Service l__ .

1303 ANSI ANSI Z88.6 N/S Respiratory Protection - Respirator not84-24 1984 R Typo - was ANSI Z88.6 1984

Use - Physical Qualifications for ANSI 288.6Personnel

1304 ANSI ANSI 1984 National Fuel Gas Code inm88055 1991 R ANSI Z223.1 1992/ 1992

Z223.1 NFPA 54

1305 APHA APHA 1976 Standard Methods for the drgesl 14.rOO 1983 R APHA - same 1992

Examination of Water and title, 18thWastewater, 14th Ed. Edition _

1306 APHA APHA 1980 Standard Methods for the inm79501 1989 R APHA - same 1992Examination of Water and title, 18th

Wastewater, 1 5th Ed. Edition

1307 APHA APHA 1989 Standard Methods for the not94-07 1994 R APHA - same 1992

Examination of Water and title, 18thWastewater, 17th Ed. Edition

1308 APHA APHA 1971 Standard Methods for the regl.107.rOl 1977 R APHA - same 1992

Examination of Water and title, 18th

Wastewater Edition

1309 APHA APHA 1971 Standard Methods for the rag 1.1 38.rOO 1978 R APHA -same 1992


Wastewater, 13th Ed. Edition

1310 APHA APHA 1971 Standard Methods for the reg4.14.rOl 1980 R APHA - same 1992

Examination of Water and title, 18thWastewater, 13th Ed. Edition

1311 APHA APHA 1975 Standard Methods for the reg4.15.rO1 1979 R APHA - same 1992Examination of Water and title, 18th

. Wastewater, 13th Ed. Edition



:Rlcord Stny andard .................... Doe. -Acet LaetSadr Latest Version

1312 APHA APHA 1977 Methods for Air Sampling and reg4.15.rOl 1979 R Not found n/a

____ ___ __ ___ ___ ___ A nalysis _ _ _ _ _ _ _ _

Notot found nA'a

1313 APHA APHA 1977 Methods for Air Sampling and reg4;15.rOl 1980 R Not found n/a

Analysis

1314 APHA APHA 1978 Quality Assurance Practices for inm79501 1989 R Not found n/a

Health Laboratories

1315 APHA APHA 1978 Quality Assurance Practices for reg4.15.rol 1979 R Not found n/a

Health Laboratories

1316 APHA APHA 428 N/S Standard Methods for the regl.35.rO3 1990 R APHA- same 1992


Wastewater Edition

1317 APHA APHA 7110 N/S Gross Alpha and Gross Beta not94-07 1994 R Not found n/a

Radioactivity iTotal, Suspended,and Dissolved)

1318 API API 620 N/S Design and Construction of Large, regl.143.rOl 1979 P API 620 1990

Welded, Low-Pressure StorageTanks

1319 API API 620 N/S Design and Construction of Large, drg1010.rOO 1992 P Endorsed by API 620 1990

Welded, Low-Pressure Storage regl.26

Tanks .

1320 - API API620 NIS Design and Construction of Large, regl.26.rO3 1976 A API 620 1990

Welded, Low-Pressure StorageTanks l

1321 API API 620 1977 Design and Construction of Large, srp3.2.2 1981 A Quality Group API 620 1990.

Welded, Low-Pressure Storage D

Tanks

1322 API API650 N/S Welded Steel Tanks for Oil drgl O.rOO 1992 P Endorsed by API 650 1993

Storage regl.26

1323 AP API 650 N/S Welded Steel Tanks for Oil regl.143.rOl 1979 P AP1650 1993

Storage

1324 API API 660 N/S Welded Steel Tanks for Oil regl.26.rO3 1976 A API 650 1993

Storage

1325 API API 650 1978 Welded Steel Tanks for Oil srp3.2.2 1981 A Quality Group API 650 1993

Storage .. _ __ D _

-4

z

t71C:2

-3Wk

CD

Ib

z

U)

00


R orSt n rd " e . A cce t-' LatW tStand ard La e tV ersionSvied. t eionF .;ti i D-um n a a':,bility C m nt ; Ver'o Datei<

1326 ASCE ASCE N/S Structural Analysis and Design of g1t78-011 1978 R Latest Version ASCE 58 1980

Nuclear Plant Facilities may beincorrect

1327 ASCE ASCE N/S Structural Analysis and Design of srp3.8.4 App. D 1981 R Latest Version ASCE 58 1980

Nuclear Plant Facilities may beincorrect

1328 ASCE ASCE 4 1986 Seismic Analysis of Safety- srp3.7.1 1989 P Implied ASCE 4 1986

Related Nuclear Structures and endorsementCommentary on Standard for on a case by

Seismic Analysis of Safety- case basis

Related Nuclear Structures

1329 ASCE ASCE 4 1986 Seismic Analysis of Safety- srp3.7.2 1989 P Implied ASCE 4 1986

Related Nuclear Structures and endorsementCommentary on Standard forSeismic Analysis of Safety-Related Nuclear Structures

1330 ASCE ASCE 4 1986 Seismic Analysis of Safety- srp3.7.3 1989 R ASCE 4 1986

Related Nuclear Structures andCommentary on Standard forSeismic Analysis of Safety-Related Nuclear Structures

1331 ASHRAE ASHRAE15 N/S Safety Code for Mechanical inm8 055 1991 R ASHRAE15 1994

Refrigeration

1332 ASME ASME Code N/S ASME Boiler and Pressure Vessel 1 Ofr2 App. C 1994 R ASME B&PV 1995

Code Code

1333 ASME ASME Code N/S ASME Boiler and Pressure Vessel drglO35.rOO 1995 R ASME B&PV 1995

Code Code

1334 ASME ASME Code NIS ASME Boiler and Pressure Vessel gIt88-005.s05 1995 R ASME B&PV 1995

Code Code

1335 ASME ASME Code N/S ASME Boiler and Pressurn Vessel g1t95-005 1995 R ASME B&PV 1995

Code Code

1336 ASME ASME Code N/S ASME Boiler and Pressure Vessel inm50001 1995 R ASME B&PV 1995

Code Code

1337 ASME ASMECode N/S ASME Boiler and Pressure Vessel inm53051 1984 R ASME B&PV 1995

Code . Code



co ASME LtstStabdard l er}Lii .r63._

1338 ASME ASME Code NIS ASME Boiler and Pressure Vessel inm62703 1995 R ASME-B&PV 1995

Code __ _ _ _ _ _ ____Code_ _ _ _ _ _

1339 ASME ASME Code NIS ASME boiler and Pressure Vessel not95-12 1995 R ASME-B&PV 1995

Code ________Code

1340 ASME ASME Code NIS ASME Boiler and Pressure Vessel not915-1 0.5s 1995 R_ ASME B&PV 1995

Code Code

1341 ASME ASME B&PV 1972 ASME Boiler and Pressure Vessel 10cfr50.55a 1994 P ASME B&PV 1995

Code Code Code

1342 ASME ASME B&PV 1989 ASME Boiler and Pres sel cfr50.55a 1994 P ASME B&PV 1995

Code Code Code

1343 ASME ASME B&PV 1977 ASME Boiler and Pressure Vessel 10cfr5O.55a 1994 A ASMEB&pV 1995

Code Code

1344 ASE ASME B&PV 1980 ASME Boiler and Pressure Vessel 1 0cfr5O.55a 1994 A ASME B&PV 1995

Code Code Cd

1345 ASME ASME B&PV N/S ASME Boiler and Pressure Vessel bul78-01.1 1978 R Used ASME B&PV 1995

Code Code Generically in CodeNRC Text

1346 ASME ASME B&PV 1975 ASME Boiler and Pressure Vessel bu180-008 1980 R Reere ASME B&PV 1995

ode Code text Code

X 37 AM SE&V NiS ASME Boiler and Pressure Vessel bu8-0 93 R - ASMEB&V19

Code Code Code

1348 ASME ASME B&PV 1974 ASME Boiler and Pressure Vessel bul89-0 2 1989 R ASME B&PV 1995

Code Code Code

1349 ASME ASME B&PV N97 ASME Boiler and Pressure Vessel git79-057 1979 R ASMEB&PV 1995

Code Code Code

Code Code1350 ASME ASME B&PV N/S ASME Boiler and Pressure Vesel gitBo-O9 1 1980 R ASMEB&PV 1995

Code Code Code

zc)i

-0:

zCi

'.0

LI)

0



R ecord U oandard - D oe. 'A cceptr an d L atest^ Stan dard L st V M i o n

o Stade Vocument Dated ai Ve

1351 ASME ASME B&PV N/S ASME Boiler and Pressure Vessel 91t95-0 20 1985 R ASME B&PV 1995

Code Code Code

1352 ASME ASME B&PV N/S ASME Boiler and Pressure Vessel glt91-001 1991 R ASME B&PV 1995

Code Code Code

1353 ASME ASME B&PV N/S ASME Bo5ler and Pressure Vessel gOt92-002 1992 R ASME B&PV 1995

Code Code Code

1354 ASME ASME B&PV N/S ASME Boiler and Pressure Vessel inm251511 10 1993 2 ASME B&PV 1995

Code Code Code

1355 ASME ASME B&PV N/S ASME Boiler and Pressure Vessel inm25l51114 1992 R ASMEB&PV 1995

Code Code Code

1356 ASME ASME B&Pv N/S ASME Boiler and Pressure Vessel inm2515/109 1993 R ASME B&PV 1995

Code Code Code

1357 ASME ASME B&PV N/S ASME Boiler and Pressure Vessel inm2700 1990 R ASME B&PV 1995

Code Code Code

1358 ASME ASME B&PV N/S ASME Boiler and Pressure Vessel inm6l715 1986 R. ASME B&PV 1995

Code Code Code

1359 ASME ASME B&PV N/S ASME Boiler and Pressure Vessel inm73756 1995 R ASME B&PV 1995

Code Code Code

16 1 ASME ASME B&PV N/S ASME Boiler and Pressure Vessel not79-1 1 1979 R -ASME B&PV 1995

Code Code Code

1361 ASME ASMEB&PFV N/S ASME Boiler and Pressure Vessel not81-31 1981 RF ASME B&PV 1995

Code Code Code

_362 ASME ASME B&PV N/S ASME Boiler and Pressure Vessel not84-52 19 A &PV 1995

Code Code Code

z

kA

tj0



.edord .a d .54...: Doe. t t tadard L e V

~ ~ C d e? Standard ` ~, V e ~ o T te docu m o n a e ab lt o m e t et l nD t

1363 ASME ASME B&PV N/S ASME Boiler and Pressure Vessel not84-52.sOl 1985 R ASME B&PV 1995

Code Code Code

1364 ASME ASME B&PV N/S ASME Boiler and Pressure Vessel not86-56 1986 R ASME B&PV 1995

Code Code Code

1365 ASME ASME B&PV N/S ASME Boiler and Pressure Vessel not89-7 9 1989 R ASME B&PV 1995

Code Code Code

1366 ASME ASME B&PV NIS ASME Boiler and Pressure Vessel not90-30 1 990 R ASME B&PV 1995

Code Code Code

1367 ASME ASME B&PV NIS ASME Boiler and Pressure Vessel polpr280 1988 P ASME B&PV 1995

Code Code Code

1368 ASME ASME B&PV NIS ASME Boiler and Pressure Vessel pol54FR7530 1989 R ASME B&PV 1995

Code Code Code

1369 ASME ASME B&PV N/S ASME Boiler and Pressure Vessel pol53FR21981 1988 R ASME B&PV 1995

Code Code Code

1370 ASME ASME B&PV NIS ASME Boiler and Pressure Vessel pol50FR32138 1985 R ASME B&PV 1995

Code Code Code

1371 ASME ASME B&PV NIS ASME Boiler and Pressure Vessel regl.139.rOO 1978 P ASME B&PV 1995

Code Code Code

1372 ASME ASME B&PV NIS ASME Boiler and Pressure Vessel sts4-ge5.7.2.12 1992 R ASME B&PV 1995

Code Code Code

1373 ASME ASMEB&PV NIS ASME Boiler and Pressure Vessel sts4-geB3.1.6 1992 R ASME B&PV 1995

Code Code Code

1374 ASME ASME B&PV NIS ASME Boiler and Pressure Vessel sts4-geB3.4.3 1992 R ASME B&PV 1

Code Code Code

z

?5s


N o .. C o s t ' 5 t:dit a f _ _ _ _ _ n V. a rXs - .l o T itl e ao t D a|t e a b l t t C m m n t t l | V er sao n . D t

1375 ASME ASME B&PV NIS ASME DOW and Pressure Vessel sts6-ge5.7.2 .12 1992 R ASME B&PV 1995

Code Code Code

1376 ASME ASME B&PV N/S ASME Boiler and Pressure Vessel sts6-geB3.1.6 1992 R As_ &pv 1995

Code Code Code

1377 ASME ASME B&PV N/S ASME 8oiler and Pressure Vessel stsb&w5.7.2.12 1992 R ASME B&PV 1995

Code Code Code

1378 ASME ASME B&PV NIS ASME Boiler and Pressure Vessel stsce5.7.2.12 1992 _ ASME B&PV 1995

Code Code Code

1379 ASME ASME B&PV N/S ASME Boiler and Pressure Vessel stswst5.7.2.12 1992 R ASME B&PV 1995

Code Code Code

1380 ASME ASME B&PV 1972 ASME Boiler and Pressure Vessel lOcfrSO App. G 1994 R ASME 8&PV 1995

Code Code Code

1381 ASME ASME B&PV N/S ASME Boiler and Pressure Vessel 10cfr50.55a 1994 R Footnotes to ASME B&PV 1995

Code Code CFR 50.55(a) Code

Addenda

1382 ASME ASME Code 1976 Foreign Produced Steel reg1.85.r30 1994 N Annulled by n/a n/a

Case 1141- ASME

1

1383 ASME ASME Code 1979 Requirements for Steel Forgings, reg1.85.r30 1994 N Annulled by n/a nea

Case 1332- Section III, Requirements for ASME

6 Corrosion-Resisting Steel Bars andShapes, Section ill

1384 ASME ASME Code 1978 Requirements for Bolting regl.85.r30 1994 N Annulled by n/a n/a

Case 1335- Materials, Section III ASME

9



eodStnadDoc. Accepot-: Lat:st StadardLastVeio

. Codei. Standard -ersioh *'dtm Tt D Dat ablt Com.ents Ve n Date

1385 ASME ASME Code 1975 Special Type 403 Modified reg1.85.r30 1994 N ASME Code 1993

Case 1337- Forgings or Bars, Section III, Case N-4-11

9 Division 1, Class 1 and CS

1386 ASME ASME Code 1978 Special Type 403 Modified regl.85.r30 1994 N ASME Code 1993

Case 1337- Forgings or Bars, Section 1II, Case N-4-11

10 Division 1, Class 1 and CS

1387 ASME ASME Code N/S Electroslag Welding, Sections I, Ill regl.34.rOO 1972 N Annulled by n/a n/a

Case 1355- and Vil, Divisions 1 and 2 ASME

3

1388 ASME ASME Code 1979 Socket Welds, Section III regl.84.r30 1994 N Annulled by n/a n/=

Case 1361- ASME

2

1389 ASME ASME Code 1979 SA-508, Class 2 Forgings with regl.85.r30 1994 N Annulled by n/a n/a

Case 1395- Modified Manganese Content, ASME

3 Section III or Section VilI, Division

1390 ASME ASME Code 1974 Time of Examination for Class 1, reg1.85.r30 1994 N Annulled by n/a n/a

Case 1407- 2, and 3, Section III Vessels ASME

2

1391 ASME ASME Code 1977 Modified High Yield Strength Steel reg1.85.r30 1994 N Annulled by n/a n/a

Case 1412- for Section III, Division 1, Class 1 ASME

4 Vessels

1392 ASME ASME Code 1976 High Yield Strength Cr-Mo Steel reg1.85.r30 1994 N Annulled by n/a n/a


3 Vessels

1393 ASME ASME Code 1977 High Yield Strength Cr-Mo Steel regi.85.r30 1994 N Annulled by n/a n1=


4 Vessels

U)

z

-3U)

Cs_

U)

c:

r_

.



eor;> < Stfi .. d. A et- L Lit it atet r d L4test ero

.. c o e ... . . . .. S t a d r $ ~ ~ i : K : - " " W D | u m n ^ ' . ., D + . b ~ t C o m m e r ..t s . . , e s o D M A

1394 ASME ASME Code 1977 Wrought Type 304 and 316 with regl.85.r30 1994 N Annulled by n/a n/a

Case 1423- Nitrogen Added, Sections I, Ill, ASME

2 Vill, Division 1 and 2

1395 ASME ASME Code 1978 Postweld Heat Treatment of SA- reg1.85.r30 1994 N Annulled by n/a n/a

Case 1434- 487 Class 8N Steel Castings, ASME

1 Section III

1396 ASME ASME Code 1977 Electron Beam Welding, Section 1, regy.84.r30 1994 N Annulled by n/a n/a

Case 1461- ill, and Villi, Division 1 and 2 ASME

1

1397 ASME ASME Code 1974 External Pressure Charts for High- regl.84.r30 1994 N Annulled by n/a n/a

Case 1470- Strength Carbon Steels and for ASME

2 Low-Alloy Steels, Section Vill,Division 1 and 2, and Section III

1398 ASME ASME Code 1978 Vacuum Electron Beam Welding of regl.84.r30 1994 N Annulled by n/a nla

Case 1471- Tube Sheet Joints, Section III ASME

1n /

1399 ASME ASME Code 1975 Ferritic-Austenitic Stainless Steel reg .85.r30 1994 N Annulled by n/a n/a

Case 1475- Seamless Tubes for Section III, ASME

1 Class 2 and 3 Construction

1400 ASME ASME Code 1978 Use of 1970 Addenda of ANSI reg1.84,r30 1994 N Annulled by n/a nla

Case 1477- B31.7, Section III ASME

1

1401 ASME ASME Code 1974 SB-163 Nickel-Chromium Iron regl.85.r30 1994 N ASME Code 1994

Case 1484- Tubing (Alloy 600) at a Specified Case N-20-3

1 Minimum Yield Strength of 40.0Ksi, Section ill, Class 1



Recdid- S * ;ndsdeEE|; Docue Do. Acet. - Latest Stndr LatVeso

Case 1484- Iron Tubing (Alloy 600 and 690)CaeN2-2 and Nickel-Iron Chromium Alloy

800 at a Specified Minimum Yield.Strength of 40.0 Ksi, Section IaL,Division 1, Class 1

1403 ASME ASME Code 1986 SB-163 Nickel-Chromium(N-20) regl.85.r30 1994 N Annulled by nla n/a

Case 1484- Iron Tubing (Alloy 600 and 690) ASME

3 and Nickel-Iron Chromium Alloy800 at a Specified Minimum Yield

Strength of 40.0 Ksi, Section III,

Division 1, Class 2

1404 ASME ASME Code 1975 Post Weld Heat Treatment, reg1.85.r30 1994 N Annulled by n/a nia

Case 1492 Section i, Ill and V 6II, Division 1 ASME

and 2

1405 ASME ASME Code 1973 Weld Procedure Qualiication Test, reg1.84.r30 1994 N Annulled by n/a a/a

Case 1494- Section III ASME

1

140 AS ME E Code 1978 S reg1.84.r30 1994 N Annulled by n/a na

Case 1506 Section 1II, Class 2 and 3 Piping ASME

1407 ASME ASME Code 1975 Allowable Stresses, Design reg1.84.r30 1994 N Anulled by n/a n/a

Case 1508 Intensity and/or Yield Strength ASME

Values, Section I, Ill, and Vil,

Divisions 1 and 2 _______

1408 ASME ASME Code 1977 Ultrasonic Examination of Ring reg1 .85.r30 1994 N Annulled by n/a n/a

Case 1515 Forgings for Shell Sections, ASME

Section III, Class 1 Vessels

U)

z

U'

'10

z

:U'%0

AD


i e o dS o d i r D o d . A c t -L t s S a n r d L t 1 V r io n

N o o e t h a r$ iVr ~ nT i l o u e tD t e b l t ~ C m e t :V e lo l Dot

1409 ASME ASME Code 1975 Welding of Seats in Valves for regl.84.r30 1994 N Annulled by n/a n/a

Case 1516- Section III Applications ASME

1

1410 ASME ASME Code 1980 Welding of Seats in Valves for reg1.84.r30 1994 N Annulled by n/a n/a

Case 1516- Section III Applications ASME

2

1411 ASME ASME Code 1978 Use of H-Grades of SA-240, SA- regl.85.r30 1994 N Annulled by n/a n/a

Case 1521- 479, SA-336, and SA-358, ASME

1 Section III

1412 ASME ASME Code 1991 Integrally Finned Tubes, Section III reg1.85.r30 1994 N Annulled by n/a n/a

Case 1527 ASME

1413 ASME ASME Code 1978 High Strength Steel SA-508, regl.85.r30 1994 N Annulled by n/a n/a

Case 1528- Class 2 and SA-541, Class 2 ASME

3 Forgings, Section liI, Class 1

Components 194 N Anledb____

1414 ASME ASME Code 1973 Materials for Instrument Line regl .85.r30 1994 N Annulled by nla n/a

Case 1529 Fittings, Section III ASME

1415 ASME ASME Code 1977 Electrical Penetrations, Special regl.85.r30 1994 N Annulled by n/a n/a

Case 1531 Alloys for Electrical Penetration ASMESeals, Section III

1416 ASME ASME Code 1978 Section III, Class 3 Components reg1.85,r30 1994 N Annulled by nla n/a

Case 1532 Made of 8 Percent and 9 Percent ASMENickel Steel

1417 ASME ASME Code 1975 Pressure Temperature Ratings of reg1.84.r30 1994 N Annulled by n/a n/a

Case 1533 SA-35 of SA-351 Grades CF8A, ASMECF3, and CF3M, Section III



Record tndd Do. Atoe 0t Lates Stanrdard Laest Version

.zo. codel tada Versio Title Doate nbilitN om nt VersiOt ate

1418 ASME ASME Code 1977 Hydrostatic Testing of Section 111, regl.84.r30 1994 N Annulled by n/a n/a

Case 1535- Class 1 Valves ASME

2

1419 ASME ASME Code 1977 Closing Seam for Electrical reg :.84.r30 1994 N Annulled by nWa n/a

Case 1536 Penetrations for Section III, Class ASME2, 3, and MC

1420 ASME ASME Code 1977 Elastomer Diaphragm Valves, regl.84.r30 1994 N Annulled by n/a n/a

Case 1540- Section III Class 2 and 3 ASME

1421 ASME ASME Code 1976 Hydrostatic Testing of Embedded regl.84.r30 1994 N Annulled by n/a n/a

Case 1541- Class 2 and Class 3 Piping for ASME

i1 Section III Construction

1422 ASME ASME Code 1978 Hydrostatic Testing of Embedded regl .84.r30 1994 N Annulled by n/a n/a

Case 1541 - Class 2 and Class 3 Piping for ASME

2 Section III Construction

1423 ASME ASME Code 1977 Design by Analysis of Section 1I1, regl .84.r30 1994 N Annulled by nla n/a

Case 1552 Class 1 Valves ASME

1424 ASME SME Code 1975 Upset Heading and Roll Threading regI.84.r30 1994 N Annulled by n/a nla

Case 1553 of SA-453 for Bolting in Section III ASME

1425 ASME ASME Code 1976 Upset Heading and Roll Threading reg1.84.r30 1994 N Annulled by n/ana

Case 1553- of SA-453 for Bolting in Section III ASME

1:

1426 ASME ASME Code 1977 Certification of Safety Relief regl.84.r30 1994 N Annulled by n/a nia

Case 1555 Valves on Liquids ASME

-4

z

C-)

- 4

z

I-,

L.)

00


Rfeordteir dae . t t, tV ts nN oSo d ta f d a id V e e0 :i l o u e t D t bi i y C i t t n sV r l nD t

1427 ASME ASME Code 1978 Certification of Safety Relief reg1 .84.r30 1994 N Annulled by n/a n/a

Case 1555- Valves, Section III, Division 1 ASME

1

1428 ASME ASME Code 1979 Steel Products Refined by reg1.85.r30 1994 N Annulled by nla n/a

Case 1557- Secondary Remelting, Section III ASME

2 and Vill, Division 1 and 2

1429 ASME ASME Code 1978 Testing Lots of Carbon and Low reg1.85.r30 1994 N Annulled by n/a n/a

Case 1567 Alloy Steel Covered Electrodes, ASMESection III

1430 ASME ASME Code 1978 Testing Lots of Flux Cored and regi.85.r30 1994 N Annulled by n/a n/a

Case 1568 Fabricated Carbon and Low Alloy ASMESteel Welding Electrodes, Section

1431 ASME ASME Code 1979 Design of Piping for Pressure regi.84.r30 1994 N Annulled by n/a n/a

Case 1569 Relief Valve Station, Section III ASME

1432 ASME ASME Code 1978 Vacuum Relief Valves, Section III reg1.84.r30 1994 N Annulled by n/a n/a

Case 1573 ASME

1433 ASME ASME Code 1974 Hydrostatic Test Pressure for regl.84.r30 1994 N Annulled by n/a n/a

Case 1574 Safety Relief Valves, Section III ASME

1434 ASME ASME Code 1978 Buttwelded Alignment Tolerance reg1.84.r30 1994 N Annulled by n/a n/a

Case 1580- and Acceptable Slopes for ASME

1 Concentric Centerlines for SectionIll, Class 1, 2, and 3 Construction


Raod SndadDe. 'Ace Lats S tnad Latest versloni

N. Cd. tadd VerlnTi DOcument" Dae Abiity Cotins Version Date:

1435 ASME ASME Code 1979 Power-Operated Pressure Relief reg1.84.r30 1994 N Annulled by n/a n/a

Case 1581 Valves, Section III ASME

1436 ASME ASME Code 1977 Use of 80-40 Carbon Steel reg1.85.r30 1994 N Annulled by n/a n/a

Case 1583 Castings, Section III ASME

1437 ASME ASME Code 1975 SA-508 Class 3 Forgings with reg1.85.r30 1994 N Annulled by n/a n/a

Case 1587 0.4/1.0 Ni for Section III and Vil, ASMEDivision 2 Construction ChemicalAnalysis Variations, Section IIIConstruction

1438 ASME ASME Code 1977 Chemical Analysis Variations, reg1.8.r30 1994 N Annulled by n/a n/a

Case 1590 Section III Construction ASME

1439 ASME ASME Code 1974 Section 1II, Class 1 Components in reg1.87.rOl 1975 N Annulled by n/a n/a

Case 1592 Elevated Temperature Service ASME

1440 ASME ASME Code 1973 Fabrication and Installation of regi .87.rO1 1975 N Annulled by n/a n/a

Case 1593 Elevated Temperature ASMEComponents

1441 ASME ASME Code 1973 Examination of Elevated regi.87.rOl 1975 N Annulled by n/a n/a

Case 1594 Temperature Components ASME

1442 ASME ASME Code 1973 Testing of Elevated Temperature reg1.87.rO1 1975 N Annulled by n/a n/a

Case 1595 Components ASME

'0

z

C)

'0n-

z

P-

L,)

61


r Standafrd D"e Accept- Latest Stan ard L tiet Vrsion

~N o C od ei LStahdird er i nT teD c m t D J te~ abilit Co mrn hts 7 V etso n Dat

1443 ASME ASME Code 1973 Protection Against Overpressure reg1.87.rO1 1975 N Annulled by n/a n/a

Case 1596 of Elevated Temperature ASMEComponents

1444 ASME ASME Code 1974 Limits of Reinforcement for Two- regl.84.r30 1994 N Annulled by n/a n/a

Case 1601 Thirds Area, Section III, Class 1 ASME

1445 ASME ASME Code 1974 Use of SB-42 Alloy 122, SB-111 reg1.85.r30 1994 N Annulled by n/a n/a

Case 1602- Alloys 122, 715 and 706, SB-171 ASME1 Alloys 715 and 706 and SB-466

Alloys 706 and 715, Section Ill,Class 2 and 3 Components

1446 ASME ASME Code 1974 Toughness Tests When Cross- reg1.85.r30 1994 N Annulled by n/a n/a

Case 1603 Section Limits Orientation and ASMELocation of Specimens

1447 ASME ASME Code 1980 Cr-Ni-Mo-V Bolting Material for reg1.85.r30 1994 N Annulled by n/a n/a

Case 1605 Section lil, Class 1 Components ASME

1448 ASME ASME Code 1974 Stress Criteria for Section III, reg1.84.r30 1994 N Annulled by n/a n/a

Case 1606 Class 2 and 3 Piping Subjected to ASMEUpset, Emergency, and FaultedOperating Conditions

1449 ASME ASME Code 1977 Stress Criteria Section III, Classes reg1.84.r30 1994 N Annulled by n/a n/a

Case 1606- 2 and 3 Piping Subject to Upset, ASME1 Emergency, and Faulted Operating

Conditions


.. r.; . . .; .. . . .5 . . ... :~ -LX . :~.,j.S:Sd. -: i .d,....f i.. .0if.0,

ecdStd ad - D: A t at; Standad L. VEsi

1450 ASME ASME Code 1974 Stress Criteria for Section 1II, reg1.84.r30 1994 N Annulled by n/a n/a

Case 1607 Classes 2 and 3 Vessels ASMESubjected to Upset, Emergency,and Faulted Operating Conditions

1451 ASME ASME Code 1977 Stress Criteria for Section 11I, reg1.84.r30 1994 N Annulled by n/a n/a

Case 1607- Classes 2 and 3 Vessels Designed ASME

1 to NC/ND-3300 Excluding the NC-3200 Alternate

1452 ASME ASME Code 1977 Use of ASME S8-265, SB-337, SB regl.85.r30 1994 N Annulled by n/a n/a

Case 1608- 338, SB-348, and SB-381, Grades ASME

1 1, 2, 3, and 7 Unalloyed Titaniumand ASTM B-363 TitaniumWelding Fittings, Section Ill Class2 and 3 Components

1453 ASME ASME Code 1978 Use of SA-372 Class IV Forgings, regi.85.r30 1994 N Annulled by n/a n/a

Case 1613 Section IlIl Construction ASME

1454 ASME ASME Code 1979 Hydrostatic Testing of Piping Prior reg1.84.r30 1994 N Annulled by n/a n/a

Case 1614 To or Following the Installation of ASMESpray Nozzles for Section IlIl,

Class 1 Construction

1455 ASME ASME Code 1978 Use of A587-73, Section ill, Class regl.85.r30 1994 N Annulled by n/a n/a

Case 161 5 3 Construction ASME

1456 ASME ASME Code 1975 Ultrasonic Examination of regi.85,r30 1994 N Annulled by n/a n/a

Case 1616 Seamless Austenitic Steel Pipe, ASMESection IlIl, Class 1 Construction

z

'0

w.

tjh



dD A teStandard Latest Versilon_

Code Standard Version Th~~~s. Djocumont Dt ablt Cmens Vronat

14 ASME AS C M ateri ASME Code 1994

Case 1fi18 Structures, Section ill, Division 1 Case N-60-S

1458 ASME ASME Code 1976 Material for Core Support 85.r3 1994 N ASME Code 994

Case 1618- Structures, Section III, Division 1 Case N-60-5

1

1459 ASME ASME Code 1976 PWHT of Repair Welds in Carbon regj.85.r30 1994 N Annulled by n/a n/a

Case 1622 Steel Castings, Section III, Class ASME

1, 2, and 3

i1460 ASME ASME Code 1979 Design by Analysis for Section III, regl .84.30 1994 N Annulled by n/a nla

Case 1623 Class I Sleeve-Coupled and Other ASME

Patented Piping Joints

1461 ASME ASME Code 1974 Repair of Section III Class 2 and 3 reg1.85.r30 1994 N Annulled by n/a nla

Case 1625 Tanks ASME

1462 ASME S o 1979 Norm-lalized and Tempered 1-1/4 reg1 .85.r30 1994 N Annulled by n/a n/a

Case 1626 Cr Low Alloy Steel Forgings, ASMESection 1, Section III, and SectionVilI, Division 1 and 2

4----0-- r: .. 1Arn 1994 N Annulled bv n/a n/a1~~JI.... urain _,T .e~ . I

1463 ASME ASME CodeCase 1633

I1URI brazing Ot Zbea175 10 'bAklb 1, dc,

and 3 Valve Body or Bonnets,Section III

: I .11 . v ,

ASME

I

__---____ .1 - . ... Annud bna I n/aI UsIf B3b orscto in, rag _A 11 . I A n id1464 ASME ASME Code

Case 16341974 Use of SBC359 tor Section uIc,

Class 3 Constructionrey I .85-K30 , -:, A.-M..E ,

ASME

L I _ _I__ _I__ _ - I__ _ _ _ _ _ I.. . . . . I__ _ - - -- - - _ _ _ _ I _ _ _ _ _ _ _ _ _ _



..4 .... ... . PIPoc;K f

1465 ASME ASME Code 1976 Use of SB-359 for Section III, regl.85.r30 1994 N Annulled by n/a n/a

Case 1634- Class 3 Construction ASME

1

1466 ASME ASME Code 1977 Stress Criteria for Section ill, regl.84.r30 1994 N Annulled by n/a n/a

Case 1635- Class 2 and 3 Valves Subjected to ASME

1 Upset, Emergency, and FaultedOperating Conditions

1467 ASME ASME Code 1977 Stress Criteria for Section III, regl.84.r30 1994 N Annulled by n/a

Case 1636- Class 2 and 3 Pumps Subjected to ASME

1 Upset, Emergency, and FaultedOperating Conditions

1468 ASME ASME Code 1975 Effective Date for Compliance regl.85.r30 1994 N Annulled by n/en/a

Case 1637 with NA-3700 of Section III ASME

1469 ASME ASME Code N/S Additional Materials for regl.124.rOl 1978 N ASME Code 1993

Case 1644 Subsection NF, Class 1, 2, 3 and Case N-71-16

MC Component SupportsFabricated by Welding, Section III,Division 1

1470 ASME ASME Code N/S Additional Materials for regl.130.rOl 1978 N ASME Code 1993


MC Component SupportsFabricated by Welding, Section III,

Division 1

1471 ASME ASME Code 1975 Additional Materials for regl.85.r30 1994 N ASME Code 1993


MC Component SupportsFabricated by Welding, Section III,

Division 1 I

z

no

w

zci

(5



ER co ddDL t dard Latest Version

No. Code Standard Version Ti t Hod 1 ' i 0 ate ablity Cow

1472 ASME ASME Code 1975 Additional Materials for regi .85.r30 1994 N ASME Code 1993

Case 1644- Subsection NF, Class 1, 2, 3 and Case N-71-16

1 MC Component SupportsFabricated by Welding, Section III,Division 1

1473 ASME ASME Code 1975 Additional Materials for regi.85.r30 1994 N ASME Code 1993





3 MC Component SupportsFabricated by Welding, Section lii,Division 1




1476 ASME ASME Code 1977 Additional Materials for regl.85,r30 1994 N ASME Code 1


5 MC Component SupportsFabricated by Welding, Section ill,Division 1

1477 ASME ASME Code 1977 Additional Materials for regl .85.r30 1994 N ASME Code 1993


6 MC Component SupportsFabricated by Welding, Section III,

Division 1

1478 ASME ASME Code 1976 Use of DeLong Diagram for regl ,85,r30 1994 N Annulled by n/a n/a

Case 1645 Calculating the Delta Ferrite ASMEContent of Welds in Section III,Class 1, 2, and CS Construction

IL.



No oe tnar esinTtl oumDt Ablte Comments Vetelon Date

1479 ASME ASME Code 1976 SA-537 Plates for Section III, regl.85.r30 1994 N Annulled by n/a n/a

Case 1648 Class 1, 2, 3, and MC ASME

Components

1480 ASME ASME Code 1976 Modified SA 453-GR 660 for regi .85.r30 1994 N Annulled by n/a n/a

Case 1649 Class 1, 2, 3, and CS ASMEConstruction

1481 ASME ASME Code 1974 Use of SA-4 14 Grade C for Class regl.85.r30 1994 N Annulled by n/a n/a

Case 1650 2 and 3 Components, Section III, ASMEDivision 1

1482 ASME ASME Code 1974 interim Requirements for reg1.84.r30 1994 N Annulled by n/a n/a

Case 1651 Certification of Component ASMESupports, Section III, SubsectionNFN _ _ _. __ ___

1483 ASME ASME Code 1977 Stress Criteria for Class 2 and 3 regl.84.r30 1994 N Annulled by n/a n/a

Case 1657 Atmospheric and Low Pressure (0- ASME1 5 psig) Steel Storage Tanks

1484 ASME ASME Code 1977 interconnection of Two Piping regl.84.r30 1994 N Annulled by n/a n/a

Case 1659 Systems for Section 1II, Class 1, ASME2, and 3 Construction

1485 ASME ASME Code 1978 Postweld Heat Treatment P-No. 1 regl.84.r30 1994 N Annulled by n/a n/a

Case 1661 Materials for Section III, Class I ASME

Vessels

1486 ASME ASME Code 1978 Shop Assembly of Components, reg1.84.r30 1994 N Annulled by n/a nla

Case 1662 Appurtenances and Piping ASMESubassemblies for Section III,Class 1. 2, 3 and MC

Construction

z

C0

(-I'-35¢vW

w

z

U'

CD)

0~'



R ecord ......ta r , . .D ..: a a r . .er.ion.- 0iR rd;;$ ^ - : - l.X) . itf X. | ~~~~~~. . . -̂ .l -........ ; .0 at;:t...... ;;

.;X;No. Code 'i :sd - .Stand rd .: V; e i Title Doc D t C m ts Ve t.

1487 ASME ASME Code 1977 Use of Cr-Ni-Fe-Mo-Cu-Cb reg1.85.r30 1994 N Annulled by n/a n/a

Case 1664 Stabilized Alloy Cb-3 for Section ASME

lil Class 2 and 3 Construction

1488 ASME ASME Code 1975 Use of SB-12, Alloy 122 for regl.85.r30 1994 N Annulled by n/a n/a

Case 1666 Section Ill, Class 2 and 3 ASME

Construction

1489 ASME ASME Code 1977 Nuclear Valves for Section IlIl, reg1.84.r30 1994 N Annulled by n/a n/a

Case 1672 Division 1 Class 1, 2, 3 ASMEConstruction

1490 ASME ASME Code 1976 Tubesheet to Shell or Formed regl.84.r30 1994 N Annulled by n/a n/a

Case 1675 Head Weld Joints, Section IlIl, ASMEClass I Vessels

1491 ASME ASME Code 1976 Clarification of Stress Intensities regl.84.r30 1994 N Annulled by n/a n/a

Case 1676 in Curved Pipe or Welded Elbows, ASME

Section IlIl

1492 ASME ASME Code 1980 Butterfly Valves of Circular Cross regl,84.r30 1994 N Annulled by n/a n/a

Case 1678 Section Larger than 24 in. NPS for ASMESection Illi, Class 2 and 3Construction

1493 ASME ASME Code 1975 Alternate Rules for Material regl.85.r30 1994 N Annulled by n/a n/a

Case 1682 Manufacturers and Suppliers, ASME

Section IlIl, Subarticle NA-3700

1494 ASME ASME Code 1975 Alternate Rules for Material regl.85.r30 1994 N Annulled by n/a n/a

Case 1682- Manufacturers and Suppliers, ASME

1 Section IlIl, Subarticle NA-3700

1495 ASME ASME Code 1976 Bolt Holes for Section 1II, Division reg1.84.r30 1994 N Annulled by n/a n/a

Case 1683 1, Class 1, 2, 3 and MC ASMEComponent Supports



ReodSad e. Accpt Lais Sandard Latest Veralef

N. oz | ^ tan::Cdard f Veio TtlDouet Dat _blt _oimt _Vro Dat

1496 ASME ASME Code 1976 Bolt Holes for Section 1ii, Division regl .84.r30 1994 N Annulled by n/a n/a

Case 1683- 1, Class 1, 2, 3 and MC ASME

1 Component Supports

1497 ASME ASME Code 1976 A637 Grade 718 for Bolting Class reg1.85.r30 1994 N Annulled by nla n/_

Case 1684 1 and 2 Construction ASME

1498 ASME ASME Code 1978 Furnace Brazing Section i, Class regl .84.r30 1994 N Annulled by n/a a

Case 1685 1, 2, 3 and MC Construction ASME

1499 ASME ASME Code 1978 Furnace Brazing, Section I11, regl.84.r30 1994 N Annulled by n/a n/a

Case 1686 Subsection NF, Component ASMESupports

1500 ASME ASME Code 1976 Alternate PWHT Time and regl.84.r30 1994 N Annulled by n/a n/a

Case 1689 Temperature for SA-182 Grade ASMEF22 Section lIl, Class 1, 2, 3 and

.__ CS ,,___- ___ .______

1501 ASME ASME Code 1978 Alternate PWHT Time and reg1.84.r30 1994 N Annulled by n/a n/a

Case 1689- Temperature for SA-182 Grade F- ASME

1 22, SA-387 Grade 22, Class 2,and SA-335 Grade P-22 SectionIII, Class 1, 2, 3 and CS

1502 ASME ASME Code 1975 Stock Materials for Section Ill regl.85.r30 1994 N Annulled by n/a n/a

Case 1690 Construction, Section III, Division ASME1

1503 ASME ASME Code 1978 Ultrasonic Examination in Lieu of regl .85.r30 1994 N Annulled by n/a n/a

Case 1691 Radiography of Repair Welds for ASME

Vessels, Section lIl, Class 1

ZC-�9C)rtA104

w

iFw

~4.

~0


Ri tc -d - Stand rd iD . Ac Lat~st :tandard atet Version

N o. C o d e ; s ta nd a ed V e so n -Ti lD c u nt D at ab lt0 1m etWer i nD t

1504 ASME ASME Code 1976 Brazing, Section III, Class 3 regl.84.r30 1994 N Annulled by n/a n/a

Case 1695 ASME

15 05 ASME ASME Code 1978 Determination of Capacities of regl .84.r30 1994 N Annulled by n/a n/a

Case 1701 Vacuum Relief Valves Section III, ASMEClass MC

1606 ASME ASME Code 1977 Flanged Valves Larger than 24 reg1.84.r30 1994 N Annulled by n/a n/a

Case 1702 inches for Section 1II, Class 1, 2 ASMEand 3 Construction

1507 ASME ASME Code 1978 Brazing of Copper Alloys Section regl.84.r30 1994 N Annulled by n/a n/a

Case 1703 III, Class 2 ASME

1508 ASME ASME Code 1975 Data Report Forms for Component regl.84.r30 1994 N Annulled by n/a n/a

Case 1706 Supports, Section III, Class 1, 2 ASMEand 3

1509 ASME ASME Code 1975 Small Material Items, Section III, reg1.85.r30 1994 N Annulled by n/a n/a

Case 1713 Division 1, Class 1, 2, 3, CS and ASMEMC

1510 ASME ASME Code 1977 Postweld Heat Treatment of P-1 regl.85.r30 1994 N Annulled by n/a n/a

Case 1714 Material, Section III, Class MC ASME

1511 ASME ASME Code 1976 Design of Structural Connections regl .84,r30 1994 N Annulled by n/a n/a

Case 1718 for Linear Type Component ASMESupports, Section 1II, Division 1,Class 1, 2 and 3 and MC



Co, t di . m u bae b - C V dona

1512 ASME ASME Code 1976 Single-Welded, Full-.Penetration regl .84.r3 1994 N Annulled by n/a n/a

Case 1719 Sidewall Butt Joints in ASME

Atmospheric Storage Tanks,Section iII, Division 1, Class 2

1513 ASME ASME Code 1976 Weld End Preparation for Section reg1.84,r30 1994 N Annulled by n/a n/a

Case 1720 III, Division 1 Construction ASME

1514 ASME-- ASME Code 1979 Weld End_ Preparatilon for Section regl1 84.r30 1 99_4 N Annulled by n/ana

Case 1720- i, Division 1 Construction ASME

1

1515 ASME ASME Code 1979 Vacuum, Carbon Deoxidized SA- regl.85.r30 1994 N Annulled by n/an/

Case 1722 508 Forgings, Section 1II, Division ASME

1, and VIII, Division 1 and 2

156 ASME ASME Code 1975 Steel Structural Shapes anSmlrel5r3 199 N Annulled by n/a

Case 1727 Material Products for Component ASME

Supports, Section III, Division 1

Construction

1517 ASME ASME Code 1977 Steel St rnd Small reg1.85.r30 1994 N Annulled by n/a n/a

Case 1728 Material Products for Component ASME

Supports, Section III, Division 1Construction

1518 ASME ASME Code 1975 Examination - Acceptance reg 1.143.rOl 1979 N Annulled by n/a n/s

Case 1738 Standards for Surface Indications ASME

in Cladding, Section Xi

1519 ASME ASME Code 1976 Weld Metal Test, Section III, Class reg1.85.r30 1994 N Annulled by n/a nla

Case 1740 1, 2, 3, MC and CS ASME

. --- -.---

z

t5l

LA)

z

(5

0



tdat | D cet- Latist Standrd Latt Verion

-ii N o . C o d S taus h i-: :0 g nd rd . V er. i o nite Dic m e n D att a b il t . .z ity C o t l e t V e. o D at

1520 ASME ASME Code 1977 Interim Rules for the Required regl.85.r30 1994 N Annulled by n/a n/a

Case 1741 Number of Impact Tests for Rolled ASME

Shapes, Section lil, Division 1,Subsection NF, ComponentSupports

1521 ASME ASME Code 1978 Interim Rules for the Required regi.85.r30 1994 N Annulled by n/an/a

Case 1741- Number of Impact Tests for Rolled ASME

1 Shapes, Section 1II, Division 1,Subsection NF, ComponentSupports

1522 ASME ASME Code 1976 Use of SB-75 Annealed Copper regl.85.r30 1994 N Annulled by nan/a

Case 1742 Alloy 122, Section lil, Division 1, ASMEClass 2 Construction

1523 ASME ASME Code 1976 Use of SB-98 Cu-SiB Rod reg1 .85.r30 1994 N Annulled by n/an/a

Case 1743 CDA651 Section IlIl, Division 1, ASMEClass 2 Components

1524 ASME ASME Code 1977 Alternative Rules for Examination regi .85.r30 1994 N Annulled by n/an/a

Case 1755 of Welds in Piping, Class 1 and 2 ASME

Construction, Section IlIl, Division

1525 ASME ASME Code 1992 Alternative Rules for Examination reg1.i5.r30 1994 N Annulled by n/an/a

Case 1755- of Welds in Piping, Class 1 and 2 ASME

1 Construction, Section 111, Division2

1526 ASME ASME Code 1978 Material for Internal Pressure regl .85.r30 1994 N Annulled by n/an/a

Case 1759 Retaining Items for Pressure Relief ASMEValves, Section IlIl, Division 1,Class 1, 2, and 3

1527 ASME ASME Code 1978 Maximum Dimensions for Isolated regl.85.r30 1994 N Annulled by n/an/a

Case 1760 Pores in Welds--Class 1 ASMEComponents, Section IlIl, Division1 _ _ _


R cord Standard; atest tandard L.te Version

o. Codle Stanfdard V...io Ti.. Dometune aliy~Cmet Voerson Dt1528 ASME ASME Code 1977 Use of SB-148 Alloy CA954 for regl.84.r30 1994 N ASME Code 1994

Case 1761 Section IlIl, Division 1, Class 2 or Case N-133-3

3 Flanged End Valves

1529 ASME ASME Code 1977 Machining After Hydrostatic regl.84.r30 1994 N Annulled by n/a n/a

Case 1765 Testing Class 2 and 3 ASMEConstruction, Section 111, Division1

1530 ASME ASME Code 1977 Testing Requirements for Welding regl.85.r30 1994 N Annulled by n/a n/a

Case 1766 Materials, Class 1, 2, 3, MC and ASMECS Construction, Section III,Division 1

1531 ASME ASME Code 1977 Examination of Tubular Products regl.85.r30 1994 N Annulled by n/a n/a

Case 1767 Without Filler Metal--Class 1 ASMEConstruction, Section IlIl, Division1

1532 ASME ASME Code 1978 Permanent Attachments to regl.84.r30 1994 N Annulled by n/a n/a

Case 1768 Containment Vessels--Class MC, ASMESection IlIl, Division 1

1533 ASME ASME Code 1977 Qualification of NDE Level Ill regi.84.r30 1994 N Annulled by n/a n/a

Case 1769 Personnel, Section Ill, Division 1 ASME

1534 ASME ASME Code 1977 Qualification of NDE Level Ill regil .84.r30 1994 N Annulled by n/a n/a

Case 1769- Personnel, Section IlIl, Division 1 ASME

1

1535 ASME ASME Code 1977 Use of Other Product Forms of reg1.85.r30 1994 N Annulled by n/a n/a

Case 1773 Materials for Valves, Section 111, ASMEDivision 1

1536 ASME ASME Code 1977 Minimum Wall Thickness for Class regl.84.r30 1994 N Annulled by n/a n/a

Case 1774 2 and 3 Valves, Section IlIl, ASMEDivision 1

zci

10~

z

VI

(5



Recor - - Standrd ' ;,, ~e. A~Opt- Latst Sandad Letet Vrsio

N, ce¾ Sadd Vrin ' ie>Document; Da bll~ Comns VrinDat

1537 ASME ASME Code 1979 Data Report Forms for Core regi.84.r30 1994 N Annulled by n/a n/a

Case 1775 Support Structures, Class CS, ASME

Section III, Division 1

1538 ASME ASME Code 1977 Use of SA-106, Grade C in Class reg1.85.r30 1994 N Annulled by n/a n/a

Case 1777 MC Construction, Section III, ASMEDivision 1

1539 ASME ASME Code 1978 Hydrostatic Testing and Stamping regl.84.r30 1994 N Annulled by n/a n/a

Case 1780 of Pumps for Class 1 ASME

Construction, Section 11I, Division

1540 ASME ASME Code 1977 Qualification of Nondestructive regl .84.r30 1994 N Annulled by n/a n/a

Case 1783 Examination Personnel, Section I11, ASMEDivision 1

1541 ASME ASME Code 1979 Qualification of Nondestructive regl.84.r30 1994 N Annulled by n/a n/a

Case 1783- Examination Personnel, Section I11, ASME

1 Division 1

1542 ASME ASME Code 1978 Depth of Weld Repairs for regl.85.r30 1994 N Annulled by na n/a

Case 1787 Forgings, Section III Division 1, ASMEClass 1, 2, 3, MC and CSConstruction Structural SteelRolled Shapes, Section III, Division1, Class 2, 3, and MC _-

1543 ASME ASME Code 1978 Use of ASTM A352-75, Grades regl.85.r30 1994 N Annulled by n/a n/a

Case 1798 LCA and LCC, Section III, Division ASME1, Class 1, 2, and 3

1544 ASME ASME Code 1978 F-Number Classification of Low regl.84.r30 1994 N Annulled by n/a n/a

Case 1808 Allow and Carbon Steel Bare Rod ASMEElectrodes Sections I, II, Ill, IV, VIVIII, and IX



Record Satar Doe MOetLts Stndard Litastetverglon

1545 ASME ASME Code 1980 Testing Lots of Carbon Steel reg I.85.r30 1994 N Annulled by n/a n/a

Case 1810 Solid, Bare Welding Elec-trode or ASME

Wire, Section Ill, Division 1, Class1, 2, 3, MC, and CS

1546 AsME ASME Code 1978 Use of Type XM-19 for regl.85.r30 1994 N Annulled by n/a nla

Case 1819 Construction, Section IlIl Division ASME

1, Class 1, 2, and 3

1547 ASME ASME Code 1982 Requirements for Steel Forgings, regl,85.r30 1994 N Annulled by n/a nia

Case N-1 -7 Section III, Division 1 ASME

(1332-71

1548 ASME ASME Code 1981 Steel Bars and Shapes, Section III regl.85.r30 1994 N Annulled by n/a n/a

Case N-2 ASME

(1334-3)

1549 ASME ASME Code 1984 Requirements for Bolting reg1.85.r30 1994 N Annulled by n/a n/a

Case N-3-10 Materials, Section III ASME

(1335-10)

1550 ASME ASME Code 1990 Special Type 403 Modified reg1.85.r30 1994 A ASME Code 1993

Case N-4-11 Forgings or Bars, Section III, Case N-4-1 1

(1337-11) Division 1, Class 1 and CS

1551 AME ASME Code 1982 Nickel-Chromium, Age Hardenable reg1.85.r30 1994 N Annulled by n/a

Case N-5 Alloys (Alloy X750), Section III ASME

(1344-5)

1552 ASME ASME Code 1985 Nickel Chromium Age Hardenable regi .85r30 1994 N Annulled by n/a n/a

Case N-5-1 Alloys (Alloy X750), Section ill, ASME

Division 1, Classes 1, 2, 3, MC,and CS ___ . _

z

ci

t~h

L.)



ec dS anda d -D c. A c p-L at m M Stanidard Lates V0rsion

_o Cod St: a a :r i V eri; - ocument b Ve ln

1553 ASME ASME Code 1979 Requirements for Nickel- regl.85.r30 1994 N Annulled by n/a n/a

Case N-6 Molybdenum-Chromium-Iron ASME

(1345-2) Alloys, Section IlIl

1554 ASME ASME Code 1982 High Yield Strength Steel, Section reg1.85.r30 1994 N ASME Code 1992

Case N-7 Ill, Division 1, Class 1 Vessels Case N-7-1

(1358-5)

1555 ASME ASME Code 1992 High Yield Strength Steel, Section regl.85.030 1994 A ASME Code 1992

Case N-7-1 Ill, Division 1, Class 1 Vessels Case N-7-1

1556 ASME ASME Code 1982 SA-508, Class 2 Forgings with reg1.85.r30 1994 N Annulled by n/a n/a

Case N-9-4 Modified Manganese Content, ASME

(1395-4) Section Ill

1557 ASME ASME Code 1987 Time of Examination for Classes regl .85.r30 1994 N Annulled by n/a n/a

Case N-10 1, 2, and 3 Section Illi Vessels ASME

(1407-3)

1558 ASME ASME Code 1980 High Yield Strength Cr-Mo Steel regl.85.r30 1994 N Annulled by n/a n/a

Case N-1 1-5 for Section 1II, Division 1, Class 1 ASME

(1414-5) Vessels

1559 ASME ASME Code 1979 Substitution of Ultrasonic regl .85.r30 1994 N Annulled by n/a n/a

Case N-1i Examination for Progressive ASME

(1456-2) Penetrant or Magnetic ParticleExaminations of PartialPenetration and Oblique NozzleAttachment Welds, Section IlIl

1560 ASME ASME Code 1991 Integraily Finned Tubes for reg1.85.r30 1994 N Annulled by n/a n/a

Case N-1 7 Section IlIl ASME

(1474-1)



R....S.d.d oo ccpt LtstStnard LatestVersion

No. Cd Standard i Vorwo - TitleDcmn Dt blty Cmet Version Dt

1561 ASME ASME Coda 1985 SB-163 Nickel-Chromium Iron regl.85.r30 1994 N ASME Code 1991

Case N-20 Tubing (Alloy 600 and 690) and Case N-20-3

(1484-3) Nickel-Iron-Chromium Alloy 800 ata Specified Minimum YieldStrength of 40.0 Ksi, and ColdWorked Alloy 800 at a YieldStrength of 47.0 Ks!, Section III,Division 1, Class 1

1562 ASME ASME Code 1987 SB-1 63 Nickel-Chromium Iron reg1.85.r30 1994 N CasMe Code 1991

Case N-20-1 Tubing (Alloy 600 and 690) andCae-23Nickel-Iron-Chromium Alloy 800 ata Specified Minimum YieldStrength of 40.0 Ksi, and ColdWorked Alloy 800 at a YieldStrength of 47.0 Ksi, Section III,Division 1, Class 1

153 AMSAMBoe 98 5-163 Nickel-Chromium Iron regl.85.r30 1994 N ASME Code 1991

Case N-20-2 Tubing (Alloy 600 and 690) andNickel-Iron-Chromium Alloy 800 ata Specified Minimum YieldStrength of 40.0 Ksi, and ColdWorked Alloy 800 at a YieldStrength of 47.0 Ksi Section III,Division 1, Class 1

1 - n-f1 CD12 laS KHM,1Lrh-him Inn rpnn _95.r30 1994 1 A JASME Code 1991

LAU',

z

q)

-4

Cs

1564 AbMt

Case N-20-31 Z70 1

Tubing (Alloy 600 and 690) andNickel-Iron-Chromium Alloy 800 ala Specified Minimum YieldStrength of 40.0 Ksi, and ColdWorked Alloy 800 at a YieldStrength of 47.0 Ksi, Section III.Division 1, Class 1

Case N-20-3

___ ___ __ I __ _ _ _ _I __ _ _ _ _I I I I _ _ _ _ _ _ _ _ _

'C

-'I


R . or .St e n d. d .U- D oe. A c e t- .at est Si tan d ard te t V e r

N od eCo de * S t an d a d Vr'nT t eD c m n e e a ~ i y C m e t V er io q W D a te :

1565 ASME ASME Code 1982 SA-508-Class 2 and 3, Minimum regl.85.r30 1994 N Annulled by n/a n/a

Case N-22 Tempering Temperature, Section ASME

11498-1) lII

1566 ASME ASME Code 1980 Welding of Seats or Minor Internal regl.84.r30 1994 N Annulled by n/a n/a

Case N-24 Permanent Attachments in Valves ASME

(1516-2) for Section ill Applications

1567 ASME ASME Code 1991 Integrally Finned Tubes, Section III regl.85.r30 1994 N Annulled by n/a n/a

Case N-26 ASME

(1527)

1568 ASME ASME Code 1981 Metal Bellows and Metal reg1 .84.r30 1994 N Annulled by n/a n/a

Case N-30-1 Diaphragm Stem Sealed Valves, ASME

(1539-1) Section IiI, Classes 1, 2, and 3

1569 ASME ASME Code 1985 Elastomer Diaphragm Valves, reg1.84.r30 1994 N Annulled by n/a n/a

Case N-31 Section III. Class 2 and 3 ASME

(1540-21

1570 ASME ASME Code 1991 Elastomer Diaphragm Valves, regl .84.r30 1994 P Annulled by n/a n/a

Case N-31-1 Section IR, Class 2 and 3 ASME

1571 ASME ASME Code 1979 Hydrostatic Testing of Embedded reg1.84.r30 1994 N Annulled by n/a n/a

Case N-32-3 Class 2 and Class 3 Piping for ASME

(1541-3) Section III Construction

1572 ASME ASME Code 1984 Hydrostatic Testing of Embedded reg .84.r30 1994 N Annulled by n/a n/a

Case N-32-4 Class 2 and 3 Piping for Section ASME,ll, Division I Construction

1673 ASME ASME Code 1985 Type 403 Forgings or Bars for regl.85.r30 1994 N Annulled by n/a n/a

Case N-33 Bolting Material, Section IlIl ASME

(1542-1)


Recorda Standar Dc. -Accept lLa-tet Stndard Latest VersIon

. Code Standard Verio Tht 5ocument d Dat abili te

1574 ASME ASME Code 1981 Inservice Inspection of Welds on regl .147.r1 1 1994 N Annulled by n/a n/a

Case N-34 Nuclear Components, Section Xl ASME(1551)

1575 ASME ASME Code 1979 Design by Analysis of Section III, reg1.84.r30 1994 N Annulled by nla n/a

Case N-35-1 Class 1 Valves ASME(1552-1)

1576 ASME ASME Code 1982 Steel Products Refined by regl.85.r30 1994 N Annulled by n/a n/a

Case N-37-3 Secondary Remelting, Section III ASME

(1557-3) and VIII, Division 1 and 2

1577 ASME ASME Code 1985 Additional Material for SA-234 reg1.85.r30 1994 N Annulled by n/a n/a

Case N-41 Carbon Steel Fittings, Section III ASME(1571)

1578 ASME ASME Code 1982 SB-167 Nickel-Chromium-Iron regl.85.r30 1994 N Annulled by n/a n/a

Case N-43 (Alloy 600) Pipe or Tube, Section ASME(1578) III

1579 ASME ASME Code 1982 Electro-Etching of Section III Code regl.84.r30 1994 N Annulled by n/a n/a

Case N-46 Symbols ASME(1588)

1580 ASME ASME Code 1984 Inertia and Continuous Drive (N- reg1.84.r30 1994 N Annulled by n/a n/a

Case N-55 55) Friction Welding, Section I, Ill, ASME(1609-1) IV, VIII, Division 1 and 2, and IX

1581 ASME ASME Code 1987 Inertia and Continuous Drive regl.84.r30 1994 N Annulled by nWa n/a

Case N-55-1 Friction Welding, Section 1II, ASME(1609) Division 1

1582 ASME ASME Code 1973 Use of Type 308 Stainless Steel reg1 .85.r30 1994 N Annulled by n/a n/a

Case N-56 Rod and Bar for Section III, Class ASME(1612) 1, 2, 3, and CS Construction

zC)1

tk)

\0


aRecord * . ' Stndard ' ,o A' pt- at Stenda d Lete Ot oh

N o.0 Code Standard ; V erson Til D cument Dt 0 te ii C m n V rsonte

1583 ASME ASME Code 1983 Material for Core Support regl.85.r30 1994 N ASME Code 1994

Case N-60 Structures, Section 111, Division 1 Case N-60-5

(1618-2)

1584 ASME ASME Code 1984 Material for Core Support reg1.85.r30 1994 N ASME Code 1994

Case N-60-1 Structures, Section IlIl, Division 1 Case N-60-5


Case N-60-2 Structures, Section 1I1, Division 1 Case N-60-5


Case N-60-3 Structures, Section IlIl, Division 1 Case N-60-5

1587 ASME ASME Code 1991 Material for Core Support regl.85.r30 1994 P ASME Code 1994

Case N-60-4 Structures, Section lIl, Division 1 Case N-60-5

1588 ASME ASME Code 1982 Stress Category for Partial regl.84.r30 1994 N Annulled by nlan/a

Case N-61 Penetration Welded Penetrations, ASME

(1620) Section 111, Class 1 Construction

1689 ASME ASME Code N/S Internal and External Valve Items, regl.148.rOO 1981 N ASME Code 1994

Case N-62-2 Section 1II, Division 1, Classes 1, Case N-62-7

2 and 3

1590 ASME ASME Code 1985 Internal and External Valve Items, regl.84.r3O 1994 N ASME Code 1994

Case N-62-2 Section 1II, Division 1, Class 1, 2 Case N-62-7

(1621-1) and 3

1591 ASME ASME Code 1985 Internal and External Valve Items, reg1.84.r30 1994 N ASME Code 1994

Case N-62-3 Section IlI, Division 1, Class 1, 2 Case N-62-7

and 3.



192 ASM |ASME CodE 198 dr |internal and External Valv Igtes rel.4.3 199 Nj ~ ASM Cod 1994l m

Case N-62-4 Section ll, Division 1, Ciass 1, 2 Case N-62-7

and 3

1593 ASME ASME Code 1989 Internal and External Va veItes reg1 .84.r30 1994 N AAS M E Code 1994

Case N-62-5 SeCtion III, Division 1, Class 1, 2 Case N-62-7

and 3

1594 ASME ASME Code 1989 Internal and External Valve Items, regi.84.r30 1994 P ASME Code 1994

Case N-62-6 Section ll, Division 1, Class 1, 2 Case N-62-7

and 3

1595 ASME ASME Code 1985 Normalized and Tempered 1-1/4 regl.85.r30 1994 N Annulled by n/a

Case N-65-1 Cr Low Allow Steel Forgingss ASME

(1 626-11 Section I and Section las

1596 AASME SME Code 1987 External Pressure Charts for High regl.84.r30 1994 N Annulled by n/a n/a

Case N-66-1 Yield Strength Carbon Steels and ASME

(1630-1) Low Alloy Steels. (Yield Strengthabove 38 Ksi to 60 Ksi Inclusive.)

For Section Ill, Class 1, 2, 3, andMC

1597 ASME ASME Code 1978 Use of SB-359 for Section Illi, regt.85.r30 1994 N Annulled by n/a n/a

Case N-68 Division 1, Class 3 Construction ASME

(1634-2)

-onAI IPrIAib {qr .. n1 Rl 1994 N ASME Code 1993

'0

<5

6t.

1598 ASME ASME CodeCase N-71-711644-7)

I Y78 Additional IvaturicsI 101Subsection NF, Class 1, 2, 3 andMC Component SupportsFabricated by Welding, Section Ill,Division 1

.Uy .-. u .. -v wNA

Case N-71-16

I L I . L ..-. ..I . . I I _ _- --_ _

z

'0

-4



Record - tandard DCC Accpt Lae StDad ae tVe io

1699 ASME ASME Code 1980 Additional Materials for regi.85.r30 1994 N ASME Code 1993

Case N-71-8 Subsection NF, Class 1, 2, 3 and Case N-71-16

(1644-8) MC Component SupportsFabricated by Welding, Section III,Division 1 _ _ _ _ _ _

1600 ASME ASME Code 1981 Additional Materials or regi.85.r30 1994 N ASME Code 1993

Case N-71-9 Subsection NF, Class 1, 2, 3 and Case N-71-16

(1644-9) MC Component SupportsFabricated by Welding, Section 1II,Division 1

1601 ASME ASME Code 1982 Additional Materials for reg1.85.r30 1994 N ASME Code 1993

Case N-71- Subsection NF, Class 1, 2, 3 and Case N-71-16

10 MC Component SupportsFabricated by Welding, Section 111,

D ivision 1 _ _ _ _ _ _ __ _ _ _



11 MC Component SupportsFabricated by Welding, Section 1II,Division 1

-

- A S MEd eC

o de41 9 9 3

1603 i-i ASME Code 1984 Additional Materials for regl .85.r30 1994 NAME 1993


12 MC Component SupportsFabricated by Welding, Section Ill,Division 1

1604 iASME ASME Code 1986 Additional Materials for re-1.85.r30 1994 N ASME Code 1993



1605 ASME ASME Code 1986 Additional Materials for regl .85.r30 1994 N ASME Code 1993


14 MC Component SupportsFabricated by Welding, Section III,

Division 1 _ .. _ _ _



RtideSeidr - DO AcetLt'Standard LatestVrso

cd St-nd..d..V. io -.. t ^ c .e. ^ i llj CommantCd Vnitsi:Da -teld :

1606 ASME ASME Code 1989 Additional Materials for regl.85.r30 1994 P ASME Code 1993

Case N-71 - Subsection NF, Class 1, 2, 3 and Case N-71-16

15 MC Component SupportsFabricated by Welding, Section IlIl,Division 1

1607 ASME ASME Code 1978 Partial Postponement of Category regi. 1 47.r 11 1994 N Annulled by n/a n/a

Case N-72 B-C Examination for Class 1 ASME

(1646) Components, Section Xl

1608 ASME ASME Code 1978 Partial Postponement of Category reg1.1 47.r 1 1994 N Annulled by n/a n/a

Case N-73 8-D Examination for Class 1 ASME

(1647) Components, Section Xl

1609 ASME ASME Code 1978 External Pressure Charts for High regl.84.r30 1994 N Annulled by n/a n/a

Case N-77 Yield Strength Carbon Steels and ASME

(1630) Low Alloy Steels. (Yield strengthabove 38 Ksi to 60 Ksi Inclusive.)For Section 1II, Class 1, 2, 3, andMC; and Section Vill, Division 1and 2

1610 ASME ASME Code 1979 Overpressure Protection Under reg1 .84.r30 1994 N Annulled by n/a nla

Case N-77 Emergency Operating Conditions ASME

(1660) for Section III, Class 1

1611 ASME ASME Code 1978 Pressure-Temperature Ratings for reg1.84.r30 1994 N Annulled by n/a n/a

Case N-81 Class 1 Valves Made from 5 Cr- ASME

(1665) 112 Mo, Section IlIl

1612 ASME ASME Code 1979 Clarification of Flange Design reg1.84.r30 1994 N Annulled by n/a n/a

Case N-82 Loads, Section III, Class 1, 2, and ASME

(1677) 3

(7s

z

'0

t.r

z

Vi

-4

(5

'-.

w-

0K


Record :Standard: D c A La;s t nd d L Version

i ; N o. c o de:Sta d ard V er iondentD o cu m ent D b C o m m ents V e D ate

1613 ASME ASME Code 1979 Organizations Accepting Overall regl.84.r30 1994 N Annulled by nla n/a

Case N-84 Responsibility for Section IlIl ASME

(1681-1) Construction

1614 ASME ASME Code 1978 Rules for Design of Welded Class regl.84.r30 1994 N Annulled by n/a n/a

Case N-90 1 Pumps ASME

1 692)

1615 ASME ASME Code 1981 Waiver of Ultrasonic Transfer reg1.85.r30 1994 N Annulled by nla n/a

Case N-92 Method, Section IlIl, V, and Vill, ASME

(1698) Division 1

1616 ASME ASME Code 1982 Determination of Capacities of reg1.84.r30 1994 N Annulled by n/a n/a

Case N-94 Liquid Relief Valves, Section 1II, ASME

(1700) Division 1, Class 1, 2, and 3

1617 ASME ASME Code 1979 Determination of Capacities of reg1.84.r30 1994 N Annulled by n/a nla

Case N-95-1 Vacuum Relief Valves, Section IlIl, ASME(1701-1) Division 1 and 2, Class MC

1618 ASME ASME Code 1982 Determination of Capacities of reg1.84.r30 1994 N Annulled by n/a n/a

Case N-96-2 Vacuum Relief Valves, Section Ill, ASME

(1701-2) Division 1, Classes 2, 3, and MCand Division 2 ConcreteContainments

1619 ASME ASME Code 1980 Flanged Valves Larger than 24 reg .84.r30 1994 N Annulled by n/a n/a

Case N-96-1 inches for Section Illi, Division 1, ASME(1702-1) Class 1, 2 and 3 Construction

1620 ASME ASME Code 1990 Ultrasonic Examination -- regl.147.rl 1 1994 A ASME Code 1993

Case N-98 Calibration Block Tolerances, Case N-98

(1705-1) Section XI


d RAcod ;Standard: D c L s -t-nd td Ltt Vs

oNo. Cde . o Stanidad .- Verslon. . Domn Dae ab9t t V o D t -

1621 ASME ASME Code N/S Pressure Relief Valve Design srp3.9.3 1981 N Annulled by n/a n/a

Case N-100 Rules, Section 1I1, Division 1, ASME

(1711) Classes 1, 2, and 3

1622 ASME ASME Code 1983 Pressure Relief Valve Design reg1.84.r30 1994 N Annulled by n/a n/a

Case N-1 00 Rules, Section Ill, Division 1, ASME

(1711) Class 1, 2 and 3

1623 ASME ASME Code 1979 Nameplates and Stamping for reg1.84.r30 1994 N Annulled by n/a We

Case N-101 Section III, Division 1, Class 1, 2, ASME

(1712) 3 and MC Construction asReferenced in NA-8300

1624 ASME ASME Code 1978 Postweld Heat Treatment of P-1 regl.85.r30 1994 N Annulled by n/a n/a

Case N-102- Material, Section III, Class MC ASME

1 (1714-1)

1625 ASME ASME Code 1981 Postweld Heat Treatment of P-1 reg1.85.r30 1994 N Annulled by n/a n/a

Case N-102- Material, Section III, Class MC ASME

2 (1714-2)

1626 ASME ASME Code 1990 Weld End Preparation for Section reg1.84.r30 1994 P Annulled by n/a n/a

Case N-1 06- III, Division 1 Construction ASME

2 (1720-2)

1627 ASME ASME Code 1982 Vacuum, Carbon Deoxidized SA- regl.85.r30 1994 N Annulled by n/a n/a

Case N-107- 508 Forgings, Section 1II, Division ASME

1 (1722-1) 1, and VilI, Division 1 and 2

03\U.)

z

tri

'J0

z

c::U'

;0


A o' id Stand rd D... e Latest S dad Latest VeWsN o o eS t a n d r e s o i l e-D c m u t ' a e ' a i i y C m e t e t s ia ~~D a t e

1628 ASME ASME Code 1978 Deviation from the Specified regl.85.r30 1994 N Annulled by n/a n/a

Case N-I08 Silicon Ranges in ASME Material ASME(1724) Specifications, Section Ill, Division

1, and Vil, Division 1 and 2

1629 ASME ASME Code 1979 Refinement of Low Alloy Steel regl.84.r30 1994 N Annulled by n/a n/a

Case N-109 Heat Affected Zone Under Overlay ASME(1726) Cladding, Section 1II, Division 1,

Class 1 Components

1630 ASME ASME Code 1979 Alternate Test Fluids, Section IIl, regl.84.r30 1994 N Annulled by n/a n/a

Case N-1 10 Division I ASME(1727)

1631 ASME ASME Code 1979 Minimum Edge Distance-Bolting regl.84.r30 1994 N Annulled by n/a n/aCase N-111 for Section IlIl, Division 1, Class 1, ASME(1729) 2, and 3 and MC Construction of

Component Supports

1632 ASME ASME Code 1979 Acceptance Standards for Class 2 regi .147.rl 1 1994 N Annulled by n/a n/aCase N-1 12 and 3 Components, Section Xl, ASME(1730) Division 1

1633 ASME ASME Code 1982 Basic Calibration Block for regl.147.rl1 1994 N ASME Code 1993

Case N-1 13 Ultrasonic Examination of Welds Case N-113-1(1731) 10 in. to 13 in. Thick, Section Xl,

Division 1

1634 ASME ASME Code 1990 Basic Calibration Block for regl.1 47.r 1 1994 A ASME Code 1993

Case N-1 13- Ultrasonic Examination of Welds Case N-113-11 10 in. to 14 in. Thick, Section Xl,

Division 1


eRcord ; Cadar D Standard Ltet Ver sion0

No oa 6:: i Standard Version;;. TileDcuen bate 416i Commnts VerionDate

1635 ASME ASME Code 1979 Hard-surfaced Valves with Inlet reg1.84.r30 1994 N Annulled by n/a n/a

Case N-1 14 Connections less than 2-in. ASME

(1732) Nominal Pipe Size for Section 1II,Division 1 Class 1 and 2Construction

1636 ASME ASME Code 1978 Evaluation of Safe Shut Down regl .84.r30 1994 N Annulled by nla n/a

Case N-1 15 Earthquake Loadings for Section ASME

(1733) fii, Division 1, Class MCContainment Vessels

1637 ASME ASME Code 1978 Weld Design for Use for Section regl.84.r30 1994 N Annulled by n/a n/a

Case N-1 16 III, Division 1, Class 1, 2, 3 and ASME

(1734) MC Construction of ComponentSupports

1638 ASME ASME Code 1990 Examination -- Acceptance reg1.147.rl 1 1994 N Annulled by n/a n/

Case N- 18 Standards for Surface Indications ASME

(1738) in Cladding, Section Xl

1639 ASME ASME Code 1980 Pump Internal Items, Section III, regl.84.r30 1994 N Annulled by n/a n/a

Case N-119- Division 1, Class 1, 2, and 3 ASME

2 (1739-2)

1640 ASME ASME Code 1980 Pump Internal Items, Section II; , reg1.84.r30 1994 N Annulled by n/a nla

Case N-1 19- Division 1, Class 1, 2, and 3 ASME

3 (1739-3)

1641 ASME ASME Code 1985 Pump Internal Items, Section III, regl.84.r30 1994 N Annulled by n/a o/a

Case N-1 19- Division 1, Class 1, 2, and 3 ASME

4 (1739-4)

aN

t~1

C)4

~ziU'

tJh

C'I

z

U'1

0M

10.


Part A - Industry Consensus Codes and StandardsReod tA'ptL Latest V er.i

o ' cod e ta dar L VLa .. T DoE t D tem ts V' rs Date

1642 ASME ASME Code 1985 Pump Internal Items, Section III, regl,84.r30 1994 N Annulled by n/a n/a

Case N-1 19- Division 1, Class 1, 2, and 3 ASME5

1643 ASME ASME Code 1991 Pump Internal Items, Section III, regl.84.r30 1994 A Annulled by n/a n/a

Case N-119- Division 1, Class 1, 2, and 3 ASME

6

1644 ASME ASME Code 1979 Carbon Steel Pipe Flanges Larger regl.84.r30 1994 N Annulled by n/a n/a

Case N-121 than 24 in., Section III, Division ASME(1744)

1645 ASME ASME Code 1989 Stress Indices for Structural regl.84.r30 1994 N ASME Code 1994

Case N-1 22 Attachments, Class 1, Section III, Case N-1 22-2

(1745) Division 1

1646 ASME ASME Code 1979 Leak Testing of Seal Welds, regl.85.r30 1994 N Annulled by n/a n/a

Case N-123 Section 1II, Division 1, Class 1, 2, ASME

(1746) and 3 Construction

1647 ASME ASME Code 1984 Requirements for Martensitic reg1.85.r30 1994 N Annulled by n/a n/a

Case N-1 24 Stainless Steel Forgings with 13% ASME

(1747) Chromium and 4% Nickel, SectionIII, Division 1

1648 ASME ASME Code 1978 Low Carbon Austenitic Stainless regl.85.r30 1994 N Annulled by n/a n/a

Case N-1 25 Steel Pipe Welded With Filler ASME(1748) Metal, Section Ill, Division 1,

Construction



*-RAcord S; I St and9rd _

I F A A naeby n t|a Lat'|t e on

tir wuyi.fI uy .ps vv . __

1649 ASME

1650 ASME

ASME CodeCase N-126(1754)

ASME Code

Case N-127(1755-1)

ASME CodeCase N-131-1 (1759-1)

ASME CodeCase N-133(1761-1)

1 988t Nara Surlaumv by %11- ota-M ru1Method, Section 1II, Class 1, 2,and 3 Construction

1-1 I.--..--

I I I__ _ _ _ _ _ _ _ _ I. I ---4 --- -- I . ~. _ .

1651 ASME

1989

1990

19Y82

Alternative Rules for Examinationof Welds in Piping, Class 1 and 2Construction, Section III, Division1

Material for Internal PressureRetaining Items for Pressure ReliefValves, Section III, Division 1,Class 1, 2 and 3

ireg-l.85.r3u I YZI4 1\1

ASME__s ne ,on 1 1aOA N Anniulan nv Inla I *n/tA.. ,

IASME

IegiI.5. .c- r3 1 Q1A9regl .85.r30 1994 F

Case N-131-3I---.

I- I . _ ASME CIdA 1 1994

1652 1- ASME Use of SB-148 Alloys 952 and954, Section I1, Division 1, Class

iregl .84.r30 1 YY4+ III

Case N-1 33-3

3

__ __- I_ L.1 QA I K OA 1°. _ IASME Code | 1994

Case N-i 33- 11531 ASME PASME Code

Case N-133-1

Case N-133.15 7> ASME

1985

1985

1991

Use of SB-t48 Alloys YbZ anco954, Section 1II, Division 1, Class3

Fug . -,7 ...

reI I8.3 19 N 1 -rnau Iuy !RCelAUse of SB-148 Alloys 952 and954 Section 11I, Division 1, Class3

r eg1.84.r30 1994 TM AnSMnute. oy

ASME Case N-133-3. <_

Case N- 133-3

2z

~a-

I 176fW rq1 T

16551 ASME ASME CodeCase N-133-3

Use of SB-148 Aloys 952 and954 Section 1II, Division 1, Class3

regl1.84.r30 19U94 A' C -N- -3---

Case N- 133-3Ale

__ I __________________I _________I ________ . _____

z

C)

-4

(I

00


Re or S a d' d , . , , Do AC'cepto: Laes S a dard Watet Vers~io

N o C od i 0 te - biit Com m e t rin _ 'Dat

1656 ASME ASME Code 1979 Testing of Electroslag Wire and reg1.85.r30 1994 N Annulled by n/a n/a

Case N-139 Flux for Class 1, 2, 3, MC, and ASME

I1770) CS Construction, Section liI,Division 1

1657 ASME ASME Code 1985 Use of SA-453 Bolts in Service regi.85.r30 1994 N Annulled by n/a nia

Case N-1 40 Below 800 degrees F Without ASME

(1772) Stress Rupture Tests, Section III,Division 1

1658 ASME ASME Code 1980 Minimum Wall Thickness for Class regi.84.r30 1994 N Annulled by n/a n/a

Case N-142- 2 and 3 Valves. Section 111, ASME

1 (1774-1) Division 1

1659 ASME ASME Code 1982 Hydrostatic Testing and Stamping reg1.84.r30 1994 N Annulled by n/a n/a

Case N-146- of Pumps for Class 1 ASME

1 (1780-1) Construction, Section lII, Division2

1660 ASME ASME Code 1978 Use of Modified SA-487 Grade reg1.85.r30 1994 N Annulled by n/a n/a

Case N-147 CA6NM, Section III, Division 1, ASME

(1781) Class 1, 2, 3, MC or CS

1661 ASME ASME Code 1983 Use of Copper-Nickel Alloy 962 reg3.85.r30 1994 N Annulled by n/a n/a

Case N-148 for, Castings, Section ill, Division ASME

(1782) 1, Class 3 Construction

1662 ASME ASME Code 1985 Projection Resistance Welding of regl.84.r30 1994 N ASME Code 1992

Case N-1 54 Valve Seats. Section )II, Division Case N-1 54-1

(1791) 1, Class 1, 2 and 3 Valves



ecrStanrdD. Ac'ep.. Latest Standard Latest Verson

No. ~Code Stnad Vrsion''teDcmn ae ciit otnns VrinDt

1663 ASME ASME Code 1988 Projection Resistance Welding of reg ,84.r30 A ASME Code 1992

Case N-1 54- Valve Seats, Section IlIl, Division Case N-154-1

1 1, Class 1, 2 and 3 Valves

1664 ASME ASME Code N/S Fiberglass Reinforced regl .72.rO2 1978 N ASME Code 1994

Case N-155- Thermosetting Resin Pipe, Section Case N-1 55-2

1 (1792-1) III, Division I

1665 ASME ASME Code 1991 Fiberglass Reinforced reg1.84.r30 1994 P ASME Code 1994

Case N-155- Thermosetting Resin Pipe, Section Case N-1 55-2

2 (1792-2) III, Division 1

1666 ASME ASME Code 1986 Structural Steel Rolled Shapes, reg1.85.r30 1994 N Annulled by n/a n/a

Case N-1 56 Section III, Division 1, Class 2, 3, ASME

(17931 and MC

1667 ASME ASME Code 1983 Use of Seamless Al-Br, Alloy CDA regl.85.r30 1994 N Annulled by n/a n/a

Case N-157 614 Pipe, Section III, Division 1, ASME

(1794) Class 3:n/a

1668 ASME ASME Code 1978 Examination of Weld Repairs in reg1.85.r30 1994 N Annulled by n/a n/a

Case N-1 58 Forgings, Section III, Division 1, ASME

(1795) Class 1, 2, 3, MC and CS

1669 ASME ASME Code 1978 Body Neck Thickness regl.84.r30 1994 N Annulled by n/a nla

Case N-1 59 Determination for Valves with ASME

(1796) Inlet Connections 4-inch NominalPipe Size and Smaller, Section III,

Division 1, Class 1, 2, and 3

P

C-,\.-I

W!

z

0



Re o dS a d r .. Do...c pt LA~te tStandard Latest ~VersioniNo |. Coded A Stadrd rslr .m 'itl e-*| i Doc ent6 | ta ability .. Cmmts VeIn Dat

1670 ASME ASME Code 1985 Finned Tubing for Construction, regl.84.r30 1994 N ASME Code 1994

Case N-i1 60 Section IlIl, Division 1 Case N-160-1

(1797)

1671 ASME ASME Code 1991 Finned Tubing for Construction, reg1.84.r30 1994 A ASME Code 1994

Case N-1 60- Section Ill, Division 1 Case N-160-1

1

1672 ASME ASME Code 1977 Minimum Section Thickness regl.147.rl1 1994 N Annulled by n/a nia

Case N-167 Requirements for Repair of ASME

(1804) Nozzles, Section Xl, Division 1

1673 ASME ASME Code 1981 Size of Fillet Welds for Socket regl.84.r3; 1994 N Annulled by n/a n/a

Case N-1 74 Welding, of Piping, Section lii, ASME

(1812) Division 1

1674 ASME ASME Code 1979 Welded Joints in Component reg1 .84.r30 1994 N Annulled by n/a n/a

Case N-1 75 Standard Supports, Section IlIl, ASME

(1818) Division 1

1675 ASME ASME Code 1983 Use of Type XM-1 9 for regl.85.r30 1994 N Annulled by n/a

Case N-1 76- Construction, Section lil Division ASME

1 (1819-1) 1, Class 1, 2, and 3

1676 ASME ASME Code 1984 Alternative Ultrasonic Examination regi.85.r30 1994 N nnulled by n/a nla

Case N-1 77 Technique, Section 1I1, Division 1 ASME

(1820)

Codes and Standards .and Other Guidance Cited in Regulatory DocumentsPart A - Industry Consensus Codes and Standards

. .... .L t v ii

:Recordri b:-Wtt:... 5::-X-..U. StandatdQ Dcc :-cpt Lates Stadar Lae- Verst

:N. Cod . :Sta V l -; C e VeDst6o, lw: n: . Datew

1677 ASME ASME Code 1980 Use of ASTM B271, CDA 954, regl.8S.r30 1994 N Annulled by n/a n/a

Case N-1 78 Alloy 9C for Class 3 Construction, ASMESection lil, Division 1

1678 ASME ASME Code 1980 Openings in Valves for Section Ill, regl .84.r30 1994 N Annulled by n/a n/a

Case N-1 79 Division 1, Class 1, 2 and 3 ASME

Construction

1679 ASME ASME Code 1978 Examination of Springs for Class 1 reg1 .85.r30 1994 N Annulled by n/a n/a

Case N-180 Component Standard Supports, ASME

Section lil, Division 1

1680 ASME ASME Code 1980 Steel Castings Refined by the reg1.85.r30 1994 N Annulled by n/a r/r

Case N-1 81 Argon Decarburization Process, ASME

Section III, Division 1,Construction

1681 ASME ASME Code 1981 Alternate Rules for Procedure reg1.84.r30 1994 N Annulled by n/a n/a

Case N-1 82 Qualification Base Material ASMEOrientation, Section 111, Division 1,Class 2 and 3 Construction

1682 ASME ASME Code 1980 Use of Modified SA- 182 Grade regl.85.r30 1994 N Annulled by n/a n/a

Case N-1 83 F22 for Section III, Division 1, ASMEClass 1, 2 and 3 Construction

1683 ASME ASME Code 1979 Roll Threading of SA-453 Bolting regl.84.r30 1994 N Annulled by n/a nla

Case N-1 84 for Section III, Division 1, Class 1, ASME

2, 3 or CS Construction

1684 ASME ASME Code 1977 Use of Welded Ni-Fe-Cr-Mo-Cu regl.85.r30 1994 N ASME Code 1993

Case N-1 88 (Alloy 825) and Ni-Cr-Mo-Cb Case N-1 88-1

(Alloy 625) Tubing, Section III,Division 1, Class 2 and 3.

U,

C:

U)

U)

zC)~

F5

-3

Codes and Standards and Other Guidance Cited. in Regulatory Documents


Reeed0 Standard Doc. '' t.S Li-test St L Versio.

Noe. - -nCode: t 1 s Title Document Dt ility C e rsi Date

1685 ASME ASME Code 1990 Use of Welded Ni-Fe-Cr-Mo-Cu regl.85.r30 1994 A ASME Code 1993

Case N-188- (Alloy 825) and Ni-Cr-Mo-Cb Case N-1 88-1

1 (Alloy 625) Tubing, Section Iii,Division 1, Class 2 and 3.

1686 ASME ASME Code 1979 Primary Membrane Plus Primary regl.84.r30 1994 N Annulled by n/a n/a

Case N-189 Bending Stress Intensity Limits for ASME

Other Than Solid RectangularSections for Section 1I1, Division 1,Class MC Construction

1687 ASME ASME Code 1978 Use of SA-455 for Class 3 regl.85.r30 1994 N Annulled by n/a n/a

Case N-190 Components, Section lIl, Division ASME1

1688 ASME ASME Code 1979 Use of Braided Flexible regl.84.r30 1994 N ASME Code 1993

Case N-192 Connectors for Section 1I1, Division Case N-1 92-2

1, Class 1, 2, and 3 Construction

1689 ASME ASME Code 1981 Use of Braided Flexible regl.84.r30 1994 N ASME Code 1993

Case N-1 92- Connectors for Section IlIl, Division Case N-1 92-2

1 1, Class 1, 2, and 3 Construction

1690 ASME ASME Code 1990 Use of Braided Flexible regi.84.r30 1994 P ASME Code 1993

Case N-192- Connectors for Section IlIl, Division Case N-192

2 1, Class 1, 2, and 3 Construction

1691 ASME ASME Code 1980 Use of SB-61 and SB-62 Bronze regl.84.r30 1994 N Annulled by n/an/a

Case N-193 for Section IlIl, Division 1, Class 3 ASMEFlange and Socket Weld EndValves _



IeodSard d.. .D.... Acet' Latesit' Standard Latest VeMIonI :- .....r.Es. i -in

...........TLi. ;.;.. ,i ,-fES, t E t00i!i

N~o. Coe tandaird Vora" o Tit 'Dcmn at blt CoIns VralDt

1692 ASME ASME Code 1979 Exemption from the Shakedown regl.84.r30 1994 N Annulled by n/a n/a

Case N-1 96 Requirements When Plastic ASMEAnalysis is Performed for SectionIll, Division 1, Class 1Construction

1693 ASME ASME Code 1990 Exemption from the Shakedown reg1.84.r30 1994 A Annulled by n/a n/a

Case N-196- Requirements When Plastic ASME

1 Analysis is Performed for SectionIII, Division 1, Class 1 and CSConstruction

1694 ASME ASME Code 1981 Intervening Elements, Section III, regl.84.r30 1994 N Annulled by n/a

Case N-199 Division 1, Classes 1, 2,3 and ASME

MC Component Construction

1695 ASME ASME Code 1981 Use of Modified SA-508, Class 3, reg1.85.r30 1994 N Annulled by n/a n/a

Case N-204 and SA-541, Class 3 for Section ASME

Ill, Division 1, Class 1, 2, and 3Construction

1696 ASME ASME Code 1990 Use of Ductile Iron SA-395 for regl.85.r30 1994 A ASME Code 1993

Case N-205 Section lil, Division 1, Class 3 Case N-205

Construction

1697 ASME ASME Code 1983 Use of ASTM 8151-75 Copper- regl.85.r30 1994 N Annulled by n/a nla

Case N-206 Nickel Alloy 706 Rod and Bar for ASME

Section III, Division 1, Class 3

Construction

1698 ASME ASME Code 1979 Use of Modified SA-479 Type XM reg1.85.r30 1994 N Annulled by n/a n/a

Case N-207 19 for Section III, Division 1, ASME

Class 1, 2 or 3 Construction

-4

zC,

'0tA

(a0

zci

vb'0

(!5


Re o dS en eD c. Ac sM LateSt Stanidard L a~tes VersioniN o C d eS t , d ~ d V e s o z T t l - D o u m n ..... i l t y C o h r e ns, V efini tt

1699 ASME ASME Code 1985 Use of Modified SA-479 Type XM regl.85.r30 1994 N Annulled by n/a n/a

Case N-207- 19 for Section III, Division 1, ASMEClass 1, 2, 3, or CS Construction

1700 ASME ASME Code 1978 Exemption to Hydrostatic Tests reg .147.r 1 1994 N Annulled by n/a n/a

Case N-210 After Repairs, Section Xi, Division ASME. 1

1701 ASME ASME Code 1990 Recalibration of Ultrasonic regl .147.rl 1 1994 A ASME Code 1993

Case N-21 1 Equipment Upon Change of Case N-211

Personnel, Section Xl, Division 1

1702 ASME ASME Code 1981 Welding Procedure Qualification of regl.84.r30 1994 N Annulled by n/a n/a

Case N-212 Dissimilar Metal Welds When ASME

(1693) 'Buttering' with Alloy Weld Metaland Heat Treatment May BeInvolved, Section III, Division 1,and Section IX

1703 ASME ASME Code 1982 Use of SA-351, Grade CN7M, for regl.84.r30 1994 N Annulled by n/a n/a

Case N-214 Valves for Section III, Division 1, ASMEConstruction

1704 ASME ASME Code 1983 Use of SA-351 Grade CN7M, for regl.84.r30 1994 N Annulled by n/a n/a

Case N-214- Valves, Section III, Division 1 ASME

1

1705 ASME ASME Code 1983 Use of SA-351 Grade CN7M, for regl.84.r30 1994 N Annulled by n/a n/a

Case N-214- Valves, Section 111, Division 1 ASME

2

1706 ASME ASME Code 1981 Integrally Finned Titanium Tubes, regl.84.r30 1994 N Annulled by n/an/a

Case N-21 5 Section 1II, Division 1, Class 3 ASMEConstruction



RAc t K' . ats"at St andrd Laat sn

1707 ASME ASME Code 1987 Alternative Rules for Reactor regl .147.rl 1 1994 N Annulled by n/a n/a

Case N-216 Vessel Closure Stud Examination, ASME

Section Xl, Division 1

1708 ASME ASME Code 1987 Postweld Heat Treatment of Weld regl.84.r30 1994 N Annulled by n/a n/a

Case N-217- Deposit Cladding on Classes 1, 2, ASME

1 3, MC, and CS Items, Section Ill,Division 1

1709 ASME ASME Code 1984 Code Effective Date for regl .84.r30 1994 N Annulled by n/a n/a

Case N-220 Component Supports, Section 1II, ASMEDivision 1

1710 ASME ASME Code 1981 Requirements for Stainless Steel reg1.85.r30 1994 N Annulled by n/a n/a

Case N-223 Precipitation Hardening, Section ASMEIll, Division 1, Class MC

1711 ASME ASME Code 1981 Use of ASTM A500 Grade B and regl.85.r30 1994. N Annulled by n/a n/a

Case N-224 ASTM A501 Structural Tubing for ASMEWelded Attachments for SectionIll, Class 2, 3, and MC

1712 ASME ASME Code 1990 Use of ASTM AS00 Grade B and reg1.85.r30 1994 N Annulled by n/a nla

Case N-224- ASTM A501 Structural Tubing for ASME

1 Welded Attachments for SectionIll, Class 2, 3, and MC

1713 ASME ASME Code 1981 Certification and Identification of reg1.85.r30 1994 N Annulled by n/a n/a

Case N-225 Material for Component Supports, ASMESection i, Division 1

1714 ASME ASME Code 1980 Temporary Attachment of regt.84.r30 1994 N Annulled by n/a nla

Case N-226 Thermocouples, Section IlIl, ASMEDivision 1, Class 1, 2 and 3Component Construction

Uts

z

C)M

Uj

I~

(5

(-4~0


oC odeSta d rd '~: T t e: C D ate . eon Date

1715 ASME ASME Code 1982 Examination of Repair Welds, regl.85,r30 1994 N Annulled by n/a n/a

Case N-227 Section Ill, Class 2 and 3 Tanks ASME

1716 ASME ASME Code 1982 Alternate Rules for Sequence of reg1.84.r30 1994 N Annulled by n/a n/a

Case N-228 Completion of Code Data Report ASME

Forms and Stamping for SectionIll, Class 1, Z, 3 and MCConstruction

1717 ASME ASME Code 1988 Alternate Rules for Fabrication regl.84.r30 1994 N Annulled by n/a n/a

Case N-229 Welding S-148 Alloy CDA 954 ASME

for Section III, Division 1, Class 3

Construction

1718 ASME ASME Code 1987 Alternate Rules for PWHT of P-No. regl.84.r30 1994 N Annulled by n/a n/a

Case N-233 5, Group 4 Material for Section III, ASME

1719 ASME ASME Code 1990 Time Between Ultrasonic regl.147.rl 1 1994 N Annulled by n/a l/a

Case N-234 Calibration Checks, Section Xl, ASME

Division 1

1720 ASME ASME Code 1990 Ultrasonic Calibration Checks per regl.147.rl 1 1994 A ASME Code 1993

Case N-235 Section V, Section Xl, Division I Case N-235

1721 ASME ASME Code 1985 Repair and Replacement of Class regl.147.r1l 1994 N ASME Code 1994

Case N-236 MC Vessels, Section Xl, Division Case N-236-1

1722 ASME ASME Code 1991 Repair and Replacement of Class regl.147.rll 1994 A ASME Code 1994

Case N-236- MC Vessels, Section Xl, Division Case N-236-1

1 1



Ricord Standard .-- Dec. Pcet ,. Latt S a

-ate: V:r ion

No. Cod aE' Standard .'Version.i' d Ti tinI Docmn Date bil.t Comet Verion Dat

Case N-237 Piping, Section 111, DIvision 1 ASME

_ _ A E Code 1982.st.i etin of Internal reol B4.r30 1994 N Annulled by n/a n/aASME

1724 ASME ASME CodeCase N-237-

1

1 98s3 riyorosunitr I xsllH Ul 11 -6G ...-

Piping, Section Ill, Division 1,

Classes 2 and 3

.by . zv.v

ASME

II___ _ . I .A . - --- I Oa 1994 N Annulled by rn/a i n/aHydrostat.... tesin .. .r~ia


1 988 Hydirostatic: I estung OT ITMI I M

Piping, Section Ill, Division 1,Classes 2 and 3

i., -yIw9v l vw . .

ASME

I __ I I -- . - -... I _A I _. __nnt r,__: hA tn/a 1 n/aHigh empeature1-urace .a..n

1726 I ASME ASME Code

Case N-238

1982 High Temperature Furnace Brazing

of Seat Rings in Valve Bodies or

Bonnets for Section III, Division 1,

Class 1, 2, and 3 Valves

rag 1.-+I. §rV , 7-F I.M

ASME

'-3-- I

z

0

PO

-$3

I,)

-e -- .ts (IASMECod e 1993. - -I - , A ICa se NA .40

1727 1 ASME ASME CodeCase N-240

1990 Hydrostatic Testing of Open

Ended Piping, Section Ill, Divisionreg I .84.rov , WI4 .

Case N-240

1

_ I I J - . . L..- OA .'- ba A I T t tASME Code I 1992it~. i

1728 1 ASME ASME CoCase N-2

ASME CcCase N-2

cde41

1 989 Hydrostatic DIesting o1 Fiping,

Section lli, Division 1

rgI .U9 rv . - - r7

Case N-241

---_ _-__ _ _ _ . Q -A I Kt . . " ~ dii l r , .m h I n /a

1729 1 ASME42

1980- Materials Certification, Section III,Division 1, Classes 1, 2, 3, MC,and CS Construction

reg I .t5b.r.30 IYY4VI TV

ASMEqa}U

l I I -- ~~~ ~~ ~~I. - - 4 4 - - - - - t ,, .I I - - - - - i - - - . ! - - i .- I I . - -. - A 1r g -i


1984 Materials Certification, Section III,Division 1, Classes 1, 2, 3, MC,and CS Construction

reg 1.85-r60 I uu� I �

ASMEI U"* ,_e of: vQ{5 | 1aqiSN Anntillell DV lard I algared WX Wp-^utJ vr . .,

I________ I _________ I

z

00



Recod Standard| D Accrpt- Letet nStanda

rd Loteit Version

No. C d Stanidard Veso TteDo u e t selt omniment . Varsion D t

1731 ASME ASME Code 1991 Boundaries Within Castings Used regI.84.r30 1994 A ASME Code 1994

Case N-243 for Core Support Structures, Case N-243

Section III, Division 1, Class CS

1732 ASME ASME Code 1985 Use of ASTM B61-76 and B72-76 regl;85.r30 1994 N Annulled by n/a n/a

Case N-245 Copper Alloy Castings for Section ASME

III, Division 1, Class 3

Construction reN ASME Code 1992

173 ASME ASME Code 1982 Use of SB-169, Alloy CA 614, regl.85.r30 1994 N CasMe Code4199

Case N-246 Section 1I1, Division 1, Class 3 Case N-246-2

1734 ASME ASME Code 1983 Use of SB-169, Alloy CA 614, regl.85.r30 1994 N ASME Code 1992

Case N-246- Section III, Division 1, Class 3 Case N-246-2

1735 ASME ASME Code 1989 Use of SB-169, Alloy CA 614, regl.85.r30 1994 A ASME Code 1992

Case N-246- Section 111, Division 1, Class 3 Case N-246-2

2

1736 ASME ASME Code 1991 Certified Design Report Summary regl.84.r30 1994 A Annulled by n/a nla

Case N-247 for Component Stand-ard ASMESupports, Section III, Division 1,Class 1, 2,3 and MC

1737 ASME ASME Code 1980 Alternative Reference reg1 .85.r30 1994 N Annulled by n/a n/a

Case N-248 Radiographs, Section III, Division ASME

1, Classes 1, 2, 3, MC, and CSConstruction

1738 I ASME ASME Code 198i Additional Material for Subsection reg1.85.r30 1994 N ASME Code 1994

Case N-249 NF, Classes 1, 2, 3, and MC Case N-249-13

Component Supports FabricatedWithout Welding, Section 11I,Division 1



Record Standad 1, 2-Dec. Acept Ltest: Standard Lts eso

Nomcd Staridaid Vrln '> K il ouet Dt blt omns 'eso Date.

1739 ASME ASME Code 1982 Additional Material for Subsection regl.85.r30 1994 N ASME Code 1994

Case N-249- NF, Classes 1, 2, 3, and MC Case N-249-13

1 Component Supports FabricatedWithout Welding, Section Ill,Division 1

1740 ASME ASME Code 1983 Additional Material for Subsection reg1.85.r30 1994 N ASME C; 19



1741 ASME ASME.Code 1984 Additional Material for Subsection regl.85.r30 1994 N ASME Code 1994


3 Component Supports FabricatedWithout Welding, Section III,Division 1




1743 ASME ASME Code 1985 Additional Material for Subsection reg1.85.r30 1994 N ASME Code 1994





6 Component Supports FabricatedWithout Welding, Section I11,Division 1

z

C-,

MJ

C,

00

10



R ec rd i:t andaD . A ct. ...... at..es tnCr ate t V esOR r t 4; :f000-0000030tt li00ii 0?of 0 t.-.. : . -a :.Tit ;i :

.Code. tfn ddad s : -- ' - tl _ D oculent Dn D t -



7 Component Supports FabricatedWithout Welding, Section lil,Division 1


Casfe N-249- NF, Classes 1, 2, 3, and MC Case N-249-13

8 Component Supports FabricatedWithout Welding, Section IlIl,Division 1



9 Component Supports FabricatedWithout Welding, Section IlIl,Division 1



10 Component Supports FabricatedWithout Welding, Section IlI,Division 1

1749 ASME ASME Code 1991 Additional Material for Subsection regl.85.r30 1994 p ASME Code 1994



1750 ASME ASME Code 1982 Low Energy Capacitive Discharge regl.147.rl1 1994 N Annulled by nla n/a

Case N-252 Welding Method for Temporary or ASME

Permanent Attachments toComponents and Supports,Section IlIl, Division 1, and Xl

Codes and Standards and Other Guidance. Cited in Regulatory Documents


";Reordi Standar Doe. -AboepV LtetU Stanft tdard est Ves lon6

0No. C Standariid..;. . .id i . .: Title Document Dae a -t Come ; DVersion Date :

1751 ASME ASME Code 1982 Low Energy Capacitive Discharge regl.84.r30 1994 N Annulled by n/a n/a

Case N-252 Welding Method for Temporary or ASMEPermanent Attachments toComponents and Supports,Section III, Division 1, and XI

1752 ASME ASME Code 1984 Ni^Cu-Al Bolting Material SB 164 reg1.85.r30 1994 N Annulled by n/a n/a

Case N-259 Modified, Section III, Division 1, ASMEClass 3

1753 ASME ASME Code 1985 Weld Repair of SA-182 Type 316 regl.84.r30 1994 N Annulled by n/a n/a

Case N-260 Forgings Section lil, Division 1, ASMEClasses 1, 2, 3, and MC

1754 ASME ASME Code 1985 Weld Rep regl.84r30 1994 N Annulled by n/a n/a

Case N-260- Forgings, Section Illi, Division 1, ASME

1 Classes 1, 2, 3, and MC

1755 ASME ASME Code 1988 Weld Repair of SA-182 Type 316 regl.84.r30 1994 N Annulled by n/a n/a

Case N-260- Forgings, Section III, Division 1, ASME

2 Classes 1, 2, 3, and MC

1756 ASME ASME Code 1982 Weld Procedure Qualification for reg1.84.r30 1994 N Annulled by n/a n/a

Case N-261 Materials with Impact ASMERequirements for Section 1I1,Division 1, Class 3 Construction

1757 ASME ASME Code 1991 Electric Resistance Spot Welding regl .84.r30 1994 A Annulled by n/a n/a

Case N-262 for Structural Use in Component ASMESupports, Section III, Division 1

1758 ASME ASME Code 1983 Alternate Thread Forms, Series regl .84.r30 1994 N Annulled by n/a nla

Case N-263 and Fits for Component Supports, ASME

Section III, Division 1

00

z

tU,

z

100



Recd |StEtdard|185 DoEec ... | A pt' L..at Stana rdL...t Vesion|

SadD N-265 Sectintn ill, D1te

1759 ASME ASME Code 1985 Modified SA-487 Castings, Cas8. ; 1994 N ASME Code 1994

Case N-265 Section Ilil, Division 1, Class 1 Case N-265-l

1760 ASME ASME Code 1988 Modified SA-48 Catns ei.5r0 1994 A ASME Coe19

Case N-265- Section Ill, Division 1, Class 1 Case N-265--1

1

1761 ASME ASME Code 1981 Double-Wall Radiography, Section regl.85.r30 1994 N Annulled by n/a n/a

Case N-267 Ill, Division 1, Class 1 and 2 ASME

1762 ASME ASME Code 1986 SimpiidMthod for Analyzing regil.84.r30 1994 N Annuledb nan/

Case N-271 Flat Face Flanges with Metal to ASMEMetal Contact Outside the BoltCircle for Section IlIl, Class 2, 3,and MC Construction

1763 ASME ASME Code 1982 Compiling Data Report Forms, reg1 .84.r30 1994 N Annulled by n/a n/a

Case N-272 Section III, Division 1 ASME

n n/an/a

1764 ASME Code 1986 Alternative Rules for Examination 85.r3 1994 N Annulled by n/a

Case N-274 of Weld Repairs for Section IlIl. ASME

Division 1 Construction

__-_ _ __ _ -' A' *' S. = = _ r1 PA B40 194 N Annulled bY nla n/a

1765 ASME ASME CodeCase N-275

I Utsi Depair on 1eVUZ, Oenutil ....Division I

-I |.--. vv r vr 5

ASME

1766 ASME ASMbiE Cod 1986 [Welding of SA-358 Pipe, Section reyl.84.r30 1994 NWnuleeb l n/a

Case N-276 Ill, Division 1 .9ASME_I____ _ _ _ _


_eor Sitinda d D A Latest Standard Latest Ves ion.m wd0i t't0. t- 0X'Xi '-ii' f .0 . .X.. .0, , t - "'W iti'0''''0i'

N6o -. DCode ta ndeh1t erdion ' h~ -oumn .. C i Dt

1767 ASME ASME Code 1980 Use of Type XM-1 9 Austenitic reg1.85.r30 1994 N Annulled by n/a n/a

Case N-277 Stainless Steel for Section III, ASMEDivision 1, Class MC Construction

1768 ASME ASME Code 1992 Alternative Ultrasonic Calibration regl.147.rl 1 1994 N Annulled by n/a n/a

Case N-278 Block Configuration, 1-3131 and ASMET-434.3, Section Xl, Division 1

1769 ASME ASME Code 1981 Use of Torquing as a Locking regl.84.r30 1994 N Annulled by n/a n/a

Case N-279 Device for Section III, Division 1, ASMEClass 1, 2, 3, and MC ComponentSupports __ _

1770 ASME ASME Code 1981 Alternate Rules for Examination of reg1.84.r30 1994 N Annulled by n/a n/a

Case N-280 Welds in Section III, Class 3 ASMEStorage Tanks

1771 ASME ASME Code 1981 Welding Operator Performance reg1.84.r30 1994 N Annulled by n/a n/a

Case N-281 Qualification, Section III, Division ASME1

1772 ASME ASME Code 1989 Nameplates for Valves, Section i1, regl.84.r3O 1994 N Annulled by n/a n/a

Case N-282 Division 1, Class 1, 2, and ASMEConstruction

1773 ASME ASME Code 1989 Metal Containment Shell Buckling reg1.84.r30 1994 P ASME Code 1995

Case N-284 Design Methods, Section iii, Case N-284-1Division 1, Class MC

1774 ASME ASME Code 1983 Hydrostatic Test Requirements for reg9 .1 47. r1 1994 N Annulled by n/a n/a

Case N-288 Class 1 and Class 2 Components, ASMESection Xl, Division 1

00

zC)

'10

zCxi

PC

004:,



Reaord S Dest CStandard LaIs Ver-ion

N .c dS t n d a rd , ~ e s o T itlei C 4 D o u m n t :a e a i y C m m n sV r i nD t

1775 ASME ASME Code 1989 Depositing Weld Metal Prior to reg1.84.r30 1994 P ASME Code 1995

Case N-292 Preparing Ends For Welding, Case N-292

Section III, Division 1, Class 1, 2and 3 Construction

1776 ASME ASME Code 1989 SB-148Alloy 952 and 954. and regl.85.r30 1994 A ASME Code 1992

Case N-294 SB-62 Alloy 836 Fittings, Section Case N-294

Ill, Division 1, Class 2

1777 ASME ASME Code 1981 NCA-1 140, Materials, Section lil, regl.85.r30 1994 N Annulled by n/a nla

Case N-295 Division 1 ASME

1778 ASME ASME Code 1983 Welding Material, Section 111, reg .85.r30 1994 N Annulled by n/a n/

Case N-296 Division 1 Construction ASME

1779 ASME ASME Code 1983 Examination of Component regl.85.r30 1994 N Annulled by n/a n/a

Case N-298 Supports, Section III, Division 1, ASMEClass 1, 2, 3, and MC

1780 ASME ASME Code 1985 Use of Nickel-Chromium- reg1.85.r30 1994 N Annulled by n/a n/a

Case N-299 Molybdenum-Columbium Alloy ASME625 Forgings, Section III, Division1, Class 2 and Class 3Components

1781 ASME ASME Code 1987 Use of Nickel-Chromium regl .85.r30 1994 N Annulled by n/a n/a

Case N-299- Molybdenum-Columbium Alloy ASME

1 625 Forgings, Section ill, Division1, Class 2 and Class 3Components

1782 ASME ASME Code 1983 Pressure-Temperature Ratings, reg1.84.r30 1994 N Annulled by n/a n/a

Case N-300 Hydrostatic Tests, and Minimum ASMEWall Thickness of Valves, SectionIll, Division 1, Class 1



Recofd itedet c. ~~ Latest Standard Lates Version

Noa . lereon nDat

1783 ASME ASME Code 1983 Tack Welding, Section 111, Division regi .84.r3O 1994 N Annulled by n/n/

Case N-302 1 Construction ASME

1784 ASME ASME Code 1984 Use of 2OCr-25Ni-6Mo (Alloy UNS regl.84.r30 1994 N ASME Code 1993

Case N-304 N08366) Plate, Sheet, Strip and Case N-3044

Welded Pipe, Class 2 and 3

Section III, Division 1 ________

1785 ASME ASME Code 1985 Use of 20Cr-25Ni-6Mo (Alloy UNS regl .84.r3 1994 N ASME Code 1993

Case N-304- N08366) Plate, Sheet, Strip and Case N-304-4

1 Welded Pipe, Class 2 and 3Section III, Division 1 1994 . Co_ _1

1786 ASME ASME Code 1985 Use of 2OCr-25Ni-6Mo (Alloy UNS regl.84.r3Q 1994 N ASME Code 1993

Case N-304- N08366) Plate, Sheet, Strip and Case N-304-4

2 Welded Pipe, Class 2 and 3Section lI, Division 1

.____ __ . ~A.e itKAIA It--- INS Io, RA r. 1994 N ASME Code 1993ASME Cod us00

---1787 ASME ASME Code

Case N-304-3

Iutse/ use OT 1_iVr->"V3m-sVvw Heavy ,

N08366) Plate, Sheet, Strip and

Welded Pipe, Class 2 and 3

Ia ( w-_wvCase N-304-4

zcil

M~

tJ)

00L!A



S to. d . St a Ve o tl 2 D D at e abi.it Cts V D ati

1791 ASME ASME Code 1990 Revised Ultrasonic Examination reg1.147.rl 1 1994 A ASME Code 1993

Case N-307- Volume for Class 1 Bolting, Table Case N-307-1

1 IWB-2500-1, ExaminationCategory 8-G-1. When theExaminations Are Conducted fromthe Center-Drilled Hole, SectionXl, Division 1

1792 ASME ASME Code 1990 Documentation of Repairs and reg1.147.rll 1994 N Annulled by n/a n/a

Case N-308 Replacements of Compo-nents in ASMENuclear Power Plants, Section Xi,Division 1

1793 ASME ASME Code 1985 Identification of Materials for reg1.84.r30 1994 N ASME Code 1991

Case N-309 Component Supports, Section 1II, Case N-309-1

Division 1

1794 ASME ASME Code 1991 Identification of Materials for reg1.84.r30 1994 A ASME Code 1991

Case N-309- Component Supports, Section IlIl, Case N-309-1

1 Division 1

1795 ASME ASME Code 1982 Certification of Bolting Materials, reg1.85.r30 1994 N Annulled by nla n/a

Case N-31 0- Section 1II, Division 1, Class 1, 2, ASME1 3, MC and CS

1796 ASME ASME Code 1990 Alternative Examination of Outlet reg1 .147.r 1 1994 P ASME Code 1993

Case N-311 Nozzle on Secondary Side of Case N-311Steam Generators, Section Xl,Division 1

1797 ASME ASME Code 1989 Alternate Rules for Half Coupling reg1.84.r30 1994 A ASME Code 1992

Case N-313 Branch Connections, Section IlIl, Case N-313

Division 1

1798 ASME ASME Code 1984 Alternate Rules for Thread reg1.84.r30 1994 N Annulled by n/a n/a

Case N-314 Engagement, Section IlIl ASME



.eor S t .n da.r -ii. - iatst standard Latest Veirsion

No d. cod Standard eo T.t:: Documednt' Date bt Comfldent. Version Date

1799 ASME ASME Code 1989 Repair of Bellows, Section III, regl,84.r30 1994 P ASME Code 1992

Case N-315 Division 1 Case N-315

1800 ASME ASME Code 1990 Alternate Rules for Fillet Weld regi.84.r30 1994 A Annulled by n/a n/a

Case N-316 Dimensions for Socket Welded ASMEFittings, Section 11I, Division 1,Class 1, 2, and 3

1801 ASME ASME Code 1982 ASTM A276 Bar Section III, reg1.85.r30 1994 N Annulled by n/an/a


1802 ASME ASME Code 1984 Procedure for Evaluation of the reg1.84.r30 1994 N ASME Code 1994

Case N-318 Design of Rectangular Cross Case N-318-5

Section Attachments on Class 2or 3 Piping, Section III, Division 1

1803 ASME ASME Code 1984 Procedure for Evaluation of the regi.4.r30 1994 N ASME Code 1994

Case N-31 8- Design of Rectangular Cross Case N-318-5

1 Section Attachments on Class 2or 3 Piping, Section III, Division 1

1804 ASME ASME Code 1985 Procedure for Evaluation of the reg1.84.r30 1994 N ASME Code 1994

Case N-318- Design of Rectangular Cross Case N-318-5

2 Section Attachments on Class 2or 3 Piping, Section III, Division 1

1805 ASME ASME Code 1989 Procedure for Evaluation of the regl .84.r30 1994 N ASME Code 1994


3 Section Attachments on Class 2

or 3 Piping, Section III, Division 1

00

z

0

F-4

zci

C0

00

0W

toh%0



Recod Stndar Doe Accpt~Latest Standard Lates Version

No. :C dode - Sta ndard v eris~io n T iteDo u e t e ablt C ominments i V ersion D t

1806 ASME ASME Coda 1989 Procedure for Evaluation of the regl .84.r3| 1994 P ASME Coda 1994


4 Section Attachments on Class 2or 3 Piping, Section Ill, Division 1

1807 ASME ASME Code 1989 Alternate Procedure for Evaluation regl.84.r30 1994 N ASME Code 1995

Case N-319 of Stresses in Butt Weld Elbows in Case N-319-2

Class 1 Piping, Section lil, Division

1808 ASME ASME Code 1989 Alternate Procedure for Evaluation reg1.84.r30 1994 N ASME Code 1995

Case N-319- of Stresses in Butt Weld Elbows in Case N-319-2

1 Class 1 Piping, Section III, Division

1809 ASME ASME Code 1983 Alternate PWHT for SA-487, regl.84.r30 1994 N Annulled by n/a n/a

Case N-320 Grade CA6NM, Section 111, ASME

Division 1

1810 ASME ASME Code 1985 Use of Modified SA-249, Type reg1.85.r30 1994 N Annulled by n/a nia

Case N-321 304 for Section III, Division 1, ASMEClass 1 Construction

1811 ASME ASME Code 1988 Use of Modified SA-249, Grade regl .85.r30 1994 N Annulled by n/a n/

Case N-321 - TP 304, Section III, Division 1, ASME

1 Class 1

1812 ASME ASME Code 1987 Thermit Brazing or Welding of reg1.84.r30 1994 N Annulled by n/a n/a

Case N-328 Nonstructural Attachments, ASME

Section 1II, Division 1

1813 ASME ASME Code 1990 Examination of Bar Material, regl.85.r30 1994 A ASME Code 1993

Case N-329 Section III, Division 1, Class 1 Case N-329



Record ... . . adAcpt Latet Stadard terio

1814 ASME ASME Code 1985 Rules for Ultrasonic Examination regl.147.r 1 1994 N ASME Code 1994

Case N-335 of Similar and Dissimilar Metal Case N-335-1

Piping Welds, Section Xl, Division

1815 ASME ASME Code 1991 Rules for Ultrasonic Examination regl.147.rl 1 1994 A ASME Code 1994

Case N-335- of Similar and Dissimilar Metal Case N-335-1

1 Piping Welds, Section Xl, Division1

1816 ASME ASME Code 1983 Examination of Welds Inaccessible reg1.84.r3D 1994 N Annulled by n/a n/a

Case N-336 During Pressure Test, Section III, ASME

Division 1, Class MC

1817 ASME ASME Code 1985 Use of ASTM 8525-70 Grade II, regl.85.r30 1994 N Annulled by n/an/a

Case N-337 Type II, Sintered Austenitic ASMEStainless Steel for Class 2, 3, andMC Component StandardSupports, Section III, Division 1

1818 ASME ASME Code 1991 Use of ASTM B525-70 Grade II, regl.95.r30 1994 A Annulled by n/a

Case N-337- Type II, Sintered Austenitic ASME

Stainless Steel for Class 2, 3, andMC Component StandardSupports, Section III, Division 1

1819 ASME ASME Code 1984 Examination of Ends of Fillet regl .84.r30 1994 N Annulled by n/a

Case N-339 Welds, Section III, Division 1, ASME

Classes 1, 2, and MC

1820 ASME ASME Code 1988 Certification of Level Ill NDE regl.84.r30 1994 N Annulled by n/a n/a

Case N-341 Examiner, Section 11I, Division 1 ASME

and 2

1821 ASME ASME Code 1985 Use of SA-249 and SA-312 Type regl.85.r30 1994 N Annulled by n/an/a

Case N-342 317 Stainless Steel, Section III, ASME

Division 1, Classes 1, 2, and 3

00

z

C)~

Pb

Cb

z

0

'.0

C)



- -R.ec.o ,rd... S E.i.L .. , . ...... ,tanad - Dc. Accpt Latestig S,0 T .......... i -B tan:0 ;dad: Lates V..... :ersion: .

1822 AsME ASME Code 1990 Alternative Scope of examination reg.147.rl 1 1994 N Annulled by n/a n/a

Case N-343 of Attachment Welds for ASME

Examination Categories B-H, B-K-1, and C-C, Section Xl, Division 1

1823 ASME ASME Code 1982 Attachment of AMS 5382 Alloy reg1.84.r30 1994 N ASME Code 1994

Case N-345 31 Seat Rings by Friction Welding, Case N-345-1

Section ill, Division 1, Classes 1,2, and 3

1824 ASME ASME Code 1991 Attachment of AMS 5382 Alloy regl.84.r30 1994 A ASME Code 1994

Case N-345- 31 Seat Rings by Friction Welding, Case N-345-1

1 Section Ilil, Division 1, Classes 1,2, and 3

1825 ASME ASME Code 1986 Explosive Welding, Section IlIl, regl .84.r30 1994 N Annulled by n/a nla


1826 ASME ASME Code 1985 Continuous Electric Resistance regl.84.r30 1994 N Annulled by n/a a

Case N-347 Seam Welding of P-No. 8 ASME

Materials for ComponentSupports, Section Ill, Division 1

1827 ASME ASME Code 1985 Use of SA-574 Socket Head Cap reg 1.85.r30 1994 N Annulled by n/a n/a

Case N-348 Screws, Section Ill Division 1 ASME

1828 AASME SME Code 1986 Use-of SA-574 Socket Head Cap regl.85.r30 1994 N Annulled by n/a n/a

Case N-348- Screws, Section III, Division 1 ASME

1

1829 ASME ASME Code 1990 Use of SA-S74 Socket Head Cap regl.85.r30 1994 P Annulled by n/a

Case N-348- Screws, Section lIl, Division 1 ASME

2


Reaod |nrd Doc, Accet Latest Standard Latt rsi

No. code Standar Vtsion . Title :'Documen Date i

1830 ASME ASME Code 1985 Pressure Testing Piping Systems, regl.84.r30 1994 N Annulled by n/a n/a

Case N-349 Section 1II, Division 1, Classes 2 ASME

and 3

1831 ASME ASME Code 1985 Postweld Heat Treatment - reg1.84.r30 1994 N Annulled by n/a n/a

Case N-350 Thickness of Material, Section IlIl, ASME

Division 1

1832 ASME ASME Code 1991 Use of Subsize Charpy V-Notch reg1.85.r30 1994 A ASME Code 1994

Case N-351 Specimens. Section IlIl, Division 1 Case N-351

1833 ASME ASME Code 1985 Use of SA-638 Grade 660 regl.85.r30 1994 N Annulled by n/a n/a

Case N-352 Forgings and Bars Below 700xF ASME

Without Stress Rupture Tests,

Section IlIl, Division 1

1834 ASME ASME Code 1986 Use of SA-638 Grade 660 regl.85.r30 1994 N Annulled by n/a n/a

Case N-352- Forgings and Bars Below 700xF ASME

1 Without Stress Rupture Tests,Section lil, Division 1

1835 ASME ASME Code 1988 Marking of SA-354 Grade BD regl.85.r30 1994 N Annulled by n/a n/a

Case N-353 Bolting, Section 1II, Division 1 ASME

1836 ASME ASME Code 1990 Calibration Block for Angle Beam reg1.147.r11 1994 A ASME Code 1993

Case N-355 Ultrasonic Examination of Large Case N-355

Fittings in Accordance with

Appendix 111-3410, Section Xl,Division 1

1837 ASME ASME Code 1988 Certification Period for Level Ill reg .147.rl 1 1994 A ASME Code 1994

Case N-356 NDE Personnel, Section Xl, Case N-356

Division 1, 2 and 3

1.0

z

C-�M

PU(!A%-0

W

�V

W

-4


R e or St. n..rd Do e. A c ce pt L at e st S t a nd a d L at s e s o

N o. CZ o de ~ St nd r V rsio n il D o cu m ednt., D atea abil t Co m m n s e s onD t

1838 ASME ASME Code 1988 Certification of Material for reg1.84.r30 1994 N Annulled by n/a n/a

Case N-357 Component Supports, Section IlIl, ASMEDivision 1 Class 1

1839 ASME ASME Code 1984 Weld Connection for Coaxial reg1.84.r30 1994 N Annulled by n/a n/a

Case N-359 Cylinders, Section 1II, Division 1 ASME

1840 ASME ASME Code 1983 Alternate Rules for Pressure regi.84.r30 1994 N Annulled by n/a n/a

Case N-362 Testing of Containment Items, ASMESection 1II, Division 1

1841 ASME ASME Code 1984 Pressure Testing of Containment reg1.84.r30 1994 N Annulled by n/a n/a

Case N-362- Items, Section III, Division 1, ASMEClasses 1, 2, and MC

1842 ASME ASME Code 1987 Pressure Testing of Containment regl .84.r30 1994 N Annulled by n/a nla

Case N-362- Items, Section Itl, Division 1, ASME

2 Classes 1, 2, and MC

1843 ASME ASME Code 1989 SA-372 Type V, Grade 1, Class B, regb.85.r30 1994 N Annulled by n/a n/a

Case N-367 Section III, Division 1 ASME

1844 ASME ASME Code 1990 Pressure Testing of Pump regl.84.r30 1994 P ASME Code 1993

Case N-368 Discharge, Section III, Division 1, Case N-368Classes 2 and 3

1845 ASME ASME Code 1992 Resistance Welding of Bellows, regl.84.r30 1994 A ASME Code 1992

Case N-369 Section III, Division 1 Case N-369

1846 ASME ASME Code 1985 Modified SA-705 Grade XM-13 regl.85.r30 1994 N ASME Code 1994

Case N-370 Forgings, Section III, Division 1 Case N-370-2


ecdStnad Doc Aet attStdrdLateso eso

No oe Sadr eso i.Ddcunet Dae aiy Comments - eson:Dt

1847 ASME ASME Code 1985 Modified SA-705 Grade XM-13 regl.85.r3O 1994 N ASME Code 1994

Case N-370- Forgings, Section III, Division 1 Case N-370-2

1848 ASME ASME Code 1991 Modified SA-705 Grade XM-13 regl.85.r30 1994 A ASME Code 1994

Case N-370- Forgings, Section 1II, Division 1 Case N-370-2

2

1849 ASME ASME Code 1985 12 Cr-lW-IMo-1/4V Martensitic regl.85.r30 1994 N Annulled by n/a n/a

Case N-371 Stainless Steel Valve Internals, ASMESection III, Division 1

1850 ASME ASME Code 1988 12CR-lW-IMo-1/4V Martensitic reg1.85.r30 1994 N Annulled by n/a n/a

Case N-371- Stainless Steel Valve Internals, ASME

1 Section III, Division 1

1851 ASME ASME Code 1983 SB-1 63 Ni-Fe-Cr-Mo-Cu Alloy 825 reg1.85.r30 1994 N Annulled by n/a n/a

Case N-372 IUNS N08825) Tubing, Section III, ASMEDivision 1

1852 ASME ASME Code 1983 Rules for Ultrasonic Examination regi .147.r 1 1994 N Annulled by n/a nla

Case N-375 of Bolts and Studs, Section Xl, ASMEDivision 1

1853 ASME ASME Code 1984 Rules for Ultrasonic Examination regl.147.rl 1 1994 N Annulled by n/a

Case N-375- of Bolts and Studs, Section Xl, ASMEDivision 1

1854 ASME ASME Code 1990 Rules for Ultrasonic Examination reg1.147.r1 1 1994 N Annulled by n/a n/a

Case N-375- of Bolts and Studs, Section Xl, ASME

2 Division 1

1855 ASME ASME Code 1986 Pressure Testing of Embedded regl.84.r30 1994 N Annulled by n/a n/a

Case N-376 Class 2 and 3 Piping, Section III, ASMEDivision 1

z

'C)t-J

(A

-.3

(a

'0



ASME ASME Code 1983 Effectiv t Ss of regi .84.r3 1 994 N Annulled by n/a n/a

Case N-377 Partial Penetration Groove Welds, ASME

Section IlIl, Division 1, Classes 1,

2, and 3 _ _ _ _ _ _

1ASME ASME Code 1986 Examnation of Piping Support regi;85.r30 1994 N Annulied by n/a nla

Case N-378 Material, Section Ill, Division 1, ASME

Class 1

1858 ASME ASME Code 1985 Bimetallic Tubing Section lIl, reg1.85.r30 1994 N Annulled by n/a n/a

Case N-379 Division 1, Class 1 ASME

15 ASME ASME Code 1991 Bimetallic Tubing Section III, reg1.85.r30 1994 A Annulled by n/a a/a

Case N-379- Division 1, Class 1 ASME

1

1860 ASME ASME Code 1985 Weld Repair of SA-182 Austenitic regl.84.r30 1994 N Annulled by n/a

Case N-383 Forgings, Section lIl, Division 1, ASME

Classes 1, 2, and 3

1861 ASME ASME Code 1985 Weld Repair of SA-182 Austenitic regl.84.r30 1994 N Annulled by n/a n/a

Case N-383- Forgings, Section Ill, Division 1, ASME

1 Classes 1, 2, and 3

1862 ASME ASME Code 1987 Component Support Bolting, regl.85.r30 1994 N Annulled by n/a n/a

Case N-388 Section Ill, Division 1, Classes 2, ASME

3, and MC

1863 ASME ASME Code 1989 Alternative Rules for Repairs, reg 1.147.r1 1 1994 P ASME Code

Case N-389 Replacements, or Modifications, Case N-389-1


Codes and Standards and Other Guidance. Cited in Regulatory Documents


Record Standard Doe. Accp- Latet Standaod Letet Vetsion

No. Code tandard VersionTteDcmn ae~ bft omns VrinDt

1864 ASME Code 1989 Procedure for Evaluation of the reg|.84.r30 1994 N ASME Code 1995

Case N-391 Design of Hollow Circular Cross Case N-391-1

Section Welded Attachments onClass 1 Piping, Section III,

Division 1 _ _ _ _ _

1865 ASME ASME Code 1992 Procedure for Evaluation of the regl.84.r30 1994 P ASME Code 1995

Case N-391- Design of Hollow Circular Cross Case N-391-1

1 Section Welded Attachments onClass 1 Piping, Section III,

Division 1 _ _ _ _ _ _ __________ ____

186 ASME ASME Code 1989 Procedure for Evaluation of the regl .84.r30 1994 N ASME Code 1995

Case N-392 Design of Hollow Circular Cross Case N-392-3

Section Welded Attachments onClasses 2 and 3 Piping, SectionIll, Division 1

1867 ASME ASME Code 1986 Procedure for Evaluation of the regl.84.r30 1994 P ASME Code 1995

Case N-392- Design of Hollow Circular Cross Case N-392-3

1 Section Welded Attachments onClasses 2 and 3 Piping, SectionIlI, Division 1

4 ' ... -- .C.,- _9 Rrin' ir Woltfinn Strurtural Steel real.84.r30 1994 A ASME Code 1992

tA

1868 ASMECase N-393

I t7-1

Rolled Shapes and Plates forComponent Supports, Section III,Division 1

z -

Case N-393

II I 1 . 4 A nUi - . I- - !fl A tASMF Code 1 199519~~t esrictng Lorift) to Acheva_

. _ A tb izCri

IJ.

1869

L-

ASME ASME CodeCase N-394

1992 Restricting Lift to AchieveReduced Relieving Capacities ofFull Lift, Nozzle Type, and FlatSeated Safety and Safety ReliefValves for Compressible FluidApplications, Section III, Division1, Classes 2 and 3

Ie -oelo { ivy ..

Case N-394

.I I__ _ _ I1_ _ _ _ _ I _ _ _ _ _ _ _ _ __ _ _ _ L . . -

- - -

zci

0"



Rac~d - Standard -- - Dec. Accept-Lato t Sadd Ltat.t Vers on

Na cdeSrdidr Versin ~ - Ttebcmn e aiiy Cmet eSion Date

870 ASME ASME Code 1989 Laser Welding, Section Ill, Division regc.84.r30 1994 A ASME Code 1992

Case N-395 1 Case N-395

1871 ASME ASME Code 1987 Alternative Rules to the Spectral reg1.84.r30 1994 N Annulled by n/a n/a

Case N-397 Broadening Procedures of N- ASME

1226.3 for Classes 1, 2, and 3Piping, Section IlIl, Division 1

1872 ASME ASME Code 1987 Reporting of Charpy-V Notch Test regi .85.r30 1994 N Annulled by n/a nla

Case N-398 Results, Section lIl, Division 1 ASME

1873 ASME A9ME Code 19 Edd urrent Examination, regl.147.rll 1994 N ASME Code 1994

Case N-401 Section Xl, Division 1 Case N-401 -1

1874 ASME ASME Code 1991 Eddy Current Examination, regl.147.rl 1 1994 A ASME Code 1994

Case N-401 - Section Xl, Division 1 Case N-401-1

1

1875 ASME ASME Code, 1990 Eddy Current Calibration Standard regl.147.rll 1994 N ASME Code 1994

Case N-402 Material, Section Xl, Division 1 Case N-402-1

1876 ASME ASME Code 1991 Eddy Current Calibration Standard reg1.147.rl1 1994 A ASME Code 1994

Case N-402- Material, Section Xl, Division 1 Case N-402-1

1877 ASME ASME Code 1989 Annealed Alloy UNS N06625 Over reg1.85.r30 1994 P ASME Code 1992

Case N-404 UNS N06600 Bimetallic Tubing, Case N-404

Section IlIl, Division 1, Class 1



Reord ' : : t-ndd 1v' oe. Acc ' - :i' -iLate-t Standard L t Vr sion

No. Coe Standr Veb il Dcmn aa 'aiy Cmets VrinDt

1878 ASME ASME Code 1990 Alternative Rules for Replacement, regl.147.rl 1 1994 N Annulled by n/a nla

Case N-406 Section Xi, Division 1 ASME

1879 ASME ASME Code 1989 Alternative Rules for Examination reg .147.r11 194 N ASME Code 1993

Case N-408 of Class 2 Piping, Section Xl, Case N-408-3

Division 1

1880 ASME ASME Code 1989 Alternative Rules forExamination reg1A47.r1 1 1994 N ASME Code 1993

Case N-408- of Class 2 Piping, Section Xl, Case N-408-3

1 Division 1

1881 ASME ASME Code 1989 Alternative Rules for Examination regl.147.rl1 1994 P ASME Code 1993

Case N-408- of Class 2 Piping, Section Xl, Case N-408-3

2 Division 1

1882 ASME ASME Code 1987 Procedure and Personnel regl.147.r11 1994 N ASME Code 1993

Case N-409 Qualification Requirements for Case N-409-3

Ultrasonic Detection and Sizing ofFlaws in Piping Welds, Section Xl,Division 1

1883 ASME ASME Code 1988 Procedure and Personnel regl.147.r11 1994 N ASME Code 1993

Case N-409- Qualification Requirements for Case N-409-3

Ultrasonic Detection and Sizing ofFlaws in Piping Welds, Section Xl,Division 1 _ _ _ _ _ _

1884 ASME ASME Code 1991 Procedure and Personnel regl.147.rl 1 1994 P ASME Code 1993

Case N-409- Qualification Requirements for Case N-409-3

2 Ultrasonic Detection and Sizing ofFlaws in Piping Welds, Section Xl,

Division 1 ___

z

'0i%O

(5

z

Ce

100

n4w

T

w


;ecor td Do.. Accept Ldad Lat:s .Vesion

-i-. 0 N o ..C ode St n ard V ei n Titl D.u m n O at atllt C o m e t V e s o D ata, ).ny iDE

1885 ASME ASME Code 1991 Certified Relieving Capacities of reg1.84.r30 1994 A ASME Code 1994

Case N-41 0 Pressure Relief Valves Having Set Case N-41 0

Pressure of 3 psig up to but NotIncluding 15 psig Installed forOverpressure of CompressibleFluid Systems, Section 1II, Division1, Classes 2 and 3

1886 ASME ASME Code N/S Alternative Damping Values for nuregO933, 1991 R ASME Code 1992

Case N-411 Response Spectra Analysis of 3.119 Case N-411 -1

Classes 1, 2, and 3 Piping,Section III, Division 1

1887 ASME ASME Code 1986 Alternative Damping Values for regl.84.r3O 1994 N ASME Code 1992

Case N-411 Response Spectra Analysis of Case N-411-1Classes 1, 2, and 3 Piping,Section III, Division 1

1888 ASME ASME Code 1992 Alternative Damping Values for reg1.84.r30 1994 P ASME Code 1992

Case N-41 1- Response Spectra Analysis of Case N-41 1-1

1 Classes 1, 2, and 3 Piping,Section ill, Division 1

1889 ASME ASME Code 1991 Alternative Rules for Witnessing reql 84.r30 1994 N Annulled by n/a n/a

Case N-412 the Piping System Pressure Tests ASMEof Classes 1, 2, and 3 PipingSystems, Section III, Division 1

1890 ASME ASME Code 1988 Minimum Size of Fillet Welds for reg1.84.r30 1994 N Annulled by n/a n/a

Case N-413 Subsection NF Linear Type ASMESupports, Section III, Division I

1891 ASME ASME Code 1992 Tack Welds for Class 1, 2, 3 and regl.84,r30 1994 N Annulled by n/a n/a

Case N-414 MC Components and Piping ASME

Supports, Section 1II, Division 1

Codes and Standards.and Other Guidance Cited in Regulatory Documents


Reco rd 'Standard Do Accept-, LatemstiStanard Laest Versi'on

No. ode Standardi Veson 'Ttecumen Daejj: ablllftj~ CoMiments Versin Dt

1892 ASME ASME Code 1991 Alternate Rules for Testing regl.147.rl 1 1994 A Annulled by n/a n/a

Case N-415 Pressure Relief Devices, Section ASME

Xl, Division 1

1893 ASME ASME Code 1990 Alternative Rules for Hydrostatic regl.147.rl1 1994 A CASME Code 1984

Case N-416 Testing of Repair or Replacementof Class 2 Piping, Section Xl,

Division 1 ASME Code 1992________

1894 ASME ME E Code 1986 Use of Seamless Ni-Fe-Cr-Mo-Cu regl.85,r30 1994 N ASME Code 1992

Case N-418 Low Carbon (UNS N08028 and Case N-418-1

UNS N08904) Tubing, Section III,Division 1, Classes 2 and 3

1895 ASME ASME Code 1989 Use of Seamless Ni-Fe-Cr-Mo-Cu regl.85.r30 1994 A ASME Code 1992

Case N-418- Low Carbon (UNS N08028 and Case N-418-1

1 UNS N08904) Tubing, Section III,Division 1, Classes 2 and 3

1896 ASME ASME Code 1991 Extent of VT-I Examinations, egl.147.rll 1994 A Annulled by n/a n/a

Case N-419 Category B-G-I of Table IWB-2500 ASME

1, Section Xl, Division 1

1897 ASME ASME Code 1991 Linear Energy Absorbing Supports regil 84.r30 1994 CasE Code 1994

Case N-420 for Subsection NF Classes 1, 2,and 3 Construction, Section III,Division 1

198 ASME ASME Code 1986 Brazing Using a Radiant Energy regl.84.r30 1994 N AnnSuled by nla

Case N-421 Source, Section III, Division 1 ASME

-- 4 fl00 1 "R ; req1.147.rl 1 1994 N Annulled by n/a n/a

z

C)

-Dw-

1899 ASME ASMt N-424Case N-424 Examination Personnel, Section

Xl, Division 1

._--......ASME

I I J _ _ _ _ I _ _ _ _ _ _ I _ _ _ _ _ _ _ _ _ _ _ _ _ I L__ _ _ _ _ .- - _ _ _ _ _

z

L.)

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R e a C - '* i, ,- D oe. .c t 7 , La wte t Stendard L!t; t V e rson

* N o . - o eS t a nd a rd K VQs o T t e . ' o c m n t D t a b lit o m n sV e s o D t .

1900 ASME ASME Code 1991 Extent of VT-I Examinations, regl .147.rI 1 1994 A Annulled by n/a n/a

Case N-426 Category B-G-2 of Table IWB- ASME

2500--1, Section Xi, Division 11

1901 ASME ASME Code 1988 Code Cases in Inspection Plans, regi1.147.r1 1 1994 P Annulled by n/a n/a

Case N-427 Section XI, Division 1 ASME

1902 ASME ASME Code 1987 Alternative Rules for Ultrasonic reg 1.1 47.r I1 1994 N ASME Code, 1992

Case N-429 Instrument Calibration, Section Xl, Case N-429-1Division 1

1903 ASME ASME Code 1990 Alternative Rules for Ultrasonic regl.147.rl 1 1994 A ASME Code 1992

Case N-429- instrument Calibration, Section Xi, Case N-429-1

1 Division 1

1904 ASME ASME Code 1992 Alternative Requirements for regl .84.r30 1994 P Annulled by n/a n/a

Case N-430 Welding Workmanship and Visual ASMEAcceptance Criteria for Class 1,2, 3 and MC Linear Type andStandard Supports, Section IIIDivision 1

1905 ASME ASME Code N/S Repair Welding Using Automatic glt90-005 1990 R ASME Code 1994

Case N-432 or Machine Gas Tungsten-Arc Case N-432

Welding (GTAW) TemperbeadTechnique

1906 ASME ASME Code 1989 Repair Welding Using Automatic regl .147.r 1 1994 A ASME Code 1994

Case N-432 or Machine Gas Tungsten-Arc Case N-432

Welding IGTAW) TemperbeadTechnique, Section Xi, Division 1



-:,,,;t ..,t;:!I0t:;!t- b;,0 ........ ;::,. .- ' ' .S.','..,;t~' : . ..... Do --Rac:dStandard

Do.Acet-Ltet Standard Lats Vaon

dodo:Code Sta'ndard:' VriniteDu t Date ablt Cmens VeloDae

1907 ASME ASMECode 1989 Non-Threaded Fasteners for rega.e .r3 1S C oN 433

Case N-433 Section lil, Division 1, Class 1, 2, a -43

and 3 Component and PipingSupports Section 1II, Division I

1908 ASME ASME Code 1986 Alternative Examination regl.147.r1 1 1994 N ASME1Code 1992

Case N-435 Requirements for Vessels withWall Thickness 2 in. or Less,

Section Xi, Division 1 ______

1909 ASME Code 1989 Alternative Examination regl .147.r1 1 1994 A ASME Code 1995SME CodeCase N-435-1

Case N-435- Requirements for Vessels with

1 Wall Thickness 2 in. or Less,

Section Xi, Division 1_______

1910ve Methods for Evaluation regl.l47.rl 1 1994 N Annulled by n/a nla

Case N-436 of Flaws in Austenitic Piping, ASME


.I _- _-, _e .7 ,F1-1 tA7 4.11 1994 N Annulled by n/a n/altstiU i.nernauv. Ivw ...

0


1 UUU Alternauive Iviemwh or 101~ dl~

of Flaws in Austenitic Piping,


I.... ASME

1912

1913I

ASME ASME Code 1989 Use of Digital Readout and Digital regl .147.rl 1 1994 A ASMECode 1992

Case N-437 Measurement Devices for

Performing Pressure Tests,

Section Xi, Division 1 ______

ASME Code 1989 e45NTi21Cr-6.5 Mo-0.2N regl.85.r30 1994 N Annulled by n/a n/a

Case N-438 (Alloy UNS N08367) Seamless ASME

and Welded Pipe, Tube, Plate, Bar,

Fittings, and Forgings, Class 2 and

3 Construction, Section Ill,

Division 1

z

(!A

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t')

0


R ec o rd ta d rD o A '' eptCL ates St a nd ar t st V rs o:NI L ;Cbde-: - i0 ' :t.: ,'02|.. 40SXt on t : 00..........;. i,

Tif MARilV, -S- .r.. n...en-t g:~;:T .S.-.-

No e St andar d Ve si n Ttl ocu mf ent Iae a iiy o m n sV ersion Dat#::

1914 ASME ASME Code 1i90 Fe-24.5Ni-21Cr-6,5 Mo-0.2N regC.85.r30 1994 N ASME Code 1992

Case N-438- (Alloy UNS N08367) Seamless Case N-438-3

1 and Welded Pipe, Tube, Plate, Bar,Fittings, and Forgings, Class 2 and3 Construction, Section 111,Division 1

1915 ASME ASME Code 1990 Fe-24.5Ni-21 Cr-6.5Mo-0.2N regl.85.r3 1994 A ASME Code 1992


2 and Welded Pipe, Tube, Plate, Bar,Fittings, and Forgings, Class 2 and3 Construction, Section III,Division 1

1916 ASME ASME Code 1992 Fe-24.5Ni-21Cr-6.5Mo-0.2N reg1.85.r30 1994 A ASME Code 1992


3 and Welded Pipe, Tube, Plate, Bar,Fittings, and Forgings, Class 2 and3 Construction, Section 1II,Division 2

1917 ASME ASME Code 1989 Use of 20Cr-18Ni-6Mo (Alloy UNS regl.85.r30 1994 A ASME Code 1992

Case N-439 S31254) Forgings, Plate, Case N-439

Seamless and Welded Pipe, andWelded Tube, Class 2 and 3Construction, Section lII, Division

1918 ASME ASME Code 1987 Use of 20Cr-18Ni-6Mo (Alloy UNS reg1.85.r30 1994 A ASME Code 1992

Case N-440 J93254) Castings, Class 2 and 3 Case N-440

Construction, Section III, Division

1919 ASME ASME Code 1989 Use of 20Cr-18Ni-6Mo (Alloy UNS regl.85.r30 1994 A ASME Code 1992

Case N-441 S31254) Fittings, Class 2 and 3 Case N-441-1

Construction, Section III, Division1 . _ _



| No. Cod Stiad ',. Verion t'' '-0 '-'' Doun Date abiit CXommns Version Dataril

1920 ASME ASME Code 1990 1977 Addendum to ANSI/ASME regl.84.r30 1994 A Annulled by n/a n/a

Case N-442 PTC 25.3-1976, Safety and ASMESafety Relief Valves, Class 1, 2,3, and MC, Section 11i, Division 1

1921 ASME ASME Code 1989 High Yield Strength Cr-Mo Steel, regl.85.r30 1994 N ASME Code 1995

Case N-443 Class 1 Components, Section Ill, Case N-443-1

Division 1

1922 ASME ASME Code 1992 High Yield Strength Cr-Mo Steel, regl.85.r30 1994 A ASME Code 1995

Case N-443- Class 1 Components, Section 1II, Case N-443-1

1 Division 1

1923 ASME ASME Code 1990 Preparation of Inspection Plans, regl .147.rl 1 1994 N Annulled by n/a n a

Case N-444 Section Xl, Division 1 ASME

1924 ASME ASME Code 1990 Use of Later Editions of SNT-TC- reg.1 47.rl 1 1994 N Annulled by n/a n/a

Case N-445 1A for Qualification of ASMENondestructive ExaminationPersonnel, Section Xl, Division 1,2, and 3

1925 ASME ASME Code 1990 Recertification of Visual regl.147.r 1 1994 N Annulled by n/a n/a

Case N-446 Examination Personnel, Section ASMEXi, Division 1

1926 ASME ASME Code 1990 Qualification of VT-2 and VT-3 regl.147rl 1 1994 A ASME Code 1993

Case N-448 Visual Examination Personnel, Case N-448


1927 ASME ASME Code 1990 Qualification of VT-4 Visual regl.147.r1 1994 A ASME Code 1993

Case N-449 Examination Personnel, Section Case N-449

Xl, Division 1

z

Jth

-40

Z

a~

Lii)



e. Stan ard. 00.X Accept-D. .. . Latest S ta d'aird Lto t version

N o o eS t a n d a d V r $ i l -'-D c u e tD t e ~~~. C m e t s e a nD t

1928 ASME ASME Code 1992 Specialized Subcontracted reg1.84.r30 1994 A ASME Code 1995

Case N-452 Welding Process (Electron Beam Case N-452

Welding), Section 111, Division 1,Class 2 and 3 Construction

1929 ASME ASME Code 1988 Nickel Chromium-Molybdenum- reg 1.84.r30 1994 N ASME Code 1995

Case N-453 Copper Stainless Steel (UNS Case N-453-2

N08925) Seamless and WeldedPipe for Class 2 and 3Construction Section III, Division 1

1930 ASME ASME Code 1988 Nickel-Chromium-Molybdenum- reg1.84.r30 1994 A ASME Code 1995

Case N-453- Copper Stainless Steel (UNS Case N-453-2

1 N08925) Seamless and WeldedPipe for Class 2 and 3Construction Section iII, Division 1

1931 ASME ASME Code 1992 Nickel-Chromium-Molybdenum- regl.84.r30 1994 A ASME Code 1995


2 N08925) Seamless and WeldedPipe for Class 2 and 3Construction Section III, Division 2

1932 ASME ASME Code 1990 Nickel-Chromium-Molybdenum- regl.84.r3O 1994 A ASME Code 1995


N08925) Wrought Fittings forClass 2 and 3 Construction,Section III, Division 1

tA~

0

(I

z



adco d St nd, D e A'e~L atest Standard L atest i Ve rsioG ., C d ;S a d rV e i oT tlDo c u m e nit D a e a i i y C m e t e rs o D t

1933 ASME ASME Code 1992 Nickel.Chromium-Molybdeunm- reg1.84.r30 1994 A ASME Code 1995


1 N08925) Wrought Fittings forClass 2 and 3 Construction,Section III, Division 2

1934 ASME ASME Code 1990 Nickel-Chromium-Molybdenumr reg1.84.r30 1994 A ASME Code 1995


N08925) Forged Flanges andFittings for Class 2 and 3Construction, Section III, Division1

1935 ASME ASME Code 1992 Nickel-Chromium-Molybdenum- reg1.84.r30 1994 A ASME Code 1992


1 N08925) Forged Flanges andFittings for Class 2 and 3Construction, Section III, Division1

1936 ASME ASME Code 1990 Qualification Specimen Notch reg1.147.rl 1 1994 A ASME Code 1993

Case N-457 Location for Ultrasonic Case N-457

Examination of Bolts and Studs,Section Xl, Division 1

1937 ASME ASME Code 1991 SA-508 Basic Oxygen-Ladle regl.85.r30 1994 A Annulled by n/a n/a

Case N-459 Furnace Process for Code ASMEConstruction, Section III, Division

1938 ASME ASME Code 1991 Alternative Examination Coverage regl.147.rl 1 1994 A CasE Code 1994

Case N-460 for Class 1 and Class 2 Welds Case N-460


1939 ASME ASME Code 1991 Alternative Rules forPiping regl.147.rl1 1994 P ASME Code 1995

Case N-461 Calibration Block Thickness, Case N-461-1


z

C)

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R ecord it ndar D C A: : LIStiidard

1940 ASME ASME Code N/S Evaluation Procedures and glt90-005 1990 A Annulled by n/a n/a

Case N-463 Acceptance Criteria for Flaws in ASME

Class I Ferritic Piping that exceedthe Acceptance Standards of IWI-3514.2, Section Xl, Division 1

ev- Anulld by n/an/a

1941 ASME ASME Code 1 90 Evaluation Procedures and regl .147.rl 1 1994 N Annulled by n/a

Case N-463 Acceptance Criteria for Flaws in ASMEClass I Ferritic Piping that exceedthe Acceptance Standards of IWB-3514.2, Section Xl, Division 1

1942 ASME ASME Code 1990 Evaluation Procedures and reCl.147.rl 1994 A ASME Code 1995

Case N-463- Acceptance Criteria for Flaws in

1 Class I Ferritic Piping that exceedthe Acceptance Standards of IWB-3514.2, Section Xl, Division 1

1943 ASME ASME Code 1992 Laser Welding of Lap-Joints, regl.84.r30 1994 A ASME Code 1995

Case N-464 Section III, Division 1, Class 2 and Case N-464

3 Construction

1944 ASME Code 1991 Alternative Rules for Pump regS.147.rl 1994 A Annulled by n/a

Case N-465 Testing, Section Xl, Division 1 ASME

1945 ASME ASME Code 1990 Modified 9Cr-1 Mo Material, regl.85.r30 1994 N Annulled by n/an/a

Case N-466 Section III, Division 1, Classes 1, ASME

2, and 3

1946 ASME ASME Code 1990 Modified 9Cr-1 Mo Material, regi.85,r30 1994 A ASME Code 1993

Case N-466- Section III, Division 1, Classes 1,

1 2, and 3



ReodSadr e. Acp-Lt Stanar'LtesdVrson

N Cd Stdrd VeioTilDocument Dae aiiy Cmet eon Dt

1947 ASME ASME Code 1992 Martensitic Stainless Steel for regi.85.r0 1994 A ASME Code 1 995

Case N-469 Class 1, 2, and 3 Components, Case N-469

Section 1II, Division 1

1948 ASME ASME Code 1992 Class MC Material Requirements reg .85.r30 1994 A Annulled by n/a n/a

Case N-470 INE-2121 (c)I, Section IlIl, Division ASME

1949 ASME ASME Code 1990 Acoustic Emission for Successive reg 1.1 47.r1 1 1994 P ASME Code 1993

Case N-471 Inspections, Section Xi, Division 1 Case N-471

1950 ASME ASME Code 1991 Use of Digital Readout and Digital regl.147.r11 1994 A ASME Code 1994

Case N-472 Measurement Devices for Case N-472

Performing Pump VibrationTesting, Section XI, Division 1

1951 ASME ASME Code 1991 Alternative Rules for Valve reg1.147.r1 1 1994 A Annulled by n/a

Case N-473 Testing, Section Xl, Division 1 ASME

1962 ASME ASME Code 1990 Design Stress Intensities and Yield regl.85.r30 1994 N -SME Code 1993

Case N-474 Strength Values for UNS N06690 Case N-474-2

with a Minimum Specified YieldStrength of 35 ksi, Class 1Components, Section lilt Division1

1953 ASME ASME Code. 1990 Design Stress Intensities and Yield regl.85.r30 1994 A ASME Code 1993

Case N-474- Strength Values for UNS N06690 Case N-474-2

1 with a Minimum Specified YieldStrength of 35 ksi, Class 1Components, Section IlIl, Division1

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Case N-4761989 Cljass1, 2, 3, and MC Linear

Component Supports - DesignCriteria for Single Angle Members,Section 111, Division 1, SubsectionNFBoiling Water Reactor (BWR) MainSteam Hydrostatic Test, SectionXl, Division I

1,ASME CodeCase N-476

I _ . - . -- i reg1.147.r11 1994r N Annulled byASME

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1966 ASME ASME CodeCase N-479

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1990

N/S1958 1 ASME ASME CodeCase N-480

Boiling Water Reactor (BWRi MainSteam Hydrostatic Test, SectionXl, Division 1

Examination Requirements forPipe Wall Thinning Due to SinglePhase Erosion and Corrosion

Aiternate ExaminationRequirements for Cast AusteniticPump Casings, Section Xl,Division 1Direct Quenched Stainless Bar,ASTM A 479-88b, Section III,Division 1

-in1 .147

0490- 0 R

nri 119941 AIvu 'j I I-

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ASME CodeCase N-480

ASME CodeCase N-481

1993

1993

1,9 9 5

1959 j ASME ASME Code j 1990Case N-481 I

;egl.47rl I 19941 A

1 960 ASME ASME CodeCase N-482

ASME CodeCase N-484-1

1990

I I 44regl.85.r30 1 A IAnue by la nla

I I ASME

1961 ASME 1991 Real Time RadioscopicExamination of Welds, Class 1components, Section III, Division

regl.85-r30 t h T Annulled byASME

n/a n/a


Record SX~Xt4.i tN :f..:..Ondat i j~i- .EE;;-Si: V-.. .; Dee . ..... <- ,.0 .................... _-.:e Laes Stn d L atestVeio

1 6 2. A.. SME ASME Code .199 Eddy C rent i o regi . .rl 1

Case N-485 Coated Ferritic Surfaces as an Case N-485-1Alternative to Surface l

Examination, Section Xl, Division.

1963 ASME ASME Code 1991 Eddy Current Examination of regl.147.rl 1 1994 A ASME Code 1994

Case N-485- Coated Ferritic Surfaces as an Case N-485-1

1 Alternative to SurfaceExamination, Section Xl, Division

1964 ASME ASME Code 1990 Alternative Rules for Level o ll NDE regl.147.r11 1994 A ASME Code 1993

Case N-489 Qualification Examinations, Case N-489

Section Xl, Division 1, 2, and 3

1965 ASME ASME Code 1990 Alternative Vision Test regl.147.r1 1994 N ASME Code 1994

Case N-490 Requirements for Nondestructive Case N-490-1

Examiners, Section Xl, Divisions1, 2, and 3

1966 ASME ASME Code 1991 Alternative Vision Test reg 1.147.r 1 1994 A ASME Code 1994

Case N-490- Requirements for Nondestructive Case N-490-1

Examiners, Section Xl, Divisions1, 2, and 3

1966 ASME ASME Code 1991 Alternative Rules fo e i regl.147.r 11 1994 A ASME Code 1993

Case N-491 of Class 1, 2, and 3 and MC Case N-491-1Component Supports of Light-Water Cooled Power Plants,Section Xl, Division 1

1968 ASM ASME Code 1990 Grade 9 Titanium Alloy Section iii, regli85.r30 1994 A ASME Code 1994

Case N-492 Division 1, Class 1, 2, and 3 Case N-492-1

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1969 ASME ASME Code 1990 Pipe Specific Evaluation rel.1 47.r 1 1994 A ASME Code 1993

Case N-494 Procedures and Acceptance Case N-494-2

Criteria for Flaws in Class 1Ferritic Piping that Exceeds theAcceptance Standards of IWB-3514.2, Section Xl, Division 1

1970 ASME ASME Code 1992 Pipe Specific Evaluation regl.147.r 1 1994 A ASME Code 1993

Case N-494- Procedures and Acceptance Case N-494-2

1 Criteria for Flaws in Class 1Ferritic Piping that Exceeds theAcceptance Standards of IWB-3514.2, Section Xi, Division 1

1971 ASME ASME Code 1990 Hydrostatic Testing of Relief regi.147.rll 1994 A ASME Code 1993

Case N-495 Valves, Section Xl, Division 1 Case N-495

1972 ASME ASME Code 1991 Helical Coil Threaded Inserts, regl.147.rl 1 1994 A ASME Code 1994

Case N-496 Section Xl, Division 1 Case N-496-1

1973 ASME ASME Code 1991 Use of FE-Ni-Cr-M0-N (Cn-3MN) regl .85.r39 1994 A ASME Code 1993

Case N-497 Cast Materials, Section III, Case N-497-1

Division 1, Class 2 and 3Construction

1974 ASME ASME Code 1991 Alternative Rules for 10-Year regl.147.r11 1994 A ASME Code 1994

Case N-498 Hydrostatic Pressure Testing for Case N-498-1

Class 1 and 2 Systems, SectionXl, Division 1Afl -- ') - P,,Io tn NCrA-qROn- raal.85.r30 1994 1 A ---- Annulled by nla n/a


Rei iDrd A . Latei StIndd tet' LVersio

1976 ASME ASME Code 1992 Use of FE-N-Cr-MO-N iCn-3MN) regi.85.r30 1994 A ASME Code 1992

Case N-502 Cast Materials, Section III, Case N-502

Division 1, Class 2 and 3Construction

1977 ASME ASME Code 1992 Limited Certification of Non- reg1.147.rl 1 1994 A Annulled by n/a n/a

Case N-503 destructive Examination ASMEPersonnel, Section Xl, Division 1

1978 ASME ASME Code 1992 Alternative Rules for Repair of reg1.147.rl 1 1994 A ASME Code 1993

Case N-504 Class 1, 2, and 3 Austenitic Case N-504-1Stainless Steel Piping, Section Xl,Division 1

1979 ASME ASME Code N/S Titled Individually regl.136.rO2 1981 R ode Cases ASME Code 1992

Cases approved in RG Cases1.86

1980 ASME ASME Code N/S Titled Individually srp3.2.2 1981 R ASME Code 1992

Cases Cases

1981 ASME ASME NIS Power Boilers bu171-003 1971 ASME Section I 1995

Section I

1982 ASME ASME N/S Materials inm49055 1982 R ASME Section II 1995

Section II1983 AsmE ASME 1980 Materials not84-63 1984 P ASME Section 1 1995

Section II1984 ASME ASME N/S Materials regl.143.rO1 1979 P ASME Section II 1995

Section II1985 ASME ASME NIS Materials srp5.3.1 1981 P General ASME Section 1 1995

Section Il endorsements

1986 ASME ASME N/S Materials srp5.3.3 1981 P General ASME Section iI 1995

Section II endorsements

1987 ASME ASME NIS Materials srp5.4.1.1 1981 R ASME Section It 1995

Section II __ __

1988 ASME ASME N/S Materials srp5.4.2.1 1981 R ASME Section If 1995

Section It 11 _ _

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1990 ASME ASMIIE N/S Materials srp4.5.1 1981 A ASME Section II 1995

S e c tio n II_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

1991 ASME -ASME -N/S Materials srp4.5.2 1981 A ASME Section 1I 1995

S e ctio n Ii _ _ _ __ _ _ _ _ _ _ _ _

1992 ASME ASIMIE NIS Materials srp5.2.3 1981 A ASME Section _ 1995

Section li

1993 ASME ASME NS Materials sr 6. 1.1 1981 A ASME Section 11 1995

Section 111 Power Plant Components lli

1994 ASME ASME N/S Rules for Construction of Nuclear 1 Ocfr50.66 1996 Ri ASME Section 1995

Section III Power Plant Components Ill

1995 ASME ASME N/S Rules for Construction of Nuclear inmOO40 1995 R ASME Section 1995

Section III Power Plant Components il1

1996 ASME ASME N/S Rules for Construction of Nuclear 1 bcf7rO App. H 1994 R ASME Section 1995

Section iII Power Plant Components Ill

1997 AS ASME NiS Rules for Construction of Nuclear bui88-003 1979 R ASME Section 1995

Section III Power Plant Components ill

0998 ASME ASME N/S Rules for Construction of Nuclear bu179-003a 197 ASME Section 1995

Section iII Power Plant Components Ill

-19-99 ASW§ME ASME NS Rules for Construction of Nuclear bu188-005.sO 1988 P ASME Section 1995


2000-- ASME ASME N/S Rules for Construction of Nuclear buI88-01 1 1988 P ASME Section 1995


2001 ASME ASME N/S Rules for Construction of Nuclear drg101O.rOO 1992 P Proposed ASME Section 1995

Section iII Power Plant Components regl.28.rO4 iII



Record St -det~d Dc.:, Acet! i yli 4' 0- Lates -t S -tandar -,,LaX;tet Verio

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2003 ASME ASME N/S Rules for Construction of Nclear drgs90 -4rO 1981 R ASME Section 1995

Section oII Power Plant Components I

2004 ASME ASME N/S Rules for Construction of Nuclear gt79-005 1979 P lASME Section 1995

Section lIl Power Plant Components

2005 ASME ASME N/S Rules for Construction of Nuclear gmt8O-001 1980 R ASME Section 19

Section Illi Power Plant Components ll

2006 ASME ASME N/S Rules for Construction of Nuclear gt80-088 1980 R ASME Section 1995

Section Illi Power Plant Components ll

2007 ASME SME N/S Rules for Construction of Nuclear glt8l-006 1981 R ASME Section 1995

Section lIl Power Plant Components

2008 ASME ASME N/S Rules for Construction of Nuclear g1t89-008 1989 R ASME Section 1995

Section IlIl Power Plant Components ill

2009 ASME ASME N/S Rules for Construction of Nuclear g1t8l9-09 1989 R ASME Section 1995

Section lIl Power Plant Components .ll

2010 ASME ASME N/S Rules for Construction of Nuclear g1t89-S1O6 199 R ASME Section 1995

Section IlIl Power Plant Components Ill

2011 ASME ASME N/S Rules for Construction of Nuclear glt89-013 1989 R Before 1971 ASME Section 1995

Section IlIl Power Plant Components AftE ill1AS990 e ASME Section 1995

Sectionn Ill Power Plant Components__

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Section III Power Plant Components ll

2014 ASME ASME 1989 Rules for Construction of Nuclear in-toc1995 R ANS 3.2 1994

Section III Power Plant Components

2015 ASME ASME N/S Rules for Construction of Nuclear inm 245 App. B 1991 R ASME Section 1995


2016 ASME ASME N/S Rules for Construction of inm2500.0 2 7 1989 R ASME Section 1995


2017 ASME ASME N/S Rules for Construction of Nuclear inm3S0165 1975 R ASME Section 1995

Section Ill Power Plant Components IlIl

2018 ASME ASME N/S Rules for Construction of Nuclear inm3501 88 1975 R ASME Section 1995

Section III Power Plant Components IlIl

2019 ASME ASME N/S Rules for Construction of Nuclear inm35028B 1975 R ASME Section 1995

Section lII Powver Plant Components ill

2020 ASME ASME N/S Rules for Construction of NuCear inm39701 1992 R ASME Section 1995


2021 ASME ASME N/S Rules for Construction of Nuclear inm38702 1992 R ASME Section 1995






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Section nII . Power Plant Components o







2029 ASME ASME NIS Rules for Construction of Nuclear inm52053 1984 R ASME Section 1995






ASME ASME NIS Rules for Construction of Nuclear inm55093B 1977 R ASME Section 1995



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Section Illi Power Plant Components Ill




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Section III Power Plant Components IIl



2040 AsME ASME N/S Rules for Construction of Nuclear inm73052 1986 R ASME Section 1995


2041 ASME ASME N/S Rules for Construction of Nuclear inm9900/ ASME 1989 R ASME Section 1995

Section III Power Plant Components IlIl ll

2042 ASME ASME N/S Rules for Construction of Nuclear inm9900/ 1994 R ASME Section 1995

Section ill Power Plant Components SGTUBE Ill

2043 ASME ASME NIS Rules for Construction of Nuclear not80-38 1980 R ASME Section 1995


2044 ASM ASME 1972 Rules for Construction of Nuclear not93-31 1983 R ASME Section 1995

Section ill Power Plant Components ill

2045 ASME ASME 1974 Rules for Construction of Nuclear not83-31 1983 R ASME Section 1995

Section Itl Power Plant Components Ill


Section ill Power Plant Components Ill

2047 ASME ASME N/S Rules for Construction of Nuclear not83-48.sOl 1988 P ASME Section 1995


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2051 ASME ASME 1986 Rules for Construction of Nuclear not86-21 1986 ASME Section 1995

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2052 ASME ASME NIS Rules for Construction of Nuclear not86-21.sO1 1986 R ASME Section 1995



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2055 ASME ASME N/S Rules for Construction of Nuclear not88-i 7 1988 _ ASME Section 1995

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2056 ASME ASME N/S Rules for Construction of Nuclear1995


2057 ASME ASME N/S Rules for Construction of Nuclear not89-36 1989 P -IASME Section 1995


2058 ASME ASME NiS Rules for Construction of Nuclear not89-56 1989 R ASME Section 1995


2059 ASME ASME NS Rules for Construction of Nuclear not89-79 .sO1 1989 R ASME Section 1995


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2064 ASME ASME NIS Rules for Construction of Nuclear nuregO933, 2.B- 1983 R ASME Section 1995

Section III Power Plant Components 27 III

2065 ASME ASME N/S Rules for Construction of Nuclear nuregO933, 2.8- 1988 R ASME Section 1995

Section III Power Plant Components 5 lil

2066 ASME ASME N/S Rules for Construction of Nuclear nuregO933, 1990 R ASME Section 1995

Section III Power Plant Components 3.109 ill

2067 ASME ASME NIS Rules for Construction of Nuclear nuregO933, 1991 R ASME Section 1995

Section III Power Plant Components 3.111 III

2068 ASME ASME NIS Rules for Construction of Nuclear nuregO933, 1987 R ASME Section 1995

Section III Power Plant Components 3.127 III

2069 ASME ASME N/S Rules for Construction of Nuclear nuregO933, 1991 R ASME Section 1995

Section Ill Power Plant Components 3.135 III

2070 ASME ASME NIS Rules for Construction of Nuclear nuregO933, 3.78 1992 R ASME Section 1995


2071 ASME ASME NIS Rules for Construction of Nuclear nuregO933, 3.89 1992 R ASME Section 1995


2072 ASME ASME N/S Rules for Construction of Nuclear reg1.116.rOO 1976 R ASME Section 1995




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Code. Standard Vri Title Dom t DIae a |omments Verio Dt

2073 ASME ASME N/S Rules for Construction of Nuclear reg 1.1 21 .rO0 1976 P ASME Section 1995


2074 ASME ASME 1976 Rules for Construction of Nuclear regl .124.rOl 1978 P ASME Section 1995

Section III Power Plant Components lii

2075 ASME ASME 1977 Rules for Construction of Nuclear regl.130.rOl 1978 R ASME Section 1995

Section iII Power Plant Components ll

2076 ASME ASME N/S Rules for Construction of Nuclear reg1.143.rOl 1979 P ASME Section 1995

Section iII Power Plant Components ll

2077 ASME ASME 1977 Rules for Construction of Nuclear reg1.148.rOO 1981 R General ASME Section 1995

Section III Power Plant Components endorsements Ill

2078 ASME ASME 1981 Rules for Construction of Nuclear regl .151 .rOO 1983 R ASME Section 1995


2079 ASM.E ASME 1971 Rules for Construction of Nuclear regl.26.rO3 1976 A ASME Section 1995


2080 ASME ASME 1976 Rules for Construction of Nuclear regl.31.r03 1978 R ASME Section 1995

Section IlIl Power Plant Components 1ll

2081 ASME ASME 1972 Rules for Construction of Nuclear reg1.34.rOO 1972 R ASME Section 1995


2082 ASME ASME. N/S Rules for Construction of Nuclear regl .43.rOO 1973 P ASME Section 1995


2083 ASME ASME N/S Rules for Construction of Nuclear reg .50.rOO 1973 P With ASME Section 1995

Section Ilil Power Plant Components supplements Ill

2084 ASME ASME 1973 Rules for Construction of Nuclear reg1.57.rDD 1973 R Referenced in ASME Section 1995

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2086 ASME ASME N/S Rules for Construction of Nuclear reg1.68.r02 1978 P ASME Section 1996


2087 ASME ASME NIS Rules for Construction of Nuclear regl.70.rO3 1978 P ASME Section 1995


2088 ASME ASME N/i Rules for Construction of Nuclear reg1.71.rOO 1973 P ASME Section 1995


2089 ASME ASME NIS Rules for Construction of Nuclear reg1.77.rOo 1974 P ASME Section 1995

Section Ill Power Plant Components ill

2090 ASME ASME N/S Rules for Construction of Nuclear reg1.83.rO1 1975 P ASME Section i995

Section III Power Plant Components 111

2091 ASME ASME N/S Rules for Construction of Nuclear regl.87.rOl 1975 R ASME Section 1995


2092 ASME ASME NIS Rules for Construction of Nuclear reg 1.99.r02 1988 R ASME Section 1995

Section Ill Power Plant Components ill

2093 ASME ASME 1974 Rules for Construction of Nuclear reg3.28.rOO 1975 P ASME Section 1995

Section iII Power Plant Components ill

2094 ASME ASME 1971 Rules for Construction of Nuclear reg3.29.rOO 1975 ASME Section 1995


2095 ASME ASME N/S Rules for Construction of Nuclear reg3.60.rOO 1987 P ASME Section 1995

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2098 ASME ASME 1977 Rules for Construction of Nuclear reg7.6.r3l 1978 P ASME Section 1995


2099 ASME ASME NIS Rules for Construction of Nuclear srpl0.2.3 1981 P ASME Section 1995

Section III Power Plant Components .

2100 ASME ASME N/S Rules for Construction of Nuclear srpl5.0 1981 . ASME Section 1995

Section Illi Power Plant Components Ill

2101 ASME ASME N/S Rules for Construction of Nuclear srpl5.0 1981 P ASME Section 1995


2102 ASME ASME NIS Rules for Construction of Nuclear srp15.1.1 1981 R ASME Section 1995


2103 ASME ASME N/S Rules for Construction of Nuclear srpl 5.2.1 1981 R ASME Section 1995


2104 ASME ASME N/S Rules for Construction of Nuclear srp15.4.4 1981 R ASME Section 1995


2105 ASME ASME N/S Rules for Construction of Nuclear srpl5.4.8 1981 P ASME Section 1995


2106 ASME ASME N/S Rules for Construction of Nuclear srp1 5.4.9 1981 P ASME Section 1995

Section III Power Plant Components il

2107 ASME ASME N/S Rules for Construction of Nuclear srpl5.5.1 1981 R ASME Section 1995

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Section liI Power Plant Components ll

2110 iASME ASME N/S Rules for Construction of Nuclear srpI7.3 1990 P ASME Section 1995


2111 ASME ASME 1972 Rules for Construction of Nuclear srp3.6.1 1990 P ASME Section 1995


2112 ASME 1977 Rules for Construction of Nuclear srp4.2 1981 R ASME Section 1996


2113 ASME ASME NIS Rules for Construction of Nuclear srp4.5.1 1981 p ASME Section 1995


2114 ASME ASME NIS Rules for Construction of Nuclear srp4.5.2 1981 P ASME Section 1995


2115 ASME ASME 1980 Rules for Construction of Nuclear srp5.2.1.1 1981 P ASME Section 1995




2117 ASME ASME NIS Rules for Construction of Nuclear srp5.2.4 1981 R ASME Section 1995


2118 ASME ASME N/S Rules for Construction of Nuclear srp5.3.1 1981 P ASME Section 1995



Section III Power Plant Components IIl




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2121 ASME ASME N/S Rules for Construction of Nuclear srp5.4.1.1 1981 R ASME Section 1995








2125 ASME ASME 1971 Rules for Construction of Nuclear sts4-geB2.1.2 1992 R ASME Section 1995


2126 ASME ASME N/S Rules for Construction of Nuclear sts4-geB3.3.11 1992 R ASME Section 1995

Section Ill Power Plant Components Ilil

2127 ASME ASME N/S Rules for Construction of Nuclear sts4-geB3.3.4,2 1992 R ASME Section 1995


2128 ASME ASME 1974 Rules for Construction of Nuclear sts6-geB2.1.2 1992 R ASME Section 1995


2129 ASME ASME N/S Rules for Construction of Nuclear sts6-geB3.3.1.1 1992 R ASME Section 1995


2130 ASME ASME N/S Rules for Construction of Nuclear sts6-geB3.3.4.2 189 R ASME Section 1995


2131 ASME ASME N/S Rules for Construction of Nuclear sts6-ge33.4.4 1992 R ASME Section 1995

Section III Power Plant Components lIl

2132 ASME ASME N/S Rules for Construction of Nuclear stsb&wB3.4.10 1992 P ASME Section 1995


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Section III Power Plant Components .ll

2134 ASME ASME N/S Rules for Construction of Nuclear stswstB3. 4.10 1992 P ASME Section 1995


2135 ASME ASME N/S Rules for Construction of Nuclear stswstB3.4 .12 1992 R ASME Section 1995


2136 ASME ASME 1982 Rules for Construction of Nuclear regi' .8-.r3 1985 R ASME Section 1995

Section III Power Plant Components lIl

2137 ASME ASME N/S ASME Section III, Subsection NB srp3.2.2 1981 P ASME Section 1995

Section III, III, SubSection

Class 1 NB

2138 ASME ASME N/S ASME Section il, Subsection NB srp5.2.1.1 1981 P ASME Section 1995

Section 1I1, Ill, SubSection

Class 1 NB

2139 ASME ASME N/S ASME Section Ill, Subsection NC srp3.2.2 1981 P ASME Section 1995

Section Iii, Ill, SubSection

Class 2 NC

2140 ASME ASME N/S ASME Section Ill, Subsection NC srp5.2.1.1 1981 P ASME Section 1995

Section Ill, Ill, SubSection

Class 2 NC

2141 ASME ASME N/S ASME Section Iil, Subsection NC srp3.6.1 1990 P ASME Section 1995

Section Illi Ill, SubSection

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NOl SubSectionND

__________ --- I Ia aI _ __ _ _.13_ __ _ _ _ _ __ _ _


Part A - Industry Consensus Codes and Standards.. .. .. .

Record;. Sta d D-. .A-i.- Latet Stndard L -t V l

No C:ode -:- Standa d Veion ite Document Da ility Com serion Da: te 6

2143 ASME ASME N/S ASME Section 1Il, Subsection ND srp5.2.1.1 1981 P ASME Section 1995

Section Ill, IIl, SubSection

Class 3 ND

2144 ASME ASME 1980 Rules for Construction of Nuclear 1 0cfr50.55a 1994 A No earlier than ASME Section 1995

Section Ill, Power Plant Components I1980 for Ill Division 1

Division 1 systems andcomponents

2145 ASME ASME 1989 Rules for Construction of Nuclear 1Ocfr5O.55a 1994 P Except (c)(2), ASME Section 1995

Section 1I1, Power Plant Components (c)(3), and Ill, Division 1

Division 1 (c)(4) in RegPo _.____

2146 ASME ASME NIS Rules for Construction of Nuclear not90-27 1990 P ASME Section 1995

Section Ill, Power Plant Components Ill, Division 1

Division 1

2147 ASME ASME N/S Rules for Construction of Nuclear reg1.72.r02 1978 P ASME Section 1995


Division 1



Division 1


Section Ill, Power Plant Components ill, Division 1

Division 1

2150 AsME ASME N/S Rules for Construction of Nuclear srp3.9.1 1981 R ASME Section 1995


Division 1

z

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_~~~~~~. . . .i~ .. Iii.X . . .i~fniR e c o r d S t a d a r d D ee, ..e. ..L.t e .

t a.d.rLaa t e s t V ed sl o n


Section HI, Power Plant Components Ill, Division 1

Division 1

2152 ASME ASME N/S Rules for Construction of Nuclear srp39 P IlME Section 1995

Section III, Power Plant Components Ill Division 1

Division 1


Section 1II, Power Plant Components Ill Division 1

Division 1


Section 1i1, Power Plant Components Ill, Division 1

Division 1

2155 ASME ASME N/S Rules for Construction of Nuclear srp6.1 .1 1981 P ASME Section 1995


Division 1

GI n1 'AA r(9 1Q77 R ASME Section 19952156 ASME A IstIllE N/UM

On-.-o Pitnt rnhmnnnPntM

. _, .III, Division 1

Codes and Standards. and Other Guidance Cited in Regulatory DocumentsPart A - Industry Consensus Codes and Standards

ReodStandar'd DoiAcp-Latest Standar Laftest VersIon

N6 ~ Cd tnad Vrin. Title' Douet Dt blt omments VrinDt

2159 ASME ASME N/S General Requirements for Division inm1245 App. B 1991 R ASME Section 1995

Section ill, 1 and Division 2 III, SubSection

SubSection NCA

NCA

2160 ASME ASME 1969 Not found not86-19 1986 R Typo in not86- n/a n/a

Section III, 19 - N-322.1 is

N-322.1 not a validASMEreference

2161 ASME ASME N/S Classification of Components srp6.6 1981 P ASME Section 1995

Section III, III, NCA-2000

NA-2000

2162 ASMIE ASME N/S Responsibilities of an NA not85- 15 1985 R ASME Section 1995

Section III, Certificate Holder III, NCA-3700

NA-3700

2163 ASME ASME N/S Quality Assurance inm35051B 1976 R ASMSE Section 1995

Section III, Ill, NCA-4000

NA-4000

2164 ASME ASME N/S Quality Assurance inm55092B 1976 R ASME Section 1995

Section III, Ill, NCA-4000

NA-4000

2165 ASME ASME N/S Quality Assurance inm55093B 1977 R ASME Section 1995

Section i1, III, NCA-4000

NA-4000

2166 ASME ASME N/S Certificates of Authorization, srp5.3.1 1981 P ASME Section 1995

Section III, Nameplates, Code Symbol Ill, NCA-8000

NA-8000 Stamping, and Data Reports

t'.)

C)"

'-I

U.)

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Recor| d StSnd ardndacd |cce'pt' Latest Standard Latest Ve ri on

21 7 SM --EN/-at eprsregi .87.r01 1975 R ASME Section 1995

Section lII, ,

NA-8400

2168 ASME ASME N/S Nature of These Rules and srp3.2.2 1981 R Cited for ASME Section 1995

Section iII, Components to Which They are definition Ill, NCA-1 11 0

NCA-1 110 Applicable

2169 ASME ASME N/S Nature of These Rules and srp3.9.4 1984 R ASME Section 1995

Section iII, Components to Which They are III, NCA-1110

NCA-1 110 Applicable

ASME ASME NIS Use of Code Editions, Addda 0cfr 55a 1994 P ASME Section 1995

Section III, and Cases ,

NCA-1 140

2171 ASME ASME N/S Classification of Components inm1245 App. B 1991 R ASME Section 1995

Section III, l

NCA-2000

2172 ASME ASME 1977 Establishment of Design, Service, regl.148.rOO 1981 R Referred to in ASME Section 1995

Section 1i1, and Test Loadings and Limits text Ili, NCA-

NCA-

2142(b) ASME ectio 199

2173 ASME ASME NIS Establishment of Design, Service, regl.130.rOl 1978 R Cited tor ASME Section 1995

Section III, and Test Loadings and Limits definition III, NCA-

NCA- 2142.2(b)

2142.2(b) ---

2174 ASME ASME N/S Responsibilities and Duties inm1245 App. B 1991 R ASME Section 1995

Section III, III, NCA^3000

NCA-3000

2175NS Provision of Design Specif ication regl .148.rOO 1981 P ASME Section 1995

Section III, ,

NCA-3250

Codes and Standards and Other Guidance Cited in Regulatory.DocumentsPart A - Industry Consensus Codes and Standards

RecordSadrDo. Act-Ltt StandadLts eso

No. Code Standa~rdI. Vesinml D ment -Dat %blt Comens er*1 Date.

276 AsME ASME N/S Contents of Design Specifi!cations reg 1. 148.rOO 191 P ASME Section 1995

Section Ill, Ill, NCA-

NCA- 3252(a)

3252(a) _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ _ _ _ _ _

277 ASME ASME N/AS Filing of Design Specifications regil.148,r00 1981 R ASME Section 1995

Section 11I, Ill, NCA-3256

NCA-3256

21718 ASME ASME N/S Modification of Documents and inm37051 197 R ASME Section 1995

Section Ill, Reconciliation With Design Report Ill, NCA-3554

NCA-3554

2179 ASME ASME N/S Metallic Material Organization's bu183-006 1983 R ASME Section 1995

Section III, Quality System Pogram [ill, NCA-3800

NCA-3800

2180 A~SME ASME N/S Metallic Material Organization's bul88-005 1988 P ASME Section 1995

Section III, Quality System Program Ill, NCA-3800

NCA-3800

2181 ASME ASME 1977 Metallic Material Organization's inm361 00 1983 R ASME Section 1995

Section Ill, Quality System Program fill, NCA-3800

NCA-3800

2182 ASME AS`ME ~ N/S Metallic Material Organization's inm5OO9O 1985 H ASME Section 1995

Section III, Quality System Program Ill, NCA-3800

NCA-3800

213 AsME ASME N/S Metallic Material Organization's not83-0 7 18 mle

Section III, Quality System Program endorsement Ill, NCA-3800

NCA-3800

218 AKSME- ASME N/S Metallic Material Organization's not88-95 1988 PASEecin 19

Section Ill, Quality System Program Ill, NCA-3800

NCA-3800

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Record Standard Dcc. Acct- Ltet S:.. -tandard Latest V o r:o.

N o. C o eSt n ar er i n i l D ocu m e t D at ab it C o"m m en ts i `.' lo w f l Da te

2185 ASME ASME N/S Quality Assurance inmi 245 App. 8 1991 R ASME Section 1995

Section liI, III, NCA-4000

NCA-4000

2186 ASME ASME N/S Not Found inm37051 1987 R NCA-4137.7 n/a nla

Section ill, not in current

NCA-4137.7 ASME B&PVCode

2187 ASME ASME N/S Class I Components inm48051 1986 R ASME Section 1995

Section ill, III, SubSection

SubSection NB

NB


Section Ill, III, SubSection

SubSection NB

NB


Section III, Ill, SubSection

SubSection NB

NB

2190 ASME ASME N/S Class I Components inm55092B 1976 R ASME Section 1995

Section IIl, lli, SubSection

SubSection NB

NB

2191 ASME ASME N/S Class I Components inm55093B 1977 R ASME Section 1995

Section liI, III, SubSection

SubSection NB

NB



ocd a Standard 0 Do Acomtn Ltt a LatetiVsi


Section lIl, Ill, SubSection

SubSection NB

NB


Section III, Ill, SubSection

SubSection NB

NB

2194 ASME ASME N/S Class I Components regl .121.rOO 1976 P ASME Section 1995

Section 111, Ill, SubSection

SubSection NB

NB

2195 ASME ASME N/S Class I Components regl.65.rOO 1973 P ASME Section 1995

Section IlIl, Ill, SubSection

SubSection N8

NB

2196 ASME ASME N/S Class I Components regl.70.rO3 1978 P ASME Section 1995

Section IlIl, Ill, SubSection

SubSection NB

NB

2197 ASME ASME N/S Class I Components regl.87.rOl 1975 R ASME Section 1995

Section 111, Ill, SubSection

SubSection NB

NB

2198 ASME ASME 1975 Class I Components reg3.27.rOl 1977 P ASME Section 1995

Section 1II, Ill, SubSection

SubSection NB

NB

t-)U3

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Code Standard.,,- , .. Ve,,si-n Tl . Document... , , t , bilit C omm nt \,, Ve o Date_........

2199 ASME ASME N/S Class I Components srp3.2 1981 P ASME Section 1995

Section lII, NII, SubSection

SubSection NB

NB

2200 ASME ASME N/S Class I Components srp5.2.1. 2 1981 R ASME Section 1995

Section liI, III, SubSection

SubSection NB

NB

2201 ASME ASME NS Class I Components srp5.3.1 1981 P ASME Section 1995

Section ill, ill, SubSection

SubSectionNB

2202 ASM ASME N/S Introduction srpl5.1.1 1981 R ASME Section 1995

Section III III, NB-1O0

NB-1000

2203 ASME ASME 1986 Material inm9900/ 1994 R III, Section 1995

Section III, SGTUBE III, NB-2000

NB-2000

2204 ASME ASME N/S Permitted Material Specifications glt9i-018 1991 - ASME Section 1995

Section ill, III, N.-2121

NB-2121

2205 ASME ASME N/S Permitted Material Specifications inm9900 1991 R ASME Section 1995

Section IIl, III, NB-2121

NB-21 21

2206 ASME ASME N/S Permitted Material Specifications drgl008.rOO 1991 R ASME Section 1995

Section liI, lii, NB-2121(b)

NB-21211b)



StR D.... Ac.pt Latest St':ndad Late Version

No': code'~` Standad Vrit il D~Aocuen ate abli: Cmet etlnD

2207 ASME ASME N/S Permitted Material Specifications not93-61 1993 R ASME Section 1995

Section III, Ill, NB-2121 (b)

NB-2121 (b)

2208 ASME ASME 1993 Fracture Toughness Requirements drgl027.rOO 1994 R ASME Section 1995

Section ll, for Material III, NB-2300

NB-2300

2209 ASME ASME N/S Fracture Toughness Requirements srp5,4.2.1 1981 P ASME Section 1995

Section III, for Material liI, NB-2300

NB-2300

2210 ASME ASME 1979 Material for Which Impact Testing not89-22 1989 R ASME Section 1995

Section Ill, is Required Ill, NB-231 1

NB-231 1

2211 ASME ASME NIS Material for Vessels 10cfr50 App G 1994 R ASME Section 1995

Section III, Ill, NB-2331

NB-2331

KASME ASME N/S Material for Vessels 1 0cfr50.61 1994 R Cited for ASME Section 1995

Section III, definition III, NB-2331

NB-2331

2213 ASME ASME N/S Material for Vessels reg .14.rOl 1975 P ASME Section 1995

Section III, IlI, NB-2331 (a)

NB-2331 (a)

2214 ASME ASME N/S Retests reg 165lrO0 1973 P ASME Section 1995

Section Ill, Ill, NB-2350

N8-2350

2215 ASME ASME N/S Examination and Repair of regl.14.rOl 1975 P ASME Section 1995

Section III, Pressure Retaining Material III, NB-2500

NB-2500

C-,

'-4

(5

qj1

'a



_ _ -----

Sai da , r 0, p a . 5... 7: f. .. . I.". 1. ? I ' Ell

":b; D cume"nt t ;: Doc.

Date1 981

tRecord i

No.2216

in:PJ^: -. . 64-4-dne Titla:.i U : j 900e , -: = = NS _ xaInat__- a a r of a -----

ASME ASMESection 111,NB-2530

NIS Examination ana Repair or Hiam bl P.- ."..

5iAccept-t

P

L atest St anda rd L ate st lVe rsio nX V : ~Date

ASME Section 1995IINB-2530

.Cmments

A . . . . . -48 <1R

2217 I ASME ASMESection III,NB-2530

N/S Examination and Repair ot Plate Sfp I .4.0 I - I

II ----- I--_ .. .Exm:to and Reai oo i11T1FiN/S

2218 1 ASME

2219 1ASME

iw

2220 1 ASME

ASMESection III,NB-2540

Section III,NB-2545

ASMESection III,NB-2546

ASMESection lill,NB/NC/ND2550

N/S Examination and Repair oF

Forgings and Bars

N/S jMagnetic Particle Examination regl.65.rOO 11S73 1P

s ern1 a 7 '2 I HlSrp UG.

NIS ILiquid Penetrant Examination jreg1.65.r00 1973

.gt

ASME SectionIII, NB-2530

ASME SectioniII, NB-2540


ASME Section

IlIl, NB-2546

ASME SectionIlI, NB/NCiND-2550


ASME SectionIll, NB-2550

1995

1995

1995

19951995

1995

1995

22211 ASMENIS Examination and Repair of

Seamless and Welded (Without

Filler Metal) Tubular Products and

Fittings

srp103.0 1F981 P

-. A - IN/S2222 ASME ASME

Section III,NB-2550

NIS Ex-amination and Repair of

Seamless and Welded (Without

Filler Metal) Tubular Products and

Fittings

f QA F;Q 1 SIHanot04-00 I -:0* P

P

-2 223 ASME| ,, ._ rrvt; 7 2 1 1 FIH cs01srps .4:.o 1;7U %N/SASMESection 111,NB-2550

NiS E -xmnato adRpair ofSeamless and Welded (WithoutFiller Metal) Tubular Products andFittings

slpu.4.0; =

I -- I

II .6 --------

zcri

;V


: Record; 4 6 a .Stand ard i Do- e a t StandaNo C de~ San ad Vesin -- Tte ocimtt at biit C nnint e rst-ionu ont

2224 ASME ASME N/S Examination and Repair of Tubular srpS.2.3 1981 P ASME Section 1995

Section Ill, Products and Fittings Welded with Ill, NB-2S60

NB-2560 Filler Metal

2225 ASME ASME NIS Examination and Repair of srp5.2.3 1981 P ASME Section 1995

Section lIl, Statically and Centrifugally Cast ill, NB-2570

NB-2570 Products

2226 ASME ASME N/S Examination of Bolts, Studs, and reg1.65.rOO 1973 P ASME Section 1995

Section IlIl, Nuts Ill, NB-2580

NB-2580

2227 ASME ASME N/S Liquid Penetrant Examination regl .65.rOO 1973 P ASME Section 1995

Section 1II, IlI, NE-2584NB-2584

2228 ASME ASME N/S Service Conditions srp3.9.4 1984 P ASME Section 1995

Section 11I, Ill, NB-3113

NB-3113

2229 ASME ASME NIS Special Considerations srp5.2.3 1981 P ASME Section 1995

Section IlIl, Ill, N8-3120

NB-3120

2230 ASME ASME N/S Level D Service Limits not90-49 1990 P ASME Section 1995


NB-3225

2231 ASME ASME NIS Testing Limits inm70362 1983 R ASME Section 1995

Section 11I, Ill, NB-3226

NB-3226

2232 ASME ASME N/S Testing Limits inm70462 1983 R ASME Section 1995

Section lIl, Ill, NB-3226

NB-3226

z

tin

(5

'3'



Co e198V3le ileD c me t D t ablt AoSMEe S~e ction 1995

2233 ASME ASME N/S Testing Limits inm70562 13'S NB-2S2tio 1995


NB-3226

2234 ASME ASME N/S General Requirements for drgtO08.rOO 1991 _ ASME Section99

Section III, Centrifugal Pumps Ill, NB- 341 .2

NB-3411.2

2235 ASME ASME N/S General Requirements for not93'61 1993 R ASME Section 1995

Section III, Centrifugal Pumps Ill, NB- 3411.2

N8-3411.2

2236 ASME ASME NIS Piping Design srp3.6.2 1981 P ASME Section 1995

Section 1II, III, NB-3600

NB-3600

2237 ASME ASME N/S Consideration of Design g1t79-045 1979 _ ASME Section 1995

Section III, Conditions III, NB-3652

NB-3652

2238 ASME ASME N/S Consideration of Level A Service g9t87-01 1 1987 P ASME Section 1995

Section 1II, Limits ll, NB-3653

NB-3653

2239 ASME ASME NS Consideration of Level A Service regi .96.rO1 1976 P ASME Section 1995

Section III, Limits Ill, NB-3653

NB-3653

2240 ASME ASME N/S Consideration of Level A Service srp3.6.2 1981 P ASME Section 1995

Section III, Limits Ill, NB-3653

NB-3653

2241 ASME ASME 1981 Instrument Piping regl .151 .rOO 1983 R ASME Section n/a nia


NB-3676 deleted

-4

zC)

tJh

(5


DO COO ad IM W 6. ^1 i_ __i

Reor , - i Stnd^ Dc ACdep- Lates StandardV Les Veso~N o . C o d e S t a n d a r d V e r si o n T i ~::tl e ,: b e i m n a e a i i yC m e t s o a t e

2242 ASME ASME N/S Applicability of Indices - General not83-80 1983 P ASME Section 1995

Section ill, Ill, NB-3683.2

NB-3683.2

2243 ASME ASME N/S Documentation of Repair Welds of inm55050 1983 R ASME Section 1995

Section Ili, Base Material ill, NB-4132

NB-4132

2244 ASME ASME N/S Welding Qualifications inm50082B 1976 R ASME Section 1995

Section Ill, Ill, NB-4300NB-4300

2245 ASME ASME N/S Heat Treatment inm55092B 1976 R ASME Section 1995

Section Iii, Ill, NB-4600

NB-4600

2246 ASME ASME N/S PWHT Time and Temperature git90-005 1990 R ASME Section 1995

Section Ill, Requirements Ill, NB-4622

NB-4622

2247 ASME ASME N/S Heat Treatment After Bending or inm550929 1976 R ASME Section 1995

Section Ill, Forming for Pipes, Pumps, and ill, NB-4650

NB-4650 Valves

2248 ASME ASME N/S Examination bu182-001,srl 1982 R ASME Section 1995


NB-5000

2249 ASME ASME N/S Examination bui82-001.rOl 1982 R ASME Section 1995

Section Iii, Ill, NB-5000

NB-5000

2250 ASME ASME 1977 Radiographic Acceptance reg .1 50.rOl 1983 P Implied ASME Section 1995

Section Ii, Standards endorsement Ill, NB-5320

NB-5320

z(7_1MQQ�A

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I IaCode Standard Ve~a~on Title 1 Docmont Ot blty Cmet

----- --- 199n4dm

I

2251 ASME ASMESection lIl,NB-5350

N/S Liqutan aenetrads AC-13-11Standards

ISG11T-UvI3E. _ _ .

2252 ASME ASME N/S Overpressure Protection srp15 .22.1 1981

Section 1It,NB-7000

. -e r -Mntotin s152.6 1981_

R

R2253

K24ASME ASME

Section 1Il,NB-7000

NIS uverpressure MrOMc,u,

I _ _ _ _ _ I I - -- - - - -

N/ --verpre - 4r I roie cuuri SR -_

ASME ASMESection 1II,NB-7000

NIS overpressure Protection Dp F I--. > v g

IL L - 4 1. *IiM iN/ uve-rprIessuf-

R

R

I

SLatet iard


ASME SectionMI, NB-7000

ASME Section_

III, NB-7000

ASME SectionII, NB-7000

ASME SectionII, NB-7000

_ASME SectionIII, NB-7000

ASME Section

III, NB-7000

^tesjVrsiowD..[ate -

1995

1995

1995

1995

1995

2255 - ASME ASMESection lIl,NB-7000

NISj uverpressurtl rrolerine -( . . ...

______ 1 .,.rL-i B-,,.,;..., 198112256 ASME ASME

Section Ill,N8-7000

Nlib Vver1presszure F---~v. Pwvee @

1995

1995

1995

I - *1- L ~: 1i1q'. I ----R2257 ASME ASME

Section IlIl,NB-7000

NIS Overpressure Pruiection -FM ------ v f v v a .

I/ I erressrl euauA I R2258

2259

ASME I

ASME

ASMESection Ill,NB-7000

N15 uverpressure rrOMec-1c It'l ..... . _ _ .

I I__ _A ._ ->ttoA 1 1 O i I P 1 Isrp 1 .. VI~

ASMESection 111,NB-7000

N/S Overpressure Protection tirp t D.-+.v I - .ASME Section 1995il, NB-7000

I I _ _ _ I ---- - I I - - - -- -- -



Record taniard .ASE Lt Standerd Letest Vej:ion

o. Code Stnad VrinTteDcmn ee aiiy Comet rinbt

2260 ASME ASME N/S Overpressure Protection srpl 5. 5. 1 1981 RASEecin 19

Section III, III, NB.7000

NB-7000

2261 ASME ASME N/S Overpressure Protection srpl5.6.1 1981 R ASME Section 1995

Section iII, III, NB-7000

NB-7000

2262 ASME ASME N/S Overpressure Protection sts4-geB2.1.2 1992 P ASME Section 1995


NB-7000.

2263 ASME ASME N/S Overpressure Protection sts6-geB2.1.2 1992 P ASME Section 1995

Section III, III, NB-7000

NB-7000.

2264 ASME ASME N/S Overpressure Protection stsb&w82.1.2 1992 P ASME Section 1995

Section liI, III, NB-7000

NB-7000.

2265 ASME ASME NIS Overpressure Protection stsceB2.1.2(a) 1992 P ASME Section 1995


NB-7000.

2266 ASME ASME N/S Overpressure Protection stsceB2.1.21d) 1992 P ASME Section 1995


N1B-7000.

2267 ASME ASME N/S Overpressure Protection stswstB2.1.2 1992 P ASME Section 1995


NB-7000.

2268 ASME ASME N/S ReMiefing Capacity of Pressure rei O 1995 R ASME Section 1995

Section iII, Relief Devices III, NB-73 11 (b)

NB-73 11(b)

z

%'0-4

CD

z4

0~

0



R e o r S t n a r~~.D o s A c c e p t- L a te st S ta n d a rd L t a e s o

o .C dS t a d r > V ~ i nT O . . . .: ~ . . . ~ o t m n a e a i i yC m e t e t Io n ; : D:~a t e

2269 ASME ASME N/S Burst Pressure Tolerance sr522 19886 1 A S 199b


NB-7611

2270 ASME ASME N/S Class 2 Components inm48051 1986 R ASME Section 1995

Section 111, INC, SubSection

SubSection NC

NC

2271 SME ASME N/S Class 2 Components inm48053 1986 R ASME Section 1995

Section lII, III, SubSection

SubSection NC

NC


Section III, Nll, SubSection

SubSection NC

NC

2273 ASME ASME NIS Class 2 Components not87-36 1987 A ASME Section 1995

Section III, ill, SubSection

SubSection NC

NC

2274 ASME ASME N/S Class 2 Components regi,70.rO3 1978 P -A SE Section 1995

Section lII, III, SubSection

SubSection NC

NC

2275 ASME ASME N/S Class 2 Components srp3.2.2 1981 P ASME Section 1995

Section 111. Il, SubSection

SubSection NC

NC


R "

y No. U Coe taad Vrion .. T4te Docmen O2 ,. bily Coent . Veso. i i 'e

2276 ASME ASME NIS Class 2 Components srp5.2.1.2 1981 R ASME Section 1995


SubSection NC

NC

2277 ASME ASME 1977 Class 2 Components stp6.2.7 1981 P ASME Section 1995


SubSection NC

NC

2278 ASME ASME N/S Fracture Toughness Requirements srp5.4.2.1 1981 P ASME Section 1995

Section III, for Material III, NC-2300

NC-2300

2279 ASME ASME 1979 Material for Which Impact Testing not89-22 1989 R ASME Section 1995

Section IlIl, is Required III, NC-2311

NC-231 1

2280 ASME ASME N/S Piping Design g1t87-01 1 1987 R ASME Section 1995

Section IIl, Ill, NC-3600

NC-3600

2281 ASME ASME N/S Piping Design srp3.6.1 1990 R ASME Section 1995

Section Ill, lli, NC-3600

NC-3600

2282 ASME ASME NIS Piping Design srp3.6.2 1981 P ASME Section 1995

Section liI, III, NC-3600

NC-3600

2283 ASME ASME N/S Consideration of Design g1t87-011 1987 _ ASME Section 1995

Section IIl, Conditions III, NC-3652

NC-3652

C-

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nN

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w



-. 777777 II

Recotrd.,:. ... .1:

" �� i i MStan drd Doec.:lDate-

St . . ;,, tzAT: I THlet , , D: ocUr -it'No L U~: S Stnbw I~ _ - . t. rn. ------ 81

N -1JM _._'_,-:n i _ M ~q . _ 11 8

2284 ASME ASMESection IIl,NC-3652

IN10

Conditions

v

i. .. ... 'l .. ?. ... ::Accept-

P

R

I, ...0 ,.. - . :] 0 i,,, I . I.. . I'>, , .

.C~oniments _

NC-3652.4 nolonger in LatestVersion

Latest Standard. , .; j e s-;VeftlcIoASME SectionIII, NC-3652

Woiost ~Veislo I

Date1 995

.

I I I . IJI - IU4 O )-S-t J 1 1983 nla n/a2285 ASME ASME

Section 111,NC-3652.4

I zi/ /

Conditions

... __ _ .

- ____ _I I _ L . d IAh 197t ..oniara -o -1 IL.-IAUV 18 ASME SectionIII, NC-3653

1995

2286 ASME ASMESection 111,NC-3653

NIS onsideration iT Lsvel / dll D

Service Lirnitsti-, - .,, . _ _ .

I____ _I I I :._...ir(1t_.O.-I - - -I n l 1q o Th193 R2287

2288

ASME ASMESection III,NC-3676

I U01 InstruIeTIU1 rllIlrlu vve . . . _ . .. __

ASME SectionIII, NC-3676deleted

nla n/a

4�.I ______. . -. _1..70nm q I 9 P

ASME ASMESection III,NC-5000

N/S Examination - Is ,-- ..-

I I ---- I I tS., F R2289 1 ASME ASME

Section III,NC-5000

NS Examination DUUt04-VV I .rv I I - I

_ _ _ _I __ _ _ _ _ ..._.- f, t h~.th,,R2-01.srl I T i R5-- - I

ASME SectionIlI, NC-5000

ASME Section-

Ill, NC-5000

ASME SectionIII, NC-5000

ASME SectionIII, NC-7000

ASME Sectionill, NC-7000

2290 ASME ASMESection III,NC-5000

ASMESection III,NC-7000

N/Z3 tXU111fialuon V < s

1995

1995

1995

I

1995

1995

I _ _ _ _ _ _ .1 -----It.3&W-3.. I

2291 1 ASME N/S Overpressure Protection sstsbawt5. /.1I I "U-. I

I I s s e -* I

2292 ASME-

L��ASMESection lIINC-7000

N/S Overpressure Protection ._Dt 7 1 1 1 Qq7siscet5-5. /. I -s:: P 1 _ _

I


Rcd tandard D t Standard La tet Vsn

N .VI Code d6 V . St aio tl -D. n t t e i .2293 ASME ASME NIS Overpressure Protection stswstB3.7.1 1992 P ASME Section 1995

Section lii, lil, NC-7000NC-7000

2294 ASME ASME NIS Class 3 Components inm48051 1986 R ASME Section 1995

Section ii, ii, SubSection

SubSection ND

ND


Section lii, ill, SubSection

SubSection ND

ND


Section iii, iii, SubSection

SubSection NDND

2297 ASME ASME NIS Class 3 Components not86-51 1986 R ASME Section 1995

Section Ili, iii, SubSection

SubSection ND

ND

2298 ASME ASME N/S Class 3 Components regl.137.rO1 1979 P ASME Section 1995

Section iii, lii, SubSection

SubSection NDND

2299 ASME ASME NIS Class 3 Components regl.70.r03 1978 P ASME Section 1995

Section iii, lli, SubSection

SubSection NDND

w4�-w

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nt!h�0--jU.)

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.,-,.-,. .ReceEdi .... :,CSt. n ,1 ^. , .. . -,0;.., .E , , ..davd ' ':.

,, .......... . ec Accept,,,X. ... ,;.- Late $tndr -. es Vee

. .. . ..St n A S M E o * . 2 T~ l D c w ie tD te a il t . C o n e tS r Se ci on D a9 5

2300 ASME ASME N/S Class 3 Components srp3.2- 1981 P IM m tSection .

Section 111, ND

SubSection N

ND

2301 ASME ASME N/S Class 3 Components srp5.2.1.2 1981 R ASMESection 1995


SubSection ND

NO

2302 ASME ASME NIS Piping Design srp3.6.1 1990 R ASME Section 1995

Section III, IIl, ND-3600

ND-3600

2303 AASME SME NIS Consideration of Level A and B glt87-01 1 1987 R ASME Section 1995

Section Ill, Service Limits Ill, ND-3653

ND-3653

2304 ASME ASME 1981 Instrument Piping regl.151.rOO 1983 R ASME Section n/a n/a

Section IlI, Ill, ND-3676

NeD3676' deleted

2305 ASME ASME N/S Class MC Components gIt79-005 1979 R ASME Section 1995

Section IlIl, Il, SubSection

SubSection NE

NE

--iA1 t i 1 87 P ASME Section 123066 7 ASME ASME

Section III,NIS

SubSectionNE

k'lass mu l'or"Pullunt* U--, -v .. . .

III, SubSectionNE

L-I

I t I I - _ _ _ _ - - --___ _ _ _ __I-



IRecord tonded 'd ' ,: Dcc. - L Standard La,'t e't V _,lo.

o. Cde Standd'"Vrlt titTtle louai ate bity CMIeTs' "VrnDate.

2307 ASME ASME N/S Class MC Components inm48051 1986 R ASME Section 1995

Section Ill, lil, SubSection

SubSection NENE

2308 ASME ASME N/S Class MC components inm48053 1986 R ASME Section 1995

Section Ill, l:1, SubSection

SubSection NE

NE

2309 ASME ASME NIS Class MC Components inm53050 1983 R ASME Section 1995

Section l11, il, SubSection

SubSection NE

NE

2310 ASME ASME N/S Class MC Components regl.57.rOO 1973 P ASME Section 1995

Section Ill, l e

SubSection N

NE

2311 ASME ASME N/S Class MC Components regl.70.rO3 1978 P ASME Section 1995

Section 111, iill, SubSection

SubSection NE

NE

2312 ASME ASME 1975 Class MC Components reg3.27.rO1 1977 P ASME Section 1995

Section Il1, I11, SubSection

SubSection NE

NE

2313 ASME ASME N/S Class MC Components srp3.6.2 1981 P ISME Section 1995

Section Ill, Sbci

SubSection NE

NE

'0

z

U'

(!h


Part A - Industry Consensus Codes and Standards- IU',

IRecotd'. '-.lot 1: -k�' I I C �

.. ;� , !, '.:.N 'I.,-,;,. ,

I ; I I�� .1 ,:, - ..

� 4�� :; 1 w'i"

]Standp#djI �

T .;; . ie. .!" .

-~ ni ' Documentzd. es

, c e . t -

a billi -.A PC ,omn'ehts LatestStantdard Laes Verslon

verin rDate o

ASME Section 199S

III, SubSectionNE

E N O . " D u I ~n R ? ~ ~ 9It ~- : I - I -N i9 81

2314 ASME

2315 1 ASME

ASMESection III,SubSectionNE



ASMESection lII,SubSectionNE

N/S %A!ass IMit %1V111lvU11v

N/S Cilass MC Components t-- srp3.8.3 |19811 P

2316- I ASME-I MCComponents R

N/S CIlass Mc components Isrp5.21 1151

Q M.._

2317 ASME N/S - Class MC Components |srp6.2.1 1981 R

ASME Section _Ill, SubSectionNE

ASME SectionIII, SubSectionNE

ASME SectionItt, SubSectionNE

ASME Section

Ili, SubSectionNE

ASME SectionIll, SubSectionNE

1995

1995

1995

1995

1995

I _ . =I 1 9 iN/S~4 ' 141 P2318 T ASME

2319 ASME

ASMESection tII,SubSectionNE


ASMESection III,NE-1120

N/S Class MC Components s[p0.4.I I,

N/S Ctass MC Components tsrp6.2.7 1 1981 1 P

xs^

I 1 I P

2320 ASME NIS Ruies for Csass MC ContainmentVessels

gltu7-V01 I 1 Z70 r With additionallisted designrequirements

ASME Section 1995

Il, NE-1120

_____________ --



'Reord Stndr Doc Acet Lates> Stndr Latndt der.ioNo.Cd Sadad Vrln il ...... iet .Dte.bii. Commenits V- sonDt

2321 ASME ASME N/S Rules for Class MC Containment regl .96.rOl 1976 P ASME Section 1995

Section lIl, Vessels III, NE-1 120

NE- 1120

2322 ASME ASME N/S Rules for Class MC Containment srp3.6.2 1981 P ASME Section 1995

Section Ilil, Vessels III, NE-1120

NE-1 120

2323 ASME ASME N/S Material srp3.8.2 1981 P ASME Section 1995

Section Illi, Ill, NE-2000

NE-2000

2324 ASME ASME N/S Design srp3.8.2 1981 P ASME Section 1995

Section lil, Ill, NE-3000

NE-3000

2325 ASME ASME N/S Design srp3.8.3 1981 P ASME Section 1995

Section III, Ill, NE-3000

NE-3000

2326 ASME ASME 1980 Stress Intensity and Buckling 1 0cfrSO.34 1994 A Except ASME Section 1995

Section III, Stress Values for Other Than Bolts evaluation of Ill, NE-3220

NE-3220 instability notrequired __ASME____ptfon _1_99_5_,

2327 ASME IASME 1980 IStress Intensity and Buckling 10cfr5O.44 1994 A ASME Section 1995

t-3

z

(~A

-I

4:~00



e d .tandard' 5 aD o e, A ccept- Late st Standard L Ver|ion

N o6C d a S t n a d V r i0Tt eD c u m t D a e a i t y C m n s V e rs io n D a t

2330 ASME ASME NS Examination srp3.8.2 1981 P ASME Section 1995

Section lii, Ill, NE-5000

NE-5000

2331 ASME ASME N/S Testing srp3.8.2 1981 P ASME Section 1995

Section IlIl, II, NE-6000

NE-6000

2332 ASME ASME N/S Typical Containment Penetrations bui80-028 1980 R ASME Section 1996

Section IlIl, III, Figure NE

Figure NE 1120-1

1120-1

2333 ASME ASME 1975 Typical Containment Penetrations glt8O-028 1980 P ASME Section 1995

Section lil, III, Figure NE

Figure NE 1120-1

1120-1

2334 ASME ASME N/S Component Supports drgfc798-4 1981 R ASME Section 1995


SubSection NF

NF

2335 ASME ASME N/S Supports git79-004 1979 P ASME Section 1995

Section Ill, 111, SubSection

SubSection NF

NF

233 ASME ASME N/S Supports inm48051 1986 R ASME Section 1995

Section Ill, Ill, SubSection

SubSection NF

NF



si:

ReodSadO d Doc Acep- tst Stndard Latest Vewbin

N. Cd Stnrd erinTteDocuen Date abiit Ck1ens Vetaon

2337 ASME ASME N/S Supports inm48053 1986 R ASME Section 1995

Section III, IlI, SubSection

SubSection NF

NF

2338 ASME ASME N/S supports inm70309 1985 8 ASME Section 1995

Section III III, SubSection

SubSection NF

NF

2339 ASME ASME N/S Supports inr70370 1987 R ASME Section 1995

Section 111, ill, SubSection

SubSection NF

NF

2340 ASME ASME N/S Supports r1t86.2r 1986 R ASME Section 1995


SubSection NF

NF

2341 ASME ASME N/S Supports regl.124.rOl 1978 R ASME Section 1995

Section fil, III, SubSection

SubSection NF

NF

2342 ASME ASME N/S Supports reg1.130.rO3 1978 R ASME Section 1995

Section III, 111, SubSection

SubSection NFNF

43 ASME ASME N/S Supports regl.70.r03 1978 P ASME Section 1995


SubSection NP~

NP

1z

U'

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'C od e S", ta n d a r d V e r ai TilOD c m e t D tetab l t C`e n st rs o I D t

2344 ASME ASME N/S Supports regl.87.rOl 1975 R ASME Section 1995


SubSection NF

NF

2345 ASME ASME N/S Supports srp3.8.3 1981 P ASME Section 1995

Section iII, III, SubSection

SubSection NF

NF

2346 ASME ASME N/S Supports srp3.9.3 1981 R ASME Section 1995

Section lii, III, SubSection

SubSection NF

NF

2347 ASME ASME N/S Supports srp5.2.1.2 1981 R ASME Section 1995

Section II, Illt, SubSection

SubSection NF

NF

2348 ASME ASME N/S Linear-Type Support regi .124.rOl 1978 PA S SE Section 1995

Section iII, III, NF-1213

NF-1213

2349 ASME ASME N/S Permitted Material Specification not88-95 1988 R ASME Section 1995

Section iII, IIl, NF-2121

NF-2121

2350 ASME ASME N/S Certification of Material not88-95 1958 _ ASME Section 1995

Section liI, III, NF-2130

NF-21 30

2351 ASME ASME N/S Material Test Coupons and not88-95 1988 R ASME Section 1995

Section iII, Specimens for Ferritic Material Ill, NF-2200

NF-2200



Record S -dO\ D t ..o. a. .. . . _ .. _

No;. code Stndrd . it t date it. c. entWD io

2352 ASME ASME N/S Material Manufacturer's Quality not9t-25 1991 R ASME Section 1995

Section 111, System Programs III, NF-2600

NF-2600

2353 ASME ASME N/S Design Loadings regl .1 24.rO1 1978 P ASME Section 1995

Section III, IlI, NF-3112

NF-3112

2354 ASME ASME N/S Design Loadings regl.1 30.rOl 1978 R Cited for ASME Section 1995

Section III, definition III, NF-3112

NF-3112

2355 ASME ASME N/S Service Conditions reg1.130.rO1 1978 R Cited for ASME Section 1995

Section III, definition III, NF-3113

NF-3113

2356 ASME ASME N/S Elastic Analysis srp3.8.3 1981 P NF-3231.1 not n/a n/a

Section III, in current

NF-3231.1 ASME code

2357 ASME ASME N/S Elastic Analysis regl.124.rOl 1978 P NF-3231.1 not n/a n/a

Section III, in currentNF- ASME code

3231.1 (a)

2358 ASME ASME N/S Nomenclature and Numbering of regl .1 24.rO1 1978 P ASME Section 1995

Section III, Equations Ill, NF-3313

NF-3313

2359 ASME ASME N/S Scope regl.124.rO1 1978 P NF-3331.1 not ASME Section 1995

Section III, applicable here III, NF-3331.1NF-3331.1

c-n

z

(k)

t.)

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tii

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(ri



-__- -� r I

LateBt Standard Latest Version I

RecofddNo..":

2360Code

ASME

2361 ASMME

2362 1 ASME

Un 2363 ASME

iStandiardikiiASMESection 11,SubSection

NG

ASMESection IlIl,SubSectionNG

ASMESection IlilSubSectionNG

ASMESection IlIl,SubSectionNG

ASMESection I11,NG-120

ASME

Section III,NG-2000

ASME

Section Ill,NG-5300

tandardc-eraion.

NiSf i^; *-: .Titl*e i ;

Core Support Struc~tures

: D ocumen t

inm55050

o. ̂ , .

, 3o ,

: e urDt .::nDIlrte:S:e 1:

:,Accept-i+- :_11 , -; i ' : ~~ Cutortaiaismer

193 .Rv .v. _ . : .. . .... -

1983T R _ ASME SectionIll, SubSectionNG

1 Uttor * nnE:

N/S fCore Support Structures tregl .87.rOl R-7 ASME SectionIlI, SubSectionNG

1995

b st.Stand6r I- V ..... ' 'esion.ASe Section

p .9 1 9 -811:-- a 1995N/S iCore Support Structures srpS.9.5 sa81 F

Ill, SubSectionNG

N/S jCore Support Structures Isrp5.2.1.2 1981 R

D_ iito of Stutue and~1oR u IiHfr

. I 11 ---.;.,,Date

ASME SectionIll, SubSection.NG

ASME SectionII, NG-1 120

ASME SectionIll, NG-2000

1995

1995

19952364 ASME N/S Dsfinition of Strmotures and

Application of these Rules to

Them

reg I.20.rUZ I Z / ndefinition

____________________ .4 -- j..-.� - t ]srp4.5.2 1�b1 r

2365 ---I ASME NIS Imaterial srp4.5.2 1981s r

Ir4. 1911

2366 1ASME N/S

N/S

Examination and Repair of CoreSupport Structure Material

srp4.5.2 1981 UPlll, NG-2500

I -~w

I 4-. i- - iA* qprfttfnn 1 1995i ... I

- Acceptanc-e Standards I lb I r-Ill, NG-53002367 I AWV11:

L- I.1 ..


Reor1Sanad Do. Acet-LtSt Stiand ..ar Laes VrioNooe Sadard Veso ~ - il ouet ae~, L o tt eson Date..

2368 ASME ASME N/S Overpressure Protection srp5.2.2 1988 R Typo - Should ASME Section 1995

Section 1ii, be NX-7000 ill, NM-7000

NM-7000

2369 ASME ASME NIS Joints of Category D not85-33 1985 P ASME Section 1995

Section IlIl, Ill, NX-3352.4NX-3352 .4

2370 ASME ASME N/S Welding Qualifications, Records, inm55050 1983 _ ASME Section 1995

Section III, and Identifying Stamps ll, NX-4320NX-4320

2371 ASME. ASME N/S Heat Treatment inm55050 1983 R ASME Section 1995

Section 1II, Ill, NX-4600

NX-4600

2372 ASME ASME N/S Thickness, Penetrameter bul79-013.rO2 1979 P ASME Section 1995

Section III, Designations, and Essential Holes Ill, Table NC-

Table NC- 5111.15111-1

2373 ASME ASME N/S Testing srp5.3.2 1981 P ASME Section 1995

Section lii, Ill, XI-6000XI-6000

2374 ASME ASME N/S Nonmandatory Preheat Procedures inm55092B 1976 S ASME Section 1995

Section 1ii, Ill, Appendix D

Appendix D

2375 ASME ASME N/S Nonmandatory Preheat Procedures inmS5150 1983 t ASME Section 1995

Section lIl, ill, Appendix D

Appendix .

l.A

z

-'4

F.)-

zC)

V0

Lj



H e c ord ... ' dSen d a rd ' , . D o e A c e t . s S a V ersio

'l N o . . C ..d. a. $t n d rd V er sio n T '''',- ,,it e . D o cu m' nt D. t , bility C om men ts - V e . oD t

2376 ASME ASME N/S Nonmandatory Preheat Procedures srp6.1.1 1981 P ASME Section 1995

Section III, 1ll, Appendix D

Appendix D

2377 ASME ASME N/S Minimum Bolt Cross-Sectional reg1.87.rOl 1975 R Use should be ASME Section 1995

Section III, Area justif led III, Appendix E

Appendix E

2378 ASME ASME N/S Rules for Evaluation of Service git91-018 1991 R ASME Section 1995

Section iII, Loadings with Level D Service Ill, Appendix F

Appendix F Limits

2379 ASME ASME N/S Rules for Evaluation of Service inm55150 1983 R ASME Section 1995

Section iII, Loadings with Level D Service IlI, Appendix F

Appendix F Limits

2380 ASME ASME N/S Rules for Eauation of Service not90-49 1990 P General ASME Section 1995

Section iii, Loadings with Level D Service endorsements lli, Appendix F

Appendix F Limits

2381 ASME ASME N/S Rules for Evaluation of Service not95-09 1995 R ASME Section . 1995

Section III, Loadings with Level D Service il, Appendix F

Appendix F Limits

2382 ASME ASME N/S Rules for Evaluation of Service nuregO933. 2.8- i983 _-ASME Section 1995

. Section III, Loadings with Level D Service 51 iii, Appendix F

Appendix F Limits


_ _ X~~~~~I <kj. .:l.E ijj ...... -_

Noiofi':' ~.adard' V'son TteDocumeot.* .:De. .ablt. Cmnft8 .... VrioDte2383 ASME ASME N/S Rules for Evaluation of Service regl.124.rO1 1978 P ASME Section 1995

Section ill, Loadings with Level D Service ill, Appendix F

Appendix F Limits

2384 ASME ASME N/S Rules for Evaluation of Service reg1 .87.rOl 1975 R Use should be ASME Section 1995Section 111, Loadings with Level D Service justified Ill, Appendix F

Appendix F Limits

2385 ASME ASME N/S Protection Against Nonductile 1 Ocfr5O App. G 1994 P With ASME Section 1995

Section IlIl, Failure supplemental Ill, Appendix G

Appendix G requirements

2386 ASME ASME N/S Protection Against Nonductile glt89-021 1989 P ASME Section 1995Section lIl, Failure Ill, Appendix G

Appendix 6

2387 ASME ASME N/S Protection Against Nonductile not82-17 1982 R ASME Section 1995Section Illi, Failure Ill, Appendix GAppendix G.

2388 ASME ASME NIS Protection Against Nonductile reg1.161.rOO 1995 R ASME Section 1995Section ll, Failure Ill, Appendix GAppendix G

2389 ASME ASME N/S Protection Against Nonductile regl.65.rOO 1973 P ASME Section 1995Section Ilil, Failure Ill, Appendix GAppendix G

t'~)U"

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U'

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R ecor d S D cc. c L t S n r Lates t "ersLon

N o . c oid a S ta n d a rd V e r i o T tl D... .a..b li y C m m n s e s o nD t

2390 ASME ASME NiS Protection Against Nonductile regl .70.r03 1978 P ASME Section 1995

Section lIl, Failure Ill, Appendix G

Appendix G

2391 ASME ASME N/S Protection Against Nonductile srp5.2.3 1981 P ASME Section 1995

Section lII, Failure Ill, Appendix G

Appendix G

2392 ASME ASME N/S Protection Against Nonductile srp5.3.2 1981 P ASME Section 1995

Section lil, Failure Ill, Appendix G

Appendix G

2393 ASME ASME NIS Protection Against Nonductile srp5.3.3 1981 PASMESection 1995

Section 11i, Failure Ill, Appendix G

Appendix G

2394 ASME ASME N/S Protection Against Nonductile srp5.4.1.1 1981 R ASME Section 1995

Section Ill, Failure Ill, Appendix G

Appendix G

2395 ASME ASME NIS Protection Against Nonductile sts4-geB3.4.10 1992 A ASME Section 1995

Section [il, Failure III, Appendix G

Appendix G

2396 ASME ASME N/S Protection Against Nonductile sts6-geB3.4.11 1992 A ASME Section 1995

Section Ill, Failure Ill, Appendix G

Appendix G



Record - Standard Lae .Sta.dard Latest V e.son

No.; Code lilt Standard Version t D D t Comments¢ Ve *in Date

2397 ASME ASME NIS Protection Against Nonductile stsb&wB3.4.3 1992 A ASME Section 1995

Section III, Failure III, Appendix G

Appendix G

2398 ASME ASME N/S Protection Against Nonductile stsceB3,4.3 1992 A ASME Section 1995

Section IlI, Failure Ill, Appendix G

Appendix G

2399 ASME ASME N/S Protection Against Nonductile stswstB3.4.3 1992 A ASME Section 1995

Section Ill, Failure III, Appendix G

Appendix G

2400 ASME ASME N/S Design Stress Intensity Values, inm9900 1991 R ASME Section 1995

Section III, Allowable Stresses, Material Ill, Appendix I

Appendix I Properties, and Design FatigueCurves

2401 ASME ASME N/S Design Stress Intensity Values, reg1.70.rO3 1978 P ASME Section 1995



2402 ASME ASME N/S Design Stress Intensity Values, srp10.3.6 1981 P ASME Section 1995

Section Ill, Allowable Stresses, Material Ill, Appendix I



Section lii, Allowable Stresses, Material III, Appendix I



Section 1II, Allowable Stresses, Material :II, Appendix I

Appendix I Properties, and Design FatigueCurves _

z

'0

-4

z

00



Recod ...ID Acndrd Laet VXr0ited

6o c d S ta n d a d V e ioT i lD o ' m nb a e a i ty C m ntV e s c a ts


Section 1II, Allowable Stresses, Material III, Appendix I


2406 ASME ASME NIS Design Stress Intensity Values, srpS.2.3 1981 P ASME Section 1995

Section III, Allowable Stresses, Material III, Appendix I



Section 1iI, Allowable Stresses, Material III, Appendix I


2408 ASME ASME N/S Design Stress intensity Values, srp5.4.2.1 1981 P ASME Section 1995

Section III, Allowable Stresses, Material III, Appendix I





2410 ASME ASME N/S Experimental Stress Analysis reg l.87.rOl 1975 R Test ASME Section 1995

Section III, procedures Ill, Appendix II

Appendix It should bedocumented

2411 ASME ASME N/S Dynamic Analysis Methods nuregO933, 1991 R ASME Section 1995

Section Ill, 3.119 III, Appendix N

Appendix N

2412 ASME ASME /S Rules for the Design of Safety srp3.9.3 1981 P ASME Section 1995

Section III, Valve Installations IllI, Div. 1,

Appendix O Appendix O


Recod Stndar Doe "Acep*. LatCtStandatdfid' LAtes ee

No ee Stan ardJ :'Versiow,.~ -*lqDolnen ae blt aomns. e~n D

2413 ASME ASME NIS Design of Linear Type Supports by git79-004 1979 P AiSC S327 1984

Section III, Linear Elastic and Plastic AnalysisAppendixXVII

2414 ASME ASME N/S Design of Linear Type Supports by reg1 .124.rOl 1978 P Appendix XVII n/a n/a

Section III, Linear Elastic and Plastic Analysis not In current

Appendix ASME codeXVII

2415 ASME ASME N/S Limit Analysis Design srp3.8.4 1981 P Appendix XVII n/a n/a

Section III, not in current

Appendix ASME codeXVII-4000

2416 ASME ASME 1980 Code for Concrete Reactor 10cfr50.34 1994 P Same as ACI ASME Section 1995

Section III, Vessels and Containments 359 III, Division 2

Division 2

2417 ASME ASME N/S Code for Concrete Reactor 1 OcrS.44 1994 P Same as ACI ASME Section 1995

Section III, Vessels and Containments 359 ill, Division 2

Division 2

2418 ASME ASME 1993 Code for Concrete Reactor drg1027.rOO 1994 R . ASME Section 1995

Section Ill, Vessels and Containments Ill, Division 2

Division 2

2419 ASME ASME NIS Code for Concrete Reactor inm46091 1983 R ASME Section 1995

Section 11I, Vessels and Containments Ill, Division 2

Division 2

2420 ASME ASME N/S Code for Concrete Reactor inm47051 1983 R ASME Section 1995

Section III, Vessels and Containments III, Division 2

Division 2

z

F)

(5

LA)

z

-

I

t

6.

w

av


_ _. ... .. ..R e d S t n d d . A p L atet i;S t a n d a t t V ensi o n

NCode' Standard VersionTtle .:Docum ent:: a t C VIt o te


Section lil, Vessels and Containments Ill, Division 2

Division 2


Section ill, Vessels and Containments Ill, Division 2

Division 2



Division 2


Section lIl, Vessels and Containments Ill, Division 2

Division 2



Division 2

2426 ASME ASME 1975 Code for Concrete Reactor reg1.107.rO1 1977 P Same as ACI ASME Section 1995

Section Ill, Vessels and Containments 359 liI, Division 2

Division 2

2427 ASME ASME 1980 Code for Concrete Reactor reg1 .136.rO2 1981 P Same as ACI ASME Section 1995

Section ll1, Vessels and Containments 359 II, Division 2

Division 2

2428 ASME ASME 1980 Code for Concrete Reactor regl.142.rOl 1981 P Same as ACi ASME Section 1995

Section Ill, Vessels and Containments 359 III, Division 2

Division 2

2429 ASME ASME 1982 Code for Concrete Reactor regl.35.rO3 1990 R Same as ACI ASME Section 1995

Section Ill, Vessels and Containments 359 III Division 2

Division 2


Reod., . .i S .-..i'ij. ... i -'--'" -,- ., ~teh: t ~;-: ,,c -........... . .............. ,oet .> Laes _tndr _aes Versio.........

No' Cd Sadr- Vtlo lI:Dcmn ae L:aiiy Cmet b-t- tVe dlo d ,' DateWiion

2430 ASME ASME N.S Code for Concrete Reactor reg .38.rO2 1977 R Same as ACI ASME Section 1996

Section III, Vessels and Containments 359 .II, Division 2

Division 2

2431 ASME ASME N/S Code for Concrete Reactor reg1.70.r03 1978 P Same as ACI ASME Section 1995

Section 111, Vessels and Containments 359 lii, Division 2

Division 2

2432 ASME ASME 1975 Code for Concrete Reactor reg1.90.rOl 1977 P Same as ACI ASME Section 1995

Section III, Vessels and Containments 359 Ill, Division 2

Division 2

2433 ASME ASME 1975 Code for Concrete Reactor regl.94.r01 1976 P Same as ACI ASME Section 1995

Section 1II, Vessels and Containments 359 Ill, Division 2

Division 2

2434 ASME ASME 1975 Code for Concrete Reactor reg3.27.rOl 1977 P Same as ACI ASME Section 1995

Section III, Vessels and Containments 359 lII, Division 2

Division 2

2435 ASME ASME N/S Code for Concrete Reactor srp3.8.1 1981 P Same as ACI ASME Section 1995

Section III, Vessels and Containments 359 111, Division 2

Division 2

2436 ASME ASME N/S Code for Concrete Reactor srp3.8.3 1981 P Same as ACI ASME Section 1995

Section 111, Vessels and Containments 359 III, Division 2

Division 2

2437 ASME ASME N/S Code for Concrete Reactor srp5,2,1.2 1981 R Same as ACI ASME Section 1995

Section III, Vessels and Containments 359 III, Division 2

Division 2

2438 ASME ASME N/S Code for Concrete Reactor srp6.1.1 1981 P Same as AC£ ASME Section 1995

Section Ill, Vessels and Containments 359 Ill, Division 2

Division 2Ct.

%0~t-)



c.. .d t. andlard . A ccept- L t t S L a et Ver.ion

No; .t cod -2Standard VerisiondaTitle Doumn Dat abiit Coment -E ',at

2439 ASME Sreg 136.r2 1981 P Subject to ASME Section 1995

Section Ill, Vessels and Containments Regulatory nI, Division 2

CC-100, Position

CC-2000 &CC-4000thru CC-6000

19

2440 ASME ASME N/S Material regl .70.r03 1978 P Ill, CC-2000

Section 1II,CC-2000

2441 ASME ASME N/S Material srp3.8.1 1981 ASME Section 1995

Section 1II,CC-2000

2442 ASME ASME N/S Cement Grout for Grouted Tendon reg 1.107.rO1 1977 ill, CC-2243o 1995

Section ill, SystemsCC-2243.1

2443 ASME ASME N/S Cement Grout for Grouted Tendon regl.107.r01 1977 P Alternative ASME Section 1995

Secton llSysemsallowed not Ill, CC-2243.2

CC-2243.2 listed in currentcode

2444 AS ASME N/S Design regi.70.r03 1978 P ASME Section 1995

Section lIl,CC-3000

2445 ASME ASME N/S Design srp3.8.1 1_81 P ASME Section 1995

Section Ill, ,

CC-3000

_ ._ -.^- E'O3.8.3 1981 P ASME Section 19952446 ASME ASME

Section Iil,CC-3000

IVID wesut,91 __

I

Ill C30

L I ________I I______ j____________I_____I


Reod tcteSt ard L- Ve,.i.n

'No Cd Standard Vrsion':~ Tit: le % Douih oe ablt oinnt eso a

2447 ASME ASME N/S Allowable Stresses for Service srp3.8.3 1981 P ASME Section 1995

Section III, Loads Ill, CC-3430CC-3430

2448 ASME ASME 1980 Liner 1 Ocfr5O.34 1994 A Modest ASME Section 1995

Section lIl, deviations will Ill, CC-3720CC-3720 be considered

2449 ASME ASME 1980 Liner 10cfr5O.44 1994 A ASME Section 1995

Section lIl, Ill, CC-3720

CC-3720

2450 ASME ASME N/S Fabrication and Construction regy.70.rO3 1978 P ASME Section 1995

Section Ill, Ill, CC-4000CC-4000

2451 ASME ASME N/S Fabrication and Construction srp3.8.1 1981 P ASME Section 1995

Section Ill, Ill, CC^4000CC-4000

2452 ASME ASME 1975 Splicing of Reinforcing Bars reg1.94.rOl 1976 P ASME Section 1995

Section 111, Ill, CC-4334CC-4334 and CC-4330and CC^4330

2453 ASME ASME NIS Construction Testing and reg1.70.r03 1978 P ASME Section 1995

Section Ill, Examination Ill, CC-5000

CC-5000

2454 ASME ASME N/S Construction Testing and srp3.8.1 1981 P ASME Section 1995

. Section IlIl, Examination Ill, CC-5000

CC-5000

z

q)

(-A

etj

c

Mx

ca

x)PO



R eco d ~t nde d D o . A cet, - L te st tan diardi L at eist V eri onb

N o . C o- S t r V e. - tl D at i C o m m e ntm V n 0 -2455 ASME ASME N/S Structural Integrity Test of reg1.70.rO3 1978 P ASME Section 1995

Section III, Concrete Containments III, CC-6000

CC-6000

2456 ASME ASME N/S Not found reg1.70.rO3 1978 P Typo in n/aSecton IIregl.70 -CC-

CC-tion 9000 is not avalid ASMEreference

2457 ASME ASME 1982 Analysis Limits of Permanent reg1.35.rO3 1990 P ASME Section 1995

Section III, Coating Material for CRV Ill, Div. 2, Table

Table CC- Prestressing CC-2422-1

2422-1 ------S_ N r E i i1 9_S95

2458 ASME ASME N/S Nondestructive Examination inmm p40 1995 R ASME Section 1995

S e c tio n V _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ _ _ _ _ _ _ V_ _ _ _ _ _

2459 ASME ASME N/S Nondestructive Examination inm 245 App. B 1991 R ASE Section 1995

Section t 9 9 5

2460 ASME ASME N/S Nondestructive Examination inm49055 1982 R ASME Section 1995

S ectio n V _ _ _ _ _ _ _ __ _ _ V _ _ _

2461 ASME ASME N/S Nondestructive Examination inm57050 1983 R _AME Section 1995

SectionV N/S N e c Eaito i


Section V V


Section V _ _ _ _ _ _ _ _ __ _ _ V

2464 ASME ASME N/S Nondestructive Examination 1nm7O938 3 1983 R ASME Section 1995

Section V _ _ _ _V

2465 ASME ASME N/S Nondestructive Examination inm57090 1993 Ri ASME Section 1995

S ection V_ _ _ _ _ _ _ _ _ V _ _ _


S ection V _ _ _ _ _ _ __ _ _ _ _ V _ _ _ _

2467 ASME ASME N/S Nondestructive Examination inm73053B 1979 RASEecin 19

Section VV2468 ASME ASME NIS Nondestructive Examination nureg093 3 , 3.67 1991 R ASME Section 1995

Section V I_ _ _ _ _ _ _ _ _ _ _ _ _



-* Ri ieco _tandard .. D ee. , t Stdr tteron

.-No. ; Code S:tandard .- rlo V:i~ii - Douia ets '--.-'L Comment s: Verio . Date

2469 ASME ASME N/S Nondestructive Examination srplO.2.3 1981 P ASME Section 1995

Section V V

2470 ASME ASME N/S Nondestructive Examination srp5,2.1.2 1981 P ASME Section 1995

Section V V

2471 ASME ASME N/S Nondestructive Examination srp5.3.1 1981 R ASME Section 1995

Section V _ __ _ V2472 ASME ASME N1S Nondestructive Examination srp5.3.3 1981 R ASME Section 1995

Section V __ _ __ _V

2473 ASME ASiVME 1975 General Requirements reg3.27.rOl 1977 P ASME Section 1995

Section V, V, Article 1

Article 12474 ASME ASME N/S Radiographic Examination inm67090 1993 R ASMSE Section 1995

Section V, V. Article 2

Article 2 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ _ _ _

2475 ASME ASiciE 1980 Ultrasonic Examination Methods reg1.147.rl 1 1994 D ASME Section 1995

Section V, for Inservice Inspection V, Article 4

Article 4

2476 ASME ASME 1977 Ultrasonic Examination Methods reg1.1 50.r01 1983 R Referred to in ASME Section 1995

Section V, for Inservice Inspection text V, Article 4

Article 4

2477 ASME ASME 1980 Ultrasonic Examination Methods reg1.150.rOl 1983 A Referred to In ASME Section 1995

Section V, for Inservice Inspection text V. Article 4

Article 4

2478 ASME ASME 1977 General Techniques for Angle reg1.150.rOl 1983 P ASME Section 1995

Section V. Beam Calibrations V, Art. 4,

Article 4, Appendix B

App. B

2479 ASME ASME N/S Screen Height Linearity reg=.1 S0r01 1983 P With some ASME Section 1995

Section V, exceptions V, Art. 4,

Article 4, Appendix I

App. I

2480 ASME ASME 1977 Amplitude Control Linearity regl.150.rOl 1983 P ASME Section 1995

Section V. V, Art. 4,

Article 4, Appendix 1i

App. ll _ _ _(Ti

z

I)


Part A - Industry Consensus Codes and Standards--- I . I 1i- (;

Record: .S:a . . d a, n .

I Stahda'4d%p Vnidnt-. I i .~ * 1,

,. 1: - ., , , *, ........ ... i

DoIc. m ~ flt Date .Accept-.. .. . .lrt

i Ni-TltiA

E . .-. .,, ' , -: -; .. 4 ': f

comments ,No longer inLatest Version

1~.-- ~ ''' t.rnunu I:L...... - fn Anl=lml.5o~~ 1931 P92~ k4 - 1; 7 -j SJUIIAIOIIC1r7 i IIr9'JI"''

2481 ASMI: ASMt

Section V,Article 4,Figure I-313II1

1 U f

Beam Calibrations;s .. . .. .

Latest StandarVerson ;

n/a

ASME SectionV, Article 4, T-434

Latest Version1O X.iate :. :

n/a

1995____ 1I 4 ... I..~tn 116Yr1 1 198:31tR I-

2482 ASME ASMESection V,Article 4, T-A R4

N/to Hearcn umVL nuquivl ....... lky . . . .. _ .

248.I ___ __-_ ; - . r.- 4 'IC^ n - I l q 3 R

3- ASME ASMESection V,Article 4, T-423.1.3

1977 written Procedure Requirements [VW' I .1 -7.I ,- - -

E.-�.-.1 II__ _ _ _I I -- + - - -- ----_

2484 ASME ASMESection V,Article 4, T-1AO7 I *

1977 Calibration check on BasicCalibration Block or Similar Check

1-1 I I50.rOl -]198~31 Ar A ZA, 1 1

lvM s ̂ { x

T-423.1.3 isnot in currentASME Code

No longer inLatest Version

No longer inLatest Version

T-441.4.2 notin currentASME Code

n/a n/a

n/a 1 n/a

---__IV i~L I ., 4... -Irpgl RtOAMl UT1381 P 1 n/a n/a2485 ASME ASMI

Section V.Article 4, T-A 2''

Nlb Z 1-alludialvntil %.1v1111avl-u | v>,,, . .. .

I ___ I-2..- . . t~inn Tivese - .1- minani IAl I n/a n/a2486 ASME ASME

Section V,Article 4, T-AA1 A49

N/S vessel Examinations -ki , I -v.l - X _v

I______ -=h-4ZK-.1- i G-1 r-l19941 Pp2487 ASME ASME

Section V,A-t;Ain 5

IU/ fItrasels r-and Fablriction

for Materials and Fabricationv * .vV.t

I I-, - . - I I t- ---- p

2488 ASME ASMESection V,A _ I

1Y70 Ultrasonic Examination Methodsfor Materials and Fabrication

1-1y- . -s . . _ . .1-,o . 7 ru-1 I U I //

ASME SectionV, Article 5



1995

1995

1995I__ _ _ _ _ _ _ 41.. .-~ - -' 97 rA1 1 i977 1 P2489 ASME ASME

Section V,~ A--I.^ A

1 U7b ILiquid reneirdlit {U,-.L . . _ . .

I1 I - " . I .rI _I_ _

zci

tjh



R c o r d. tV , S t M -a r V riio n

2490 ASME ASME N/S Liquid Penetrant Examination reg3.37.rO1 1975 P ASME Section 1995

Section V, V, Article 6

Article 62491 ASME ASME 1975 Magnetic Particle Examination reg32701.rO 1977 P ASME Section 1995

Section VI V, Article 7

A rticle 7 : __________

2492 ASME ASME N/S Visual Examination bu79-01 7.rOl 1979 P Applies to ASME Section 1995

Section V, Visual V, Article 9

Article 9 examination

2493 ASME ASME 1975 Leak Testing reg3.27.rOl 1977 P SME Section 1995

Section V. V, Article 10

Article 10 0

2494 ASME ASME N/S Rules for Construction of Pressure drgl 01 0.rOO 1992 P Proposed A9ME Section 1995

Section Vil Vessels reg1.28.rO4 Vill

2495 ASME ASME N/S Rules for Construction of Pressure git89-009 1989 R KASME Section 1995

Section Vil Vessels Vill

2496 ASME ASME NIS Rules for Construction of Pressure inm1245 App. B 1991 R ASME Section 1995

Section Vill Vessels Vill

2497 ASME ASME N/S Rules for Construction of Pressure git92-001 .rOl 1992 R ASME Section 1995

Section VIil. Vessels VIII

2498 ASME ASME N/S Rules for Construction of Pressure not90-18 1990 R ASME Section 1995

Section VilI Vessels Vill

2499 ASME ASME N/S Rules for Construction of Pressure regl .1 10.rOO 1976 R ASME Section 1995

Section Vill Vessels VIII

2500 ASME ASME NIS Rules for Construction of Pressure regl.143.rOl 1979 P ASME Section 1995

Section VilI Vessels . Vill

2501 ASME ASME mNS Rules for Construction of Pressure reg .71 .rOO 1973 P ASME Section 1995

Section VilI Vessels VIIl

z

0~

%0



S tiondard Ve Tetll aCo'

2502 ASME ASME 1974 Rules for Construction of Pressure reg3.28.rOO 1975 P ASME Section 1995

Section Vill Vessels Vil

2503 ASME ASME 1971 Rules for Construction of Pressure reg3.29.rOO 1975 P ASME Section 1995


2504 ASME ASME N9/S Rules for Construction of Pressure reg3.60.r2 1987 ASME Section 1995


2505 ASME ASME 1980 Rules for Construction of Pressure srp3.2.2 1981 P ASME Section 1995


2506 ASME ASME N/S Rules for Construction of Pressure not89-26 1987 P ASME Section 1995

Section VilI, Vessels Vill, Division 1

Division 1

2507 ASME ASME N/S Rules for Construction of Pressure not92-58 1992 R ASME Section 1995

Section VIl, Vessels VilIl, Division 1

Division 1

268 AM SE N/S Rules for Construction of Pressure srp3.9.4 1984- A ASME Section 1995

Section VIII. Vessels ViII, Division 1

Division 1

2509 ASME ASME 1986 Welding and Brazing Qualifications inm-toc 1995 R ANS 3.2 1994

Section IX _ _ _ _ _

2510 ASME ASME N/S Welding and Brazing Qualifications inm49055 1982 R ASME Section 1995

Section IX IX

2511 ASME ASME N/S Welding and Brazing Qualifications inm50082B 1976 R ASIMESection 1995

Section IX IX

2512 ASME ASME NS WligadBaigQlfctons inrn50085B 1976 R ASME Section 1995

Section IX Welding and Brazing IX i 513, E o95

2513 ASME ASME N/S Welding and Brazing Qualifications inm55050 1983 R ASME Section 1995

Section IX ___ _ IX _ i


- tRt ; ^ S -- - : i: - :. . . . .. . . . . ...

Record Standa d . Staidad L st .et n

NoMVrinTtl ouet Dt isbit Citrneints VeioDte2515 ASME ASME N/S Welding and Brazing Qualifications inm55093B 1977 R ASME Section 1995

Section IX IX

2516 ASME ASME N/S Welding and Brazing Qualifications inm9900/ ASME 1986 R ASME Section 1995

Section IX IX IX ....

2517 ASME ASME N/S Welding and Brazing Qualifications inm9900/ 1994 R ASME Section 1995

Section IX SGTUBE IX

2518 ASME ASME NIS Welding and Brazing Qualifications not83-61 1983 P ASME Section 1995

Section IX IX

2519 ASME ASME N/S Welding and Brazing Qualifications not89-75 1989 R ASME Section 1995

Section IX IX

2520 ASME ASME NIS Welding and Brazing Qualifications reg .143.r07 1979 P ASME Section 1995

Section IX _ IX ..

2521 ASME ASME N/S Welding and Brazing Qualifications regl.34.rOO 1972 P ASME Section 1995

Section IX IX

2522 ASME ASME NIS Welding and Brazing Qualifications regl .43.rOO 1973 P ASME Section 1995

Section IX I IX

2523 ASME ASME NIS Welding and Brazing Qualifications regl.50.rOO 1973 P With ASME Section 1995

Section IX _ supplements IX

2524 ASME ASME NIS Welding and Brazing Qualifications reg1.71.rOO 1973 P ASME Section 1995

Section IX _ _ IX2525 ASME ASME 1974 Welding and Brazing Qualifications reg3.28.rOO 1975 P ASME Section 1995

Section IX IX

2526 ASME ASME 1971 Welding and Brazing Qualifications reg3.29.rOO 1975 P ASME Section 1995

Section IX IX2527 ASME ASME N/S Welding and Brazing Qualifications reg7,1O.rOl 1986 A -ASME Section 1995

Section IX ix

2528 ASME ASME NIS Welding and Brazing Qualifications srp'10.3.6 1981 P ASME Section 1995

Section IX IX

2529 ASME ASME NIS Welding and Brazing Qualifications srp4.5.2 1981 P ASME Section 1995

Section IX IX

2530 ASME ASME NIS Welding and Brazing Qualifications srp5.2.1.2 1981 P ASME Section 1995

Section IX ______ IX

2531 ASME ASME N/S Welding and Brazing Qualifications srp5.2.3 1981 P- ASME Section 1995

Section IX _ IX

'0

%0

t~bh

--3

0


R e c o rd S a d d D e .' A c c e pt- L. te.t Stfl Lio n

N o. . Ci d S tCdard Vier ion- i D c etat e :66,abil i: C V r-i; ien Date

2532 ASME ASME NIS Welding and Brazing Qualifications srp5.3.1 1981 P Supplemented ASME Section 1995

Section IX by Reg. Guide IX1.50 and 1.34

2533 ASME ASME N/S Welding and Brazing Qualifications srp5.3.3 1981 R Supplemented ASME Section 1995

Section IX by Reg. Guide IX1.50 and 1.34

2534 ASME ASME N/S Welding and Brazing Qualifications srp5.4.2.1 1981 P ASME Section 1995

Section IX IX

2535 ASME ASME N/S Welding and Brazing Qualifications srp6.1.1 1981 P General ASME Section 1995

Section IX endorsements IX

2536 ASME ASME NIS Rules for Inservice Inspection of 1 Ocfr5O App. G 1994 R ASME Section 1995

Section Xl Nuclear Power Plant Components Xi

2537 ASME ASME NIS Rules for Inservice Inspection of lOcfr50 App. H 1994 R ASME Section 1995

Section Xl Nuclear Power Plant Components Xl

2538 ASME ASME 1973 Rules for Inservice Inspection of 1 Ocfr50.55a 1994 P ASME Section 1995


2539 ASME ASME 1974 Rules for Inservice Inspection of 10cfrS0.55a 1994 P ASME Section 1995

Section Xl Nuclear Power Plant Components Xi.P

2540 ASME ASME 1983 Rules for Inservice Inspection of 1Ocfr5O.55a 1994 P ASME Section 1995


2541 ASME ASME 1974 Rules for Inservice Inspection of bu176-001 1976 P for specific ASME Section 1995

Section Xl Nuclear Power Plant Components hydro test Xi

2542 ASME ASME 1975 Rules for Inservice Inspection of bul79-017.rOl 1979 P ASME Section 1995

Section Xi Nuclear Power Plant Components Xl



Record - 7 Stabdard- ------ Do- - cc-p--L-s ta d t aes eso

254 AS |ASME N/S=a~ Rules For Inservice Inspection of |bulS3-002 1 983 A ASIME Secio 1995 |

SeCtiOn XI NUClear Power Plant Comnponents :Xl

2544 ASME ASME N/S Rules for Inservice Inspection of bul93-003 1983 P ASMM E Section 1995

.Section Xl Nuclear Power Plant Components Xl

2545 ASME ASME NIS Rules for Inservice inspection of bu188-005.sO2 1988 R ASME Section 1995

Section Xl NUClear Power Plant Components X1

2546 ASME ASME NIS Rules for Inservice Inspection of bu188-011 1988 P ASME Section 1995


2547 ASME ASME N/S Rules for Inservice Inspection of bu189-002 1989 P ASME Section 1995


2548 ASME ASME 1974 Rules for Inservice Inspection of cir76-06 1976 P Fr hydrostatic ASME Section 1995

Section Xl Nuclear Power Plant Components testing Xl

2549 ASME ASME NIS Rules for Inservice OIspection of drglO9.rOO 1990 P ASME Section 1995


2550 ASME ASME NIS Rules for Inservice Inspection of drg1010.rOO 1992 P Proposed ASME Section 1995

Section Xl Nuclear Power Plant Components regl.28.rO4 Xl

2551 ASME ASME 1977 Rules for Inservice Inspection of drgms901 -4.rOO 1981 -M ASME Section 1995

Section Xl Nuclear Power Plant Components t Xl

2552 i ASME ASME N/S Rules for Inservice Inspection of drgop618^4.r00 1982 R Proposed ASME Section 1995

Section XI Nuclear Power Plant Components reg8.8r.04 Xl

2553 ASME ASME N/S Rules for Inservice Inspection of g1t78-002 1978 R ASME Section 1995


2554 ASME ASME N/S Rules for Inservice Inspection of glt79-005 1979 P ASME Section 1995


Seto XNul a PoerPan ComponentsXi

z

C-)

.4

z

(i

LI)

-4


-o;.c)E.7.Ei 4.:,_n5.f.,gE.. L ft't':&6ii, , .k4 i -oe i CE

R ecor Standardte D. Accept- L S L-a. c o eS t ain da r d e s o i l e .D c m n Dt e b ltwCili n s e r i n. D t

2555 ASME ASME N/S Rules for Inservice Inspection of git79-020 1979 P ASME Section 1995


2556 ASME ASME N/S Rules for Inservice Inspection of gIt80-101 1980 P ASME Section 1995Section Xl Nuclear Power Plant Components Xi

2557 ASME ASME N/S Rules for Inservice Inspection of gIt83-002 1983 P ASME Section 1995


2558 ASME ASME N/S Rules for Inservice Inspection of g1t88-001 1988 R ASME Section 1995Section Xl Nuclear Power Plant Components Xl

2559 ASME ASME NIS Rules for Inservice Inspection of glt88-001 .sOl 1988 P ASME Section 1995Section XI Nuclear Power Plant Components Xl

2560 ASME ASME NIS Rules for Inservice Inspection of gIt88-005 1988 R ASME Section 1995Section Xl Nuclear Power Plant Components Xl

2561 ASME ASME 1989 Rules for Inservice Inspection of glt89-004.sO1 1995 R ASME Section 1995Section Xl Nuclear Power Plant Components . Xl

2562 ASME ASME N/S Rules for Inservice Inspection of git89-010 1989 8 Problems with ASME Section 1995

Section Xl Nuclear Power Plant Components Section Xl XlI _discussed

2563 ASME ASME NIS Rules for Inservice Inspection of glt89-010.sO1 1990 R Problems with ASME Section 1995Section Xl Nuclear Power Plant Components Section Xi Xl

discussed

2564 ASME ASME NIS Rules for Inservice Inspection of g1t89-010.s03 1990 R ASME Section 1995


2565 ASME ASME N/S Rules for Inservice Inspection of git89-01 0.s06 1994 R Problems with ASME Section 1995

Section Xl Nuclear Power Plant Components Section XI Xidiscussed

2566 ASME ASME NIS Rules for Inservice Inspection of glt90-006 1990 P ASME Section 1995




2568 ASME ASME N/S Rules for Inservice Inspection of glt9l-018 1991 R ASME Section 1995


2569 ASME ASME NIS Rules for Inservice Inspection of g1t93-005 1993 P ASME Section 1995


2570 ASME ASME N/S Rules for Inservice Inspection of git94-003 1994 R ASME Section 1995


2571 ASME ASME 1986 Rules for Inservice Inspection of inm-toc 1995 R ANS 3.2 1994

Section Xl Nuclear Power Plant Components

2572 ASME ASME NIS Rules for Inservice Inspection of inm2515 1993 R ASME Section 1995


2573 ASME ASME NIS Rules for Inservice Inspection of inm251 5/1.10 1993 R ASME Section 1995


2574 ASME ASME N/S Rules for Inservice Inspection of inm25151114 1992 R ASME Section 1995


2575 ASME ASME NIS Rules for Inservice Inspection of inm2515/118 1995 R ASME Section 1992

Section Xl Nuclear Power Plant Components Xli

2576 ASME ASME N/S Rules for Inservice Inspection of inm2515/109 1993 R ASME Section 1995

Section Xi Nuclear Power Plant Components Xi


Section XI Nuclear Power Plant Components Xi

2578 ASME ASME NiS Rules for Inservice Inspection of inm49055 1982 R ASME Section 1995


!4

0

;PkA%D4

W

�vCD

W

d

t~h-4



R e c o r d O Mtn

a dD e A c a t a e t S a d a d L t e s o;. . .i Cff \i ViiiN0 - ........... ..-Om-

. ig E<e L - ~ 1'70. E i~ - i' ' d o .S

, o. C oda Stan ar - D a .bilit Ct Versi


Section xi Nuclear Power Plant Components Xl

2580 ASME ASME N/S Rules for inservice Inspection of inm61700 1983 R ASME Section 1995






2583 ASME ASME N/S Rules for Inservice tnspection of inm73052 1986 R ASME Section 1995


2584 ASME ASME N/S Rules for Inservice Inspection of inm73053B 1979 -R ASME Section 1995





Section XI Nuclear Power Plant Components Xl

2587 ASME ASME NIS Rules for Ins;rvice Inspection of inm73755 1986 R ASME Section 1995


2588 ASME ASME 1980 Rules for Inservice Inspection of inm73756 1995 R ASME Section 1995





Section XI Nuclear Power Plant Components xi

z

t~x1

%0-4


Record .. . L a ... ..t. .t

No. Codo . andard f ersion Til Document. - Dato S .ommens . V o .Datb.r

2591 ASME ASME N/S Rules for Inservice Inspection of inm9900/4.5.1 1986 R ASME Section 1995


2592 ASME ASME NIS Rules for Inservice Inspection of inm9900/4.7.9 1975 R ASME Section 1995Section Xl Nuclear Power Plant Components Xi

2593 ASME ASME 1983 Rules for Inservice Inspection of inm9900/ ASME 1986 R ASME Section 1995

Section Xi Nuclear Power Plant Components IX Xl

2594 ASME ASME 1980 Rules for Inservice Inspection of inm9900/ 1994 R ASME Section 1995

Section Xl Nuclear Power Plant Components SGTUBE Xl

2595 ASME ASME 1986 Rules for Inservice Inspection of inm9900/ 1994 R ASME Section 1995Section Xl Nuclear Power Plant Components SGTUBE Xi


Section Xl Nuclear Power Plant Components SGTUBE Xi


Section Xl Nuclear Power Plant Components SGTUBE Xi

2598 ASME ASME NIS Rules for Inservice Inspection of not80-15 1980 R ASME Section 1995Section Xi Nuclear Power Plant Components Xi

2599 ASME ASME NIS Rules for Inservice Inspection of not80-27 1980 R ASME Section 1995


2600 ASME ASME NIS Rules for Inservice Inspection of not80-38 1980 R ASME Section 1995


2601 ASME ASME 1978 Rules for Inservice Inspection of not82-39 1982 R ASME Section 1995


2602 ASME ASME N/S Rules for Inservice Inspection of not86-106.s01 1987 R ASME Section 1995


Q.A

*0

W.5

-4



Record Standar D( |ASME | Lates tf 98 | St Latest vetaion

Co Steion Dlcuceat Power Pblaty Compnents. Ver.ion . DatX

2603 ASME ASME N/S Rules for Inservice Inspection of not88-7 1988 P 199

. Section Xi Nuclear Power Plant Components Xi

2604 ASME ASME N/S Rules for Inservice Inspection of not92-32 1991 R ASME Section 1995

Section Xi Nuclear Power Plant Components

2605 ASME ASME N/S Rules for Inservice Inspection of not92-3 5 1992 R ASME Section 1995


2606 ASME ASME N/S Rules for Inservice Inspection of not92-8 5 1992 R AAS ME Section 1 995




2608 ASME ASME N/S Rules for Inservice Inspection of not93-21 1993 R -ASME Section 1995




. .~~_-,, ........ . .. _ { __OV____ I nntx fnn9-7 619 ASME Section 19952 ASME ASME N es for Inservice inspection of not94-19


___-' rQ,~tA-7A I 94 R ASE ecio 1995

261

261

261

26'

'1 ASME ASMESection XI

NIS Nules towervU Plant Copo. v,Nuclear Power Plant Components

. - . _ . .Xi

._.____ I -i -._---- .I. - , on _1 R - ASME Section 1995

T

F-3

R

71 ASME ASMESection Xi

NIS Nules tor Inservice mspecmpne nlNuclear Power Plant Component s

w v v vXiASME___ _ . .. _ . . _ :, .... ,. L...g.r, I A`SME Sec.ti ---ion t71995

ASME

A-7sM

ASMESection Xl

ASMESection X

iI

N/S Nules tor inservice inspteComponeNuclear Power Plant Components

, $ tv t v-u i , I---Xi

I II_ . .. ._ _if_ I_

A ' - - 4 . . A SM E Section I 1995nuregusJ- - - L A.MM A ~ i z tg 9

I

1974 Rules for Inservice Inspection otNuclevar Power Plant Cornponents

nureg14313, Z.A

141 MV 01 n1

Xi

I- I _ __ _ _ I __ _ _ _ _I __ _ _ _ _ _ _ _ _ _ _ _ _I I.__ _ __ _ I.... _____I_______-

-4

z

(C'1



Record tandar Dec. Acept- atist Sta'ndard Lts so

o. C od S tan d ard . V ewe n | 0 Z 5 | Title! D oc m en D at abiit C o m e t V r ioh D $ t |

2615 ASME ASME 1974 Rules for Inservice Inspection of |nuregO933, 2.8- 1984 R ASME Section 1995

Section Xl Nuclear Power Plant Components 26 Xl

2616s ASME ASME 1980 Rules for Inservice Inspection of nuregO933, 2.8- 1983 R ASMM E Section 1995

Section Xi Nuclear Power Plant Components 47 Xl

2617 ASME ASME 1974 Rules for Inservice Inspectio~n of nuregO933, 3.10 1983 R ASME Section 1995


2618 ASMIE ASME N/S Rules for Inservice Inspection o nuregO933, 1991 R ASME Section 1995

Section Xi Nuclear Power Plant Components 3.111 Xl

2619 ASME ASME 1974 Rules for Inservice Inspection of nuregO933, 1987 R ASME Section 1996

Section Xl Nuclear Power Plant Components 3.127 Xl

2620 ASME ASME N/S Rules for Inservice Inspection of nuregO933, 3.67 1991 R ASME Section 1995


2621 ASME ASME N/S Rue o nevc npcino nureg0933, 3.86 1988 R ASMM E Section 1995

.. ... ..


2622 ASME ASME N/S Rules for :IseicInspetono reg 1.11 6.rOO 1976 R ASME Section 1995


2623 ASME ASME N/S Rules for Inservice Inspection of regil .1 37.rO1 1979 P tASME Section 1995


2624 ASM\E ASME N/S Rue o nevc npcino regi .147.rr11 1994 R ASME Section 1995


2625 ASME ASME 1977 Rules for Inservice Inspecion of regl .150.rO1 1983 P ASME Section 1995


2626 SE ASME N/S Rules for inservicec Inspection of r eg1 .1 61 .rOO 1 995 8 - ASME Section 1 995

Su Pla nt C o m p o ns _ .

et on 7 i

zC)C)

U'

00

W

of



R ec] r d S ta d a r 'o c k A cek* - La te s t n a L t e St V e rs iotnd

No ~ Code Setaondr Verio Nuclear T t~e Powerent Plate Comionity Xlom nt es~2627 ASME ASME N/S Rules for Inservice Inspection of regl.28.rO3 1985 R ASME Section 1995


2628 ASME ASME N/S Rules for Inservice Inspection of regl.35.rO3 1990 P Cited for ASME Section 1995

Section Xl Nuclear Power Plant Components definition Xl

2629 ASME ASME N/S Rules for Inservice Inspection of regl.38.r02 1977 R ASME Section 1995


2630 ASME ASME N/S Rules for Inservice Inspection of regl .44.rOO 1973 P ASME Section 1995


2631 ASME ASME N/S Rules for Inservice Inspection of regl.65.rO 1973 P ASME Section 1995


2632 ASME ASME N/S Rules for Inservice Inspection of regi.68.rO2 1978 P ASME Section 1995


2633 ASME ASME N/S Rules for Inservice Inspection of regl.70.rO3 1978 P ASME Section 1995


2634 ASME ASME N/S Rules for Inservice Inspection of regl.72.rO2 1978 P ASME Section 1995


2635 ASME ASME N/S Rules for Inservice Inspection of regl.96.rOl 1976 R ASME Section 1995


2636 ASME ASME N/S Rules for Inservice Inspection of reg7.I2.rOO 1991 R ASME Section 1995


2637 ASME ASME N/S Rules for Inservice Inspection of reg8.8.r30 1978 R - ASME Section 1995


2638 ASME ASME NS Rues for nserice Inspection of SECY95-1 80 195 R ASME Section



0 g 0 ,,,~~~~~~~.....-''.... " .' ' ."-''..':''-" . __,.j ,,.__

N .- Cod. St.ndard 'Versin .... .. n Wd LO

2639 ASME ASME N/S Rulss for Inservice Inspection of srpl0O.2 1981 P ASME Section 1995Section Xl Nuclear Power Plant Components Xl

2640 ASME ASME N/S Ruls for Inserviea Inespein of srpl O.2.3 1981 P ASME Section 1995.Section Xl Nuclear Power Plant Components Xl

2641 ASME ASME N/S RUleS for Inservice Inspection of srp3.2.2 1981 P -A SME Section 1995Section Xl Nuclear Power Plant Components X

2642 ASME ASME N/S Rue o nevc npcino srp3.6.1 1990 P ASME Section 1995.Section Xl Nuclear Power Plant Components Xl

2643 ASME ASME N/S Rules for Inservice Inspeotion of srp3.6.2 1981 P .ASME Section 1995Section Xl Nuclear Power Plant CDomponents Xl

2644 ASME ASME N/S Rules for inservice Inspection of srp3.9.6 1981 P _ASME Sectiotn 1995Section Xl Nuclear Power Plant Components Xi

2645 ASME ASME N/S Rules for Inservice Inspection of srp5.2.1 .2 1981 P ASME Section 19955Section Xl NuClear Power Plant Components Xi

2646 ASME ASME N/S Rules for inseic I nspection of srp5.2.2 1988 P ASME Section 1995Section Xi Nuclear Power Plant Components Xi

2647 ASME ASME N/S Rules for Inservice Inspection of srp5.2.4 1981 P ASME Section 1995Section Xi NuClear Power Plant Components Xl

2648 ASME ASME N/S Rules Xfor Inservice inspection of srpS.3. t 1981 PASME Secotion 1995Section Xl Nuclear Power Plant Components Xl

2649 ASME ASME N/S Rules for inservice Inspection of srp5.3.3 1981 R ASME Section 1995Section Xi Nuclear Power Plant ComponentsX Xi

:o d S::::: f d 0 .ji::.

2650 ASME ASME N/S Rules for Inservice Inspection of srp5.4.1.1 1981 R ASME Section 1995Section Xi Nuclear Power Plant Components Xi

.2 : : _ "

z

-3

zci

n%O

00

00

C)


----Reco.rd ;' ' Standard.S. Dec. ,.cat . . Latest.; Standar .aes Ve_ io

N o . C o d i S ta n d a rd V e s o .,, a.... T.............l.... : D c . e n D a t .~ b I~ C o ..m ..t s . V e r s.. o . . D a t

2651 ASME ASME N/S Rules for Inservice Inspection of srp6.6 1981 P ASME Section 1995


2652 ASME ASME N/S Rules for Inservice Inspection of srp9.1.3 1981 R ASME Section 1995


2653 ASME ASME N/S Rules for Inservice Inspection of sts4-ge5.7.2.11 1992 P ASME Section 1995




2655 ASME ASME N/S Rules for Inservice Inspection of sts4-geB3. 1O. 1992 R ASME Section 1995


2656 ASME ASME N/S Rules for Inservice Inspection of sts4-geB3.5.1 1992 P ASME Section 1995


2657 ASME ASME N/S Rules for Inservice Inspection of sts4-geB3.6.1.6 1992 ASME Section 1995


2658 AWS-ME ASME N/S Rules for Inservice Inspection of sts4-geB3.6.2.3 1992 R ASME Section 1995


2659 ASME ASME N/S Rules for Inservice Inspection of sts4-geB3.6.2.4 1992 R ASME Section 1995


2660 ASME ASME N/S Rules for Inservice Inspection of sts4-geB3.8.1 1992 R ASME Section 1995






00

(AI


Racerd ,::Stsndsrd . 7 . ~~iDose. ncpa.Laetlan ad ats V rso.; ~ ~ ~ ~ ~ ~ . ..... .d ---

iNo: ; .; CodeS ndar : :Versio it . :. l Docum unt - .: :Date . ii Comments V ersi on D e



2664 ASME ASME NIS Rules for Inservice Inspection of sts6-geB3.5.1 1992 P ASME Section 1995

Section Xi Nuclear Power Plant Components Xi,



2666 ASME ASME NIS Rules for Inservice Inspection of sts6-geB3.6.1.7 1992 R ASME Section 1995Section Xl Nuclear Power Plant Components Xl



2668 ASME ASME N/S Rules for Inservice Inspection of sts6-geB3.8.1 1992 R ASME Section 1995Section Xi Nuclear Power Plant Components Xl



2670 ASME ASME N/S Rules for Inservice Inspection of stsb&w6.7.2.11 1992 P ASME Section 1995

Section Xi Nuclear Power Plant Components XI

2671 ASME ASME NIS Rules for Inservice Inspection of stsb&w5.7.2.12 1992 P ASME Section 1995

Section Xi Nuclear Power PlantComponents Xi

2672 ASME ASME N/S Rules for Inservice Inspection of stsb&wB3.4.10 1992 A ASME Section 1995

Section Xl Nuclear Power Plant Components : Xl

2673 ASME ASME N/S Rules for Inservice Inspection of stsb&wB3.4.1 1 1992 R ASME Section 1995


2674 ASME ASME N/S Rules for Inservice Inspection of stsb&wB3.6.6 1992 P ASME Section 1995


z

00

Lh

'I

I


R e c ord t D ob c L t t V e s o

2675 ASME ASME N/S Rules for Inservice Inspection of stsb&wB3.7.3 1992 R ASME Section 1995


2676 ASME ASME N/S Rules for Inservice Inspection of stsb&wB3.8.1 1992 R ASME Section 1995


2677 ASME ASME N/S Rules for Inservice Inspection of stsce5.7.2.11 1992 P ASME Section 1995


2678 ASME ASME N/S Rules for Inservice Inspection of stsb&w83.8.3 1992 P ASME Section 1995


2679 ASME ASME N/S Rules for Inservice Inspection of stsce5.7.2.12 1992 P ASME Section 1995


2680 ASME ASME N/S Rules for Inservice Inspection of stsceB3.4.10 1992 A ASME Section 1995


2681 ASME ASME N/S Rules for Inservice Inspection of stsceB3.4.11 1992 R ASME Section 1995


2682 ASME ASME N/S Rules for Inservice Inspection of stsceB3.5.2 1992 P ASME Section 1995


2683 ASME ASME N/S Rules for Inservice Inspection of stsceB3.6.12 1992 A ASME Section 1995


2684 ASME ASME N/S Rules for Inservice Inspection of stsceB3.6.6A 1992 P ASME Section 1995


2685 ASME ASME N/S Rules for Inservice Inspection of stsceB3.6.6B 1992 P ASME Section 1995

. Section Xi Nuclear Power Plant Components Xl

2686 ASME ASME N/S Rules for Inservice Inspection of stsceB3.8.1 1992 R ASME Section 1995


00

z

'0

PCr

WJ

Codes and Standards, and Other Guidance Cited in Regulatory DocumentsPart A - Industry Consensus Codes and Standards

.. Cdd V in....... .

2687 ASME ASME NIS Rules for Inservice Inspection of stsceB3.8.3 1992 P ASME Secthon 1995

Section Xl 0 Ncear Power Plt Components Xl |

2688 ASME ASME N/S Rules for Inservice Inspection of stswst5.7.2.11 1992 P ASME Section 1995


2689 ASME ASME N/S Rules for Inservice Inspection of stswst5.7.2.12 1992 P ASME Section 1995


2690 ASME ASME NIS Rules for Inservice Inspection of stswstB3.4.10 1992 A ASME Section 1995


2691 ASME ASME NIS Rules for Inservice Inspection of stswstB3.4.1 1 1992 R ASME Section 1995


2692 ASME ASME N/S Rules for Inservice Inspection of stswstB3.4.12 1992 R ASME Section 1995


2693 ASME ASME N/S Rules for Inservice Inspection of stswstB3.5.2 1992 P ASME Section 1995


2694 ASME ASME NIS Rules for Inservice Inspection of stswstB3.6.12 1992 A ASME Section 1995


2695 ASME ASME N/S Rules for Inservice Inspection of stswstB3.6.6A 1992 P - ASME Section 1995


2696 ASME ASME N/S Rules for Inservice Inspection of stswstB3.6.6B 1992 P ASME Section 1995


2697 ASME ASME N/S Rules for Inservice Inspection of stswstB3,6,6C 1992 P ASME Section 1995


2698 ASME ASME N/S Rules for Inservice Inspection of stswst93.6.6D 1992 P ASME Section 1995


z(1W8M(�n�0.1W

. �VIW



No. fCe StCbat. coop OD;te

269 ASME ASME NS Rules for Inservice Inspe in of stswstB3.6.6E 1992 P ASME Section 1995


2700 ASME ASME N/S Rules for Inservice Inspection of stswstB3.7.3 1992 R ASME Section 1995


2701 ASME ASME NIS Rules for Inservice Inspection of stswst93.8.1 1992 R ASME Section 1995


2702 ASME ASME N/S Rules for Inservice inspection of stswstB3.8.3 1992 P ASME Section 1995


2703 ASME ASME 1989 Rules for Inspection and Testing 10cfr50.65a 1994 P ASME Section 1995

Section Xl, of Components for Light-Water Xl, Division 1

Division 1 Cooled Plants

2704 ASME ASME 1980 Rules for Inspection and Testing 1Ocfr50.55sa 1994 P ASME Section 1995

Section Xi, of Components for Light-Water Xi, Division 1

Division 1 Cooled Plants

2705 ASME ASME N/S Analysis of Flaws g1t88-001 19B8 R - ASME Section 1995

Section Xl, Xi, Appendix A

Appendix A

2706 ASME N/S Evaluation of Unanticipated sts4-geB3.4.10 1992 PAME Section 1995

Section XI, Operating Events Xi, Appendix E

Appendix E

2707 ASME ASME NIS Evaluation of Unanticipated sts6-geB3.4.1 1 1992 P ASME Section 1995

Section Xl, Operating Events Xl, Appendix E

Appendix E


e SMan Dc. Aciatet Standdate Ver sionL

Section Xi, Operating Events Xl, Appendix E

Appendix E

2709 ASME ASME N/S Evaluation of Unanticipated stsceB3.4.3 1992 P ASME Section 1995


Appendix E

2710 ASME ASME N/S Evaluation of Unanticipated stswstB3.4.3 1992 P ASME Section 1995


Appendix E

2711 ASME ASME 1974 Ultrasonic Examinations bui75-001 1975 P ASME Section 1995

Section Xi, Xl, Appendix I

Appendix I

2712 ASME ASME N/S Not found bui74-003 1974 R Typo in bu174- n/a n/a

Section Xl, 03 - Table IS-

Table IS-251 251 is not avalid ASMEreference

2713 ASME ASME N/S Ultrasonic Examinations reg .1 50.rOl 1983 P No longer in n/a n/a

Section Xl, Latest Version

Appendix I

2714 ASME ASME 1974 Not found reg1.150.r01 1983 R Deleted from n/a n/a

Section Xi, ASME Sec Xl

Appendix I prior to 1980

Article I, I- Edition

4420

00

w

tJI

\0

00



ecord - 1 . St0nd erd ' e .. L - L Ve;sro'

MN.c d ~ S a d r V r i n i l o u e n !D a t Wbl t o t e ~ V rs io n a t

2715 E ASM . NS Assessment of Reactor Vessels regl.161.rO 1995 R ,SME Sectiond19

Section Xl, with Low Upper Shelf Charpy Xl, Appendix K

Appendix K Impact Energy Levels

2716 ASME ASME N/S Design Stress Intensity Values, reg1.150.rOl 1983 R No Longer in n/a =la

Section XI, Allowable Stresses, Material Latest Version

Article i, I- Properties, and Design Fatigue

4410 Curves

2717 ASME ASME N/S Design Stress Intensity Values, regt .1 50.rO1 1983 R No longer in nn/aSection Xl, Allowable Stresses, Material Latest Version

Article I, I- Properties, and Design Fatigue

4510 Curves -___Nolonge

2718 ASME ASME 1974 Design Stress Intensity Values, reg 2 .1 50.rOl 1983 R N loge in n/a n/a

Section XI, Allowable Stresses, Material Latest Version

Article I, I- Properties, and Design Fatigue

4520 Curves ______ _Section __ ____9

2719 ASME ASME N/S Owner's Responsibility not93-21 1993 RAMEScin 19

Section Xl,IWA-1 400

2720 ASME ASME N/S Accessibility - srp5.2.4 1981 P ASME Section 1995

IWA-1X500

2721 ASME ASME N/S Accessibility srp S.6 1981 P ASSM E Section 19

Section Xi,

A

IWA-1 500_ t1snnini~7;199_ASME Section t 1995

Sec io XIra on o~ t~ p u~

__ __ _'.d-'~I~,70A!1 7 rni I q75 P AME Section 1995

2722 ASME ASMESection Xl,IWA-2000

IMIZ txaminalivi anc 1fnspejt;VV DU%>a-V ., .. w . . ,

Xl, IWA-2000

L I _______ _I ______. _______I__________ I__ ______ I I__ I_____ _________ I____I_____

00

z

0

(A

&I


scord SA Accept Le S:tad ad Let; t Vertion

2723 ASME ASME N/S Examination and Inspection regl.150.rOl 1983 P General ASME Section 1995Section Xl, endorsements Xl, IWA-2000IWA-2000

2724 ASME ASME N/S Examination and Inspection srp5.2.4 1981 P ASME Section 1995Section Xl, Xl, IWA-2000IWA-2000

2725 ASME ASME NIS Examination and Inspection srp6.6 1981 P ASME Section 1995Section Xl, Xl, IWA-2000IWA-2000

2726 ASME ASME NIS Qualification of Authorized inm73051 1986 R ASME Section 1995Section Xl, Inspection Agencies, Inspectors, Xl, IWA-2120IWA-2120 and Supervisors

2727 ASME ASME N/S Examination Methods inm9900/ 1994 R ASME Section 1995Section Xl, SGTUBE Xl, IWA-2200IWA-2200

2728 ASME ASME N/S Examination Methods regl.14.rO1 1975 P ASME Section 1995Section Xl, Xi, IWA-2200IWA-2200

2729 ASME ASME 1975 Visual Examinations bu179-017 1979 P 74 edition or ASME Section 1995Section Xl, later Xi, IWA-2210IWA-2210

2730 ASME ASME 1974 Visual Examinations bu182-002 1982 P 74 edition or ASME Section 1995Section Xl, later Xi, IWA-2210IWA-221 0

2731 ASME ASME N/S Visual Examinations inm9900/ 1994 R ASME Section 1995Section Xl, SGTUBE Xl, IWA-2210IWA-2210

z

(!h

'4W

0000



.Record iSt: :-an- -dard 1 :oc Ac ep--...P.. .'. .fC : T";'.: ' :i L': ''t. :sit ':- SE: tandard.i.. L test V srslon

cor ctin Xi, t 197 ...- .' .

IWA-2220

2733 ASME ASME N/S Surface Examination inm9900/ 1994 R . ASME Section 1995

Section Xl, SGTUBE Xi, IWA-2220

IWA-2220

2734 ASME ASME NIS Alternative Examinations regi.150.r01 1983 P Implied ASME Section 2 1995Section Xi, endorement Xi, IWA-2220

IWA-2240

2735 ASME SAeSME , N/S Inspection Program FitB 1 1987 PR_ ASME Section 1995Section XI, edrmnt Xi, IWA-22400

IWA-2400

2736 ASME ASME N/S Inspection Program srp3.d1 1981 P AXi IWA-2400 1995Section Xi, XIA20

IWA-2400

2737 ASME ASME 1989 inspection Intervals l0cfrpO.55a 1994 P ASME Section 1995Section Xi, XIA

IWA-2 2430(d

28 ASME ASME N/S Multiple Planar flaws gt90O-005 1990 R ASME Section 1995277Section Xi, XI, IWA333

IWA-33302 d

2739 ASME ASME N/S Repair/Replacement Activities glt90-005 1990 R Referred to in Xi, IWASei0o 1995Section Xi,tetXWA40

IWA-4000

2740 ASME ASME N/S Repair/Replacement Activities inm7305 1 1 986 R ASM S n 1 995Section Xi, XIA40

IWA-4000...il epae n Aciite _ n 7 5 198 _ _ , .ESeton1 9

00

z

Vi

(5

Cl

w

g.!


R c dS t n a dD e Ac e p t L ate t ta n d rd IL at s V e so n

XNo C |o Standard Ve.s hIo Title e e C Vein |-|Date

2741 ASME ASME N/S Applicability inm9900/ 1994 R ASME Section 1995

Section Xi, SGTUBE Xl, IWA-4120

IWA-4120

2742 ASME ASME N/S Items for Repair/Replacement inm9900/ 1994 R ASME Section 1995

Section Xl, SGTUBE Xl, IWA-4200

IWA-4200

2743 ASME ASME 1980 Design inm9900/ 1994 R ASME Section 1995


IWA-4300

2744 ASME ASME 1983 Design inm9900I 1994 R ASME Section 1995

Section Xl, SOTUBE Xl, IWA-4300

IWA-4300

2745 ASME ASME 1986 Design inm9900/ 1994 R ASME Section 1995


IWA-4300

2746 ASME ASME N/S Design not93-21 1993 R ASME Section 1995

Section Xl, Xl, IWA-4300

IWA-4300

2747 ASME ASME N/S Welding, Brazing, Metal Removal, inm9900/ 1994 R ASME Section 1995

Section Xl, and Installation SGTUBE Xl, IWA-4400

IWA-4400

2748 ASME ASME 1992 Metal Removal inm9900/ 1994 R ASME Section 1995


IWA-4420

2749 ASME ASME 1992 General Requirements inm9900/ 1994 R ASME Section 1995


IWA-4421

zC�

w(�h�0

aU)

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w

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R edco r dd i d ~ S t a n d a r D o k A c t a t s S t d r d L e t V e i n

2750 ASME ASME NS Thermal Removal Processes inm9900/ 1994 R ASME Section 1995

Section Xl, SGTUBE XI, IWA-4422

IWA-4422

2751 ASME ASME N/S Mechanical Removal Processes inm9900/ 1994 R ASE E Section 1995


IWA-4423

2752 ASME ASME 1992 Examination Following Metal inm9900/ 1994 R ASME Section 1995

Section Xl, Removal SGTUBE Xl, IWA-4424

IWA-4424

2753 ASME A9ME N/S tube Sleeving by Expansion inm9900/ 1994 R No longer in n/a n/a

Section Xl, SGTUBE latest version

IWA-4425

2754 ASME ASME N/S Documentation Requirements inm9900/ 1994 R No longer in n/a n/t

Section Xl, SGTUBE latest version

IWA-4900

2755 ASME ASME N/S Insulated Components not86-108 1986 P AsME Section 1995

Section Xl, Xi, IWA-

IWA- 5242(a)

5 2 4 2 (a) _ _ _ _ _ _ __ _ _ _ _ _

2756 ASME ASME N/S Corrective Action gti99-018 1991 R ASME Section 1995

Section Xi, Xl, IWA-5250

IWA-5250

2757 ASME ASME N/S Corrective Action inm9900 1991 Rl ASME Section 1995

Section XI, XI, IWA-5250

IWA-5250

2758 ASME ASME N/S Records and Reports inm9900/ 1994 R ASME Section


IWA-6000


idRecord . ttndC . Doe -Accept. eStenderd SLatet ViesIon

. No- del ; . St ndard V oI .. .. - rX - ite 'oum'nv'*:'at'"';e 'b C s 'CU eV-ksli.l Dateo2759 ASME ASME N/S Replacement git89-009 1989 R No longer in n/a n/a

Section Xl, Latest VersionIWA-7000

2760 ASME ASME N/S Replacement inm73051 1986 R No longer in n/a n/aSection XI, Latest VersionIWA-7000

2761 ASME ASME N/S Replacement not93-21 1993 R No longer in n/a n/aSection XI, Latest VersionIWA-7000

2762 ASME ASME N/S Code Applicability gtt89-009 1989 R No longer in n/a n/a

Section Xl, Latest VersionIWA-7210

2763 ASME ASME 1987 Referenced Standards and 1Ocfr5O.55a 1994 R ASME Section 1995Section XI, Specifications Xl, Table IWA-Table IWA- 1600-11600-1

2764 ASME ASME 1988 Referenced Standards and 1 Ocfr5O.55a 1994 R ASME Section 1995

Section XI, Specifications XI, Table IWA-Table IWA- 1600-11600-1

2765 ASME ASME 1989 Rqferenced Standards and 1 0cfr5O.55a 1994 R ASME Section 1995Section Xl, Specifications Xl, Table IWA-

Table IWA- 1600-11600-1

2766 ASME ASME N/S Components Exempt from srp5.2.4 1981 P ASME Section 1995

Section XI, Examination Xl, IWB-1220

1WB-1 220 _

t1j%O

z

90

POk!h�10

w

i

w

z

w



R eco~r d f ; : E e 2 X ! L :i:r'' ' .'Sta n d ardt .D o c A:''c o e pt'^

t'i' L ate st S te n d ar d L ate st V ersi

2767 CodE Standard : Version.'. -- Txmna ittasp D ocwn505at Data Rblt C met Xl, IWB-2000 i 99t5

2768 ASME ASME N/S Examination and Inspection s0cfr5O.55a 1994 ASME Section 1995

Section XI,IWB-2000

2768 ASME ASME N/S Examination and Inspection srp5.2.4 1981 P ASME Section 1995

Section XI, XI, IWB-2000

IWB-2000

2769 ASME ASME N/S Preservice Examination XI,302 1981 P ASME Section 1995

Section Xl,IWB-2200

2770 ASME ASME N/S Adion Examination bui83-002 1983 P ASME Section 1995

Section Xl, Xl, IWB 2430

IWB-2430

2771 ASME ASME N/S Examination and Pressure Test gt94-003 ASME Section 1995

Section XI, Requirements XI, IWB-2500

IWB-2500

2772 ASME ASME N/S Acceptance Standards srp5.2.4 1981 P ASME Section 1995

Section Xl, ,IWB-3000

2773 ASME ASME N/S Acceptance Standards .rp6.6 1981 P ASME Section 1995

Section XI, XI, iWB-3000

IWB-3000

274 ASE ASENS Acceptance Standad glt88-001 1988 P ASME Section 1995

275 ASME A5ME N9 Acpae tdards gt1-1 91 RX ~ 50 19Setin i XI, IWB-3500

section XI,,IWB-3500

2775 ASME ASE N/S Acceptance Standards g.t9l-018 11A Secio 19

Section XI,Xi W 3 0

IWB-3500


Recor .: : :; . S i .- tandard Dc Ac.t L.es Stndr Laes -Vers.ion .i No. 6 Cd . ta V;rgl* i ' D m . D t.s . . te

2776 ASME ASME N/S Acceptance Standards inm9900 1991 R ASME Section 1995

Section Xl, Xl, IWB-35QO

IWB-3500

2777 ASME ASME N/S Acceptance Standards regl .1 50.rO1 1983 R ASME Section 1995

Section Xl, Xl, IWB-3500IWB-3500

2778 ASME ASME N/S Allowable Planar Flaws reg1.150.rOl 1983 R Unacceptable ASME Section 1995

Section Xi, in this Xl, IWB-3510.1IWB-3510.1 application

2779 ASME ASME N/S Standards for Examination not85-65 1985 P ASME Section n/a n/aSection Xl, Categories B-B, Pressure Retaining Xl, IWB-3511IWB-351 1 Welds in Vessels not in current

ASME Code

2780 ASME ASME N/S Standards for Examination glt94-003 1994 R ASME Section 1995Section Xl, Category B-N-1, Interior of Xi, IWB-3520IWB-3520 Reaictor Vessel, Examination

Category B-N-2, Integrally WeldedCore Support Structures andInterior Attachments to ReactorVessels, and ExaminationCategory B-N-3, Removable CoreSupport Structures

2781 ASME ASME 1986 Analytical Evaluation of Flaws glt88-001 1988 P ASME Section 1995Section Xi, Xl, IWB-3600

IWB-3600

2782 ASME ASME N/S Analytical Evaluation of Flaws glt90-005 1990 A ASME Section 1995

Section Xi, Xl, IWB-3600

IWB-3600

xl,S,

zciMq)0�0,.!h�0

LA

Po

I

W



R e o r ' ' S & s t d ~ dD e . 1 c oe hp t u .~ L t e t St a d d L a fE t V r s o

2783 ASME ASME NIS Analytical Evaluation of Flaws inm9900 1991 R ASME Section 1995

Section Xl, Xl, IWB-3600

IWB-3600

2784 ASME ASME NIS Analytical Evaluation of Flaws not85-65 1985 R ASME Section 1995

Section Xl, Xl, IW8-3600

IWB-3600

2785 ASME ASME N/S Analytical Evaluation of Flaws regl.150.rO1 1983 R Implied ASME Section 1995

Section Xl, endorsement Xl, IWB-3600

IWB-3600

2786 ASME ASME 1984 Evaluation Procedures and 10cfr50.55a 1994 P Endorsed for ASME Section 1995

Section Xi, Acceptance Criteria for Austenitic welding Xl, IWB-3640

IWB-3640 Piping practices

2787 ASME ASME N/S Evaluation Procedures and g1t88-001 P ASME Section 1995

Section Xi, Acceptance Criteria for Austenitic Xl, IWB-3640

IWB-3640 Piping

2788 ASME ASME N/S Evaluation Procedures and git9o-005 1990 R For lower- ASME Section 1995

Section Xl, Acceptance Criteria for Austenitic bound fracture Xl, IWB-3640

IWB-3640 Piping toughness

2789 ASME ASME N/S Repair and Replacement inm9900/ 1994 R ASME Section 1995


IWB-4000

2790 ASME ASME N/S Repair and Replacement srp5.2.4 1981 P ASME Section 1995


IWB-4000

2791 ASME ASME 1989 Welding Qualifications inm9900/ 1994 R Not in current n/a n/a

Section Xl, SGTUBE ASME Section

IWB-4222 Xl

z

I!,0

'IO


2792 ASME ASME 1986 Defect Removal inm9900/ 1994 R Not in current n/a n/aSection Xli SGTUBE ASME SectionIWB-4230 Xl

2793 ASME ASME 1989 Defect Removal inm9900/ 1994 R Not in current n/a n/aSection Xl, SGTUBE ASME SectionIWB-4230 Xl

2794 ASME ASME N/S Material Requirements inm9900/ 1994 R Not in current n/a n/aSection Xl, SGTUBE ASME SectionIWB-4231 Xl

2795 ASME ASME N/S Welding Qualification inm9900/ 1994 R Not in current n/a n/aSection Xl, SGTUBE ASME SectionIWB-4232 Xl

2796 ASME ASME N/S Welding Procedure inm9900/ 1994 R Not in current n/a n/aSection Xl, SGTUBE ASME SectionIWB-4233 Xl

2797 . ASME ASME N/S Examination inm9900/ 1994 R Not in current n/a n/aSection Xl, SGTUBE ASME SectionIWB-4234 Xl

2798 ASME ASME N/S Records inm9900/ 1994 R Not in current n/a n/aSection Xl, SGTUBE ASME SectionIWB-4235 Xl

2799 ASME ASME 1989 Materials inm9900/ 1994 R Not in current n/a n/aSection Xl, SGTUBE ASME SectionIWB-4241 Xl

2800 ASME ASME N/S Welding Qualifications, Records inm9900/ 1994 R Not in current n/a n/aSection Xl, and Identifying Stamps SGTUBE ASME SectionIWB-4242 Xi

z(-I

w

%0~



2801 ASME ASME 1989 Tube Plugging inm9900/ 1994 R Not in current n/a n/a


iWB-4243 Xl

2802 ASME ASME 1989 Repair Welding inm 9900/ 199 R Not in current nla nla


IWB-4300 Xl

2803 ASME ASME 1992 Repair Welding inm99001 1994 R Not in current n/a n/a


IWB-4300 Xi

2804 ASME ASME 1989 Applicable Requirements inm9900/ 1994 R Not in current n/a W


IWB-4310 Xl

2805 ASME ASME 1989 Repair Welding by Half Bead inm9900/ 1994 R Not in current n/a nla

Section Xl, Welding Technique SGTUBE ASME Section

IWB-4320 Xl

2806 ASME ASME N/S Not found inm9900/ 1994 R Not in current n/a nWa


IWB-4325 Xl

2807 ASME ASME 1989 Welding Dissimilar Materials by inm9900/ 1994 R Not in current n/a n/a

Section Xl, Half Bead Welding Technique SGTUBE ASME Section

IWB-4340 Xl

2808 ASME ASME 1989 Tube Sleeving by Expansion inm9900/ 1994 R Not in current n/a nla


IWB-4350 Xl

2809 ASME ASME 1983 Tube or Tubesheet Bore Hole inm99001 1994 R Not in current n/a n/a

Section Xl, Plugging By Explosive Welding SGTUBE ASME Section

IWB-4420 Xl

280 _ SM . M 198 Tub _levn byEpnin _ m90 94 R Nti urn /


Rod '. . Standd AtD c e.tsbt c . 1 Veru99n

2810 ASME ASME 1986 Tube or Tubesheet Bore Hole inm9900/ 1994 R Not in current n/a n/aSection Xl, Plugging 8y Explosive Welding SGTUBE ASME SectionIWB-4420 Xl

2811 ASME ASME 1989 Tube or Tubesheet Bore Hole inm9900/ 1994 R Not in current n/a n/aSection Xl, Plugging By Explosive Welding SGTUBE ASME SectionIWB-4420 Xl

2812 ASME ASME 1992 Tube or Tubesheet Bore Hole inm9S00/ 1994 R Not in current n/a n/aSection Xi, Plugging By Explosive Welding SGTUBE ASME SectionIWB-4420 Xl

2813 ASME ASME 1983 General Requirements inm9900/ 1994 R Not in current n/a n/aSection Xi, SGTUBE ASME SectionIWB-4421 Xl

2814 ASME ASME 1986 General Requirements inm9900/ 1994 R Not in current n/a n/aSection Xl, SGTUBE ASME SectionIWB-4421 Xl

2815 ASME ASME 1989 General Requirements inm9900/ 1994 R Not in current n/a n/aSection Xl, SGTUBE ASME SectionIWB-4421 Xl

2816 ASME ASME 1983 Welding Qualifications inm9900/ 1994 R Not in current n/a n/aSection Xl, SGTUBE ASME SectionIWB4422 Xl

2817 ASME ASME 1986 Welding Qualifications inm99001 1994 R Not in current n/a n/aSection Xl, SGTUBE ASME SectionIWB-4422 Xl

2818 ASME ASME 1983 Plugging Procedure Specification inm9900/ 1994 R Not in current n/a n/aSection Xl, SGTUBE ASME SectionIWB-4423 Xl

z

i04

(5

z

ci

00



co Standard DE . | Ac pt- L atest Standard L ts Vr sion

N o o aS t a d r V u t o T t e'D o c u w te f t D a e a i i yC n i n n sV r i nD t

2819 ASME ASME 1986 Plugging Procedure Specification inm9900/ 1994 R Not in current n/a n/a


IWB-4423 Xl

2820 ASME ASME 1992 Examination inm9900/ 1994 R Not in current nla nla


IWB-4424 Xl

2821 ASME ASME 1986 Tube or Tubesheet Hole Plugging inm9900/ 1994 R Not in current n/a nla

Section Xl, by Fusion Welding SGTUBE ASME Section

IWB-4430 Xl

22 ASME ASME 1989 Tube or Tubesheet Hole Plugging inm9900/ 1994 R Not in current nla n/a

Section Xl, by Fusion Welding SGTUBE ASME Section

IWB-4430 Xi

2823 ASME ASME 1980 Steam Generator Tube Plugging inm9900/ 1994 R Not in current n/a nta

Section Xl, by Manual Welding Techniques SGTUBE ASME Section

IWB-4440 Xl

2824 ASME ASME 1983 Steam Generator Tube Plugging inm9900/ 1994 R Not in current n/a n/a

Section Xl, by Manual Welding Techniques SGTU8E ASME Section

IWB-4440 Xl



IWB-4440 Xl



IWB-4440 Xl

2827 ASMEM E ME 1980 Materials inm9900/ 1994 R Not in current n/a n/a


IWB-4441.1 Xl

X0

zC)

I'D


-., i T; -t': .-'- t'''; ';ES ........... t X .t?... , 0 .....000., ,S,,, ,X ., f ''' .S,,'. .......... ..g ~t..Reco d S d D.c .It La es ^ St andard L ate .Version

.No. ode Standard. Version T.l D o.c. . ..en..Comm ents Vesi.on e Dat

2828 ASME ASME 1983 Materials inm9900/ 1994 R Not in current n/a n/aSection Xl, SGTUBE ASME SectionIW8-4441.1 Xl

2829 ASME ASME 1986 Materials inm9900/ 1994 R Not in current n/a n/aSection Xl, SGTUBE ASME SectionIWB-4441.1 Xi

2830 ASME ASME 1980 Welding Qualifications, Records, inm9900/ 1994 R Not in current n/a n/aSection Xl, and Identifying Stamps SGTUBE ASME SectionIWB-4441.2 Xl

2831 ASME ASME 1983 Welding Qualifications, Records, inm9900/ 1994 R Not in current n/a n/aSection Xl, and Identifying Stamps SGTUBE ASME SectionIWB-4441.2 Xi

2832 ASME ASME 1986 Welding Qualifications, Records, inm9900/ 1994 R Not in current n/a n/aSection Xi, and Identifying Stamps SGTUBE ASME SectionIWB-4441.2 Xl

2833 ASME ASME 1980 Tube Plugging inm9900/ 1994 R Not in current n/a n/aSection Xi, SGTUBE ASME SectionIWB-4441.3 Xl

2834 ASME ASME 1983 Tube Plugging inm9900/ 1994 R Not in current n/a n/aSection Xl, SGTUBE ASME SectioniW8-4441.3 Xi

2835 ASME ASME 1986 Tube Plugging inm9900/ 1994 R Not in current n/a n/aSection XI, SGTUBE ASME SectionIWB-4441.3 Xi

2836 ASME ASME 1980 Steam Generator Tube Plugging 1nm9900/ 1994 - Not In current n/a n/aSection Xi, by Explosive Welding Techniques SGTUBE ASME SectionIWB-4450 Xi

LA

P0

(5



Re o dS a d r e . A "C ept L ate ist t ndard L at s k V ersi n

2837 ASME ASME 1980 Materials inm9900/ 1994 R Not in current n/a nla

Section Xl. SGTUBE ASME Section

IWB-4451 Xl

2838 ASME ASME 1980 Welding Qualifications and inm9900/ 1994 R Not in current n/a n/a

Section XI, Records SGTUBE ASME Section

IW8-4452 XI

2839 ASME ASME 1980 Tube Plugging by Explosive inm9900/ 1994 R Not in current n/a n/a

Section XI, Welding SGTUBE ASME Section

IWB-4453 Xl

2840 ASME ASME 1980 Records inm9900/ 1994 R Not in current n/a nla


IWB-4455 Xl

2841 ASME ASME N/S System Pressure Tests srp5.2.4 1981 P ASME Section 1995

Section Xl, Xl, IWB-5000

IWB-5000

,2842 ASME KSME N/S System Pressure Tests stsb&w82.1.2 1992 P Typo - IW- ASME Section 1995

Section Xl, 5000 for Class Xl, IWB-5000

IWB-5000 1 components

2843 ASME ASME 1989 Examination Categories 1 Ocfr50.55a 1994 R ASME Section 199

Section Xl, Xl, Table IWB-

Table IWB- 2500-1

2500-1

2844 ASME ASME NiS Examination Categories bu182-002 1982 R ASME Section 1995


Table IWB- 2500-1

2500-1


Recod Sandad De. cceg LaestStandardi Latest Vesiloil

No Cd Standard M T o e e . Date

2845 ASME ASME N/S Examination Categories regl.147.rl.1 1994 R ASME Section 1995

Section Xl, XI, Table IWB-

Table IWB- 2500-1

2500-1

2846 ASME ASME 1975 Examination Categories 1 Ocfr50.55a 1994 P ASME Section 1995

Section Xl, Xl, Tables IWB-

Tables IWE- 2500 and IWB-

2500 and 2500-1

IWB-2500- 1

2847 ASME ASME 1974 Not found 10cfr60.55a 1994 P ASME Section n/a n/a


Table IWB- 2600 not in

2600 current ASMEcode

2848 ASME ASME N/S Allowable Planar Indications not90-04 1990 R ASME Section n/a n/a


Table iWB- 3511-1 not in

3511-1 current ASMECode

2849 ASME ASME 1975 Components Exempt from 1Ocfr5O.55a 1994 P ASME Section 1995

Section Xl, Examination Xl, IWC-1220

IWC-1220

2850 ASME ASME NIS Components Exempt from srp6.6 1981 P ASME Section 1995

Section Xl, Examination Xl, IWC-1 220IWC-1 220

2851 ASME ASME N/S Examination and Inspection srp6.6 1981 P ASME Section 1995

Section Xl, Xl, IWC-2000

IWC-2000

0

z

-4

(a

z

(!A

\0tU)



Re o dSt"n ar D oi. A c pt La te st St ndaird La e t V rioNoXj.t~ittTMg; 0 f~a.t Code Sf tandar Ver io Titl Do-m n 1at ablt Com't Verio Date

X 4;t i;:'''fE~i''t0'

2852 ASME ASME 1975 Inspection Program A lOcfr5o.5a 1994 P AM SWC to41 1

Section Xl,IWC-241 1

2853 ASME ASME N/S A not9O-04 1990 R ASME Section 1995

Section Xl, .

IWC-3000

2854 ASME ASME N/S Acceptance Standards srp6.6 _ 1981 P A C o 199

Section Xl, .

IWC-3000

2855 ASME ASME N/S Acceptance Standards gIt91-01 8 1991 R ASME Sectin 1995

Section Xl, XI C 3 0

. IWC-3500

2856 ASM i ASME N/S Accptnc Stnad inm9900 1991 R A.M SeIC tio00 1995

Section Xl,

IWC-3500

2857 ASME ASME N/S Repair and Replacement srp6.6 1981 P ASME Section 1995

Section Xl,

IWC-4000

. c iAR1981 P ASME Section 1995IWC I40000

2858 ASME ASMESection Xl,IWC-5000

N/S Systemn lressur I ests b§ V-.V . .

Xl, IWC-5000

I I1 4 . II f ! -t' d f n m i / n /a_1 -- _ _. 1 i+x Q;A i .t P Delented from inlan/1 9 7 4. .. ..

2859 ASME ASMESection Xl,Table IWC-

1974 Not found -I U~U~Vu.vUU 1 -<7 I

ASME Sec Xlprior to 1980Edition

L- 1~~2 5 2 L0 I I I _ _ _ _ _ _ _ _ I - II _ _ _ _ _ _



:eodSadr o~ AcptLaetSndr LateswvtVesiono . Cod. Stana .d:si -on ....-. T.i. e . . .bilty Coment eri Da t.- .

;i dX> ;Code I- .2860 ASME ASME 1975 Not found 1Ocfr5O.55a 1994 P Deleted from n/a n/a

Section Xi, ASME Sec XI

Table IWC- prior to 1980

2520 or Edition

IWC-2520-1

2861 ASME ASME N/S Examination and Inspection srp6.6 1981 P ASME Section 1995

Section XI, Xl, IWD-2000

IWD-2000

2862 ASME ASME N/S Acceptance Standards srp6.6 1981 P ASME Section 1995

Section Xl, Xl, IWD-3000

IWD-3000

2863 ASME ASME N/S Repair and Replacement srp6.6 1981 P ASME Section 1995


IWD-4000

2864 ASME ASME N/S System Pressure Tests srp6.6 1981 P ASME Section 1995

Section Xl, Xl, IWD-5000IWD-5000

2865 ASME ASME 1989 Inservice Inspection of Pumps in glt89-004.sOt 1995 R ASME OM Part 1995

Section Xl, Light-Water Reactor Power Plants 6

SubsectionIWP

2866 ASME ASME N/S Inservice Inspection of Pumps in inm73756 1987 R ASME OM Part 1996


SubsectionIWP

0

C,

tAI

-4

Rt5kq



R ec o r d S t a n d a r d D c c . A c c e p t- L a t e s t S t a nd ard L ' e s t ^ e r e l--

X No. code Stand d v ersion TileDoc'ument:: ~ D ate abiit comment eeotD t

2867 ASME ASME NIS inservice Inspection of Pumps in srp3.9.6 1981 R See GM (OM is ASME OM Part 1995

Section Xi, Light-Water Reactor Power Plants a separate 6

Subsection ASME vol.)

lWP

2868 ASME ASME NIS Inservice Inspection of Pumps in git89-0 04 1989 R ASME OM Part 1995

Section Xi, Light-Water Reactor Power Plants 6

IWP-1 100

2869 ASME ASME NIS Inservice Inspection of Pumps in inm2515/114 1992 RF ASME OM Part 1995


IWP-3000

2870 ASME ASME NIS Inservice Inspection of Pumps in inm35743B 1982 R ASME GM Part 1995


IWP-3000

2871 ASME ASME N/S Inservice Inspection of Pumps in inm3574 4 5 1979 R ASME OM Part 1995

Section XI, Light-Water Reactor Power Plants 6

IWP-3000

2872 ASME ASME N/S Inservice Inspection of Pumps in inm37702 1987 R A6ME OM Part 1995


IWP-3000



IWP-3000

2874 ASME ASME N/S Inservice Inspection of Pumps in srp3.9.6 1981 P See OM (OM is ASME OM Part 1995

Section XI, Light-Water Reactor Power Plants a separate 6

iWP-3000 ASME vol.)

_ - .. _--.----_- ..


o,| t r D A' d Ldtst Version'

No. Cod StIdr Vrd Document Dae blj Co ens Vtonae

2875 ASME ASME NIS Inservice Inspection of Pumps in bu188-004 1988 R ASME OM Part 1995


IWP 31 00

2876 ASME ASME NIS Inservice tnspection of Pumps in inm2500.027 1989 R ASME OM Part 1995


IWP-3100

2877 ASME ASME N/S Inservice Inspection of Pumps in glt89-004 1989 R Now in OM ASME OM Part 1995

Section Xi, Light-Water Reactor Power Plants only IWP- 6

IWP-3220 1000, 1100 in89 code

2878 ASME ASME 1974 Inservice Inspection of Pumps in inm9900/50.55a 1980 R ASME OM Part 1995


IWP-3220



IWP-3230

2880 ASME ASME 1974 Inservice Inspection of Pumps in inm9900150.55a 1980 R ASME OM Part 1995


IWP-3230(b)


Section Xl, Light-Water Reactor Power Plants only IWP- 6

IWP-3230(c) 1000, 1100 in89 code

2882 ASME ASME N/S Inservice Inspection of Pumps in srp3A9.6 1981 P See OM (OM is ASME OM Part 1995

Section Xi, Light-Water Reactor Power Plants a separate 6

IWP-4000 . ASME vol.

0tAJ

z

'0nJ

(5

z

-a

PT

C.


Recordd O W d""d''''>0 S d D . A e ' ' td t t V eteonN" C d o S tan wdar v r it e" , 'S' A . D oc wiietit' , ate ,b t . , ersi Da-

2883 ASME ASME N/S Inservice Inspection of Pumps in glt89-004 1989 P Now in OM ASME OM Part 1995

Section XI, Light-Water Reactor Power Plants only IWP- 6

IWP-41 10 1000, 1100listed in 89code



IWP-5000

2885 ASME ASME N/S Inservice Inspection of Pumps in git89-004 1989 R Now in OM ASME OM Part 1995

Section Xl, Light-Water Reactor Power Plants only IWP- 6

IWP-6000 1000, 1100 in89 code

2886 ASME ASME NIS Inservice Inspection of Pumps in inm2515/114 1992 R ASME OM Part 1995


IWP-6000



IWP-6230

2888 ASME ASME N/S Inservice Inspection of Pumps in glt89-004 1989 R ASME OM Part 1995


Table IWP-3100-1

2889 ASME ASME 1974 Inservice Inspection of Pumps in inm9900/50.55a 1980 R ASMEOM Part 1995


Table IWP-3100-1


Section Xl, Light-Water Reactor Power Plants only WIP- 6

Table IWP- 1000, 1100 in

3100-2 89 code


Record t .tandad boo. Aep Le t tt V-rsionio. CodD Standard - Ti ,M ~tl -- 0Dociumien Date abity Commentsi m e lDate

2891 ASME ASME 1989 Inservice Testing of Valves in 10cfr5O.55a 1994 P ASME OM Part 1996

Section Xl, Light-Water Reactor Power Plants 10SubsectionlWV

2892 ASME ASME 1973 Inservice Testing of Valves in drgms926-4 1981 R ASME OM Part 1995

Section Xl, Light-Water Reactor Power Plants 10Subsection.WV

2893 ASME ASME 1989 Inservice Testing of Valves in g1t89-004.sO1 1995 R ASME OM Part 1995Section Xl, Light-Water Reactor Power Plants 10SubsectionIWV


Section Xl, Light-Water Reactor Power Plants 6Table IWP-3100-2

2895 ASME ASME N/S Inservice Testing of Valves in gIt90-005 1990 R ASME OM Part 1995

Section Xl, Light-Water Reactor Power Plants 10SubsectionIWV

2896 ASME ASME N/S Inservice Testing of Valves in inm73756 1987 R ASME OM Part 1995

Section Xl, Light-Water Reactor Power Plants 10SubsectionlWV

2897 ASME ASME N/S Inservice Testing of Valves in srp3.9.6 1981 R See OM (OM is ASME OM Part 1995

Section Xl, Light-Water Reactor Power Plants a separate 10

Subsection ASME vol.IWV

Vi0-4

~0-4Vi

Vi

z

0l

'0

W

tj

00


R rdt D . | - Staf dard- La es Version

N o.C e d 8 t i ia d V-l n11 1 o umt D t a bl W o nm oe l t e et l o D

2898 ASME ASME N/S inservice Testing of Valves in srp5.4.12 1981 P ASME OM Part 1995


SubsectionlWV

28 ASME ASME NIS Inservice Testing of Valves in sts4-geB3.4.5 1992 R ASME OM Part 1995


SubsectionIWV

2900 ASME ASME N/S Inservice Testing of Valves in sts6- ge3.4.6 1992 R ASME OM Part 1995


SubsectionIWV

2901 ASME ASME N/S lnservice Testing of Valves in nuregO737 1980 P ASME OM Part 1995


SubsectionIWV

2902 ASME ASME NIS Inservice Testing of Valves in glt89-004 1989 P General ASME OM Part 1995

Section Xl, Light-Water Reactor Power Plants endorsements 10

IWV-1100

2903 ASME ASME N/S Inservice Testing of Valves in srp3.9.6 1981 P With additional ASME OM Part 1995

Section Xl, Light-Water Reactor Power Plants requirements 10

IWV-1110

2904 ASME ASME 1974 Inservice Testing of Valves in drgms901-4.rOO 1981 R ASME OM Part 1995


IWV-1 300

2905 ASME ASME 1977 Inservice Testing of Valves in drgms901-4.rOO 1981 R ASME OM Part 1995


IWV-1300


No oe Sedad VrinTil ouen ae -aiity C rSens Vrso atley

2906 ASME ASME NS Inservice Testing of Valves in drgms90l-4.r00 1981 6 ASME OM Part 1995


IWV-2000

2907 ASME ASME N/S Inservice Testing of Valves in srp3,9.6 1981 P See OM (OM is ASME OM Part 1995

Section Xl, Light-Water Reactor Power Plants a separate vol. 10

IWV-2000 of ASME code)

2908 ASME ASME NIS Inservice Testing of Valves in drgms90 -4.rOO 1981 R ASME OM Part 1995


IWV-2100

2909 ASME ASME N/S Inservice Testing of Valves in not91-56 1991 P ASME OM Part 1995


IWV-2200

2910 ASME ASME N/S Inservice Testing of Valves in regl.148.r00 1981 R See OM (now ASME OM Part 1995

Section Xl, Light-Water Reactor Power Plants a separate 10

IWV-2200 ASME volume)

2911 ASME ASME N/S Inservice Testing of Valves in inm35743B 1982 R ASME OM Part 1995


IWV-3000

2912 ASME ASME NIS Inservice Testing of Valves in inm357448 1979 R ASME OM Part 1995


IWV-3000

2913 ASME ASME: N/S Inservice Testing of Valves in inm37702 1987 R ASME GM Part 1995


IWV-3000

0

z

C,

tJh-3

z

C)1

(k)

I-.

0



Recor-Td Standard Doe. Aoceft- LatesL St-'ard Latest. Vesion

No o e Stand ard 'V ersio - i eD cum ent Dat a'lt--m en sVe s o Date

2914 ASME ASME N/S Inservice Testing of Valves in inm6270 2 1987 A ASME OM Part 1995


IWV-3000

2915 ASME ASME N/S Inservice Testing of Valves in inm9900/ ASME 1986 _ ASME OM Part 1995

Section Xl, Light-Water Reactor Power Plants IX 10

IWV-3000

2916 ASME ASME N/S Inservice Testing of Valves in inm9900/ ASME 1986 R ASME OM Part 1995

Section Xi, Light-Water Reactor Power Plants IX 10

IWV-31 00

2917 ASME ASME N/S Inservice Testing of Valves in inm9900/4.5.1 1986 R ASME OM Part 1995


IWV-3300

2918 ASME ASME N/S Inservice Testing of Valves in drgms901-4.rOO 1981 R ASME OM Part 1995


IWV-3400

2919 ASME ASME N/S Inservice Testing of Valves in not89-32 1989 P ASME OM Part 1995


IWV-3400

2920 ASME ASME N/S Inservice Testing of Valves in stsb&wB3.5.2 1992 P ASME OM Part 1995


IWV-3400

2921 ASME ASME N/S Inservice Testing of Valves in stsb&wB3.7.2 1992 R ASME OM Part 1995


IWV-3400



IWV-3400

i-.

z

\0-I4


. fi - ; .; .,...,,, .. i.,-..0j .,.: ,i- t.. T. ~i- 20 I '" ",'",i',,,, ~l' .iiS... ..''........-: ....

RecordO Stn 0d - e c t La ,tet Sanda

No. Code St an rd VerslVn T i- stle:: i- o m b abrlfty -Cf ments s eion Date

2923 ASME ASME N/S Inservice Testing of Valves in stsceB3.7.2 1992 R ASME OM Part 1995


IWV-3400



IWV-3400


Section Xl, Light-Water Reactor Power Plants 10IWV-3400

2926 ASME ASME NIS Inservice Testing of Valves in stswstS3.7.2 1992 R ASME OM Part 1995


IWV-3400

2927 ASME ASME N/S Inservice Testing of Valves in stswst83.7.5 1992 R ASME OM Part 1995


IWV-3400

2928 ASME ASME N/S Inservice Testing of Valves in drgms901-4.r00 1981 R ASME OM Part 1995

Section Xi, Light-Water Reactor Power Plants 10IWV-3410

2929 ASME ASME N/S Inservice Testing of Valves in inm9900/ ASME 1986 R ASME OM Part 1995


IWV-3412

2930 ASME ASME N/S Inservice Testing of Valves in git89-004 1989 R Now in OM ASME OM Part 1995

Section Xl, Light-Water Reactor Power Plants only IWV- 10

IWV- 1000, 1100 in

34131a) 89 code

2931 ASME ASME X 1980 Inservice Testing of Valves in not85-84 1985 P ASME OM Part 1995

Section Xl, Light-Water Reactor Power Plants 10IWV-341 5

zCM00

�0t!hW-4W

110:eW

U3

t-4



2932 ASME ASME WS Inservice Testing of Valves in g"t89-004 1989 R Now in OM ASME OM Part 1995

Section Xl, Light-Water Reactor Power Plants only IWV- 10

lWV- 1000, 1100 in

34 17(b) __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _89 code

933 ASME AsME N/S Inservice Testing of Valves in inm2515/114 1992 R ASME OM Part 1995


lWV-3417(b)

2934 ASME ASME N/S inservice Testing of Valves in drgms901-4.r00 1981 P ASME OM Part 1995


IWV-3420

2935 ASME ASME N/S Inservice Testing of Valves in glt89-004 1989 P Now in OM ASME OM Part 1995

Section Xli Light-Water Reactor Power Plants IWV-1 000, 10

IWV-3421 1100 in 89code

2936 AsmE ASME N/S Inservice Testing of Valves in inm9900i ASME 1986 R ASME OM Part 1995

Section Xi, Light-Water Reactor Power Plants IX 10

IWV-3421

2937 ASME ASME N/S Inservice Testing of Valves in stsb&wB3.4,14 1992 R ASME OM Part 1995


IWV-3422



IWV-3422

2939 ASME ASME N/S Inservice Testing of Valves in stswstB3.4.14 1992 R ASME OM Part 1995


IWV-3422

ASME ASME N/S Inservice Testing o Valves in sts4-geB3.4 .6 1992 R ASME OM Part 1995


lWV-3423(e) . . _ _ __ =


1:: Record Stadarid 0oS Aet, Latest Stand-rd atd-t V*rsionNo oe tndr eso itl ouet Dt aiiy Cmet Version Da te:

704t-N o ts C ^e: S~nd:0V ~tn0;0- 0;tri ;i

2941 ASME ASME N/S Inservice Testing of Valves in sts6-geB3.4.6 1992 R ASME OM Part 1995

Section Xl, Light-Water Reactor Power Plants 10lWV-3423(e) _ _ _


Section XI, Light-Water Reactor Power Plants 10lWV-3423(e)


Section Xl, Light-Water Reactor Power Plants 10IWV-3423(e)

2944 ASME ASME N/S Inservice Testing of Valves in stswstB3.4.14 1992 R ASME OM Part 1995

Section Xl, Light-Water Reactor Power Plants 10iWV-34231e) _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

2945 ASME ASME N/S Inservice Testing of Valves in git89 -004 1989 P Now in OM ASME OM Part 1995

Section Xi, Light-Water Reactor Power Plants only IWV- 10IWV-3426 1000, 1100 in

89 code

2946 ASME ASME N/S Inservice Testing of Valves in inm2515/114 1992 R ASME OM Part 1995Section Xl, Light-Water Reactor Power Plants 10IWV-3426

2947 ASME ASME N/S Inservice Testing of Valves in glt89-004 1989 R Now in OM ASME OM Part 1995

Section XI, Light-Water Reactor Power Plants only IWV- 10IWV- 1000, 1100 in

3427(a) 89 code

2948 ASME ASME N/S Inservice Testing of Valves in inm2515/114 1992 R ASME OM Part 1995Section Xl, Light-Water Reactor Power Plants 10lWV-3427(a)

2949 ASME ASME N/S Inservice Testing of Valves in g1t89-004 1989 R Now in OM ASME OM Part 1995Section Xi, Light-Water Reactor Power Plants only IWV- 10

IWV- 1000, 1100 in

3427(b) . 89 code

z

C,

Po~

(b

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0

-I

'IO:b

W


Re S d ard 'A -A cc'pt- Late t : .S tad'rd Lat t VersionCbNo. c S t ad Vesioni at "0 title . . Dnn ..e bil t V i .

2950 ASME ASME NIS lnservice Testing of Valves in stsb&wB3.7.1 1992 p ASME OM Part 1995


IWV-3S00

2951 ASME ASME N/S Inservice Testing of Valves in stsceB3.7.1 1992 P . ASME OM Part 1995


IWV-3500

2952 ASME ASME N/S Inservice Testing of Valves in stswstB3.7.1 1992 p ASME OM Part 1995


IWV-3500

2953 ASME ASME 1983 Inservice Testing of Valves in inm9900/ ASME 1986 R ASME OM Part 1995


IWV-3520

2954 ASME ASME N/S Inservice Testing of Valves in git89-004 1989 P Now in OM ASME OM Part 1995

Section Xi, Light-Water Reactor Power Plants only IWV- 10

IWV-3522 1000, 1100 in89 code

2955 ASME ASME 1983 Inservice Testing of Valves in inm9900/ ASME 1986 R ASME OM Part 1995


IWV-3522

2956 ASME ASME N/S System Pressure Tests sts4-geB2.1.2 1992 P ASME Section 1995

Section Xl, Xl, IWX-5000

IWX-5000

2957 ASME ASME N/S System Pressure Tests sts6-geB2.1.2 1992 P - ASME Section 1995


IWX-5000

2958 ASME ASME N/S System Pressure Tests stsceB2.1.21a) 1992 P ASME Section 1995


IWX-5000


RecordE Stnrd d A t trd lte -Vri.No d Stnt:Na Versin 2 'Title -D-.n Dt b C Version Date

2959 ASME ASME NIS System Pressure Tests stsceB2.1.2(d) 1992 P ASME Section 1995

Section Xi, Xi, IWX-5000IWX-5000

2960 ASME ASME N/S System Pressure Tests stswstB2.1.2 1992 P ASME Section 1995

Section Xl, Xi, iWX-5000IWX-5000

2961 ASME ASME AG-1 N/S Code on Nuclear Air and Gas sts4-ge5.7.2.13 1992 A ASME AG-1 1994Treatm ent _ _ _ _ _ _ _ __ _ _ _ _ _ _

2962 ASME ASME AG-1 N/S Code on Nuclear Air and Gas sts6-ge5.7.2.13 1992 A ASME AG-1 1994Treatment

2963 ASME ASME AG-1 NIS Code on Nuclear Air and Gas stsb&w5.7.2.15 1992 A ASME AG-1 1994Treatment

2964 ASME ASME AG-1 N/S Code on Nuclear Air and Gas stswst5.7.2.15 1992 A ASME AG-1 1994Treatment

2965 ASME ASME N/S Power Piping inm49001 1992 R ASME B31.1 1995

831.1 _ _ _ _ _ _ _ _ _ _

2966 ASME ASME 1980 Power Piping srp3.2.2 1981 R ASME 831.1 1995B31.1

2967 ASME usAs 831.1 1969 Power Piping sts4-geB2.1.2 1992 R ASME B31.1 1995

2968 ASME USAS B31.1 1967 Power Piping stsb&w_2.1.2 1992 _ ASME 831.1 1995

2969 ASME USAS B31.1 1967 Power Piping stsce82.1.2(a) 1992 R ASME B31.1 1995

2970 ASME USAS 831.1 1967 Power Piping stsceB2.1.2(d) 1992 R ASME B31.1 1995

2971 ASME USAS B31.1 1969 Power Piping stswstB2.1.2 1992 R ASME B31.1 1995

2972 ASME ASME 1977 Quality Assurance Program drg1 01 0.rO0 1992 P Proposed ASME NQA-1 1994

N45,2 Requirements for Nuclear Facility reg1.28.r04Applications _ _ :

2973 ASME ASME NIS Quality Assurance Program inm36100 1983 R ASME NQA-1 1994

N45.2 Requirements for Nuclear FacilityApplications

zCi

%0La

z

'0-3C..



2974 ASME ASME 1977 Quality Assurance Program inm9900/0PS 1991 R Typo was ASME NQA-1 1994

N45.2 Requirements for Nuclear Facility ASME 45.2

Applications__ _ _ _ _ _ _

2975 ASME ASME 1977 Quality Assurance Program regl.28.r03 1 985 P Endorsed by ASME NQA-1 1994

N45.2 Requirements for Nuclear Facility Reg. Guide

Applications 1.28 withsupplemental

2976 ASME ASME 19-7-8 Quality Assurance Program drgrs908-6.rOO 1979 pASENA194


____ ____ _ __ ____ ___ A p p licatio n s _ _ _ _ _ _

2977 ASME ASME 1974 Quality Assurance Program drgrs9O8-5.rOO 1979 R regil.94 ASME NQA-1 1994

N45.2.56 Requirements for Nuclear Facility endorsesApplications__ _ _ _ _ _ _

2978 ASME ASM~E --- N/S Quality Assurance Program inm45051 1984 R ASME NQA-1 1994

N45.2.5 Requirements for Nuclear FacilityA pplications _ _ _ _ _ _ __ _ _ _ _ _

2979 ASME ASME 1978 Quality Assurance Program inm45053 1984 R ASME NQA-1 .1994

N45.2.6 Requirements for Nuclear FacilityA pplications _ _ _ _ _ _ _ __

_ _ _ _ _

2980 ASME ASE1978 Quality Assurance Program inm45053 1984 R ASME NQA-1 1994

N45.2.5 Requirements for Nuclear FacilityApplications ____

2981 ASME ASME 1978 Quality Assurance Program inm 0302 1983 R ASME NQA-i 1994

N45.2.6 Requirements for Nuclear FacilityApplications _ _ _ _ _ _ _ _

2982 ASME AS-ME 1978 Quality Assurance Program inm79701 1991 R ASME NQA-1 1994


2983 ASME ASME 1977 Quality Assurance Program regl.142.rOl 1981 RASENA194

N45.2.12 Requirements for Nuclear FacilityA pplications__ _ _ _ _ _ ___ _ _ __ _ _ _ _ _

2984 ASME ASME N/ uality Assurance Program inm45051 1984 R SENA1 19

N45.2.20 Requirements for Nuclear FacilityA pp lications _ _ _ _ _ _ _ __ _ _ _ _ _ _



|D A-cept. Latest t Latesti Veilon

2985 ASME ASME 1979 Quality Assurance Program inm45053 1984 R ASME NQA-1 1994


2986 ASME ASME 1978 Quality Assurance Program lt8I001 1981 p Reg. Guide ASME NQA-1 1994

N45.2.23 Requirements for Nuclear Facility 1.146

Applications endorsesN45.2.23-1978 withcertainexceptions




N45.2.23 Requirements for Nuclear FacilityApplications .













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opod- : t n~~' o . A c l t-' h a ~ t S a daid A test Ve son

2995 ASME ASME 1978 Quality Assurance Program inm83729 1991 i ASME NQA-1 1994






Applications





Applications


N45.2.23 Requirements for Nuclear FacilityApplications -



3002 ASME ASME 1978 Quality Assurance Program inm84750 1988. R ASME NQA-1 1994






3005 ASME ASME 1978 Quality Assurance Program regl.142.rOl 1981 P Reg Guide ASME NQA-1 1994

N45.2.23 Requirements for Nuclear Facility 1.146

Applications__ _ _ _ _ _ _

3006 ASME ASME N509 1980 Nuclear Power Plant Air-Cleaning inm84101 1991 . ASME N509 1989



.',~~~~~~~~. nvv::l-. td .^ i0i ... .... .

ReodSadard, D. AcetLatest St~~iaidar Laet Ve rsio~n

o. Code Stnd Vrs ow ~l ouet Dt blt Conte t Verio Date

3007 ASME ASME N509 1976 Nuclear Power Plant Air-Cleaning inm84524 1984 R ASME N509 1989






3010 ASME ASME N509 1980 Nuclear Power Plant Air-Cleaning inm84724 1991 R ASME N509 1989Units and Components

3011 ASME ASME N509 N/S Nuclear Power Plant Air-Cleaning not93-06 1993 R ASME N509 1989Units and Components

3012 ASME ASME N509 1976 Nuclear Power Plant Air-Cleaning regl.140.rOl 1979 R ASME N509 1989


3013 ASME ASME N509 1976 Nuclear Power Plant Air-Cleaning regl.52.rO2 1978 P Several ASME N509 1989

Units and Components sectionsendorsed

3014 ASME ASME N510 N/S Testing of Nuclear Air Treatment inm1245 App. B 1991 R ASME N510 1989 R95

Systems _

3015 ASME ASME N510 1980 Testing of Nuclear Air Treatment inm84101 1991 R ASME N510 1989 R95Systems

3016 ASME ASME N510 1975 Testing of Nuclear Air Treatment inm84524 1984 R ASME N510 1989 R95Systems

3017 ASME ASME N510 1980 Testing of Nuclear Air Treatment inm84524 1984 R ASME N510 1989 R95

Systems _


._ Systems

3019 ASME ASME N510 1980 Testing of Nuclear Air Treatment inm84724 1991 -AASE NStO 1989 R95

Systems


,.._= _ __ . ._ Systems

z

C)

z

C)1U'

0



R e c o r d . ' S ta, :rd . K , - , . Do co A - L atIe st S ta d a r d a t t V ers io n

3021 ASME ASME N510 NiS Testing of Nuclear Air Treatment not92-32 1992 R ASME N510 1989 R95

System s _ _ _ _ _ _ _ _ _

3022 ASME AsME N510 N/S Testing of Nuclear Air Treatment not93-06 1993 R ASME N510 1989 R95

_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ S y s te m s_ _ _ _ _ _ _ _

3023 ASME ASME N510 1989 Testing treatment sts4-ge5.7.2.13 1992 A ASME N510 1989 R95

t______ _ S1 Sys9tems _oc AT m__ 19SM 08

|3024 ASME ASME N510 1989 Testing of Nuclear Air Treatment sts6-we5.7.2.1 3 1992 A ASME N510 1989 R95

Systems__ _ _ _ _ _

3025 ASME ASME N510 1989 Testing fotNuclear Air Treatment stsb&w5.7.2.15 1992 A ASMESN5 1nd 1989 R95

Systems__ _ _ _ _ _

3026 ASME ASME N510 1989 Testing of Nuclear Air Treatment stsce5-7.2.15 1992 A ASMEN510 1989 R95

Systems stndrdha

3027 ASME ASME N510 1989 Testing of Nuclear Air Treatment stswst5o.2.15 1992 A ASMEbNse 1989 R95

Systems

3028 ASME ASME N/S Standard for Qualification of srp3.10 1981 R Standard under n/aN551 .1 ASME Code Class 2 and 3 Pump development -

DRAFT Assemblies for Safety Systems standard has

Service General Requirements not beenpublished

3029 ASME ASME N/S Standard for Qualification of srp3.10 198i R Standard under n/a n/a

N551.2 ASME Code Class 2 and 3 Pumps development -

DRAFT for Safety Systems Service standard hasnot beenpublished

3030 ASME ASME N/S Functional Qualification of Motor srp3,10 1981 R Standard under Not issued n/a

N551 .4 Drives for Safety Related Code development -

DRAFT Class 2 and 3 Pumps for Nuclear standard has

Power Plants not beenpublished

wj

z

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0


rD c Latst Stindard Late.t Version

3031 ASME ASME NQA^ 1989 Quality Assurance Program 10cfr76 1994 A ASME NQA-1 1994

1 Requirements for Nuclear FacilityApplications

3032 ASME ASME NQA- 1989 Quality Assurance Program drgl O10.rOO 1992 R Proposed ASME NQA-1 1994

1 Requirements for Nuclear Facility regl.28.rO4

_ __________ Applications

3033 ASME ASME NQA- 1983 Quality Assurance Program drglO10.rOO 1992 R Proposed ASME NQA-1 1994

1 Requirements for Nuclear Facility regl.28.rO4Applications

3034 ASME ASME NQA- 1979 Quality Assurance Program drg1010.rOO 1992 R Proposed ASME NQA-1 1994

1 Requirements for Nuclear Facility regl.28.rO4Applications

3035 ASME ASME NQA- 1983 Quality Assurance Program drges926-4.rOO 1986 R Proposed ASME NQA-1 1994

1 Requirements for Nuclear Facility regl.23.rOlApplications _

3036 ASME ASME NQA- 1979 Quality Assurance Program drgrs9O2-4.rOO 1980 R Proposed ASME NQA-1 1994

1 Requirements for Nuclear Facility regl.3.r03Applications

3037 ASME ASME NQA- 1989 Quality Assurance Program inm-toc 1995 R ANS 3.2 1994


3038 ASME ASME NQA- N/S Quality Assurance Program inm1 245 App. B 1991 R ASME NQA-1 1994

1 S Requirements for Nuclear FacilityApplications

3039 ASME ASME NQA- NIS Quality Assurance Program inm38703 1993 R ASME NQA-1 1994


3040 ASME ASME NQA- 1979 Quality Assurance Program inm73051 1986 R ASME NQA-1 1994


3CF41 ASME ASME NQA- 1989 Quality Assurance Program inm9900/NQA-1 1990 R ASME NQA-1 1994

1 Requirements for Nuclear FacilityApplications _ ___ __ ___ ___ i _.

3042 ASME ASME NQA- 1983 Quality Assurance Program inm9900/OPS 1991 R ASME NQA-1 19941 Requirements for Nuclear Facility

Applications ____ ____ _.__ _ _

z

MQRt�,410

LI)

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33 A 1 Quality Assurance Program regl.1I2.rOO 1985 R ASME NQA-1 1994

1 Requirements for Nuclear Facility

Applications 1994___

3044 ASME ASME NQA- 1983 Quality Assurance Progra regl.28.r03 1985 P Subject to ASME NOA-1 1994

1 Requirements for Nuclear Facility modifications

Applications ----- 1994

3045 ASME ASME NQA^ 1979 Quality Assurance Program regt.28.rOS 1985 R ASME NQA-1 1994


Applications __________1994

3046 ASME ASME NQA- 1979 Quality Assurance Program regl.97.r03 1983 R Endorsement ASMEN 1994

1 Requirements for Nuclear Facility anticipated

A pplications ... _____________ 199

3047 AASME SME NQA- 1983 Quality Assurance Program reg3.48.rOl 1989 Implied ASME NQA-1 1994

1 Requirements for Nuclear Facility endorsement

Applications ASME_______1994

3048 ASME ASME NQA- N/S Quality Assurance Program reg7.10;rO1 1986 R ASME NQA-1 1994


Applications ____1994___

3049 ASME ASME NQA- 1983 Quality Assurance Program g1t88-01 8 1988 P Endorsed by ASME NQA-11994

1 Appendix Requirements for Nuclear Facility Reg. Guide

17A-1 Applications 1.28

3050 ASME ASME NQA- 1983 Quality Assurance Program regt .28.rO3 1985 P Subject to ASME NQA-1 1994

1 a Requirements for Nuclear Facility modifications

Applications --- (Addendum) _______

3051 iSME ASME NQA^ 1981 Quality Assurance Program regt .28.rO3 1985 P ASME NQA-1 1994

1 a Requirements for Nuclear FacilityApplications__ _ _ _ _ _ _

I--eAlc_ ... 9 R ra R 1 985 P ASME NQA-1 t 994u u a~~~ t y~ zs uvn_ r w d~

3052 ASME ASME NQA-Ila

I1983 quaiity Assurance lrogFa cRequirements for Nuclear Facility

*C .uJI.- -- - ---

A __1'_.:__

- JApplications I I95 -- ASME NQA-1 1994I- -. I-

3053_F 5-

ASME ASME NQA-lb

19S3t Quality Assurance rro FaciitQequirements for Nuclear FacilityI nn.~ein

ie WU I.-, -

F--

I I I__ __ _ l/1WpISuotiva i


0 ; . '.:. ' .. ............ '' , .!,\:' 0 *...................................... ... :.. ._. _ ....g. .;;. ......

Re...d Nt W Snard -oc Act Lsi t r

3054 ASME ASME NQA- 1982 Quality Assurance Program reg1.28.r03 1985 P ASME NQA-1 19941 c Requirements for Nuclear Facility

Applications3055 ASME ASME NQA- N/S Quality Assurance Program inm1 245 App. 8 1991 R ASME NQA-1 1994


3056 ASME ASME NQA- N/S Quality Assurance Program inm37550 1995 R ASME NQA-1 19942 Requirements for Nuclear Facility

Applications3057 ASME ASME NQA- N/S Quality Assurance Program inm38703 1993 R ASME NQA-1 1994

2 Requirements for Nuclear Facility_ _ Applications

3058 ASME ASME NQA- 1983 Quality Assurance Program inm9900/OPS 1991 R ASME NQA-1 19942 Requirements for Nuclear Facility

._ Applications3059 ASME ASME NQA- 1990 Quality Assurance Program inm5200t 1995 R ASME NQA-1 1994

2a Requirements for Nuclear FacilityApplications

3060 ASME ASME NQA- 1990 Quality Assurance Program inm52002 1995 R ASME NQA-1 19942a Requirements for Nuclear Facility

Applications3061 ASME ASME OM 1987 Code for Operation and glt89-010.sO1 1990 R Referred to in ASME OM 1995

Maintenance of Nuclear Power textPlants

3062 ASME ASME OM 1987 Code for Operation and glt89-013 1989 R Referred to as ASME OM 1995Maintenance of Nuclear Power industryPlants standard _

3063 ASME ASME OM N/S Code for Operation and inm2515/110 1993 R ASME OM 1995Maintenance of Nuclear PowerPlants

3064 ASME ASME OM 1990 Operation and Maintenance of inm73756 1995 R ASME OM 1995Nuclear Power Plants _ _ _

3065 ASME ASME OM 1990 Code for Operation and not89-90.sO0 1991 R ASME OM 1995Maintenance of Nuclear PowerPlants

.- - - -----

W

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R e or St<,a n d ard 0 - XD ec. A c E pt l a te ls t. t n d ar L a e t V e s oN o "C d S a d r e s o ~l o c u m o n t , D t b l tC m e u tV e lo n ,D t

3066 ASME ASME OM 1987 Requirements for inservice not89-90.sO1 1991 R ASME OM Part 1995

Part 1 Performance Testing of Nuclear 1Power Plant Pressure ReliefDevices

3067 ASME ASME OM 1987 Requirements for Inservice stsb&wB3.7.1 1992 P -ASME M Part 1995

Part 1 Performance Testing of Nuclear 1

Power Plant Pressure ReliefDevices

3068 ASME ASME OM 1987 Requirements for Inservice stsce 3.7.1 1992 P ASME OM Part 1995


3069 ASME ASME OM 1987 Requirements for Inservice stswstB3.7.1 1992 P ASME OM Part 1995


3070 ASME ASME OM 1988 Examination and Performance 10cfr50.55a 1994 PASMEOM Par 1995

Part 4 Testing of Nuclear Power Plant 4Dynamic Restraints ISnubbers)

3071 ASME OM N/S Examination and Performance inm70370 1987 R ASME OM Part 1995

Part 4 Testing of Nuclear Power Plant 4

Dynamic Restraints (Snubbers)

3072 ASME ASME OM 1988 Inservice Testing of Pumps in 10cfr50.55a 1994 P ASME OM Part 1995

Part 6 Light-Water Reactor Power Plants 6

3073 ASME ASME OM N/S Inservice Testing of Pumps in glt89-004.s01 1995 A ASME OM Part 1995


3074 ASME ASME OM 1988 Inservice Testing of Pumps in inm73756 1995 R ASME OM Part 1995



DRecord. S L t Li.tandrdt oc A-et Lates Sadd Latest Vers:on

oo oe Sadrd Ve1rsio OftDctln ae blt CofimmenhtS;, Veron DAte3075 ASME ASME OM NIS Start-Up and Periodic Performance glt89-01 0.sOl 1990 R Referred to in ASME OM Part 1995

Part 8 Testing of Electric Motor text 8Operators on Valve Assemblies inNuclear Power Plants

3076 ASME ASME OM 1988 Inservice Testing of Valves in 1Ocfr5O.55a 1994 P ASME OM Part 1995


3077 ASME ASME OM N/S Inservice Testing of Valves in glt89-004.sol 1995 A ASME OM Part 1995


3078 ASME ASME OM N/S Inservice Testing of Valves in glt89-01 0.sO1 1990 R Referred to in ASME OM Part 1995

Part 10 Light-Water Reactor Power Plants text 10

3079 ASME ASME OM 1988 Inservice Testing of Valves in inm73756 1995 R ASME OM Part 1995


3080 ASME ASME OM NIS Inservice Testing of Valves inm9900/ ASME 1986 R ASME OM Part 1995

Part 10 Light-Water Reactor Power Plants IX 10

3081 ASME ASME OM N/S Inservice Testing and Maintenance regt.9.rO3 1993 R ASME OM Part 1995

Part 16 of Diesel Drives at Nuclear Power 16Plants__ _ _ _ _ _ _ _ _ _ _ _ _ _ _

3082 ASME ASME PTC NIS Pressure Relief Devices not92-64 1992 R ASME PTC 25 1994

25.3

3083 ASME ASME PTC 1976 Pressure Relief Devices regl.84.r30 1994 P Use of 1977 ASME PTC 25 1994

25.3 addenda of831.7

3084 ASME ASME QME- N/S Qualification of Active Mechanical glt89-010.sOl 1990 R Standard under n/ n/a

1 Equipment Used in Nuclear Power development -Plants has not been

published

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-N oRil . , , i. ,i 4. C ' d e S t a ' d a d V 'e De n ' a b" i t > " ' ' o n D

3085 ASME ASME SA- NIS Carbon and Low-Alloy Steel not89-56.sOl 1989 R ASME SA-350 1995

350 Forgings, Requiring NotchToughness Testing for Piping

Components

3086 ASME ASME SA- N/S Standard Test Methods and regl .65.rOO 1973 P ASME SA-370 1995

370 Definitions for Mechanical Testingof Steel Products

3087 ASME ASME SA- NIS Standard Practice for Ultrasonic regl.65.rOO 1973 P ASME SA-388 1995

388 Examination of Heavy SteelForgings

3088 ASNT ASNT SNT- 1975 Recommended Practice drg1010.rOO 1992 R ASNT SNT-TC- 1992

TC-1 A 1A

3089 ASNT ASNT SNT- 1980 Recommended Practice drg1010.rOO 1992 R ASNT SNT-TC- 1992

TC-1A 1A

3090 ASNT ASNT SNT- 1988 Recommended Practice drg1010.rOO 1992 P ASNT SNT-TC- 1992

TC-1A 1A

3091 ASNT ASNT SNT- 1968 Recommended Practice inm363019 1976 R ASNT SNT-TC- 1992

TC-1A 1A

3092 ASNT ASNT SNT- NIS Recommended Practice inm49001 1992 R ASNT SNT-TC- 1992

TC-1A 1A

3093 ASNT ASNT SNT- N/S Recommended Practice inm49055 1982 R ASNT SNT-TC- 1992

TC-1A 1A


TC-1A 1A


TC-1A 1A


S t;t tt0 t .;. ! .; .; ..............., -i ;, ............... ,: i ...... ..: .._. ..... i

. Rncord S . D A L -tnad Ltet Vers ion

No.: Coide Standar .V-rsiion X - - .-. Ti >; i .ef Documant Date ability -vCommns VrinDt

3096 ASNT ASNT SNT- N/S Recommended Practice inm57070 1983 R ASNT SNT^TC- 1992

TC-1A 1A


TC-1A 1A


TC-1A AA


TC-1A 1A


TC-1A 1A

3101 ASNT ASNT SNT- N/S Recommended Practice regl.83.rOl 1975 P ASNT SNT-TC- 1992

TC-1A 1A

3102 ASNT ASNT SNT- N/S Recommended Practice reg7.10.rOl 1986 R ASNT SNT-TC- 1992

TC-1 A 1A

3103 ASNT ASNT SNT- N/S Recommended Practice SECY95-180 1995 R ASNT SNT-TC- 1992

TC-1A 1A

3104 ASQC ASQOC A2 1962 Terms, Symbols, and Definitions reg6.6.rOO 1974 R ASQC A2 1987

for Acceptance Sampling

3105 ASQC ASQC A2 N/S Terms, Symbols, and Definitions inm1245 App. B 1991 R ASQC A2 1987

for Acceptance Sampling

3106 ASTM ASTM N/S American Society for Testing and not86-25 1986 R General n/a n/a

Materials reference nospecific codes]cited

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R c dSt d a dD ee A c e t L at est S ta n l drd L at s e s o

No. code Sta dard Ver o Tde t D t iit C

3107 ASTM ASTM N/S American Society for Testing and not86-45 1986 R General n/a n/a

Materials reference nospecific codescited

3108 ASTM ASTM N/S American Society for Testing and regl.70.r03 1978 R General n/a n/a


3109 ASTM ASTM N/S American Society for Testing and reg1.83.rO1 1975 R General n/a n/a


3110 ASTM ASTM N/S Annual Book of ASTM iandards srp2.5.4 1981 R Annual Book ofASTMStandards

3111 ASTM ASTM N/S Annual Book of ASTM Standards srp2.5.5 1981 R Annual Book of 1995ASTMStandards

3112 ASTM ASTM A262 N/S Standard Practices for Detecting git88-001 1988 P Implied ASTM A262 1993

Susceptibility to Intergranular endorsement Rev A

Attack in Austonitic Stainless of practice A

Steels or E

3113 ASTM ASTM A262 1968 Standard Practices for Detecting regl.37.r0O 1973 R ASTM A262 1993

Susceptibility to Intergranular Rev A

Attack in Austenitic StainlessSteels

3114 ASTM 6STMA2U2 1970 Standard Practices for Detecting regl.44.rOO 1973 P Practices A or ASTM A262 1993

Susceptibility to Intergranular E Rev A

Attack in Austenitic StainlessSteels

3115 ASTM ASTM A262 1970 Standard Practices for Detecting regl .84.r30 1994 P Practices A or ASTM A262 1993

Susceptibility to Intergranular E Rev A

Attack in Austenitic Stainless

Steels .__ _


_ d hS.-i5 ;.^.- .................... , C .f-?.Fq~\ho 6'i;t! ...........) 'oF

i~~~~~~ec ~~~~~~d 0 i i -... 0 ........ -. B .. .....No oe Sadr. Vr~nTteDocumeflt, Dae bi:t Commentso, Version Dt

3116 ASTM ASTM A262 1970 Standard Practices for Detecting reg3.37.rOO 1975 P With ASTM A262 1993Susceptibility to Intergranular exceptions Rev AAttack In Austenitic StainlessSteels

3117 ASTM ASTM A262 NIS Standard Practices for Detecting srp4.5.1 1981 P Practices A or ASTM A262 1993Susceptibility to Intergranular E Rev AAttack in Austenitic StainlessSteels

3118 ASTM ASTM A262 N/S Standard Practices for Detecting srp5.2.3 1981 R Practice E. ASTM A262 1993Susceptibility to Intergranular Rev AAttack in Austenitic StainlessSteels _ _ _ _ _ _ _ _

3119 ASTM ASTM A262 N/S Standard Practices for Detecting srp6.1 .1 1981 P ASTM A262 1993Susceptibility to Intergranular Rev AAttack in Austenitic StainlessSteels _ .___

3120 ASTM ASTM A370 N/S Standard Test Methods and bul80-021 1980 R ASTM A370 1995Definitions for Mechanical Testingof Steel Products

3121 ASTM ASTM A370 N/S Standard Test Methods and bui88-005.s02 1988 R ASTM A370 1995Definitions for Mechanical Testingof Steel Products

3122 ASTM ASTM A370 N/S Standard Test Methods and glt80-092 1980 R ASTM A370 1995Definitions for Mechanical Testingof Steel Products

3123 ASTM ASTM A370 NIS Standard Test Methods and srp'0.2.3 1981 P Implied ASTM A370 1995Definitions for Mechanical Testing endorsementof Steel Products

3124 ASTM ASTM A370 1972 Standard Test Methods and srp5.4.1.1 1981 P implied ASTM A370 1995Definitions for Mechanical Testing endorsementof Steel Products

3125 ASTM ASTM A393 1963 Detection of Intergranular reg1.37.rOO 1973 R No longer Withdrawn n/aPrecipitation considered a

valid test _

ztri

Mj'0

z

C)

(5

0



fl e c o r d v a n d a r d. Lc i f. A e t L o t e s t S ta n d a r d L a t eGoi f V e L o

C dStanhdard l ~ " ,V ors o n - > il , DCke t , D t b lty C m e t e e o D a't# :

3126 ASTM ASTM A708 1974 Recommended Practice for regl.84.r30 1994 P Discontinued in n/a n/a

Detection of Susceptibility to 1989

Intergranular Corrosion in SeverelySensitized Austenitic StainlessSteel

3127 A ASTM AS708 Recommended Practice for srp4.5.1 1981 p Discontinued in n/a n/a

Detection of Susceptibility to 1989

.ntergranular Corrosion in SeverelySensitized Austenitic StainlessSteel

3128 ASTM ASTM 872 1976 Not found regl ,85.r30 19W94 R Discontinued n/a n/a

3129 ASTM ASTM C29 N/S Standard Test Method for Unit inm46051 1983 R ASTM 1991

Weight and Voids in Aggregate C29/C29M Rev

(AASHTO T 19) A

3130 ASTM ASTM C31 NIS Standard Practice for Making and inm46051 1983 R ASTM C31 1991

Curing Concrete Test Specimens

in th e F ield__ _ _ _ _ _ ___ _ _ _ _ _

3131 ASTM ASTM C39 N/S Standard Test Method for inm46051 1983 R ASTM C39 Rev 1994

Compressive Strength of A

Cylindrical Concrete Specimens(AASHTO No. T22)

3132 ASTM ASTM C40 N/S Standard Test Method for Organic inm46051 1983 R ASTM C40 1992

Impurities in Fine Aggregates for

Concrete (AASHTO No. T21)

3133 ASTM ASTM C78 N/S Standard Test Method for Flexural inm46051 1983 R ASTM C78 1994

Strength of Concrete (Using

Simple Beam with Third-Point

Loading) (AASHTO No. T97)

3134 ASTM ASTM 0 N/S Standard Test Method for inm46051 1983 R ASTM C88 1990

Soundness of Aggregates by Use

of Sodium Sulfate or Magnesium

Sulfate l


......... ... : .. 4X0 t 0RodStdard Do. Acot Ltst Stanidard L040s Veso

Ni'.' Co Sna .VE in Tit 'o t .: , "Com m't Vrsion Date3135 ASTM ASTM C109 N/S Standard Test Method for inm46051 1983 R ASTM C109 1995

Compressive Strength ofHydraulic Cement Mortars (Using2-in, or 50 mm Cube Specimens)

3136 ASTM ASTM C1O9 1973 Standard Test Method for regl.107.rOl 1977 R ASTM C109 1995Compressive Strength ofHydraulic Cement Mortars (Using2-in. or 50 mm Cube Specimens)

3137 ASTM ASTM C1 14 N/S Standard Test Methods for inm46051 1983 R ASTM C114 1994Chemical Analysis of HydraulicCement

3138 ASTM ASTM C115 N/S Standard Test Method for inm46051 1983 R ASTM C115 1994Fineness of Portland Cement bythe Turbidimeter _

3139 ASTM ASTM C117 N/S Standard Test Method for inm46051 1983 R ASTM C 17 1995Materials Finer Than 75-Micrometer (No. 200) Sieve inMineral Aggregates by Washing

3140 ASTM ASTM C123 N/S Standard Test Method for inm46051 1983 R ASTM C123 1994Lightweight Pieces in Aggregate(AASHTO No. T113)

3141 ASTM ASTM C127 N/S Standard Test Method for Specific inm46051 1983 R ASTM C127 1988 R93Gravity and Absorption of CoarseAggregate

3142 ASTM ASTM C128 N/S Standard Test Method for Specific inm46051 1983 R ASTM C128 1993Gravity and Absorption of Fine

_ __ Aggregate

z

~0

(!h

z

(pI

Cj3



Re ordd D e- L t Sdard Latit Veivaledi

:No. :C de Stand ard ei:- -rsle Doum n Date a t intVron DaJte

3143 ASTM ASTM C131 N/S Standard Test Method for inm4605 1 1983 R ASTM 0131 1989

Resistance to Degradation ofSmall- Size Coarse Aggregate byAbrasion and Impact in the LosAngeles Machine

3144 ASTM ASTM C136 N/S Standard Test Method for Sieve inm46051 1983 R ASTM C136 1995

Analysis of Fine and CoarseAggregates

3145 ASTM ASTM C138 N/S Standard Test Method for Unit inm46051 1983 R ASTM C1 38 1992

Weight, Yield, and Air Content(Gravirnietric) of Concrete(AASHTO No. T 121)

3146 ASTM ASTM C142 N/S Standard Test Method for Clay inm46051 1983 R ASTM C142 1978 R90

Lumps and Friable Particles inAggregates (AASHTO No. Ti 12)

3147 ASTM ASTM C143 N/S Standard Test Method for Slump inm46051 1983 R ASTM C143 1990

of Hydraulic Cement Concrete Rev A

3148 ASTM ASTM C157 N/S Standard Test Method for Length inm46051 1983 R ASTIM C157 1993

Change of Hardened Hydraulic-Cement Mortar and Concrete

3149 ASTM ATM C172 NiS Standard Practice for Sampling inm46051 1983 R ASTM C172 1990

Freshly Mixed Concrete

3150 ASTM ASTM C173 N/S Standard Test Method for Air inm46051 1983 R ASTM C173 1994

Content of Freshly Mixed Rev A

Concrete by the VolumetricMethod

3151 ASTM ASTM C191 N/S Standard Test Method for Time of inm46051 1983 R ASTM C191 1992

Setting of Hydraulic Cement byVicat Needle


Etcr 5trdr o. Acp- LaetStandar Latt Verio

3152 ASTM ASTM C191 1974 Standard Test Method for Time of regl.107.rOl 1977 P Implied ASTM C191 1992

Setting of Hydraulic Cement by endorsementVicat Needle

3153 ASTM ASTM C192 N/S Standard Practice for Making and inm46051 1983 R ASTM C192 1990

Curing Concrete Test Specimens Rev A

in the Laboratory

3154 ASTM ASTM C204 N/S Standard Test Method for inm46051 1983 R ASTM C204 1994

Fineness of Hydraulic Cement by

Air Permeability Apparatus(AASHTO No. T1 53)

3155 ASTM ASTM C231 N/S Standard Test Method for Air inm46051 1983 R ASTM C231 1991

Content of Freshly Mixed Rev B

Concrete by the Pressure Method

3156 ASTM ASTM C235 N/S Not Found inm46051 1983 R Replaced by n/a n/aASTM C851which hasbeendiscontinued

3157 ASTM ASTM C260 1974 Standard Specifications for Air regl .107.rO1 1977 R ASTM C260 1995

Entraining Admixtures forConcrete

3158 ASTM ASTM C266 N/S Standard Test Method for Time of inm46051 1983 R ASTM C266 1989 R95

Setting of Hydraulic-Cement Pasteby Gillmore Needles


Potential Alkali-Silica Reactivity ofAggregates (Chemical Method)

3160 ASTM ASTM C311 N/S Standard Test Methods for inm46051 1983 R ASTM 1994

Sampling and Testing Fly Ash or C311 Rev A

Natural Pozzolans for Use as a

Mineral Admixture in Portland-

Cement Concrete

w

z

(15

z

-4

CD

I,



RecoS r Latettndard Watt Veri io

o.Code Standard !:V ersionTil Docum ent Date Obtiy Cott Ve (ionD t


Fineness of Hydraulic Cement bythe 45-Micrometer (No. 325)Sieve__

_ _ _ _ _


Effectiveness of MineralAdmixtures or Ground Blast-Furnace Slag in PreventingExcessive Expansion of ConcreteDue to the Alkali-Silica Reaction

3163 ASTM ASTM C469 N/S Standard Test Method for Static inm46051 1983 R ASTM C469 1994

Modulus of Elasticity andPoisson's Ratio of Concrete inCompression _ _ _ _ _ _ _


Splitting Tensile Strength ofCylindrical Concrete Specimens

3165 ASTM ASTM C512 N/S Standard Test Method for Creep inm46051 1983 R_ ASTM C512 1987 R94

of Concrete in Compression

3166 ASTM ASTM C512 1976 Standard Test Method for Creep regl.35.1.rOO 1990 R1 ASTM C512 1987 R94

of Concrete in Compression


Resistance to Degradation ofLarge- Size Coarse Aggregate byAbrasion and Impact in the LosAngeles Machine

3168 ASTM ASTM C566 N/S Standard Test Method for Total inm46051 1983 R ASTM 0566 1995

Moisture Content of Aggregate byDrying _ _ _ _

3169 ASTM ASTM C597 1971 Standard Test Method for Pulse regl.90.rOl 1977 R. ASTM C597 1983 R91

Velocity Through Concrete


Ncd. tadar eriiTil t00urnn ae. bfly<..Cmehs.,'Vrn Date

3170 ASTM ASTM C642 N/S Standard Test Method for Specific inm46051 1983 R ASTM C642 1990Gravity, Absorption, and Voids inHardened Concrete

3171 ASTM ASTM C692 1971 Standard Test Method for regl.36.rOO 1973 A ASTM C692 1990Evaluating the Influence of Rev AThermal Insulations on theExternal Stress Corrosion CrackingTendency of Austenitic StainlessSteel

3172 ASTM ASTM C696 1972 Methods for Chemical, Mass reg5.5.rOO 1972 A ASTM C696 1993Spectrometric, andSpectrochemical Analysis ofNuclear-Grade Uranium DioxidePowders and Pellets

3173 ASTM ASTM C799 N/S Standard Methods for Chemical, reg5.39.rOO 1974 P Subject to ASTM C799 1993Mass Spectrometric, conditionsSpectrochemical, Nuclear, andRadiochemical Analysis of NuclearGrade Uranyl Nitrate Solutions

3174 ASTM ASTM C853 1979 Nondestructive Assay of Special reg5.1 1.rO1 1984 R Discontinued in n/a n/aNuclear Materials Contained in 1992Scrap and Waste

3175 ASTM ASTM C853 1979 Nondestructive Assay of Special reg5.34.rOl 1984 R Discontinued in Withdrawn n/aNuclear Materials Contained in 1992Scrap and Waste

3176 ASTM ASTM C883 N/S Standard Test Method for not83-40 1983 R ASTM C883 1989Effective Shrinkage of Epoxy-Resin Systems Used WithConcrete ____

U'

z

C)

-4

(5

0'V



R e c r dS t ndd D "A c c p - a O t n d r L t s V e s io n

N o o eS a d r V r i nT t eD c um ~ ft D a..bli y C o iw me n ts ' V e slo n . .. D a ..

3177 ASTM ASTM C884 N/S Standard Test Method for Thermal not83-40 1983 R ASTM C884 1992

Compatibility Between Concreteand an Epoxy-Resin Overlay

3178 ASTM ASTM D95 N/S Standard Test Method for Water regi.35.rO3 1990 A ASTM D95 1983 R90

in Petroleum Products andBituminous Materials byDistillation

3179 ASTM ASTM D270 1975 Standard Method for Manual git83-026 1983 P Implied ASTM D4057 1988

Sampling of Petroleum and endorsement

Petroleum Products

3180 ASTM ASTM D270 1975 Standard Method for Manual regl.137.rOl 1979 A ASTM D4057 1988

Sampling of Petroleum andPetroleum Products

3181 ASTM ASTM D421 N/S Standard Practice for Dry reg1.138.rOO 1978 P Implied ASTM D421 1985 R93

Preparation of Soil Samples for endorsement

Particle-Size Analysis andDetermination of Soil Constants

3182 ASTM ASTM D422 N/S Standard Test Method for Particle- inm45053 1984 R ASTM D422 1963 R90

Size Analysis of Soils _ _

3183 ASTM ASTM D422 N/S Standard Test Method for Particle- regl.138.rOO 1978 P Implied ASTM 0422 1963 R90

Size Analysis of Soils endorsement

3184 ASTM ASTM D423 N/S Standard Test Method for Liquid inm45053 1984 8R ASTM D4318 1995

Limit, Plastic Limit, and PlasticityIndex of Soils

3185 ASTM ASTM D423 N/S Standard Test Method for Liquid reg1.1 38.rOO 1978 P Implied ASTM D4318 1995

Limit, Plastic Limit, and Plasticity endorsement

Index of Soils

3186 ASTM ASTM D424 N/S Standard Test Method for Liquid inm45053 1984 R ASTM D4318 1995

Limit, Plastic Limit, and PlasticityIndex of Soils

3187 ASTM ASTM 0424 NIS Standard Test Method for Liquid regi1.1 38.rOO 1978 P Implied ASTM D4318 1995

Limit, Plastic Limit, and Plasticity endorsement

Index of Soils


bort Ld03 t. D - Lafte ti Stndard Late.t Version

3188 ASTM ASTM D427 N/S Standard Test Method for regl.138.rOO 1978 P Implied ASTM D427 1993Shrinkage Factor of Soils by the endorsementMercury Method

3189 ASTM ASTM D511 1982 Standard Test Methods for inm79501 1989 R _ ASTM D511 1993Calcium and Magnesium in Water

3190 ASTM ASTM D512 N/S Standard Test Methods for inm46051 1983 R ASTM D512 1989 R94Chloride ton in Water

3191 ASTM ASTM D512 1981 Standard Test Methods for inm79501 1989 R ASTM D512 1989 R94Chloride Ion in Water

3192 ASTM ASTM D512 1967 Standard Test Methods for regl.107.rOl 1977 R ASTM D512 1989 R94Chloride Ion in Water

3193 ASTM ASTM D512 NIS Standard Test Methods for regl.35.rO3 1990 A ASTM D512 1989 R94Chloride Ion in Water

3194 ASTM ASTM D512 NIS Standard Test Methods for reg1.36.rOO 1973 P Implied ASTM D512 1989 R94Chloride Ion in Water endorsement _ _

3195 ASTM ASTM D513 1982 Standard Test Methods for Total inm79501 1989 R ASTM D513 1992and Dissolved Carbon Dioxide inWater X

3196 ASTM ASTM D514 1980 Standard Test Method for inm79501 1989 R ASTM D514 1985 R89Hydroxide ton in Water __

3197 ASTM ASTM D515 1982 Standard Test Methods for inm79501 1989 R ASTM D515 1988Phosphorus in Water

3198 ASTM ASTM 0516 1980 Standard Test Method for Sulfate inm79501 1989 R ASTM D516 1990 R95Ion in Water

3199 ASTM ASTM D516 1974 Standard Test Method for Sulfate regl.107.rOl 1977 R ASTM D516 1990 R95Ion in Water

3200 ASTM ASTM D543 1967 Standard Test Method for reg5.10.rOO 1973 P Implied ASTM D543 1987Resistance of Plastics to Chemical endorsementReagents

3201 ASTM ASTM D596 1983 Standard Method of Reporting inm79501 1989 - ASTM D596 1991Results of Analysis of Water

3202 ASTM ASTM D596 1974 Standard Method of Reporting regl.107.rOl 1977 R ASTM D596 1991 -

Results of Analysis of Water

z

'0

;V~

z

0

qt!hko

Iw

w

I

W


Part A - Industry Consensus Codes and Standards, ,; .. .. .. .. ...\_ _ _ _ _-__ _..._ _ r rLatest Stndard Laes Vrs~X on

30Record

3203 ASTM.Standard

ASTM 0698

Standard ," ,,�;4 ,oi ��:: :,:ix....

It Z,� ",,� , "', . � �' , ; - .'�n ,, , '� ";.� " :,:, I

1. :%..: .,?. . .:: , .1 , :

- C - �� X . . . .

Dc.I

:. t, ., .

Accel...:~� � :. � . � "i , "' �,,, " ",, . . , i- : : �z � :!� . . .. ... .- . , � t� � :, , � ':

; fli�iikir"iik

V~ersiondd Wia W66i

VI ,raer j. - m 1i . uai 4. -lrA1A4 _R_ t 99§eg1., .rU I%#ato I I flPJ6t

N/S

_ _ _ _ _ L4 1 I _3204 ASTM ASTM D698 1 WU8

320 I ASTM IASTM D-6-98 N/S

Test Method for LaboratoryCompaction Characteristics of SoilUsing Standard Effort (12,400 ft-Ibflft)Test Method for LaboratoryCompaction Characteristics of SoilUsing Standard Effort (12,400 ft-lbf/ft)Test Method for LaboratoryCompaction Characteristics of SoilUsing Standard Effort (12,400 ft-

lbf/ft)Standard Test Method for SpecificGravity of SoilsStandard Test Method forAluminum in WaterStandard Test Method for Silica inWaterStandard Practices for SamplingWater-Formed Deposits

reg3.64.rOO 1 98g P Impliedendorsement

ASTIM U6UV lY:zF

reg I I 38.rou lb/o1 r-endorsement

s, . .w. _w

R-- Mb-- 7 I M UOt

i1nm45053

Froegi.18.roo

1984 R AZ) I M LUtj20 I ~O I

_ _ _ _ _ _ _ _ _ _ _p_a ..4.0 1989rt 1t

I I ._.. - A 4I ---

00

3206

3207

3208

3209

3210

32 1

3212

3213

3214

3215

ASTM

ASTM

AST

ASTM

ASTMASTM

ASTM D854

ASTM D857

ASTM D859

ASTM 0887

N/S

1979

1980

1982

1 9 7-8 Implied f~fl ASTM D8354

I I~Tnu7 fRin79i 1 t i 31ATAnA7 I 8inm79501 1 98Yu 1`1 -i; . v -Ju - '-

I YYZ1

I I I-~ t1 --- I I1Q-_Ii no _ . I A VI1 F t3JJ

inm79501198Y H MO II. _- o07;

I _ __ I I i..--. 4- _t -1989 R ASTM D887 I? UZ)

_ I____ I I- .. ASTM D888 | 1992

- - -- - . .6 _.ri I 2U 4 # IM i ,---1 9 M

ASTl

ASTI

M D88 1981 Standard Test MetnOas Tor HMI mu~uv I -

| IDissolved Oxygen in Water Q 4 ... A tATM nQl7A 1 15S. .re.M 0974

ASTM ASTM D9751

___STM ASTM D975

ASTM ASTM D975

ASTM ASTM D975

N/S

1977

1968

Standard Test Method for Acidand Base Number by Color-Indicator TitrationStandard Specification for DieselFuel Oils

Stnad Specification for Diesel

reg I;s 3z.ruo3 *U,7v. . _ -- I ..... . -1 . .. - I -. -

I I 1.I ________1994

git83-026 1983 PASTMV ID975l

1 UV4

I I94 -2 2 1994 II ~A WFr Qn ot94-22 t1994 R MO~v I &I M-

N/�

NI�

Fuel Oils 1_ _ _1 9Standard Specification for Diesel sts4-geB3.8.3 1992 P ASTM 0975 1994

Fuel Oils 1 11 _ _ _ _ _ _ _

S Standard Specification for Diesel sts6 ge83.8.3 1992 P ASTM 0975 1994

_ Fuel Oils ,, ,_ __ _ _19_2 _ , _ _ ASTM D975 1994r~ rv vv vFuelO - _ls

.-N/S Standard Specification for Diesel

Fuel Oilss1:sb&wf3J.8.J 1 YY4Z r, __ I - __ - -

I _ _ _ _ _ _


sRtandard De d ateAt VersIon

No dod' Standard Ve's....Title ocument Dae aoiy Cnmns Vrsion Dat

3217 ASTM ASTM D975 N/S Standard Specification for Diesel stsceB3.8.3 1992 P ASTM D975 1994

Fuel Oils

3218 ASTM ASTM D976 N/S Standard Specification for Diesel stswstB3.8.3 1992 P ASTM D975 1994Fuel Oils

3219 ASTM ASTM D992 1971 Standard Test Methods for Nitrite- regl.107.rOl 1977 R ASTM D3867 1990Nitrate in Water

3220 ASTM ASTM D992 N/S Standard Test Methods for Nitrite- regI.35.r03 1990 R ASTM D3867 1990

Nitrate in Water

3221 ASTM ASTM 1982 Standard Practice for Sampling inm79501 1989 R ASTM D1066 1982 R90

D1066 Steam

3222 ASTM ASTM 1982 Standard Test Methods for Acidity inm79501 1989 R ASTM D1067 1992

D1067 or Alkalinity of Water

3223 ASTM ASTM 1984 Standard Test Methods for Iron in inm79501 1989 R ASTM D1068 1990

D1068 Water3224 ASTM ASTM 1982 Standard Test Methods for inm79501 1989 R ASTM D1125 1991

D1125 Electrical Conductivity andResistivity of Water

3225 ASTM ASTM 1980 Standard Test Method for inm79501 1989 R ASTM D1126 1986 R92

01126 Hardness in Water

3226 ASTM ASTM 1982 Standard Terminology Relating to inm79501 1989 R ASTM D1129 1990 R95

1129 Water

3227 ASTM ASTM 1974 Standard Terminology Relating to regl.107.rOl 1977 R ASTM D1129 1990 R95

01129 _._._Water

3228 ASTM ASTM N/S Standard Test Method for Amount inm45053 1984 R ASTM D1140 1992

D1140 of Material in Soils Finer than theNo. 200 (75 Micrometer) Sieve

3229 ASTM ASTM N/S Standard Test Method for Amount regl.138.rOO 1978 P Implied ASTM D1140 1992

D1140 of Material in Soils Finer than the endorsementNo. 200 (75 Micrometer) Sieve

3230 ASTM ASTM N/S Standard Test Method for Piles inm45053 1984 R ASTM D1143 1981 R94

D1143 Under Static Axial CompressiveLoad

3231 ASTM ASTM 1980 Standard Test Methods for inm79501 1989 R ASTM D1179 1993

D1179 Fluoride Ion in Water

z

t./I

(5

z

'0

(a

%0



Rewd Sand:d D. Ace- Latest Stanar Lte A - ion

No Cd-e StandDdu nntVerton- Ttle uen Dt Iiity t D .

3232 ASTM ASTM N/S Standard Test Methods for regi.36.rOO 1973 P Implied ASTM 01179 1993

D1179 Fluoride Ion in Water endorsement

3233 ASTM ASTM 1982 Standard Test Method for Bromide inm79501 1989 R ASTM D1246 1988 R95

D1246 Ion in Water

3234 ASTM ASTM N/S Standard Test Method for Gage inm45053 1984 R ASTM D1267 1995

D1267 Vapor Pressure of LiquefiedPetroleum (LP) Gases (LP-GasMethod) _

3235 ASTM ASTM 1978 Standard Test Methods for pH of inm79501 1989 R ASTM D1293 1995

D1293 Water

3236 ASTM ASTM 1965 Standard Test Methods for pH of regl.107.rOl 1977 R ASTM D1293 1995

D1293 Water

3237 ASTM ASTM 1978 Test Methods for Sulfite in Water inm79501 1989 R Discontinued n/a n/a

01339

3238 ASTM ASTM 1978 Standard Test Method for inm79501 1989 R ASTM D1385 1988 R91

D1385 Hydrazine In Water

3239 j ASTM ASTM 1982 Standard Test Method for inm79501 1989 R ASTM D1385 1988 R91

01385 Hydrazine in Water

3240 ASTM ASTM N/S Standard Test Methods for Water inm46051 1983 R ASTM D1411 1993

D1411 Soluble Chlorides Present asAdmixes in Graded AggregateRoad Mixes

3241 ASTM ASTM 1982 Test Methods for Sodium and inm79501 1989 R Discontinued n/a

D1428 Potassium in Water and WaterFormed Deposits by FlamePhotometry

3242 ASTM ASTM N/S Standard Test Method for Length reg .138.rOO 1978 P Implied ASTM D1440 1990

D1440 and Length Distribution of Cotton endorsement

Fibers (Array Method)


R0' ecord'> St;Thdard Doe.:.A,.-pt-""-.,i,'Latest Standard Latest Versio

- ;*No- .Code -r .. ..D Dt abbetti ts esion . Date

3243 ASTM ASTM N/S Misc. - See Comments sts4-ge83.8.3 1992 P Discontinued - See Comments Misc.

D1522 replaced byASTM D3181,D3182,D3183,D3184,D3185.D3186,03188,D3190, &D3192

3244 ASTM ASTM N/S Misc. - See Comments sts6-geB3.8.3 1992 P Discontinued - See Comments Misc.D1522 replaced by

ASTM D3181,D3182,03183,03184,03185,D3186,03188,D3190, &D3192

3245 ASTM ASTM N/S Misc. - See Comments stsb&w83.8.3 1992 P Discontinued - See Comments Misc.D1522 replaced by

ASTM D3181,D3182,D3183,03184,03185,03186,D3188,D3190, &D3192

C-.

~0Mb

z

t')



Reo Sandaid tDc. A pLa0t Standard LateEt ersio

N o.; ~ C o d St i and rd Version T teD u m nD te a i ty C m n sVersion ,- at

3246 ASTM ASTM N/S Misc. - See Comments stsceB3.8.3 1992 P Discontinued - See Comments Misc.

D1522 replaced byASTM D3181,D3182,D3183,D3184,031 85,0D3186.D3188,D3190, &D3192

3247 ASTM ASTM N/S Misc. - See Comments stswstB3.8.3 1992 P Discontinued - See Comments Misc.

D1522 replaced byASTM 03181,D3182,03183,03184,03185,03186,03188,03190, &D3192

328 ASTM ASTM N/S Standard Test Method for Density inm28620 1993 R ASTM 01556 1990

D1556 and Unit Weight of Soil in Placeby the Sand-Cone Method

3249 ASTM ASMN/S Test Method for Laboratory inm45053 1984 R ASTMV 01 557 1991

01557 Compaction Characteristics of SoilUsing Modified Effort (56,000 ft-Ibf (2700 kN-mImU)

3250 ASTM ASTM N/S Test Method for Laboratory reg1.138.rOO 1978 P Implied ASTM D1557 1991

D1557 Compaction Characteristics of Soil endorsement

Using -Modified Effort (56,000 ft-Ibf (2700 kN-m/m)) __ __ _


-ecordr St d D-i; D.: Ltt Sadr Lts VErEio:

No. od Stnad VrinTte ouet Dt blt C -m t VerionDate3251 ASTM ASTM N/S Standard Test Method for inm45053 1984 R ASTM D1586 1984 R92

D1586 Penetration Test and Split-Barrel__ _ Sampling of Soils __

3252 ASTM ASTM 1967 Standard Practice for Thin-Walled regI.132.rO1 1979 P Implied ASTM D1587 1994

D1587 Tube Geotechnical Sampling of endorsementSoils

3253 ASTM ASTM .1960 Not Found inm79501 1989 8 Discontinued n/a na

D15883254 ASTM ASTM 1974 Not Found inm79501 1989 R Discontinued na n/a

D15883255 ASTM ASTM 1974 Standard Test Method for Short- reg1.72.r02 1978 P Implied ASTM D1599 1988

D1599 Time Hydraulic Failure Pressure of endorsementPlastic Pipe, Tubing, and Fittings

3256 ASTM ASTM 1980 Standard Test Methods for inm79501 1989 R ASTM D1687 1992

D1687 Chromium in Water

3257 ASTM ASTM 1982 Standard Test Methods for Copper inm79501 1989 R ASTM D1688 1995

D1688 in Water __. _.

3258 ASTM ASTM 1977 Standard Test Methods for Zinc in inm79501 1989 R ASTM D1691 1995

D1691 Water3259 ASTM ASTM 1984 Standard Test Methods for Nickel inm79501 1989 R ASTM D1886 1994

D1886 in Water3260 ASTM ASTM N/S Tests for Particulate and Dissolved inm46051 1983 R Discontinued n/an/a

D1888 Matter, Solids or Residue in Water

3261 ASTM ASTM 1978 Tests for Particulate and Dissolved inm79501 1989 R Discontinued n/a n/a


3262 ASTM ASTM 1978 Tests for Particulate and Dissolved not94-19 1994 R Discontinued n/a n/a


3263 ASTM ASTM 1981 Standard Test Methods for inm79501 1989 R AST-M D1889 1994

D1889 Turbidity of Water

3264 ASTM ASTM N/S Standard Test Method for Ignition g1t86-010.sOl 1994 R ASTM D1929 1991

D1929 Properties of Plastics Rev. A

z(19C.

(5)



A ec td.- S and rd' D e. A c ept Ltei t St tanda id L atest V ersi'on

C o de | t; 0 l S ta nd ard |e s o 'Title. D o u m nt D ate ability C o. :m rtesit . . V ers o n D t

3265 ASTM ASTM N/S Standard Test Methods for reg 1.1 38.rOO 1978 P Discontinued - ASTM D4253 & 1993/ 1 991

D2049 Maximum Index Density and Unit replaced by D4254

Weight of Soils Using Vibratory ASTM D4253

Tables & D4254

3266 ASTM ASTM N/S Standard Test Method for reg 1.1 38.rOO 1978 P Implied ASTM D2166 1991

D2166 Unconfined Compressive Strength endorsement

of Cohesive Soil

3267 ASTM ASTM N/S Standard Test Method for Density inm45053 1984 R ASTM D2167 1994

D2167 and Unit Weight of Soil in Placeby the Rubber Balloon Method

3268 ASTM ASTM 1982 Standard Test Methods for inm79501 1989 B ASTM D2187 1994

D2187 Physical and Chemical Propertiesof Particulate lan-Exchange Resins

3269 ASTM ASTM 1971 Standard Test Methods for reg1.56.rO1 1978 P Paragraphs 41- ASTM D2187 1994

D2187 Physical and Chemical Properties 49

of Particulate Ion-Exchange Resins

3270 ASTM ASTM N/S Standard Test Method for inm45053 1984 R ASTM D2216 1992

D2216 Laboratory Determination ofWater (Moisture) Content of Soiland Rock

3271 ASTM ASTM N/S Standard Test Method for reg1.138.rOO 1978 P Implied ASTM D2216 1992

D2216 Laboratory Determination of endorsementWater (Moisture) Content of Soila n d R o ck_ _ _ _ _ _ _ _ _ _ __ _ _ _ _ _

3272 ASTM ASTM N/S Standard Practice for Wet reg1.1 38.rOO 1978 P Implied ASTM D2217 1985 R93

D2217 Preparation of Soil Samples for endorsementParticle-Size Analysis andDetermination of Soil Constants

3273 ASTM ASTMIV 1970 Standard Test Method for git83-026 1983 P Implied ASTM D2274 1994

D2274 Oxidation Stability of Distillate endorsement

Fuel Oil (Accelerated Method)


c Stn d .,.'. Doc. Aicept i Laes St.i.ari Lt2 Version

3274 ASTM ASTM 1970 Standard Test Method for not91-46 1991 R ASTM D2274 1994

D2274 Oxidation Stability of DistillateFuel Oil lAccelarated Method)

3275 ASTM ASTM 1978 Standard Test Method for not91-46 1991 P ASTM D2276 1995

D2276 Particulate Contaminant in Rev AAviation Fuel by Line Sampling

3276 ASTM ASTM N/S Standard Test Method for sts4-ge5.7.2.15 1992 P ASTM D2276 1995


3277 ASTM ASTM N/S Standard Test Method for sts4-ge83.8.3 1992 P ASTM D2276 1995


3278 ASTM ASTM N/S Standard Test Method for sts6-geB3.8.3 1992 P ASTM 02276 1995


3279 ASTM ASTM N/S Standard Test Method for sts6-ge5.7.2.13 1992 P ASTM D2276 1995


3280 ASTM ASTM N/S Standard Test Method for stsb&wB3.8.3 1992 P ASTM D2276 1995


3281 ASTM ASTM N/S Standard Test Method for stsb&w5.7.2.15 1992 P ASTM D2276 1995


3282 ASTM ASTM N/S Standard Test Method for stsceB3.8.3 1992 P ASTM D2276 1995


tA)

z

A-

z

Potz0Q0;Vt�l�0-4LI)

M

w

w4�.-ON



|o d D c A ttSt d ard L atest V rs|ion

cocdT ParticulDat C n meant C e R ev D

3283 ASTM ASTM N/S Standard Test Method for stsce5.7.2.1 5 1992 P ASTM 02276 1995Rev A

D2276 Particulate Contaminant inAviation Fuel by Line Sampling

3284 ASTM ASTM NIS Standard Test Method for stswstB3..23 1992 P ASTM D2276 1995

D2276 Particulate Contaminant in Rev A

Aviation Fuel by Line Sampling

3285 ASTM ASTM N/S Standard Test Method for stswst5.7.2. 15 1992 P ASTM 02276 1995

02276 Particulate Contaminant inReAAviation Fuel by Line Sampling

3286 ASTM ASTM N/S Test Method for Permeability of regl.138.rOO 1978 P Implied ASTM D2434 1968 R94

D2434 Granular Soils (Constant Head) endorsement

3287 ASTM ASTM N/S Standard Test Method for One- regil .138.rOO 1978 P Implied ASTM D2435 1990

D2435 Dimensional Consolidation endorsementProperties of Soils

3288 ASTM ASTM N/S Standard Classification of Soils for inm45053 1984 R ASTM D2487 1993

D2487 Engineering Purposes (Unified SoilClassification System)

3289 ASTM ASTM N/S Standard Classification of Soils for regl.138.rOO 1978 P Implied ATM 2487 1993

D2487 Engineering Purposes (Unified Soil endorsement

Classification System)

3290 ASTM N/S Standard Practice for Description reg1.138.rOO 1978 P Implied ASTM D2488 1993

D2488 and Identification of Soils (Visual- endorsement

Manual Procedure)

3291 ASTM ASTM 1978 anard Test Methods for Total inm79501 1989 R ASTM 02579 1993

D2579 and Organic Carbon in Water


: i ej o rd S : ;:: f.-e ........ - : ¢ 05 ... E ;i : ::: ...... : . .: .:: :. :.. : - ;:. :E.i ? iR itEidad .ii -... . A - Latesto Stiad: ::ed Ldatest Vislon~No. code~i Standard Veso il ouet Dt biiy Cnmns VrinDt

3292 ASTM ASTM N/S Standard Test Method for Sulfur stsb&wB3.8.3 1992 P ASTM D2622 1994D2622 in Petroleum Products by X-Ray

3293______ A Spectrometry.3293 ASTM ASTM N/S Standard Test Method for Sulfur stsceB3.8.3 1992 P ASTM D2622 1994

D2622 in Petroleum Products by X-RayASTM___T____Spectrometry

3294 ASTM ASTM NIS Standard Test Method for Sulfur sts4-geB3.8.3 1992 P ASTM D2622 1994D2622 in Petroleum Products by X-Ray

Spectrometry3295 ASTM ASTM N/S Standard Test Method for Sulfur sts6-geB3.8.3 1992 P ASTM D2622 1994

D2622 in Petroleum Products by X-RaySpectrometry _ _ _ _ _ _ _ __ _ _ _ _ _ _

3296 ASTM ASTM N/S Standard Test Method for Sulfur stswstB3.8.3 1992 P ASTM 02622 199402622 in Petroleum Products by X-Ray

Spectrometry___ _____

3297 ASTM ASTM N/S Standard Test Method for Triaxial regl,138.rOO 1978 P Implied ASTM D2664 1986 R95

D2664 Compressive Strength of endorsementUndrained Rock Core SpecimensWithout Pore PressureMeasurements

3298 ASTM ASTM 1984 Standard Practices for Sampling inm79501 1989 R ASTM D2687 1995

D2687 Particulate Ion-Exchange Materials

3299 ASTM ASTM 1983 Standard Test Methods for inm79501 1989 R ASTM D2688 1994D2688 Corrosivity of Water in the

Absence of Heat Transfer (WeightLoss Methods)

3300 ASTM ASTM 1972 Standard Practice for drgesl 14.rOO 1983 R ASTM D2777 1986 R94D2777 Determination of Precision and

Bias of Applicable Methods ofCommittee D-19 on Water

I_ A __

4.,.

(1~

-3

q)

cr)

;P



331 STM SseTM^* 1 977 Standard Practice fatr | nm7950l 198 | SM 27 1598 R94;

02777 Determination of Precision andBias of Applicable Methods ofCommittee D-19 on Water

3302 ASTM ASTM 1977 Standard Test Method for inm79S0l 1 989 A S 029 1993

02791 Continuous Determination of

Sodum n Wte

3303 ASTM ASTM NIS Standard Tatie for reg.138.rOO 1978 P Implied ASTM D2845 1990

D2845 Laboratory Determination of Pulse endorsementVelocities and Ultrasonic Elastic

334ASTM 751ASTM D279_re113 oImld 95

0 2850 Unconsolidated, Undrained endorsement

Comprehensive Strength ofCohesive Soils in Triaxial

3303 ASTM ASTM I970 Standard Test Method for reg'.1 40.rOl 1979 P Implied ASTM D2854 1989 R93

D2854 Apparent Density of Activated endorsement

CaronstantsofRock

3306 ASTM ASTM 1970 Standard Test Method for reg5.10.rOO 1973 P Implied ASTM D2860 1990 R94

D2860 Adhesion of Pressure-Sensitive endorsement

Tape to Fiberboard at 90 DegreeAngle and Constant Stress l

3307 ASTM ASTM 1970 Standard Test Method for Particlergl .140.rOl 1979 A _ ASTM D2862 19892

D2862 Size Distribution of Granular

ACtiater arobon____

3308 ASTM ASTM NIS Standard Test Methods for rnm45053 1984 R _ ASTM D0922 1991

D2022 Density of Soil and Soil-Aggregate .

in Place by Nuclear MSthods{Shallow Depth)

_ .hdfrari Iel_ ,sT D26 1992

00


FtodSadrdDc cet Latest Staniidard Latest Ve~rsio; - tiNo. C - Sanr :-Verion Tiile documeyn. bf . o Verif. bate

3309 ASTM ASTM N/S Standard Test Method for Direct reg1.138.r00 1978 P Implied ASTM D2936 1995D2936 Tensile Strength of Intact Rock endorsement

Core Specimens3310 ASTM ASTM N/S Standard Test Method for Density inm45053 1984 R ASTM D2937 1994

D2937 of Soil in Place by the Drive-Cylinder Method

3311 ASTM ASTM N/S Standard Test Method for regl.138.rOO 1978 P Implied ASTM D2938 1986D2938 Unconfined Compressive Strength endorsement

of Intact Rock Core Specimens

3312 ASTM ASTM N/S Test Methods for Moisture, Ash, regl.138.rOO 1978 P implied ASTM D2974 1987 R9502974 and Organic Matter of Peat and endorsement

Other Organic Soils3313 ASTM ASTM N/S Standard Practice for Obtaining regl.72.rO2 1978 R ASTM D2992 1991

D2992 Hydrostatic or Pressure DesignBasis for 'Fiberglass' (Glass-Fiber-Reinforced-Thermosetting Resin)Pipe and Fittings

3314 ASTM ASTM N/S Standard Test Methodfor Direct regl.138.rOO 1978 P Implied ASTM D3080 199003080 Shear Test of Soils Under endorsement

Consolidated Drained Conditions

3315 ASTM ASTM 1979 Standard Test Method for Boron inm79501 1989 R ASTM D3082 1992D3082 in Water

3316 ASTM ASTM N/S Standard Test Method for Gross glt86-010.sOl 1994 R ASTM D3286 1991D3286 Calorific Value of Coal and Coke Rev. A

by the Isoperibol BombCalorimeter

3317 ASTM ASTM 1973 Standard Test Method for Gross reg1.120.rOl 1977 P Implied ASTM D3286 1991D3286 Calorific Value of Coal and Coke endorsement Rev A

by the Isoperibol BombCalorimeter _ _.__ _ _

4~-.'0

%0'-4

z

~0



331 ASTM ASTM 1973 Standard-Test Method for Gross srp9.5.1 1981 R ASTM 03286 1991

D3286 Calorific Value of Coal and Coke Rev A

by the Isoperibol BombCalorimeter

3319 ASTM ASTM 1982 Standard Practices for Sampling inm79501 1989 R ASTM D3370 1995

D3370 Water From Closed Conduits Rev. A

3320 ASTM ASTM 1976 Standard Practices for Sampling reg4.15.rO1 1979 R ASTM D3370 1995

D3370 Water From Closed Conduits Rev. A

3321 ASTM ASTM 1984 Standard Test Methods for Cobalt inm79501 1989 R ASTM D3558 1994

03558 __ _ _ _ _ in W ater _ _ _ _ _ _

3322 ASTM ASTM 1984 Standard Test Methods for Total inm79501 1989 R ASTM D3590 1989 R94

D3590 Kjeldahl Nitrogen in Water

3323 ASTM ASTM 1978 Standard Test Methods for reg4.16.rOl 1985 R ASTM D3685 1992

D3685 Sampling and Determination ofParticulate Matter in Stack Gases

3324 ASTM ASTM 1989 Standard Test Method for Nuclear- inm84750 1994 R ASTM 03803 1989 R95

D3803 Grade Activated Carbon

3325 ASTM ASTM 1979 Standard Test Method for Nuclear- not87-32 1987 R ASTM D3803 1989 R95


3326 ST ASTM 1979 Standard Test Method for Nuclear- not95-41 1995 R ASTM 03803 1989 R95


3327 ASTM ASTM 1989 Standard Test Method for Nuclear- s4-ge5.7.2 .1 3 1992 P ASTM D3803 i989 R95

D3803 . Grade Activated Carbon

3328 ASTM ASTM 1989 Standard Test Method for Nuclear- sts6-ge5.7.2.15 1992 P ASTM D3803 1989 R95



Record Stdard .. -C........:L' ats Standard Lasti Vrsi o

No S Code Standard Vrntcm Dt bt C rio Dte;

3329 ASTM ASTM 1989 Standard Test Method for Nuclear- stsb&w5.7.2.17 1992 P ASTM D3803 1989 R95


3330 ASTM ASTM 1989 Standard Test Method for Nuclear- stsce5.7.2.17 1992 P ASTM D3803 1989 R95


3331 ASTM ASTM 1989 Standard Test Method for Nuclear- stswst5.7.2.17 1992 P ASTM D3803 1989 R95


3332 ASTM ASTM 1980 Standard Guide for Good inm79501 1989 R ASTM D3856 1995

D3856 Laboratory Practices inLaboratories Engaged in Samplingand Analysis of Water

3333 ASTM ASTM 1979 Standard Guide for Continual On- inm79501 1989 R ASTM D3864 1979 R90

D3864 Line Monitoring Systems forWater Analysis

3334 ASTM ASTM N/S Standard Test Methods for Nitrite- reg1.35.r03 1990 A ASTM D3867 1990

D3867 Nitrate in Water

3335 ASTM ASTM N/S Standard Practice for Evaluating sts4-geB3.8.3 1992 P ASTM D4054 1993

D4054 the Compatibility of Additiveswith Aviation-Turbine Fuels andAircraft Fuel System Materials

3336 ASTM ASTM N/S Standard aluating sts6-geB3.8.3 1992 P ASTM 04054 1993


3337 ASTM ASTM N/S Standard Practice for Evaluating stsb&wB3.8.3 1992 P ASTM D4054 1993


WtA

z

tA

:-4W

z

VI

Q3

Litt-J



Rt adco r dA )O c S tD 6d7 o . A e p - L t s ~ a l a d L t s o ~ o

3338 ASTM ASTM N/S Standard Practice for Evaluating stsceB3.8.3 1992 P ASTM D4054 1993


3339 ASTM ASTM NIS Standard Pracice for Evaluating stswstB3.8.3 1992 P ASTM D4054 1993


3340 ASTM ASTM 1982 Standard Terminology Used with inm79501 1989 R ASTM D4127 1992

041 27 I__ _ _ _ on-Selective Electrodes _ _ _ _ _ _

3341 ASTM ASTM 1982 Standard Test Method for Total inm79501 1989 R ASTM D4129 1988 R93

D4129 and Organic Carbon In Water byHigh Temperature Oxidation andby Coulometric Detection

3342 ASTM ASTM N/S Standard Test Method for Free sts4-geB3.8.3 1992 P ASTM D4176 1993

D4176 Water and ParticulateContamination in Distillate Fuels(Visual Inspection Procedures)

3343 ASTM ASTM N/S Standard Test Method for Free sts6-geB3.8.3 1992 P ASTM D4176 1993


3344 ASTM ASTM N/S Standard Test Method for Free stsb&wB3.8.3 1992 -P ASTM D4176 1993



Part A - Industry Consensus Codes and Standards-.

. . . .-..............-....-......

192rAT D16 19ASTM ASTM

D4176N/IS Z)Xanuara lesuMenu UVULIV - ,

Water and ParticulateContamination in Distillate FuelsI(Visual Inspection Procedures)

\ IVV<V._._

__ I_ __ _ .. . + 2 R Iq T I M D4176 j 1993

3346 ASTM ASTMD4176

ASTMD4191

N/S Standard l est MeThod lof FMtlWater and ParticulateContamination in Distillate Fuels

IVisual Inspection Procedures)

| tvW>tu - s v. - § v_

.1 _ _ I - , -7 tA ' 1 Q n ASTMfD4191 t 1993

33471 ASTM 1982 Standard Test Method for Sodiumin Water by Atomic AbsorptionSpectrophotometry

inm/96Vl i vYOY rn ro s lws w

________ r. . .T.- tl f 179 R I ASTM D4192 | 1993-7CIRM ~ ~ 2. 99

3348 ASTM

zC.'

ito

ASTMD4192

1982z siandara test Method ror

Potassium in Water by Atomic

Absorption Spectrophotometry

--- Iuv

--- I . : _.__ _ i1 10 1 .: .TASTT D4210 1 1989

3349 1 ASTM ASTMD4210

1982 Standard Practice tor

Intralaboratory Quality ControlProcedures and a Discussion on- . . I . . 1 r_+__

nm::111U I I -U;

lReporting LOW-LeVel uata.. I _. pi!oIiQ5V 0 A i R t --- - ASTM D4327 1991Stndr let~to o ~i

3350 IASTM ASTMD4327

1984 Standard ITest PMexnouJ tor Aniumsin Water by ChemicallySuppressed Ion Chromatography

111111:OUV .- - - . .

_ I _ .I - __ .I.I --- I Ti I ASTM E1i 1 1995Itan -ara -pecnIcau7In r v .

3351

3352

ASTM ASTM El I 1 970Cloth Sieves for Testing Purposes

.I___ _ _ 1. I- :.J,,_lIA -n7 .nn 11994 A R ISTME23 Rev | 1994

Stanard estMetous or uy~vt.,BASTM ASTM E23 I 988lNotched Bar Impact Testing of_. . . .X .. ._ -,

UIV --- 8

,m Metanlic Materials I------ a I -- ASTM E23 Rev 1994.. v. . - __ . .I

335S 1ASTM _ASTM E23 N/S Standard Test Me ig tof

Notched Bar impact Testing ofzsv P U. �.. I __ I

B

I 1 I - IMetallic Materials III--_ I . . _

'0

w

Lil



= i:0000000: - ~~~~~~~~~~~~~~............ :o : .... t. :i:- .:. ; 0_--:tB

. Na. :- -Code t Standard Versionrd - T- ;Document Diati aility C

3354 ASTM ASTM E60 N/S Standard Practice for Photometric reg1.36.rOO 1973 P Implied ASTM E60 1993

and Spectrophotometric Methods endorsement

for Chemical Analysis of Metals

3355 ASTM ASTM E62 N/S Standard Test Methods for regl .36.rOO 1973 P Implied ASTM E62 1989

Chemical Analysis for Copper and endorsement

Copper Alloys (Photometric

Methods)

3356 ASTM ASTM E84 N/S Surface Burning Characteristics of glt86-01 0 1986 ASTM E84 Rev 1995

Building Materials B

3357 ASTM ASTM E84 N/S Surface Burning Characteristics of git86-01 0 1986 R ASTM E84 Rev 1995


3358 ASTM ASTM E84 1976 Surface Burning Characteristics of glt86-01 0 1986 R ASTM E84 Rev 1995


3359 ASTM ASTM E84 NiS Surface Burning Characteristics of glt86-01 0 1986 R ASTM E84 Rev 1995


3360 ASTM ASTM E84 1994 Surface Burning Characteristics of not95-41 1995 R ASTM E84 Rev 1995


3361 ASTM ASTM E84 1984 Surface Burning Characteristics of glt86-010 1986 R ASTM E84 Rev 1995


3362 ASIM ASTM E84 1970 Surface Burning Characteristics of g1t86-010 1986 R ASTM E84 Rev 1995


3363 ASTM ASTM E84 1970 Surface Burning Characteristics of g1t86-010 1986 R ASTM E84 Rev 1995


3364 ASTM ASTM E84 1976 Surface Burning Characteristics of glt86-010 1986 R ASTM E84 Rev 1995


CA

(51


... .....

No;i o ', i Standarid - ,: V :r - ' , i o :ae i, : ,iIt Com ents ', i e3 ' .sD t

3365 ASTM ASTM El 19 NIS Standard Test Methods for Fire bu192-001 1992 R ASTM El 19 1995


Materials

3366 ASTM ASTM El 19 N/S Standard Test Methods for Fire bul92-001.sOl 1992 R ASTM El 19 1995

Tests of Building Construction and Rev. AMaterials

3367 ASTM ASTM El 19 1971 Standard Test Methods for Fire drgrs809-5.rOO 1979 P ASTM El 19 1995


Materials

3368 ASTM ASTM El 19 NIS Standard Test Methods for Fire git86-01 0 1986 R ASTM El 19 1995

Tests of Building Construction and Rev. AM aterials _ _ _ _ _ _ _ _

3369 ASTM ASTM El119 NIS Standard Test Methods for Fire git86-010.sOl 1994 R ASTM El119 1995


3370 ASTM ASTM El 19 N/S Standard Test Methods for Fire g1t92-008 1992 R ASTM El 19 1995

Tests of Building Construction and Rev. AMaterials .

3371 ASTM ASTM E119 N/S Standard Test Methods for Fire inm51061 1984 R ASTM E 1l9 1995


Materials

3372 ASTM ASTM E 119 NIS Standard Test Methods for Fire inm51065 1984 R ASTM E119 1995


3373 ASTM ASTM E119 1976 Standard Test Methods for Fire inm88O55 1991 R ASTM E119 1995Tests of Building Construction and Rev. A

Materials

3374 ASTM ASTM El 19 N/S Standard Test Methods for Fire not88-04 1988 P Implied ASTM El 19 1995

Tests of Building Construction and endorsement Rev. AMaterials l

3375 ASTM ASTM El 19 N/S Standard Test Methods for Fire not9l-79 1991 R ASTM El 19 1995


Materials

3376 ASTM ASTM El 19 N/S Standard Test Methods for Fire not92-46 1992 R ASTM El 19 1995


Materials

z

'0

65


No. ode Standard | *V e nlon ;X, T D osU nt D erDt | *eto Verabin. l ate



Materials



Materials



Materials

3380 ASTM ASTM El 19 N/S Standard Test Methods for Fire nuregO933, 1992 R ASTM El 19 1995

Tests of Building Construction and 3.149 Rev. A

Materials

3381 ASTM ASTM El119 1976 Standard Test Methods for Fire regl .120.rOl 1977 P Implied ASTM El 19 1995

Tests of Building Construction and endorsement Rev. AMaterials

3382 ASTM ASTM El19 1971 Standard Test Methods for Fire reg3.16.rOO 1974 R ASTM El19 1995


Materials

3383 ASTM ASTM El 19 1976 Standard Test Methods for Fire srp9.5.1 1981 P With additional ASTM El 19 1995

Tests of Building Construction and acceptance Rev. A

Materials criteria

3384 ASTM ASTM El20 N/S Standard Test Methods for reg1.36.rOO 1973 P Implied ASTM El 20 1995

Chemical Analysis of Titanium and Endorsement

Titanium Alloys

3385 ASTM ASTM El36 N/S Standard Test Method For not92-82 1992 R ASTM E136 1994

Behavior of Materials in a VerticalTube Furnace at 750 Degrees C.

3386 ASTM ASTM E136 N/S Standard Test Method For not95-27 1995 R ASTM El36 1994

Behavior of Materials in a VerticalTube Furnace at 750 Degrees C.

3387 ASTM ASTM El46 N/S Methods for Chemical Analysis of regl.36.rOO 1973 P Discontinued i n/anla

Zirconium and Zirconium Alloys 1991

--- ----- ----


Record......ec. Acc tLates t d - a-te t VErsio;CodWCode Standard Version il DocumeiNt :Date ability Ctomments: Version Data

3388 ASTM ASTM El 78 1974 Standard Practice for Dealing with reg5.36.rOO 1974 P Subject to ASTM El 78 1994Outlying Observations conditions

3389 ASTM ASTM E178 1980 Standard Practice for Dealing with reg5.53.rOl 1984 R ASTM E178 1994Outlying Observations _______

3390 ASTM ASTM E181 1982 Standard General Methods for drglO25.rOO 1993 P Typo in ASTM El81 1993Detector Calibration and Analysis drg1025.rOO -

of Radionuclides Title is forASTM E181vs. E81

3391 ASTM ASTM E185 1979 Standard Practice for Conducting 10cfr50 App. G 1994 R ASTM E185 1994Surveillance Tests for Light-WaterCooled Nuclear Power ReactorVessels

3392 ASTM ASTM E£185 1982 StandardPracticeforConducting lOcfr50 App. G 1994 R ASTM E£185 1994Surveillance Tests for Light-WaterCooled Nuclear Power ReactorVessels

3393 ASTM ASTM E1 85 1973 Standard Practice for Conducting 1 Ocfr5O App. H 1994 A ASTM E18 5 1994Surveillance Tests for Light-WaterCooled Nuclear Power ReactorVessels

3394 ASTM ASTM E185 1979 Standard Practice for Conducting lOcfr5O App. H 1994 A ASTM E185 1994Surveillance Tests for Light-WaterCooled Nuclear Power ReactorVessels

3395 ASTM ASTM El185 1982 Standard Practice for Conducting l Ocf r5O App. H 1994 A AS-M E£185 1994Surveillance Tests for Light-WaterCooled Nuclear Power ReactorVessels

U)U1-4

z(I

M0

qt!A�10

IW

�0

I

W

A:

OQ



R e c o rd S tan da d :D e c e t e e t S a d t a e t V r l f

No . Cod Stndr V rio - I -Ttl Do um n Dei . bl~' C_ met - - |eso

3396 ASTM ASTM E 85 1982 Standard Practice for Conducting drglO27.rOO 1994 R ASTM El85 1994Surveillance Tests for Light-WaterCooled Nuclear Power ReactorVessels

3397 ASTM ASTM E185 1973 Standard Practice for Conducting glt92-001OrOl 1992 R ASTM E185 1994

Surveillance Tests for Light-WaterCooled Nuclear Power ReactorVessels

3398 ASTM ASTM E185 1979 Standard Practice for Conducting glt92-001.rO1 1992 P TM El 85 1994


3399 ASTM ASTM El 85 1982 Standard Practice for Conducting glt92-001.ro1 1992 R ASTM E185 1994


3400 ASTM ASTM E185 1982 Standard PracticeforConducting regl.161.r00 1995 R ASTM E185 1994


3401 ASTM ASTM E185 1979 Standard Practice for Conducting regl.161.rOO 1995 R ASTM E185 1994

Surveillance Tests for Light-WaterCooled Nuclear Power Reactor

Vessels

3402 ASTM ASTM E185 1982 Standard Practice for Conducting regl.99.rO2 1988 R ASTM E185 1994




Recrd . ... S ftendrd>'> lbd-De~Aoep*-, ULtes StanidahdLts eso

No oe~ tandai&' Versio -~>~y-Ttl . ' OcmrtS De ally onst Ver gnsionDt

3403 ASTM ASTM E185 N/S Standard Practice for Conducting srp5.3.1 1981 P Implied ASTM E185 1994

Surveillance Tests for Light-Water endorsementCooled Nuclear Power Reactor with anVessels exception

3404 ASTM ASTM El 85 1973 Standard Practice for Conducting srp5.3,2 1981 P Implied ASTM El 85 1994

Surveillance Tests for Light-Water endorsementCooled Nuclear Power ReactorVessels

3405 ASTM ASTM E185 1982 Standard Practice for Conducting stsb&wB3.4.3 1992 P ASTM E185 1994Surveillance Tests for Light-WaterCooled Nuclear Power ReactorVessels

3406 ASTM ASTM E185 1982 Standard Practice for Conducting stsceB3.4.3 1992 P ASTM E185 1994


3407 ASTM ASTM E185 1982 Standard Practice for Conducting sts4-geB3.4.10 1992 P ASTM E185 1994Surveillance Tests for Light-WaterCooled Nuclear Power ReactorVessels

3408 ASTM ASTM E185 1982 Standard Practice for Conducting stswstB3.4.3 1992 P ASTM El 85 1994


3409 ASTM ASTM E185 1982 Standard Practice for Conducting sts6-geB3.4.1 1 1992 P ASTM E185 1994


WjkA

z0

U'

ci)

Z

-4

(b


n e c or u g C ~~~...... .. . : er r: r&. . .... ' . , ,, ,, .R c r S a n a dD e A c e tL a e tSta n a d L t e t V rii o n

o i.

code; Stand r son;i Tit D. D T a litt

3410 ASTM ASTM E200 1972 Standard Practice for Preparation, inm79501. 1989 R ASTM E200 1991Standardization, and Storage ofStandard and Reagent Solutionsfor Chemical Analysis

3411 ASTM ASTM E200 1981 Standard Practice for Preparation, inm79501 1989 R ASTM E200 1991Standardization, and Storage ofStandard and Reagent Solutionsfor Chemical Analysis

3412 ASTM ASTM E208 N/S Standard Test Method for reg7.1 1.rOO 1991 R ASTM E208 1995Conducting Drop-Weight Test To Rev. ADetermine Nil-Ductility TransitionTemperature of Ferritic Steels

3413 ASTM ASTM E208 1987 Standard Test Method for reg7.12.rOO 1991 P Paragraph 7 ASTM E208 1995Conducting Drop-Weight Test To Rev. ADetermine Nil-Ductility TransitionTemperature of Ferritic Steels

3414 ASTM ASTM E208 N/S Standard Test Method for srp10.2.3 1981 P Implied ASTM E208 1995Conducting Drop-Weight Test To endorsement Rev. ADetermine Nil-Ductility TransitionTemperature of Ferritic Steels

3415 ASTM ASTM E208 N/S Standard Test Method for srp5.2.3 1981 R ASTM E208 1995Conducting Drop-Weight Test To Rev. ADetermine Nil-Ductility TransitionTemperature of Ferritic Steels

3416 ASTM ASTM E208 N/S Standard Test Method for srp5.3.2 1981 P Implied ASTM E208 1995Conducting Drop-Weight Test To endorsement Rev. ADetermine Nil-Ductility TransitionTemperature of Ferritic Steels

-Codes and Standards and Other Guidance Cited in Regulatory DocumentsPart A - Industry Consensus Codes and Standards

RcrStandatdDe Accept Latest Standard Latoit V6M diiNo. c . S:tadard - Verio Titl Dou tWo ..n

3417 ASTM ASTM E208 1969 Standard Test Method for srp5.4.1.1 1981 P Implied ASTM E208 1995

Conducting Drop-Weight Test To endorsement Rev. A

Determine Nil-Ductility TransitionTemperature of Ferritic Steels

3418 ASTM ASTM E213 N/S Standard Practice for Ultrasonic not84-63 1984 R ASTM E213 1993

Examination of Metal Pipe and.__ __ ._ __ Tubing

3419 ASTM ASTM E263 1988 Standard Test Method for drg1 02.rOO 1993 P ASTM E263 1993Measuring Fast-Neutron ReactionRates by Radioactivation of Iron

3420 ASTM ASTM E264 1987 Standard Test Method for drglO25.r00 1993 P ASTM E264 1992Measuring Fast-Neutron ReactionRates by Radioactivation of Nickel

3421 ASTM ASTM E329 N/S Standard Specification for inm46051 1983 R ASTM E329 1995

Agencies Engaged in the Testing Rev B

and/or Inspection of MaterialsUsed in Construction

3422 ASTM ASTM E329 N/S Standard Specification for inm46053 1983 R ASTM E329 1995

Agencies Engaged in the Testing Rev B

and/or Inspection of MaterialsUsed in Construction

3423 ASTM ASTM E399 1983 Standard Test Method for Plane- drg1027.rOO 1994 R ASTM E399 1990

Strain Fracture Toughness ofMetallic Materials

3424 ASTM ASTM E399 N/S Standard Test Method for Plane- regl.14.rOl 1975 P Implied ASTM E399 1990

Strain Fracture Toughness of endorsement

Metallic Materials

wj0\

(D

(V.

z

C0

-4

0'j



iR e o rd. S te f d a r D e . .t A -; ~ t L a e s 00 0Sta n d a d ; L a -X t e s;0 .t .e s o

3425 ASTM ASTM E482 1989 Standar pplication of dr:1O25.r00 1993 R ASTM E482 1989

Neutron Transport Methods forReactor Vessel Surveillance

3426 ASTM ASTM E509 1986 Standard Guide for In-Service drglO27.r00 1994 R ASTM E509 1986 991

Annealing of Light-Water CooledReactor Vessels_______

3427 ASTM ASTM E523 1987 Standard Test Method for drg1025.rOO 1993 P ASTM E523 1992

Measuring Fast-Neutron ReactionRates by Radioactivation ofCopper

3428 ASTM ASTM E526 1987 Standard Test Method for drg1;25.rOO 1993 P ASTM E526 1992

Measuring Fast-Neutron ReactionRates by Radioactivation ofTitanium__

_ _ _ _ _

3429 ASTM ASTM S604 N/S Standard Test Method for reg7.1 1 .rO 1991 R ASTM E604 1983 R94

Dynamic Tear Testing of MetallicM aterials _ _ _ _ _ _ _

3430 ASTM ASTM E693 1979 Standard Practice for reg1 .99.r02 1988 R ASTM E693 1994

Characterizing Neutron Exposuresin Iron and Low Alloy Steels inTerms of Displacements per AtomDPA

3431 ASTM ASTM E704 1990 Standard Test Method for drg1025.r00 1993 P ASTM E704 1990

Measuring Reaction Rates byRadioactivation of Uranium-238

3 AASTM E705 1993 P ASTM E705 1990

Measuring Reaction Rates byRadioactivation of Neptunium-237

3433 AS ASTM E706 1984 Standard Master Matrix for Light- drg1026.rOO 1993 R ASTM E706 1987 R94

Water Reactor Pressure VesselSurveillance Standards



=Rord Stnd " Dt=ecz.' 'Accept- .ateit anda'ird Latdst- V.io..

No. ~~Coe ai.,,:, Standad W ~ eso il ouet Dt blt omns VrinDt

3434 ASTM ASTM E814 N/S Standard Test Method for Fire not88-04 1988 P Implied ASTM E814 1994

Tests of Through-Penetration Fire endorsement Rev B

Stops _ _ _ _ _ _ _ _ _ _ _ _ _

3435 ASTM ASTM E844 1986 Standard Guide for Sensor Set drglO25.rOO 1993 P ASTM E844 1986 R91

Design and Irradiation for Reactor

Surveillance

3436 ASTM E854 1990 Standard Test Method for drg1025.rOO 1993 R ASTM E854 1990

Application and Analysis of Solid

State Track Recorder (SSTR)

Monitors for Reactor Surveillance

3437 ASTM ASTM 1984 Standard Test Method for drglO25.rOO 1993 P ASTM E1005 1984 R91

E1005 Application and Analysis of

Radlometric Monitors for ReactorVessel Surveillance

ASTM ASTM 1987 Standard Test Method for regl.161.rOO 1995 R ASTM E1152 1995

El 152 Determining J-R Curves

3439 ASTM ASTM 1988 Standard Guide for Reconstitution drg 1027.rOO 1994 R ASTM E 1253 1988 R93

E1253 of Irradiated Charpy Specimens

3440 ASTM ASTM N/S Standard Guide for Reconstitution not90-52 1990 R ASTM E1253 1988 R93

E1253-B of Irradiated Charpy Specimens

3441 ASTM ASTM N/S Standard Test Method for not95-27 1995 R ASTM El 321 1993

El 321 Determining Material Ignition and

Flame Spread Properties _____________

3442 ASTM ASTM N/S Standard Test Method for Heat not92-82 1992 R ASTM El 354 1994

El 354 and Visible Smoke Release Rates

for Materials and Products Using

an Oxygen Consumption

Calorimeter

CX

Up0UP(c

z

vi

01



Record |t and erd D ec. Acoept-X La t Mest Stanrhod L ateat v ersi on

an Oxygen ConsumptionC:aloeimeter

3444 ASTM ASTM F792 1982 Standard Practice for Design and a ini 245 App. 1991 R ASTM F792 1988 R93

Use of Ionizing RadiationEquipment for the Detection ofItems Prohibited in ControlledAccess Areas

3445 ASTM ASTM Part NIS Annual Book of American Society regl.138.rOO 1978 R Annual Book of 1995

19 for Testing and Materials ASTM

Standards Standards

3446 ASTM ASTM STP NIS Presentation of Data and Control inm79501 1989 R Out of Print n/a

15D Chart Analysis

3447 ASTM ASTM STP 1976 Presentation of Data and Control inm79701 1991 R Out of Print n/a

15D Chart Analysis

3448 ASTM ASTM STP 1970 Determination of the In Situ regl.132.rO1 1979 _ Not found n/a

477 Modulus of Deformation of Rock

3449 ASTM ASTM STP 1969 Special Procedures for Testing Soil regi.132.rOl 1979 R Withdrawn - Withdrawn n/a

479 and Rock for Engineering Purposes out of print

3450 ASTM ASTM STP 1970 Special Procedures for Testing Soil regi .138.rOO 1978 R Withdrawn - Withdrawn n/a

479 and Rock for Engineering Purposes out of print

3451 ASTM ASTM STP 1971 Use of Chemical Grouts to Sample regl.1 32.rOl 1979 R Withdrawn - Withdrawn n/a

483 Sands, Sampling of Soil and Rock out of print

3452 ASTM ASTM STP 1972 Recent Trends in Underwater Soil regl.132.rOl 1979 R Withdrawn - Withdrawn n/a

501 Sampling Methods, Underwater out of print

Soil Sampling Testing andConstruction Control AmericanSociety for Testing and Materials

Codes and Standards and Other Guidance. Cited in Regulatory. DocumentsPart A - Industry Consensus Codes and Standards

Record 0 | > - 0 | f 0 = :0 ? : ~~~~~~. . ? .. .... .. ................. -i~ecoriiidatd' - Dc Acet aetStandard Laest Versio6n

No~~ ~ Code Stantidarda Vesoiite -Dcet Dte aiiy Cemns erinDt

3453 ASTM ASTM STP 1973 Determination of Relative Density regl.132.rO1 1979 R Withdrawn - Withdrawn n/a

523 of Sand Below Groundwater Table out of print

3454 ASTM ASTM STP 1976 Effects of Storage and Extrusion regl .138.r00 1978 R Withdrawn - Withdrawn n/a

599 of Sample Properties out of print

3455 ASTM ASTM STP NIS Power Plant Instrumentation for inm79501 1989 8 Not found n/a

742 Measurement of High Purity WaterQuality

3456 ASTM ASTM STP 1983 Engineering Methods for the gIt89-010.s03 1990 R Withdrawn - Withdrawn n/a

803 Assessment of Ductile Fracture out of printMargin in Nuclear Power PlantPiping

3457 ASTM ASTM NIS Water (I) inm1 245 App. B 1991 R ASTM Volume 1995

Volume 11.01

11.01

3458 ASTM ASTM NIS Water (i) not94-07 1994 _ ASTM Volume 1995

Volume 11.01

11.013459 ASTM ASTM N/S Water (1) inm1245 App. 8 1991 R ASTM Volume 1995

Volume 11.02

11.02

3460 ASTM ASTM VV-F- 1975 Federal Oil Specification reg1.1 37.rO1 1979 A not a valid n/a n/a

800b ASTMdesignation

3461 ATC ATC-132A 1981 Radwaste Solidification not89-27 1989 R ATC-132A 1981

3462 ATC ATC-132A 1981 Radwaste Solidification not89-27 1989 R ATC-132A 1981

3463 ATC ATC-1 32A 1981 Radwaste Solidification not89-27 1989 R ATC-1 32A 1981

W

zC11

LA

(b

z

~9C)

eA



z; ...

...... S . . g7 ; 5:. S f S > .... r r 5 R . 5S

RecordD A TC tandard iltot Ver.in

N o o d t n d r e r i nT tl e D o u mn to D a e b l t . - 4 o m h Srsi o n ;D t

3464 ATC ATC N/S Tentative Provisions for the srp3.8.4 1981 R Also titled NBS ATC Report 1982

Publication 3 Development of Seismic Special ATC-3-06

Regulations for Buildings Publication510 and NSFPublication 78-

8



Regulations for Buildings Publication510 and NSFPublication 78-8




3467 ATC ATC 1978 Tentative Provisions for the reg3.48.rOl 1989 R ATC Report 1982

Publication 3 Development of Seismic ATC-3-06

06 Regulations for Buildings ___.

3468 ATC ATC N/S Tentative Provisions for the srp3.8.4 1981 P ATC Report 1982

Publication 3 Development of Seismic ATC-3-06

06 Regulations for Buildings

3469 ATC ATC-8019-1 1985 ATCOR AVRS-80 Volume not89-27 1389 R ATC-8019-1 1985

Reduction Process

3470 AWS AWS N/S American Welding Society not82-34.rOI 1982 R General n/a n/a

reference nospecific codescited


1Reord Stendatd ' Doe. e LatStandard t4st CVersio n

3471 AWS AWS A4.2 1974 Standard Procedures for reg1.31.r03 1978 A AWS A4.2 1991Calibrating Magnetic Instrumentsto Measure the Delta FerriteContent of Austenitic and Duplex-Austenitic Ferritic Stainless SteelWeld Metal

3472 AWS AWS D1.1 N/S Structural Welding Code Steel bui88-005.sOl 1988 R AWS D1.1 1994

3473 AWS AWS D1.1 N/S Structural Welding Code Steel bu188-005.s02 1988 P implied AWS D1.1 1994endorsement

3474 AWS AWS D1.1 NIS Structural Welding Code Steel inm46051 1983 R AWS D1.1 1994


3476 AWS AWS D1.1 N/S Structural Welding Code Steel inm48053 1986 R AWS D1.1 1994

3477 AWS AWS D1.1 NIS Structural Welding Code Steel inm5OO9O 1985 R AWS D1.1 1994

3478 AWS AWS D1.1 N/S Structural Welding Code Steel inm51053 1984 R AWS D1.1 1994


3480 AWS AWS D1.1 N/S Structural Welding Code Steel inm575D 1983 R AWS D1.1 1994

3481 AWS AWS 01. 1 N/S Structural Welding Code Steel inm57050 1983 8 AWS 01.1 1994

3482 AWS AWS D1.1 N/S Structural Welding Code Steel regl.85.r30 1994 R AWS D1.1 1994

3483 AWS AWS D1.1 N/S Structural Welding Code Steel srp6.1.1 1981 P Implied AWS D1.1 1994endorsement

3484 AWS AWS D1.1, NIS Structural Welding Code Steel inm55150 1983 R AWS D1.1 1994Table 4.1.1

zPO1

C)

z

p)LA

.0

4

W

TWo



e osto dr d Doe. .c c.pt' L ates Stan ard a ::r-ion

N. Cod dX tStandard Vers n T boument Datet C e Dat9

3485 AWS AWS401.1, N/S Structural Welding Code Steel inm55160 1983 R AWS D1.1 1994

Table 4.2

3486 AWS AWS 01.4 NIS Structural Welding Code inm46051 19§83 RAW D1492

Reinforcing Steel__ _ _ _ _ ___ _ _ _

3487 AWS AWS D12.1 N/S Structural Welding Code inm46051 1983 R AWS D1.4 1992

Reinforcing Steel _ _ _ _ _ _ _

3488 AWS AWS D 12.1 N/S Structural Welding Code regl .94.rOl 1976 P Now AWS AWS D1.4 1992

Reinforcing Steel D1.4 _

3489 AWWA AWWA 1971 Standard Methods for the reg 1.138.rOO 1978 R American Not found n/a

Examination of Water and Public Health

Wastewater, 13th Ed. Association,AmericanWater WorksAssociation,and WaterPollutionControlFederation,StandardMethods fortheExamination ofWater andWastewater,13th ed., NewYork, 1971.

3490 AWWA AWWA N/S Rubber-Seated Butterfly Valves not91-98 1991 R AWWA C504 1994

.. C 5 0 4 . _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ . . . _ _



eorStdrdDOM. Aclept Laettndard L atst Vataon

No C t Verio Tite D Date Con Date

3491 AWWA AWWA N/S Welded Steel Tanks for Water drg1010.rOO 1992 P Endorsed by AWWA D100 1984

D100 Storage reg1.26.Through 1989Addenda

3492 AWWA AWWA N/S Welded Steel Tanks for Water reg1.143.rOl 1979 A Typo - was AWWA D100 1984

D100 Storage AWWA D-1002. Through1989 Addenda

3493 AWWA AWWA N/S Welded Steel Tanks for Water reg1.26.r03 1976 A Through 1989 AWWA D100 1984

D100 Storage Addenda

3494 AWWA AWWA 1979 Welded Steel Tanks for Water srp3.2.2 1981 A Through 1989 AWWA D100 1984

D100 Storage Addenda

3495 CMAA CMAA 70 N/S Specifications for Electric gIt80-1 13 1980 P CMAA70 1994

Overhead Traveling Cranes

3496 CMAA CMAA 70 N/S Specifications for Electric git8l-007 1981 P Implied CMAA 70 1994

Overhead-Traveling Cranes endorsement

3497 CMAA CMAA 70 N/S Specifications for Electric g1t89-021 1989 A CMAA 70 1994

Overhead Traveling Cranes

3498 DEMA DEMA N/S Diesel Engine Manufacturers srp9.5.4 1981 A DEMA 1974

Association IDEMA) Standard


Association (DEMA) Standard







3503 FM Factory N/S Approval Guide reg1 .1 20.rO1 1977 P For metal deck Approval Guide 1996

Mutual roofconstruction

"0

z

'0

nJ.

z

(!A

ko


,R c r te n d rd- DcA - ce t-L a't est S t anid atd L a t e e s w

No.. d d I;' t D e D ot ' ' Itiy Conmea' .:*boe onD

3504 FM Factory N/S Approval Guide srp9.5 1981 P For metal deck Approval Guide 1996

Mutual construction

3505 HEI HEI 1970 Standards for Steam Surface srplO.4.2 1981 R HEI - same title 1989

Condensers, 6th Ed. 18th Edition

3506 HPS Health 1987 Not found inm1245 App. B 1991 R Not found nWa

Physics 52(no.6) 695-705

3507 HPS Health 1988 Not found inm1245 App. B 1991 R Not found n/a

Physics 55jno.6) 933-950 _ _ _ _ _ _

3508 HPS HPS HPSR-1 1980 Upgrading Environmental drg8004.rOO 1991 R HPS HPSR-1 1980

________ Radiation Data _ = _

3509 HPS HPS N13.30 1987 Performance Criteria for reg8.22.rOl 1988 R Draft Standard ANSI N1 3.30 1989

Radiobioassay

3510 HPS HPSSC- 1981 Location and Design Criteria for inmB3100 1991 R HPSSC 6.8.1 1981

6.8.1 Area Radiation MonitoringSystems for Light Water Reactors

3511 HPS HPSSC- 1981 Location and Design Criteria for inm83526 1984 R HPSSC 6.8.1 1981







Rteord : - Sten Dcc. Accept- L.t......t Standard Lst Version

No.- :'Cod~ 'Stihdaird VeWo '-il ocet ae aily C mes Versiion Ot

3514 HPS HPSSC- N/S Location and Design Criteria for reg8.8.rO3 1978 R Referenced as HPSSC 6.8.1 19816.8.1 Area Radiation Monitoring ANS/HPS 56.8

Systems for Light Water Reactors

3515 HPS HPSSC- 1981 Location and Design Criteria for srpi2.3 1981 P As relates in HPSSC 6.8.1 19816.8.1 Area Radiation Monitoring Acceptance

Systems for Light Water Reactors Criteria

3516 .. 80 UBC N/S Uniform Building Code gt2-032 1982 R _ 1991

3517 ICBO UBC NIS Uniform Building Code git82-033 1982 A UBC 1991

3518 1080 UBC N/S Uniform Building Code inm46061 1986 R UBC 1991

3519 ICBO UBC NIS Uniform Building Code not92-82 1992 R UBC 1991

3520 ICBO UBC NIS Uniform Building Code reg3.16.rOO 1974 P UBC 1991

3521 ICBO UBC NIS Uniform Building Code reg3.38.rOO 1976 P UBC 1991

3522 ICBO UBC 1979 Uniform Building Code srp3.8.4 1981 P UBC 1991

3523 ICEA ICEA NIS Power Cable Ampacities at AEIC not92-46 1992 R ICEA Standard 1967Pubiication P Temperatures P-48-42646-426

3524 ICEA ICEA NIS Power Cable Ampacities at AEIC not94-22 1994 R ICEA Standard 1967Publication P Temperatures P-48-42646-426

3525 ICEA ICEA NIS Ampacities of Cables in Open-Top not92-46 1992 R NEMA WC51 1986 R91Publication P Cable Trays54-440

3526 ICRP ICRP 1966 Human Respiratory Tract Model reg3.51.rOO 1982 R ICRP 1994for Radiological Protection Publication 66

3527 ICRP ICRP N/S Annual Limits on Intake of git79-029 1979 R ICRP 1991Publication 2 Radionuclides by Workers Based Publication 61

on the 1990 Recommendations

z

C)

z

C=

-4

CD


Re-ordSta'n dard rd: I i Acc p: L atest t at ndahid L est V e ion

o.C od6 Stani d ard V r i nileD c m nD te a i tyo h M on ts~ : V ersion D t

3528 ICRP ICRP N/S Annual Limits on Intake of inm1302 1994 R ICRP 1991

Publication 2 Radionuclides by Workers Based Publication 61on the 1990 Recommendations

3529 ICRP ICRP 1959 Annual Limits on Intake of not82-1 8 1982 P Superseded by ICRP 1991

Publication 2 Radionuclides by Workers Based ICRP-30 Publication 61


3530 ICRP ICRP 1959 Annual Limits on Intake of reg .24r00 1972 P Implied ICRP 1991

Publication 2 Radionuclides by Workers Based endorsement. Publication 61

on the 1990 Recommendations Superseded byICRP 30

3531 ICRP ICRP 1960 Annual Limits on Intake of reg1.25r00 1972 P Implied ICRP 1991

Publication 2 Radionuclides by Workers Based endorsement Publication 61


3532 ICRP ICRP 1959 Annual Limits on Intake of reg1.3.r02 1974 P ICRP 1991


3533 ICRP ICRP 1959 Annual Limits on Intake of regi .4.r02 1974 P ICRP 1991


3534 ICRP ICRP 1959 Annual Limits on Intake of reg1.5.rOO 1971 P Superseded by ICRP 1991

Publication 2 Radionuclides by Workers Based ICRP-30 Publication 61


3535 ICRP ICRP 1959 Annual Limits on Intake of regl.77.rOO 1974 P Superseded by ICRP 1991

Publication 2 Radionuclides by Workers Based ICRP-30. Publication 61



~RcrdSonIrCie. idet Lts tetdr LAtes eon

3536 ICRP ICRP 1959 Annual Limits on Intake of reg3.33.rOO 1977 R ICRP 1991Publication 2 Radionuclides by Workers Based Publication 61


3537 ICRP ICRP 1959 Annual Limits on Intake of reg3.34.rOl 1979 R ICRP 1991






3540 ICRP ICRP NIS 1990 Recommendations of the not82-18 1982 P Supplements ICRP 1991Publication 6 International Commission on ICRP-2. Publication 60

Radiological Protection Superseded byICRP-26

3541 ICRP ICRP 1962 1990 Recommendations of the reg3.33.rOO 1977 R ICRP 1991Publication 6 International Commission on Publication 60

Radiological Protection

3542 ICRP ICRP 1962 1990 Recommendations of the reg3.34.rOl 1979 R ICRP 1991

Publication 6 International Commission on Publication 60Radiological Protection

3543 ICRP ICRP 1962 1990 Recommendations of the reg3.35.rOl 1979 R ICRP 1991

Publication 6 International Commission on Publication 60Radiological Protection

3544 ICRP ICRP NIS 1990 Recommendations of the not82-18 1982 P Supplements ICRP 1991

Publication 9 International Commission on ICRP2. Publication 60Radiological Protection Superseded by

ICRP-26. l

Z

M0

vU1#�-o

.1W

I10

U.)

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R c dSt n a dD oe Acoe"a'..Latest Stand ard L Vs Ve son: . :: 0 ... .. .... .'

0 1

4t C i 0 i t ; ~ : ,. X ;.r l o,4t ; : > ; .,

N o o eS t a n d a ,'d V r i nT t eD c m n a e a i i y,-t e t e a o D a t

3545 ICRP ICRP 1968 Individual Monitoring for Intakes not8 -1 8 19 8-2 P Supplements ICRP 1989

Publication of Radionuclides by Workers: ICRP-2. Publication 54

10 Design and Interpretation Superseded byICRP-54.

3546 ICRP ICRP 1971 individual Monitoring for Intakes not82-18 1982 P Supplements ICRP 1989

Publication of Radionuclides by Workers: ICRP-2. Publication 54

1 OA Design and Interpretation Superseded byICRP-54,

3547 ICRP ICRP 1971 Individual Monitoring for Intakes reg3.51.r0O 1982 R ICRP 1989

Publication of Radionuclides by Workers: Publication 54

1 OA Design and Interpretation

3548 ICRP ICRP 1969 General Principles of Monitoring not82-18 1982 P Supplements Out of Print n/a

Publication for Radiation Protection of ICRP-2.

12 Workers Superseded byICRP-35.

3549 ICRP ICRP 1969 General Principles of Monitoring reg10.8.r02 1987 R Supplements Out of Print n/a



3550 ICRP ICRP N/S General Principles of Monitoring reg1 0.8.r02 1987 R Supplements Out of Print n/a



3551 ICRP ICRP 1969 General Principles of Monitoring reg8.21.rOl 1979 R Supplements Out of Print n/a


12 Workers Superseded byICRP-35. _ _ _ _ _

3552 ICRP ICRP 1969 General Principles of Monitoring reg8.23.rOl 1981 R Supplements Out of Print n/a



3553 ICRP ICRP 1969 General Principles of Monitoring reg8.24.rO1 1979 R Supplements Out of Print n/a




ReodSanadDc.: Accp Ltet Standard Latest Veio

= '. Code .Standard V. T i. . D C Vei3554 ICRP ICRP 1969 General Principles of Monitoring reg8.30.rOO 1983 R Supplements Out of Print n/a



3555 ICRP ICRP 1972 The Metabolism of Compounds of reg8.36.rOO 1992 R ICRP 1972

Publication Plutonium and Other Actinides Publication 19

19

3556 ICRP ICRP 1972 The Metabolism of Compounds of reg3.33.rOO 1977 R ICRP 1972

Publication Plutonium and Other Actinides Publication 19

19 _ . Eh tl_ __iss __fPrn

3557 ICRP ICRP N/S Alkaline Earth Metabolisms in not94-70 1994 R Out of Print n/a

Publication Adult Man20 .

3558 ICRP ICRP 1973 Implications of Commission drgop618-4.rOO 1982 R Proposed Out of Print n/a

Publication Recommendations that Doses be reg8.S.rO422 Kept As Low As Readily

Achievable

3559 ICRP ICRP 1974 Implications of Commission reg8.18.rOl 1982 R Out of Print nia

Publication Recommendations that Doses be22 Kept As Low As Readily

Achievable

3560 ICRP ICRP 1973 Implications of Commission reg8.8.rO3 1978 P Implied Out of Print n/a

Publication Recommendations that Doses be endorsement,

22 Kept As Low As Readily document outAchievable of print

3561 ICRP ICRP N/S Reference Man: Anatomical, not81-26 1981 R ICRP 1975

Publication Physiological and Metabolic Publication 23

23 Characteristics _

3562 ICRP ICRP N/S Reference Man: Anatomical, not82-18 1982 P Implied ICRP 1975

Publication Physiological and Metabolic endorsement Publication 23

23 Characteristics _

3563 ICRP ICRP N/S Reference Man: Anatomical, not83-59 1983 R ICRP 1975

Publication . Physiological and Metabolic Publication 23

23 Characteristics

z

C)

U'i

WJ

z

C3

(JU


-ecotd tandard Dec. La S and grd Lot V s ion

cord Doment Date |aili0t Commnt V Or ih Da :

3564 ICRP ICRP 1975 Reference Man: Anatomical, reg9 .1 09.rO1 1977 P Implied ICRP 1 975

Publication Physiological and Metabolic endorsement- Publication 23

23 Characteristics No longer inprint-1992update planned

3565 ICRP ICRP 1977 1989 Recommendations of the drg8012.rOO 1994 R Proposed ICRP 1991

Publication International Commission on reg8.29.rOl Publication 60

26 Radiological Protection

3566 ICRP ICRP N/S 1990 Recommendations of the drgfc414-4.rOO 1985 R ICRP 1991

Publication International Commission on Publication 60


3567 ICRP ICRP N/S 1990 Recommendations of the drgop212-4.rOO 1984 R ICRP 1991



3568 ICRP ICRP NIS 1990 Recommendations of the inml302 1994 R tCRP 1991


26 Radiological Protection _

3569 ICRP ICRP 1977 1990 Recommendations of the not82-18 1982 P ICRP 1991



3570 ICRP ICRP NIS 1990 Recommendations of the not92-34 1992 A ICRP 1991



3571 ICRP ICRP 1977 1990 Recommendations of the pp153FR49886 1988 R ICRP 1991



3b72 ICRP ICRP 1977 1990 Recommendations of the pol55FR27522 1990 R ICRP 1991



3573 ICRP ICRP NIS 1990 Recommendations of the reg 10.8.rO2 1987 R ICRP 1991



3574 ICRP ICRP 1977 1990 Recommendations of the reg8.27r00 1981 R ICRP 1991




.Record: -: ,'0 .Et .... Sta-ndard :; ........ ..,A . .. , Dec. Accp- Lae Stndr Lates Vsion -iN 2o.i ?'' 0i Cod ,', Stanard' Ve'rsin* - .. =~ . -ml. _____ _ :Date a}bility Commnts Ve tlon . -at

3575 ICRP ICRP 1977 1990 Recommendations of the reg8.29.rOO 1981 R ICRP 1991Publication International Commission on Publication 6026 Radiological Protection

3576 ICRP ICRP 1977 Problems Involved in Developing reg8.27rOO 1981 R Out of Print Out of Print n/aPublication an Index of Harm27

3577 ICRP ICRP 1977 Problems Involved in Developing reg8.29.rOO 1981 R Out of Print Out of Print n/aPublication an Index of Harm27 _ __ _ _

3578 ICRP ICRP N/S Radionuclide Release into the inmi245 App. B 1991 R ICRP 1979Publication Environment - Assessment of Publication 2929 Doses to Man

3579 ICRP ICRP 1978 Annual Limits on Intake of inm87102 1994 R ICRP 1991Publication Radionuclides by Workers Based Publication 6130 on the 1990 Recommendations

3580 ICRP ICRP N/S Annual Limits on Intake of inm87103 1994 R ICRP 1991Publication Radionuclides by Workers Based Publication 6130 on the 1990 Recommendations

3581 ICRP ICRP N/S Annual Limits on Intake of reg8.37.rOO 1993 P ICRP 1991Publication Radlonuclides by Workers Based Publication 6130 on the 1990 Recommendations

3582 ICRP ICRP 1979 Annual Limits on Intake of not82-18 1982 P ICRP 1991Publication Radionuclides by Workers Based Publication 6130 on the 1990 Recommendations

3583 ICRP ICRP N/S Annual Limits on Intake of not92-34 1992 A ICRP 1991Publication Radionuclides by Workers Based Publication 6130 on the 1990 Recommendations

3584 ICRP ICRP 1982 Annual Limits on Intake of reg8.34.rOO 1992 P ICRP 1991Publication Radionuclides by Workers Based Publication 6130 on the 1990 Recommendations

z

110

c0

z

t~l

-4cc



.. ...an ar I.....c A ce t Late s S tandard Lt esd~'t V ersion

o e Standrd V rsn i e oo ument Dt abil ty C t s ; Ve Date

3585 ICRP ICRP 1979 Annual Limits on Intake of reg8.36.rOO 1992 R ICRP 1991

Publication Radlonuclides by Workers Based Publication 61

30 on the 1990 Recommendations

3586 ICRP ICRP 1978 Annual Limits on Intake of reg8.9r01 1993 R ICRP 1991

Publication Radionuclides by Workers Based Publication 61

30 on the 1990 Recommendations

3587 ICRP ICRP 1983 Cost Benefit Analysis in the drg8004.rOO 1991 R Out of Print n/a

Publication Optimization of Radiation37 Protection

3588 ICRP ICRP N/S Principles for Intervention for inm1245 App. B 1991 R ICRP 1993

Publication Protection of the Public in a Publication 63

40 _ Radiological Emergency __

3589 ICRP ICRP N/S Nonstochastic Effects of Ionizing SECY94-275 1995 R ICRP 1984

Publication Radiation Publication 41

41 ____

3590 ICRP ICRP N/S Nonstochastic Effects of Ionizing SECY95-083 1995 R ICRP 1984

Publication Radiation Publication 41

41 _

3591 ICRP ICRP N/S Radiation Dose to Patients from not90-59 1990 R ICRP 1988

Publication Radiopharmaceuticals Publication 53

533592 ICRP ICRP 1988 Individual Monitoring for Intakes reg8.9rO1 1993 P ICRP 1989


54 Design and Interpretation

3593 ICRP ICRP 1988 Individual Monitoring for Intakes reg8.36.rOO 1992 R ICRP 1989


54 Design and Interpretation

3594 ICRP ICRP 1989 Age-Dependent Doses to reg8.36.rOO 1992 A ICRP 1990

Publication Members of the Public from Intake Publication 56

56 of Radionuclides: Part 1


VRecord :ij; C5 Stndr D;c .cat _aes Stdr L- Vearlor;,No.S.ti : - Coda. 1 C tStandard : iVrerloni Til Douen:- D0t ;x.alt -. omns. aso Data3595 ICRP iCRP 1991 1990 rRecommendations of the drg8012.rOO 1994 R Proposed ICRP 1991

Publication International Commission on reg8,29.rOl Publication 6060 _____ Radiological Protection___________

35i96 ICRP ICRP 1991 1990 Recommnendations of the drg8014.rOO 1994 R Proposed ICRP 1991Publication international Commission on reg8.1 3.rO03 Publication 60

__________60 _____ Radiological Protection

3597 ICRP ICRP NlS 1990 Recommendations of the minm1 302 1 994 R iCRP 1 991

Publication International Commission on Publication 6060 _____ Radiological Protection

3598 ICRU ICRU Report 1978 Certification of Standardized drgopO32-5.rOO 1984 R _iCRU Report 12 196812 Radioactive Sources ____

3599 ICRU ICRU Report N/S CeSCrtfcio of Standardizd Inrn1245 App. B 1991 R _iCRU Report 12 196812 Radioactive Sources _______

3600 ICRU ICRU Report 198 C regl108Sr02 1987 R ICRU Report 12 19681 2 Radioactive Sources

3601 iCRU ICRU Report 1968 Certification of Stanoardized reg8.21 .rO 1979 R ICRU Report 12 196812 Radioactive Sourcestion

3602 ICRU ICRU Report 1969 Certification of Standardized reg8.23.rOl 1981 R ICRU Report 12 196812 Radioactive Sourcestion

3603 ICRU ICRU Report NIS Radiation Dosimnetry: X-Rays and inmi245 App B 1991 R ICRU Report 14 196914 Gamma Rays with Maximum

Photon Energies Between 0.6 and60 Raio a P50 MeV _

3604 ICRU ICRU Report 1969 Radiation Dosimetry: X-Rays and reg8.33.rOO 1991 R ICRU Report 14 196914 Gamma Rays with Maximum

Photon Energies Between 0.6 and

3605 ICRU ICRU Report N/S Measurement of Low-Level minm 245 App. B 1991 R ICRU Report 22 197222 Radioactivity S

3606 ICRU ICRU Report 1972 Measurement of Low-Level reg4.15.rO1 1979 R ICRU Report 22 197222 Radioactivity Sourc

3607 ICRU ICRU Report N/S Qualic ation minm1 245 App. 8 1991 R ICRU Report 40 198640 Protection uc

3608 ICRU ICRU Report 1989 Quality Factor in Radiation reg8.33.rOO 1991 R ICRU Report 40 196840 Protection

__0 IC_ _CR Reor 199 Rdain__mty -asadre83.O 19 CURpr 4 16

-3

10

z

C-)

-4o

tA'I

0A0


i~R eco rd C o eS a n d r d - i ; D o u e nt~ ^ o A c e t- L tIe s S t and ard L .;. Sate t Ve r i ootaD AC e .t a h rions o .Xt 'iilt C . o Date

3609 IEEE IEEE 242 1986 Recommended Practice for not88-45 1988 R Cited as IEEE IEEE 242 1986 R91

Protection and Coordination of 24?Industrial and Commercial PowerSystems .

3610 IEEE IEEE 7-4.3.2 1993 Standard Criteria for Digital drglO39.rOO 1995 R IEEE 7-4.3.2 1993


3611 IEEE IEEE 7-4.3.2 1993 Standard Criteria for Digital drg1039.rOO 1995 R IEEE 7-4.3.2 1993


3612 IEEE IEEE 242 1986 Recommended Practice for not92-51.s01 1994 R IEEE 242 1986 R91

Protection and Coordination ofIndustrial and Commercial PowerSystems

3613 IEEE IEEE 242 1986 Recommended Practice for not93-64 1993 R IEEE 242 1986 R91

Protection and Coordination ofIndustrial and Commercial Powersystems __

3614 IEEE IEEE 245 N/S Not Found inm1245 App. B 1991 R Not found n/a

3615 IEEE IEEE 279 1971 Criteria for Safety Systems for 10cfrSO.55a 1994 P IEEE 279 also IEEE 603 1991

Nuclear Power Generating designated

Stations ANSI N42.7

3616 IEEE IEEE 279 N/S Criteria for Safety Systems for buI80-016 1980 P IEEE 279 also IEEE 603 1991


Stations ANSI N42.7

3617 IEEE IEEE 279 N/S Criteria for Safety Systems for buI90-001 1990 P IEEE 279 also IEEE 603 1991


Stations ANSI N42.7



Recotd S-tenderdrM ? Dc Acc~i Latest tandard Laiteit Version

code"; Standard .ewnin .T.t.. Document D

3618 IEEE IEEE 279 N/S Criteria for Safety Systems for buI90-001.sO1 1992 R IEEE 603 1991


3619 IEEE IEEE 279 NIS Criteria for Safety Systems for bu193-003 1993 R IEEE 603 1991


3620 IEEE IEEE 279 N/S Criteria for Safety Systems for cir78-19 1978 A IEEE 279 also IEEE 603 1991


Stations ANSI N42.7

3621 IEEE IEEE279 1971 Criteria for Safety Systems for drg1042.rOO 1995 R IEEE 603 1991

Nuclear Power GeneratingStations ______________ _______

362 IEEE IEE 279 1968 Criteria for Safety Systems for drg1O42.rOO 1995 IEEE 603 1991


_______

3623 IEEE IEE 1971 Criteria for Safety Systems for drgicl 21 -6.rOO 1982 R IEEE 603 1991


3624 IEEE IEEE 279 1971 Criteria for Safety Systems for gIt79-005 1979 P IEEE 603 1991


3625 IEEE 279 N/S Criteria for Safety Systems for gIt79-066 1979 R IEEE 603 1991

Nuclear Power GeneratingStations _

3626 IEEE IEEE 279 1971 Criteria for Safety Systems for git80-1 13 1980 R IEEE 603 1991

Nuclear Power GeneratingStations__ _ _ _ _ _ _ ___ _ _ _ _ _ _

3627 I IEEE EEET219 1971 Criteria for Safety Systems for gitsl-007 1981 P IEEE 279 also IEEE 603 1991


Stations ANSI N42.7

3628 IEEE IEEE 279 NIS Criteria for Safety Systems for gIt90-006 1990 R IEEE 279 also IEEE 603 1991


Stations ANSI N42.7

00

zx

C,

00


ecord i: S:dAi: ...... -Sc:dfd AL ef Standard Laits Vr sin

No C od, Standard V ri n Ttle. .:.:. ab"it Co m m en ts Version . . ' .,,0X3629 IEEE IEEE 279 N/S Criteria for Safety Systems for gIt92-004 1992 P IEEE 603 1991


3630 IEEE IEEE 279 N/S Criteria for Safety Systems for git92^008 1992 R IEEE 603 1991Nuclear Power GeneratingStations

3631 IEEE IEEE 279 1971 Criteria for Safety Systems for inm1245 App. B 1991 R IEEE 603 1991Nuclear Power GeneratingStations

3632 IEEE IEEE 279 1971 Criteria for Safety Systems for inm2515/065 1990 R IEEE 603 1991

Nuclear Power GeneratingStations.

3633 IEEE IEEE 279 1978 Criteria for Safety Systems for inm25615065 1990 R IEEE 603 1991Nuclear Power GeneratingStations

3634 IEEE IEEE 279 N/S Criteria for Safety Systems for inm37700 1990 R IEEE 603 1991


3635 IEEE IEEE 279 N/S Criteria for Safety Systems for inm37828 1988 R IEEE 603 1991Nuclear Power GeneratingStations


3637 IEEE IEEE 279 N/S Criteria for Safety Systems for inm51053 1984 B IEEE 603 1991Nuclear Power GeneratingStations


3639 IEEE IEEE 279 N/S Criteria for Safety Systems for inm5106l 1984 5 IEEE 603 1991Nuclear Power GeneratingStations

3640 IEEE IEEE 279 N/S Criteria or Safety Systems for inm51063 1985 R IEEE 603 1991Nuclear Power GeneratingStationsI

00I-.

zni

-4


S aRecord . it . . D - E: L:est Standard L .Atet Versionor oNon.:i C atode.. v. :Sta ndad r Do"u' ient... ' D abilit' e .. *: J. .: VOISIO.i Date:

3641 IEEE IEEE 279 N/S Criteria for Safety Systems for inm51065 1984 R IEEE 603 1991Nuclear Power GeneratingStations _

3642 IEEE IEEE 279 1971 Criteria for Safety Systems for inm52001 1995 R IEEE 603 1991Nuclear Power GeneratingStations l _..:_.__

3643 IEEE IEEE 279 1971 Criteria for Safety Systems for inm52002 1995 R IEEE 603 1991Nuclear Power GeneratingStations

3644 IEEE IEEE 279 N/S Criteria for Safety Systems for inm52051 1984 H IEEE 603 1991Nuclear Power GeneratingStations _


3646 IEEE IEEE 279 N/S Criteria for Safety Systems for inm52055 1984 _ IEEE 603 1991Nuclear Power GeneratingStations

3647 IEEE IEEE 279 N/S Criteria for Safety Systems for inm9900/STS 1986 R IEEE 603 1991Nuclear Power GeneratingStations__ _ _ _ _ _ _

3648 IEEE IEEE 279 N/S Criteria for Safety Systems for not92-46 1992 R IEEE 603 1991Nuclear Power GeneratingStations

3649 IEEE IEEE 279 1977 Criteria for Safety Systems for not95-13 1995 R IEEE 603 1991Nuclear Power GeneratingStations

3650 IEEE IEEE 279 1971 Criteria for Safety Systems for not95-13.sO1 1995 - IEEE 603 1991Nuclear Power GeneratingStations :: _____

3651 IEEE IEEE 279 1971 Criteria for Safety Systems for nurego737 1980 P IEEE 603 1991Nuclear Power GeneratingStations : :

3652 IEEE IEEE 279 NIS Criteria for Safety Systems for nuregO933, 1992 R IEEE 603 1991Nuclear Power Generating 3.110Stations .

z

(-I

tj



Recotd Sandard 7 . Dec. A .ept- Late t ASta . ..L.a . ..tVe...

3653 IEEE IEEE 279 1971 Critei o aeySsesfr nureg0933, 1992 A IEEE 603 1991

Nuclear Power Generating 3.1 56C Stations

3654 IEEE IIEEE 279 1979 Criteria for Safety Systems for nuregO933, 3.50 1984 A IEEE 603 1991

Nuclear Power Generating -

Stations

3655 IEEE IEEE 279 1971 Criteria for Safety Systems for nuregO933, 3.64 1983 R IEEE 603 1991


3656 IEEE IEEE 279 N/9 Criteria for Safety Systems for nuregO933, 3.70 1991 R IEEE 603 1991


3657 IEEE IEEE 279 1971 Criteria for Safety Systems for regl .106.r36 1977 IEEE 279 also IEEE 603 1991


Stations ANSI N42.7

3658 IEEE IEEE 279 1971 Criteria for Safety Systems for reg.1138.r73 1995 R .IEEE 603 1991


365 IEEE IEEE 279 1971 Criteria for Safety Systems for regl.151.rOO 1983 P IEEE 279 also IEEE 603 1991


Stations ANSI N42.7

3660 IEEE IEEE 279 1971 Criteria for Safety Systems for reg1.152.rOO 1985 IEEE 279 also IEEE 603 1991


Stations ANSI N42.7

3661 IEEE IEEE 279 1971 Criteria for Safety Systems for regl .153.rOO 1985 P iEEE 279 also IEEE 603 1991


Stations ANSI N42.7

3662 IEEE IEEE 279 1971 Criteria for Safety Systems for reg 1.22.rOO 1972 A IEEE 279 also IEEE 603 1991


Stations ANSI N42.7

_66 =fE IEE 27 191 Ciei oaeySsesfr rg1 .rO i8 EE29as EE6319


ecod . .t..nda .d rd or Accpt i. Latest.Standard Lats Version

No. code Stanidaird Veso li ocutnent Dae ablt Cmets Veonat3663 IEEE IEEE 279 1971 Criteria for Safety Systems for regl.45.rOO 1973 P IEEE 279 also IEEE 603 1991

Nuclear Power Generating designatedStations ANSI N42.7

3664 IEEE IEEE 279 1971 Criteria for Safety Systems for regl.47.rOO 1973 P IEEE 279 also IEEE 603 1991Nuclear Power Generating designatedStations ANSI N42.7

3665 IEEE IEEE 279 N/S Criteria for Safety Systems for regl.52.rO2 1978 A IEEE 279 also IEEE 603 1991Nuclear Power Generating designatedStations ANSI N42.7

3666 IEEE IEEE 279 N/S Criteria for Safety Systems for reg1.53.rOO 1973 P General IEEE 603 1991Nuclear Power Generating endorsementStations

3667 IEEE IEEE 279 1971 Criteria for Safety Systems for regl.62.rOO 1973 P IEEE 279 also IEEE 603 1991Nuclear Power Generating designatedStations ANSI N42.7

3668 IEEE IEEE 279 1971 Criteria for Safety Systems for regl.70.rO3 1978 P IEEE 279 also IEEE 603 1991Nuclear Power Generating designatedStations ANSI N42.7

3669 IEEE IEEE 279 1971 Criteria for Safety Systems for reg1.75.r02 1978 P IEEE 279 also IEEE 603 1991Nuclear Power Generating designatedStations ANSI N42.7

3670 IEEE IEEE 279 1971 Criteria for Safety Systems for reg1 90.rO1 1977 P With additional IEEE 603 1991Nuclear Power Generating requirementsStations stipulated

3671 IEEE IEEE 279 N/S Criteria for Safety Systems for regl.95.rOl 1977 A IEEE 279 also IEEE 603 1991Nuclear Power Generating designatedStations ANSI N42.7

U.)00

C,Z

'0W4

'4)

z

tit

00



:: Ad E ii- Standard D::: Ae . .. :-Latest Standard Laes Ver.:on

N o. C ode~ St nfdiVr l nT tl o u t D atae obilitlo m n sV r i nD t

3672 IEEE IEEE 279 1971 Criteria for Safety Systems for regl.97.rO3 1983 P IEEE 279 also IEEE 603 1991


Stations ANSI N42.7

3673 IEEE IEEE 279 N/S Criteria for Safety Systems for reg2.2.rOO 1973 A IEEE 279 also IEEE 603 1991


Stations ANSI N42.7

3674 IEEE IEEE 279 1971 Criteria for Safety Systems for regb.30.roo 1974 R IEEE 279 also IEEE 603 1991


Stations ANSI N42.7

3675 IEEE IEEE 279 N/S Criteria for Safety Systems for srp3.1 1 1981 R IEEE 279 also IEEE 603 1991Nuclear Power Generating designated

Stations ANSI N42.7

3676 IEEE IEEE 279 N/S Criteria for Safety Systems for srp3.6.1 1990 R IEEE 279 also IEEE 603 1991


Stations ANSI N42.7

3677 IEEE IEEE 279 N/S Criteria for Safety Systems for srp5.2.2 1988 P4IEEE 29 also IEEE 603 1991


Stations ANSI N42.7

3678 IEEE IEEE 279 N/S Criteria for Safety Systems for srp7.1 1984 A IEEE 603 1991Nuclear Power GeneratingStations _ _ _ _ _ _ _ _ _ _

3679 IEEE IEEE 279 N/S Criteria for Safety Systems for srp7.2 1981 A IEEE 279 also IEEE 603 1991


Stations ANSI N42.7

3680 IEEEt IEEE 279 N/S Criteria for Safety Systems for srp7.3 1981 A IEEE 279 also IEEE 603 1991Nuclear Power Generating designated

Stations ANSI N42.7


Record Stindard Do. A rd Lateist Version.o. Code. St : ._.na ...V...r..D......... Comments . . D

3681N IEEE IEEE 279 N/S Criteria for Safety Systes for srp7.6 1981 P IEEE 279 also IEEE 603 1991Nuclear Power Generating designatedStations ANSI N42.7

3682 IEEE IEEE 279 N/S Criteria for Safety Systems for srp7.7 1984 P IEEE 279 also IEEE 603 1991Nuclear Power Generating designatedStations ANSI N42.7

3683 IEEE IEEE 279 1971 Criteria for Safety Systems for srp8A 1981 P IEEE 279 also IEEE 603 1991Nuclear Power Generating designatedStations ANSI N42.7

3684 IEEE IEEE 279 N/S Criteria for Safety Systems for srp9.2.2 1986 P IEEE 279 also IEEE 603 1991Nuclear Power Generating designatedStations ANSI N42.7

3685 IEEE IEEE 279 1971 Criteria for Safety Systems for stsb&wB3.3.1 1 1992 R IEEE 603 1991Nuclear Power GeneratingStations

3686 IEEE IEEE 279 1971 Criteria for Safety Systems for stsb&wB3.3.12 1992 R IEEE 603 1991Nuclear Power GeneratingStations

3687 IEEE IEEE 279 1971 Criteria for Safety Systems for stsb&wB3.3.8 1992 R IEEE 603 1991Nuclear Power GeneratingStations _

3688 IEEE IEEE 279 1971 Criteria for Safety Systems for stsb&wB3.6.1 1992 P IEEE 603 1991Nuclear Power GeneratingStations __ I _ __

3689 IEEE IEEE 279 1971 Criteria for Safety Systems for stsceB3.3.1(A) 1992 P IEEE 603 1991Nuclear Power GeneratingStations

3690 IEEE IEEE 279 1971 Criteria for Safety Systems for stsceB3.3.1(D) 1992 P IEEE 603 1991Nuclear Power GeneratingStations _ ___ _

00

z

(a

z

(IQ

(5

00

D

W

q

oo

oo


Part A Industry Consensus Codes and Standards

369 .EE I. E 279 19 g t d71 Crie ria fo S fe ty Syste m for lstsce B 3.3.4 1992 P IEEE 03 199

Nuclear Power Generating

S tatio n s _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

3692 IEEE IEEE 279 1971 Criteria for Safety Systems for stsceB3.3.5 1992 P IEEE 603 1991


Stations

3693 IEEE IEEE 279 1971 Criteria for Safety Systems for stsceB3.3.5 1992 _ IEEE 603 1991

Nuclear Power GeneratingStations ____________





Stations PowerGneratin

369 -IEEE IEEE 279 1971 Criteria for Safety Systems for stswstB3.3.1 1992 P IEEE 603 1991


Stations

3697 IEEE IEEE 279 1971 Criteria for Safety Systems for stswstB3.1 1992 P IEEE 603 1991Nuclear Power GeneratingStations________________

3698 -IEEE IEEE 279 1971 Criteria for Safety Systems for stswstB3.3.l 1992 P IEEE 603 1991-

Nuclear Power GeneratingStations________________

-- H98 ~ E ~ EE29 17. rt~afrSft ytm o twt351 1b6 IEEE 630 1988 R9

3699 IEEE IEEE 301 1976 Standard Test Procedures for reg5.9.rO2 1983 R IEEE 301 1988 R94

Amplifiers and Pre-Amplifiers UsedWith Detectors of IonizingRadiation

IEE 0 174 Stnar IREnE 308 19913700 IEEE IEEE 308 1974 Standard Criteria for Class 1 E inm1245 App. B 1991 R

Power Systems for Nuclear PowerGenerating Stations

3701 IEEE IEEE 308 N/S Standard Criteria for Class lE 1nm51051 1984 R IEEE 308 1991

Power Systems for Nuclear Power

Generating Stations ____ _

00

z

C-4


M.

Re c r S.nd r D ec A c e t L atest S tandardi - L.ate..st V ersion. i :?~E::0z: 0; : n -i i C Li St~V:

iN oZ Code.; . Sta nid rd - . V ersion.T 0ite .. .. i D ocum ent*-. D ate ability Com ments. .. <.. V era ..... D ate

3702 IEEE IEEE 308 N/S Standard Criteria for Class lE inm51053 1984 R IEEE 308 1991Power Systems for Nuclear Power: Generating Stations-

3703 IEEE IEEE 308 N/S Standard Criteria for Class lE inm51061 1984 R IEEE 308 1991Power Systems for Nuclear PowerGenerating Stations

3704 IEEE IEEE 308 N/S Standard Criteria for Class 1E inm51063 1985 R IEEE 308 1991Power Systems for Nuclear PowerGenerating Stations

3705 IEEE IEEE 308 N/S Standard Criteria for Class lE inm5r1065 1984 R IEEE 308 1991Power Systems for Nuclear PowerGenerating Stations

3706 IEEE IEEE 308 N/S Standard Criteria for Class 1E inm52051 1984 R IEEE 308 1991Power Systems for Nuclear Power

____ __ Generating Stations

3707 IEEE IEEE 308 N/S Standard Criteria for Class IE inm52055 1984 R . IEEE 308 1991Power Systems for Nuclear PowerGenerating Stations __

3708 IEEE IEEE 308 N/S Standard Criteria for Class IE inm703408 1981 R IEEE 308 1991Power Systems for Nuclear Power

._ Generating Stations

3709 IEEE IEEE 308 1974 Standard Criteria for Class 1 E not84-02 1984 R Cited for IEEE 308 1991Power Systems for Nuclear Power definitions

.__ _ Generating Stations _

3710 IEEE IEEE 308 1974 Standard Criteria for Class 1 E not93-54 1993 R IEEE 308 1991Power Systems for Nuclear Power

Generating Stations

3711 IEEE IEEE 308 N/S Standard Criteria for Class E nurego933, 1991 R IEEE 308 1991Power Systems for Nuclear Power 3.128Generating Stations

3712 IEEE IEEE 308 N/S Standard Criteria for Class 1E reg.153.rOO 1985 R IEEE 308 1991Power Systems for Nuclear PowerGenerating Stations

3713 IEEE IEEE 308 1971 Standard Criteria for Class 1E regl.32.r32 1977 R IEEE 308 1991Power Systems for Nuclear Power .

Generating Stations _

371 IEE IEE 30 _ / tnadCiei o ls E Tg, O 18 EE3819

z

-31

LI)



R tdad D ccep Latest' Standard Latitd XVrsiono.od S ta n da rd V r i nT t eD(u e t D t b l t C 0 i e t " V o rs qIon D at e

3714 IEEE IEEE 308 1974 Standard Criteria for Class 1E regl.32.rO2 1977 P With IEEE 308 1991

Power Systems for Nuclear Power exceptions

Generating Stations

3715 IEEE IEEE 308 1971 Standard Criteria for Class 1E regl.41.rOO 1973 P Specified IEEE 308 1991

Power Systems for Nuclear Power design

Generating Stations requirements

3716 IEEE IEEE 308 1971 Standard Criteria for Class 1E regl.70.rO3 1978 R Cited for IEEE 308 1991

Power Systems for Nuclear Power definitions

Generating Stations

3717 IEEE IEEE 308 1980 Standard Criteria for Class lE regl.9.r03 1993 P Endorsed with IEEE 308 1991

Power Systems for Nuclear Power exceptions by

Generating Stations Reg, Guide1.32

3718 IEEE IEEE 308 1974 standard Criteria for Class 1E reg5.44.rO2 1980 P Endorsed by IEEE 308 1991

Power Systems for Nuclear Power Reg. Guide

Generating Stations 1.32

3719 IEEE IEEE 308 N/S Standard Criteria for Class 1E srp3.6.1 1990 R Cited for IEEE 308 1991

Power Systems for Nuclear Power definition

Generating Stations

3720 IEEE IEEE 308 1974 Standard Criteria for Class IE srp8.2 1983 P Acceptance IEEE 308 1991

Power Systems for Nuclear Power criteria/guidelin

Generating Stations es

3721 IEEE IEEE 308 N/S Standard Criteria for Class lE srp8.3.1 1981 P Acceptance IEEE 308 1991

Power Systems for Nuclear Power criteria and

Generating Stations requirements

3722 IEEE IEEE 308 N/S Standard Criteria for Class 1E srp8.3.2 1981 P IEEE 308 1991


3723 IEEE IEEE 308 1978 Standard Criteria for Class 1E sts4-geB3.8.1 1992 P IEEE 308 1991


3 IEEE IEEE 308 1978 Standard Criteria for Class 1 E sts4-geB3.8.4 1992 P IEEE 308 1991



"A RAcordStaar eAt ccept Late.t Standard iLtest ers.ionoodiie** Sta r Ti ouet te ilt^ i; ^ ; < v-.Ioi' , i - W ... Da t

3725 IEEE IEEE 308 N/S Standard Criteria for Class E sts6-geB3.8.1 1992 P IEEE 308 1991Power Systems for Nuclear PowerGenerating Stations

3726 IEEE IEEE 308 1978 Standard Criteria for Class 1E sts6-geB3.8.4 1992 P IEEE 308 1991Power Systems for Nuclear PowerGenerating Stations

3727 IEEE IEEE 308 N/S Standard Criteria for Class lE stsb&wB3.8.1 1992 R IEEE 308 1991Power Systems for Nuclear PowerGenerating Stations

3728 IEEE IEEE 308 1978 Standard Criteria for Class 1 E stsb&wB3.8.4 1992 P IEEE 308 1991Power Systems for Nuclear PowerGenerating Stations

3729 IEEE IEEE 308 1978 Standard Criteria for Class lE stsceB3.8.1 1992 P IEEE 308 1991Power Systems for Nuclear PowerGenerating Stations

3730 IEEE IEEE 308 1978 Standard Criteria for Class 1E stsceB3.8.4 1992 P IEEE 308 1991Power Systems for Nuclear PowerGenerating Stations

3731 IEEE IEEE 308 1978 Standard Criteria for Class 1 E stswstB3.8.1 1992 P IEEE 308 1991Power Systems for Nuclear PowerGenerating Stations

3732 IEEE IEEE 308 1978 Standard Criteria for Class 1E stswstB3.8.4 1992 P IEEE 308 1991Power Systems for Nuclear PowerGenerating Stations

3733 IEEE IEEE 317 N/S Standard for Electric Penetration inm51051 1984 R IEEE 317 1983 R92Assemblies in ContainmentStructures for Nuclear PowerGenerating Stations

3734 IEEE IEEE 317 N/S Standard for Electric Penetration inm51053 1984 R IEEE 317 1983 R92Assemblies in ContainmentStructures for Nuclear PowerGenerating Stations

z

C)

U'5P'C

z

F),

a

t'.



Re o dS e d r e . A 'cep Latost Standard Lotest Vetlon

0Ai IdsAi3735 IEEE IEEE 317 N/S Standard for Electric Penetration inm51055 1984 8 IEEE 317 1983 892

Assemblies in ContainmentStructures for Nuclear PowerGenerating Stations

3736 IEEE IEEE 317 N/S Standard for Electric Penetration inm52051 1984 R IEEE 317 1983 R92


3737 IEEE IEEE 317 N/S Standard for Electric Penetration inm52053 1984 R IEEE 317 1983 R92


3738 IEEE IEEE 317 N/S Standard for Electnc Penetration 1nm52055 1984 R IEEE 317 1983 R92


3739 IEEE IEEE 317 1976 Standard for Electric Penetration nureg0933, 2.B- 1983 R IEEE 317 1983 R92

Assemblies in Containment 9Structures for Nuclear PowerGenerating Stations

3740 IEEE IEEE 317 1983 Standard for Electric Penetration reg1.63.r03 1987 P Provides a IEEE 317 1983 R92

Assemblies in Containment method

Structures for Nuclear Power acceptable to

Generating Stations the NRC

3741 IEEE IEEE 317 1976 Standard for Electric Penetration regl.63.r03 1987 8 Reg. Guide IEEE 317 1983 892

Assemblies in Containment 1.63 Rev 2

Structures for Nuclear Power endorsed 317-

Generating Stations 1976 withseven except


Part A - Industry Consensus Codes and Standards. .

I: : : . : .: .: : .: A ......- :#.: I . : : f ;~ .: . t: ? ,i~. .... ,,, . V,.,:i, ,,$-,fi .. =771,I d '; Ei ii 0 f ,

Record I7No.

3742ICodeIEEE

1:.:: ::: :::.: ' .i:2 yr .: R:: -

IEStEEd3IEEE 317

jtiandard 5. , l . IN/'SthO '

Doe.I t*I ai4ii:

Cnmment,,,, ,

Aumented by

Vri.t , o-,I, . V:rst^;n i;

3i43 IEEE JIEEE 317 N/S

; . Dated..:

3744 IEEE tIEEE317 NIS

3745 IEEE IEEE 317 N/S

Standard for Electric PenetrationAssemblies in ContainmentStructures for Nuclear PowerGenerating Stations



Standard f lec netrationAssemblies in ContainmentStructures for Nuclear PowerGenerating Stations

Standard: for Qualifying Class 1 EEquipment for Nuclear PowerGenerating StationsStandard for Qualifying Class 1 EEquipment for Nuclear PowerGenerating StationsStandard f;oQualifying Class 1 E

Equipment for Nuclear PowerGenerating StationsStandard for Qualifying Class 1E

Equipment for Nuclear PowerGenerating Stations

srp3.11 1981:: : 4^t _

r Augmented byReg. Guide1.63 andNUREG-0588

I'l-Ct't u u lum I

I 1c-. . 92-- ----- - .srp8.1 1981 R Table 8-1

Acceptancecriterion/guidelines

Mr-r J3 I I

r1U FF <1'7 19834M MIZ

. --- . .1

srp8.3.1 191 P IEEE 317 1983 R92

.__._____ = 1 RR7P.. IL tJsrp8.3.2 1981 P I~r- j5 I IU~ n- 1

4 4 - - - . - I-I IEEE 323 1983 O90

3746 I IEEE JIEEE 323 1974 10Ocfr50.49 1994 H

I I 4 Ibu177-005 1977 8 Referred to in 11it 3�3 101Js ".212_

_

3747 IEEE IEE 3Z43 1974 E�W77005- 1977 R Referred to intext

Referenced intext

lIEEE -4,t I ZjUo. n.i.,= 45< t oR':I RM[l

37 V EEE 4IEE: 323 1971buI79-001IB j-i85* 8 IEEE 323 1983 R90

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currentindustrystandard_ _I-. _ :

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3750 IEEE IEEE 323 1974 Standard for Qualifying Class 1 E bul79-001 b.s01 1980 P Approved IEEE 323 1983 890

Equipment for Nuclear Power requirements

Generating Stations for equipment

3751 IEEE IEEE 323 1971 Standard for Qualifying Class 1E bul79 001b.sO2 1980 8 Referenced in IEEE 323 1983 890

Equipment for Nuclear Power text

Generating Stations

3752 IEEE IEEE 323 1974 Standard for Qualifying Class 1E bu179-001b.sO2 1980 P Licensees IEEE 323 1983 R90

Equipment for Nuclear Power reviewed

Generating Stations against IEEE323-1974

3753 IEEE IEEE 323 1974 Standard for Qualifying Class 1 E bul80-023 1980 P Standard to be IEEE 323 1983 R90

Equipment for Nuclear Power used per

Generating Stations applicablerequirements

3754 IEEE IEEE 323 1974 Standard for Qualifying Class 1E bu184-002 1984 R IEEE 323 1983 R90


3755 IEEE IEEE 323 N/S Standard for Qualifying Class 1 E bu188-003 1988 I IEEE 323 1983 R90


3756 IEEE IEEE 323 1971 Standard for Qualifying Class 1 E cir78-08 1978 R IEEE 323 1983 R90

Equipment for Nuclear PowerGenerating Stations_______

3757 IEEE IEEE 323 1974 Standard for Qualifying Class 1E cir78-08 1978 . IEEE 323 1983 R90


3758 IEEE IEEE 323 1974 Standard for Qualifying Class lE drgrsO50-2.rOO 1979 P Proposed IEEE 323 1983 R90

Equipment for Nuclear Power regl.131.rOl

G enerating Stations 0 4 9 _1979 ___. _ ____________

3759 IEEE IEEE 323 1974 Standard for Qualifying Class 1E git79-049 1979 - 8 IEEE 323 1983 R90Equipment for Nuclear PowerGenerating Stations ___.

3760 IEEE IEEE 323 1971 Standard for Qualifying Class .E glt8O-010 1980 A IEEE 323 1983 890Equipment for Nuclear Power

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3761 IEEE IEEE 323 1974 Standard for Qualifying Class lE gItBO-OlO 1980 A IEEE 323 1983 R90Equipment for Nuclear PowerGenerating Stations

3762 IEEE IEEE 323 1971 Standard for Qualifying Class 1E glt80-013 1980 R IEEE 323 1983 R90


3763 IEEE IEEE 323 1974 Standard for Qualifying Class 1E gIt80-013 1980 R IEEE 323 1983 R90Equipment for Nuclear PowerGenerating Stations

3764 IEEE IEEE 323 1974 Standard for Qualifying Class 1E git80-097 1980 R IEEE 323 1983 R90Equipment for Nuclear PowerGenerating Stations

3765 IEEE IEEE 323 1974 Standard for Qualifying Class 1 E gIt82-009 1982 Requirement IEEE 323 1983 R90

Equipment for Nuclear Power for equipment

Generating Stations

3766 IEEE IEEE 323 1971 Standard for Qualifying Class 1 E glt82-021 1989 R Referenced in IEEE 323 1983 R90Equipment for Nuclear Power . text

Generating Stations

3767 IEEE IEEE 323 1974 Standard for Qualifying Class lE g1t89-021 1989 R Referenced in IEEE 323 1983 R90Equipment for Nuclear Power textGenerating Stations

3768 IEEE IEEE 323 N/S Standard for Qualifying Class 1E inml 245 App. B 1991 R IEEE 323 1983 R90Equipment for Nuclear PowerGenerating Stations .

3769 IEEE IEEE 323 1974 Standard for Qualifying Class 1E inmr25154076 1986 R IEEE 323 1983 R90Equipment for Nuclear PowerGenerating Stations

3770 IEEE IEEE 323 N/S Standard for Qualifying Class 1E inm235061 1985 R IEEE 323 1983 R90Equipment for Nuclear PowerGenerating Stations

3771 IEEE IEEE 323 N/S Standard for Qualifying Class 1E inm35703 1993 R IEEE 323 1983 R90Equipment for Nuclear Power

Generating Stations

3772 IEEE IEEE 323 1974 Standard for Qualifying Class 1E inm50100 1985 R IEEE 323 1983 890Equipment for Nuclear PowerGenerating Stations

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Equipment for Nuclear Power under generic

Generating Stations implication

3785 IEEE IEEE 323 1974 Standard for Qualifying Class 1 E not81 -29 1981 8 Referenced IEEE 323 1983 R90

Equipment for Nuclear Power under Test

Generating Stations SummaryReport No. 1 _ ____

3786 IEEE IEEE 323 N/S Standard for Qualifying Class 1 E not82-04 1982 R Referenced in IEEE 323 1983 R90


Generating Stations _______ ______

3787 IECEE IEEE 323 1971 Standard for Qualifying Class 1E not82-52 1982 R Referenced IEEE 323 1983 890

Equipment for Nuclear Power under generic

Generating Stations implfcation

3788 IEEE IEEE 323 1974 Standard for Qualifying Class 1 E not82-52 1982 8 Referenced in IEEE 323 1983 R90

Equipment for Nuclear Power test report

Generating Stations _____section

3789 IEEE IEEE 323 N/S Standard for Qualifying Class 1 E not83-72 1983 R lReferred to in IEEE 323 1983 R90

Equipment for Nuclear Power types of testGenerating Stations

3790 IEE IEEE 323 1974 Standard for Qualifying Class 1 E not84-23 1984 R Test program IEEE 323 1983 R90

Equipment for Nuclear Power patterned after

Generating Stations 323(Referenced)

-3791 IEEE IEEE 323 1974 Standard for Qualifying Class 1 E not84-47 1984 R References IEEE 323 1 983 R90

Equipment for Nuclear Power test conditions

Generating Stations in Appendix Aof IEEE 323

3792 IEEE IEEE 323 1971 Standard for Qualifying Class 1 E not85-39 198 8 Defines IEEE 323 18 9

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IEEE IEEE 323 1974 Standard for Qualifying Class 1 E not85-4 0 1985 P Reg. Guide

Equipment for Nuclear Power 1.89.endorses

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IEEE IEEE 323 1983 Standard for Qualifying Class 1 E not85-4 0 1985 R in


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Standard for Qualifying Class 1 EnEquipment for Nuclear PowerGenerating StationsStandard for Qualifying Class 1 E nEquipment for Nuclear PowerGenerating StationsStandard for Qualifying Class 1 E;Equipment for Nuclear PowerGenerating StationsStandard for Qualifying Ciass 1E r

Equipment for Nuclear PowerGenerating StationsStandard for Qualifying Class 1 EEquipment for Nuclear Power

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3804 IEEE IEEE 323 1974 Standard for Qualifying Class 1E srp3.11 1981 P Provides IEEE 323 1983 R90

Equipment for Nuclear Power acceptance

Generating Stations criteria

3805 IEEE IEEE 325 1971 (R77) Standard Test Procedures for reg5,9.rO2 1983 R IEEE 325 1986

Germanium Gamma-Ray Detectors

3806 IEEE IEEE 334 N/S IEEE Standard for Qualifying inm51051 1984 R IEEE334 1994

Continuous Duty Class 1 E Motorsfor Nuclear Power GeneratingStations

3807 IEEE IEEE 334 1971 IEEE Standard for Qualifying reg1.40.rOO 1973 P IEEE 334 1994

Continuous Duty Class 1E Motorsfor Nuclear Power GeneratingStations

3808 IEEE IEEE 334 1974 IEEE Standard for Qualifying regi.52.rO2 1978 P IEEE 334 1994


3809 IEEE IEEE 334 N/S IEEE Standard for Qualifying srp3.1 1 1981 P IEEE 334 1994


3810 IEEE IEEE 336 N/S Standard Installation, Inspection, drglO10.rOO 1992 P Endorsed by IEEE 336 1985 R91

and Testing Requirements for regi .30


3811 IEEE IEEE 336 N/S Standard Installation, Inspection, inm51061 1984 R IEEE 336 1985 R91

and Testing Requirements forPower, Instrumentation, andControl Equipment at NuclearFacilities

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and Testing Requirements for ANS 3.2, ANSIPower, Instrumentation, and 45.2.3, Reg.Control Equipment at Nuclear Guide 1.39Facilities

3813 IEEE IEEE 336 1971 Standard Installation, Inspection, regl.30.rOO 1972 P IEEE 336 also IEEE 336 1985 R91

and Testing Requirements for designated as

Power, Instrumentation, and ANSI N45.2.4Control Equipment at NuclearFacilities

3814 IEEE IEEE 338 N/S Standard Criteria for the Periodic inm37700 1990 R IEEE 338 1987 R93Surveillance Testing of NuclearPower Generating Station SafetySystems _ _ _ _ _ _

3815 IEEE IEEE 338 N/S Standard Criteria for the Periodic inm37828 1988 R IEEE 338 1987 R93

Surveillance Testing of NuclearPower Generating Station SafetySystems__ _ _ _ _ _

3816 IEEE IEEE 338 1977 Standard Criteria for the Periodic inm52001 1995 R IEEE 338 1987 R93Surveillance Testing of NuclearPower Generating Station SafetySystem s _ _ _ _ _ _ _ _ _ _

3817 IEEE IEEE 338 1977 Standard Criteria for the Periodic inm52002 1995 R IEEE 338 1987 R93Surveillance Testing of NuclearPower Generating Station SafetySystems

3818 IEEE IEEE 338 1975 Standard Criteria for the Periodic not95-13 1995 R IEEE 338 1987 R93Surveillance Testing of NuclearPower Generating Station SafetySystems

3819 IEEE IEEE 338 1975 Standard Criteria for the Periodic not95-13.sOl 1995 R IEEE 338 1987 R93Surveillance Testing of NuclearPower Generating Station SafetySystems



Record StndrdDoe. Accep` Laes tadadLaet Version

No Cde Standard Veso'il ouet Dt bilit Commrenits eso Date:

3820 IEEE IEEE 338 N/S Standard Criteria for the Per nureg933, 1990 R IEEE 338 1987 R93

Surveillance Testing of Nuclear 3.120Power Generating Station Safety

systems ______

382 IEEE IEEE 338 1987 (R93) Standard Criteria for the Periodic regi.1 18.r03 1995 P IEEE 338 1987 R93

Surveillance Testing of NuclearPower Generating Station SafetySystems________

3822 IEEE IEEE 338 N/S Standard Criteria for the Periodic reg1 .1 39.rOO 1978 A IEEE 338 1987 R93

Surveillance Testing of NuclearPower Generating Station Safety

Systems_______

3823 IEEE IEEE 338 N/S Standard Criteria for the Periodic srp5.4.7 1984 P Testability shall IEEE 338 1987 R93

Surveillance Testing of Nuclear meet

Power Generating Station Safety requirements

Systems _______of IEEE 338

3824 IEEE IEEE 338 /S Standard Criteria for the Periodic srp7.1 1984 P Endorsed by IEEE 338 1987 R93

Surveillance Testing of Nuclear Reg. Guide

Power Generating Station Safety 1 .118 for

Systems applicability toRTS andESFAS

3825 IEEE IEEE 338 NIS Standard Criteria for thePe;riodic srp7.2 1981 P Implied, Reg. IEEE 338 1987 R93

Surveillance Testing of Nuclear Guide 1.118

Power Generating Station Safety Supplements

Systems__________ ___

3826 IEEE IEEE 338 N/S Standard Criteria for the Periodic srp7.3 1981 P Implied, Reg. IEEE 338 1987 R93



Systems

3827 IEEE IEEE 338 NIS Standard Criteria for the Periodic srp8.3.1 1981 P Implied, Reg. IEEE 338 1987 R93



Systems ____ _

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Standatd VersionIEEE 344 1975

.. :fi0: : f : :,Doc. .I . 6 . i !i:Date:

1980

* Accep t Latest:Standarcd Lat Ve ionberComments *Vertionl Date i

P Per applicable IEEE 344 1987 R93

requirements

3829 1 IEEE tIEEE 344 j 1975

3830 EE J IEEE 344 N/S

3831 IEEE IEEE 344 1975

0

3832 1 IEEE FIEEE 344 1 976

Tnitle

Recommended Practice for

Seismic Qualification of Class 1 E

Equipment for Nuclear PowerGenerating StationsRecommended Practice forSeismic Qualification of Class 1 E

Equipment for Nuclear PowerGenerating StationsRecommended Practice forSeismic Qualification of Class 1 EEquipment for Nuclear PowerGenerating StationsRecommended Practice for

Seismic Qualification of Class 1E

Equipment for Nuclear PowerGenerating StationsRecommended Practice forSeismic Qualification of Class 1EEquipment for Nuclear PowerGenerating StationsRecommended Practice forSeismic Qualification of Class 1 EEquipment for Nuclear PowerGenerating StationsRecommended Practice forseismic Qualification of Class 1EEquipment for Nuclear PowerGenerating StationsRecommended Practice forSeismic Qualification of Class 1 EEquipment for Nuclear PowerGenerating StationsRecommended Practice forSeismic Qualification of Class 1 EEquipment for Nuclear Power

buR88-003 1988 R

bu184-002 1984 R

glt80-097 11980 R IIEEE 344 1987 R93

-IIE 344 1987 R93

bDoc0entbu180-023

gIt87-002.sO1 19921 R _IEEE .344 1987 R93

__ _I IEEE 344 1987 R93

g~t87-00 3 ~ ~ IIEEE 344 1987 R93

3833 1 IEEE EEE 344 1975

3834 f IEEE IEEE 344 N/S inm 245 App. 8119911 . IEEE 344 1987 R93

3835 IEEE IEEE 3 1975 inm2525/1 2 4 1 R IEEE 344 4 1987 R93

3836 IEEE IEEE 344 1 NIS inm3870 3 I1993 R. IEEE 344 987 R93

L�� lGenerating Stations I L��

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3837 IEEE IEEE 344 1975 Recommended Practice for inmLOO 1985 R IEEE 344 1987 R93

Seismic Qualification of Class 1E.

. Equipment for Nuclear Power :Generating Stations

3838 IEEE IEEE 344 N/S Recommended Practice for inm51051 1984 R IEEE 344 1987 R93

Seismic Qualification of Class 1 EEquipment for Nuclear PowerGenerating Stations


Seismic Qualification of Class lEEquipment for Nuclear Power

Generating Stations

3840 IEEE IEEE 344 1976 Recommended Practice for inm52005 1995 R IEEE 344 1987 R93



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Seismic Qualification of Class 1 EEquipment for Nuclear Power

Generating Stations

3842 IEEE IEEE 344 NS5 Recommended Practice for inm52051 1984 R IEEE 344 1987 R93




3844 IEEE IEEE 344 N/S Recommended Practice for inrn5205 1984 R IEEE 344 1987 R93


3845 IEEE IEEE 344 1971 Recommended Practice f r not0-21 1980 R IEEE 344 1987 R93

Seismic Qualification of Class 1 EEquipment for Nuclear Power

Generating Stations384 IEE IEE 34 197 Reomene Prciefr.t 2 9 EE3418 9

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3848 i IEEE JIEEE 344

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1975 Recommended Practice for



Generating Stations

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Generating Stations

Doe.oAccepn-

t82-04 1982 R

wt83-11 1983 A

..Comments

Referenced intext

Endorsed byReg. Guide1.100

Latest: Standard.0$Version ;

IEEE 344

ot84-23 1 1984 R iTest program tIEEE 344 1987 R93

IEEE 344 1987 R93

section citation

nuregO737 I1980 1A 1 JIEEE 344 1987 R93

Lat1st RVeta3n

1987 R93

3850 t IEEE IEEE 344,uregO933, 2.5-

24

1984 1 R- IIEEE 344 1987 R93

ifl.E 1988j P {With -IEEE 344 1987 R9regl.100excepuIoI

3851 1 IEEE IEEE 344 exceptions

3852 1 IEEE EEE 344

_ _r_lregl.100.r 02 198 - IIEEE 344

1987 R9

3853 IEEE IEEE 344regl .1 28.r01 1978 1 P Should be

supplementedby Reg. Guide1.100

IEEE 3441987 R93

__ I -



Cod iStdrd Veso t ......... . . ..... 7' Tabitle - . Docuet Dat J ~ ComentSi- Version Date

3854 -- IEEE IEEE 344 1975 Recommended Practice for regil.9.r03 199 P Subject to IEEE 344 1987 R93

Seismic Qualification of Class 1 E regulatory

Equipment for Nuclear Power position of

Generating Stations Reg. Guide1 .100

3855 IEEE IEEE 344 1975 Recommended Practice for srp3.10 1981 P References IEEE 344 1987 R93

Seismic Qualification of Class 1 E endorsement

Equipment for Nuclear Power by Reg Guide

Generating Stations 1.100______

3856 IEEE IEEE 344 1971 Recommended Practice for srp3.10 1981 P Listed as IEEE 344 1987 R93

Seismic Qualification of Class 1E minimum

Equipment for Nuclear Power requirement

Generating Stations

3857 IEEE IEEE 344 N/S Recommended Practice for srp3.1 1 1981 P IEEE 344 1987 R93

Seismic Qualification of Class 1EEquipment for Nuclear PowerGenerating Stations______________

3858 IEEE IEEE 344 1975 Recommended Practice for srp5.4.12 1981 P With Reg. IEEE 344 1987 893

Seismic Qualification of Class 1E Guide 1.100,

Equipment for Nuclear Power 1.92, SRP

Generating Stations 3.92, 3.43,3.10Supplementing

3859 IEEE IEEE 352 1976 Guide for General Principles of nureg0933, Ref 1991 R IEEE 352 1987 R

Reliability Analysis of NuclearPower Generating Station SafetySystems

3860Standard Criteria for the eridic srp8.3.2 1981 R Typo in SRP IEEE 338 1987 R93

Surveillance Testing of Nuclear 338 vs. 378

Power Generating Station SafetySystems__ _

3861 IEEE IEEE 379 1977 Standard Application of the Single gIt81-018 1981 IEEE 379 1994

Failure Criterion to Nuclear PowerGenerating Station SafetySystems ____ __

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3862 IEEE IEEE 379 N/S Standard Application of the Single inm51051 1984 R IEEE 379 1994

Failure Criterion to Nuclear PowerGenerating Station SafetySystems



3864 IEEE IEEE 379 N/S Standard Application of the Single inm51055 1984 R- IEEE 379 1994

Failure Criterion to Nuclear PowerGenerating Station SafetySystems _

3865 IEEE IEEE 379 N/S Standard Application of the Single inm51061 1984 R- IEEE 379 1994


3866 IEEE IEEE 379 N/S Standard Application of the Single inm51063 1986 . IEEE 379 1994



Failure Criterion to Nuclear PowerGenerating Station SafetySystems ._ l

3868 IEEE IEEE 379 1977 Standard Application of the Single inm52001 1995 R IEEE 379 1994


3869 IEEE IEEE 379 1977 Standard Application of the Single inm52002 1995 R IEEE 379 1994

Failure Criterion to Nuclear Power

Generating Station SafetySystems




Recor'd . nar. .... ep-LtetSanadLeotVeeo


Failure Criterion to Nuclear PowerGenerating Station SafetySystems .



3873 IEEE IEEE 379 N/S Standard Application of the Single regl .153.rOO 1985 R IEEE 379 1994


3874 IEEE IEEE 379 1972 Standard Application of the Single regl.53.rOO 1973 P Generally IEEE 379 1994

Failure Criterion to Nuclear Power acceptableGenerating Station SafetySystems

3875 IEEE IEEE 379 N/S Standard Application of the Single srp7.1 1984 P IEEE 379 1994


3876 IEEE IEEE 379 N/S Standard Application of the Single srp7.2 1981 P Reg. Guide IEEE 379 1994

Failure Criterion to Nuclear Power 1.53

Generating Station Safety SupplementsSystems

3877 IEEE IEEE 379 N/S Standard Application of the Single srp7.3 1981 P Reg. Guide IEEE 379 1994

Failure Criterion to Nuclear Power 1.53

Generating Station Safety SupplementsSystems

3878 IEEE IEEE 379 N/S Standard Application of the Single srp8.3.1 1981 P IEEE 379 1994Failure Criterion to Nuclear PowerGenerating Station SafetySystems

3879 IEEE IEEE 379 N/S Standard Application of the Single srp8.3.2 1981 P IEEE 379 1994

Failure Criterion to Nuclear PowerGenerating Station SafetySystems _,,__ _ _

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I. , Ii-j a I IEEE IEEE 381 Nib

8821 IEEE 11EEE 382 I 1972

3883 i IEEE EEE 382 1982

000

Definitions of Terms Used in IEEEStandards on Nuclear PowerGenerating StationsStandard Criteria for Type Testsof Class 1 E Modules Used inNuclear Power GeneratingStationsStandard for Qualification ofActuators for Power OperatedValve Assemblies With Safety-Related Functions for NuclearPower PlantsStandard for Qualification ofActuators for Power OperatedValve Assemblies With Safety-Related Functions for NuclearPower PlantsStandard for Qualification ofActuators for Power OperatedValve Assemblies With Safety-Related Functions for NuclearPower PlantsStandard for Qualification ofActuators for Power OperatedValve Assemblies With Safety-Related Functions for NuclearPower PlantsStandard for Qualification ofActuators for Power OperatedValve Assemblies With Safety-Related Functions for NuclearPower Plants

l nm99uuWb I a:_tXtlNl{:TC q QRffI vvU

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Out of Print

IEEE 381withdrawn1991

Latest StandardVersionn/a

bulBO-023 T-1-9" j R _ _ _ l IEEE 382 1985

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not81 -29

1980

1981

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3884 IEEE IEEE 382 1972

3885 IEEE IEEE 382 1972not82-62 I~ H

Referenced intest resultssection

Referenced totest reportsection

Referred to inproblemdiscussion

IEEE 382 1 1985

IEEE 382 1985

3886 1 IEEE iEEE 382 1972 not83-72 1983 H IEEE 382 1985

L��_ _ .. S


-Record ... t.da e.s-. A Stiadard Latee't Ves.ion:iNo.d d ' Standa ri :' ' Title -; :--Document at at osmn . Verson ' .Date

3887 IEEE IEEE 382 1980 Standard for Qualification of not84-23 1984 R Referred to in IEEE 382 1985

Actuators for Power Operated discussion ofValve Assemblies With Safety- test programRelated Functions for NuclearPower Plants

3888 IEEE IEEE 382 1972 Standard for Qualification of regl.73.rOO 1974 P IEEE 382 1985Actuators for Power OperatedValve Assemblies With Safety-Related Functions for NuclearPower Plants

3889 IEEE IEEE 382 N/S Standard for Qualification of srp3.1 1 1981 P Implied, IEEE 382 1985

Actuators for Power Operated SupplementedValve Assemblies With Safety- by Reg. GuideRelated Functions for Nuclear 1.73Power Plants

3890 IEEE IEEE 383 N/S Standard for Type Test of Class git83-033 1983 R IEEE 383 1974 R921 E Electric Cables, Field Splices,and Connections for NuclearPower Generating Stations

3891 IEEE IEEE 383 N/S Standard for Type Test of Class git86-010 1986 P IEEE 383 1974 R921E Electric Cables, Field Splices,and Connections for NuclearPower Generating Stations

3892 IEEE IEEE 383 1974 Standard for Type Test of Class glt86-01 0.sO1 1994 R IEEE 383 1974 R92

1 E Electric Cables, Field Splices,and Connections for NuclearPower Generating Stations

3893 IEEE IEEE 383 N/S Standard for Type Test of Class inm1245 App. B 1991 R IEEE 383 1974 R921 E Electric Cables, Field Splices,and Connections for NuclearPower Generating Stations

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3894 IEEE IEEE 383 NIS Standard for Type Test of Class drgrsO50-2.rOO 1979 P Proposed IEEE 383 1974 R92

lE Electric Cables, Field Splices, reg1.131 .rO

and Connections for NuclearPower Generating Stations

3895 IEEE IEEE 383 N/S Standard for Type Test of Class inrn51061 1984 R IEEE 383 1974 R92

1E Electric Cables, Field Splices,and Connections for NuclearPower Generating Stations

3896 IEEE IEEE 383 N/S Standard for Type Test of Class inm51063 1985 R IEEE 383 1974 R92


3897 IEEE IEEE 383 N/S Standard for Type Test of Class inm51065 1984 R IEEE 383 1974 R92


3898 IEEE IEEE 383 N/S Standard for Type Test of Class not84-09 1984 R IEEE 383 1974 R92

1E Electric Cables, Field Splices,and Connections for NuclearPower Generating Stations

3899 IEEE IEEE 383 N/S Standard for Type Test of Class not92-28 1992 R IEEE 383 1974 R92


3900 IEEE IEEE 383 1974 Standard for Type Test of Class not93-33 1993 R IEEE 383 1974 R92


Codes and Standards-and Other Guidance Cited in Regulatory DocumentsPart A - Industry Consensus Codes and Standards

Recad D Sard Late 'Version

No. Code Stnad Veso il ouln ae aiiy Cmet etei DW:a3901 IEEE IEEE 383 1974 Standard for Type Test of Class regl .1 20.rOl 1977 P IEEE 383 1974 R92


3902 IEEE IEEE 383 1974 Standard for Type Test of Class regl.131.rOO 1977 P With IEEE 383 1974 R92

1E Electric Cables, Field Splices, conditionsand Connections for NuclearPower Generating Stations

3903 IEEE IEEE 383 N/S Standard for Type Test of Class regi .70.rO3 1978 P Minimum IEEE 383 1974 R92

1 E Electric Cables, Field Splices, requirementand Connections for NuclearPower Generating Stations

3904 IEEE IEEE 383 N/S Standard for Type Test of Class srp3.1 1 1981 P Implied: Reg. IEEE 383 1974 R92

1`E Electric Cables, Field Splices, Guide 1.131and Connections for Nuclear NUREG-0588Power Generating Stations supplement

3905 IEEE IEEE 383 1974 Standard for Type Test of Class srp9.5.1 1981 P IEEE 383 1974 R921 E Electric Cables, Field Splices,and Connections for NuclearPower Generating Stations

3906 IEEE IEEE 384 1974 Standard Criteria for 10cfr5O App. R 1994 P Alternate IEEE 384 1992

Independence of Class 1 E method: Reg.Equipment and Circuits Guide 1.75 and

Section 4.5

3907 IEEE IEEE 384 N/S Standard Criteria for Inml245 App. B 1991 R IEEE 384 1992Independence of Class 1 EEquipment and Circuits

z

-4

Cs

z

'10

is



RcrStdad ;Dbb;i: ~Acce' Lat. est Stanidard Latest Vers On

ecord:S til- n id d e. .-; i ..._.._..-

.- dcode S idta da t Version il Doc e t D t mb ili Com ments 0 V s Date

3908 IEEE IEEE 384 N/S Standard Criteria for inm5Ol 00 1985 R IEEE 384 1992

Independence of Class 1 EEquipment and Circuits

3909 IEEE IEEE 384 N/S Standard Criteria for 1nm51051 1984 R IEEE 384 1992


3910 IEEE IEEE 384 N/S Standard Criteria for inm51053 1984 R IEEE 384 1992


3911 IEEE IEEE 384 N/S Standard Criteria for inm51061 1984 H IEEE 384 1992




3913 IEEE IEEE 384 N/S Standard Criteria for inm51065 1984 8 IEEE 384 1992


3914 IEEE IEEE 384 1977 Standard Criteria for inm52001 1995 R IEEE 384 1992


3915 IEEE IEEE 384 1977 Standard Criteria for inm52002 1995 R IEEE 384 1992








3919 IEEE IEEE 384 1974 Standard Criteria for not85-1 1 1985 P Implied IEEE 384 1992

Independence of Class 1 E endorsement

Equipment and Circuits .


X Record tandad DoeR.A L;;re iDIst Stadard:. ...L..t..t Vesosca ,,d. ''' :'ii' i' li' ' .:':.':,Eil'i:.7:.:f . inI'''i: -M.r aol .. . . . ....... ..... . ., iriir . . . ~ii

3920 IEEE IEEE 384 N/S Standard Criteria for regi.1 53.rOO 1985 R Endorsed by IEEE 384 1992Independence of Class 1 E Reg. GuideEquipment and Circuits 1.75

3921 IEEE IEEE 384 1973 Standard Criteria for regl .75.rO2 1978 R Basis for IEEE IEEE 384 1992Independence of Class 1E 384-1974.Equipment and Circuits Draft Std.

3922 IEEE IEEE 384 1974 Standard Criteria for regl.75.rO2 1978 P leee 384 also IEEE 384 1992Independence of Class 1E designatedEquipment and Circuits ANSI N41.14

3923 IEEE IEEE 384 N/S Standard Criteria for srp7.1 1984 P Endorsed by IEEE 384 1992Independence of Class 1 E Reg. GuideEquipment and Circuits 1.75

3924 IEEE IEEE 384 N/S Standard Criteria for srp7.2 1981 P Implied, Reg. IEEE 384 1992Independence of Class 1E Guide 1.75Equipment and Circuits Supplements

3925 IEEE IEEE 384 N/S Standard Criteria for srp7.3 1981 P Implied, with IEEE 384 1992Independence of Class 1 E Reg. GuideEquipment and Circuits 1.75

Supplements

3926 IEEE IEEE 384 N/S Standard Criteria for srp8.3.1 1981 P Review IEEE 384 1992Independence of Class 1 E considers IEEEEquipment and Circuits 384

augmented byReg. Guide1.75

3927 IEEE IEEE 384 N/S Standard Criteria for srp8.3.2 1981 P Acceptance IEEE 384 1992Independence of Class 1E criteria,Equipment and Circuits augmented by

Reg. Guide1.75

z

'IO

zLII

4:9


R odStondaird. DOe Accept' Latest Standard Latest Versio

No. Code Standa en | Tit Document Date: t Cmments.. Von Dat

3928 IEEE IEEE 387 1984 Standard Criteria for Diesel- regl.1 55.rOO 1988 R IEEE 387 Withdrawn n/a

Generator Units Applied as withdrawnStandby Power Supplies for 1993Nuclear Power GeneratingStations

3929 IEEE IEEE 387 N/S Standard Criteria for Diesel- re IEEE 387 Withdrawn n/a


3930 IEEE IEEE 387 1977 Standard Criteria for Diesel- regl.9.rO3 1993 R IEEE 387 Withdrawn n/a


3931 IEEE IEEE 387 1984 Standard Criteria for Diesel- regl.9.r03 1993 P IEEE 387 Withdrawn n/a


3932 IEEE IEEE 387 N/S Standard Criteria for Diesel- srp8.3.1 1981 P IEEE 387 Withdrawn n/a


3933 IEEE IEEE 387 N/S Standard Criteria for Diesel- srp8A 1981 P IEEE 387 Withdrawn n/a


3934 IEEE IEEE 387 N/S Standard Criteria for Diesel- srp9.5.4 1981 P IEEE 387 Withdrawn n/a

Generator Units Applied as withdrawnStandby Power Supplies for 1993



ai e. Ret Vs .. .<I'.g. .. t -t ;i; .- I. aStandartd dardDoI' cet aetSanadLts eso: No a Code Standard e:s ion ; 0... i atleoumen Date Abiitfy -Coient' Vi i iDate

3935 IEEE IEEE 387 N/S Standard Criteria for Diesel- srp9.5.0 1981 P IEEE 387 Withdrawn n/aGenerator Units Applied as withdrawnStandby Power Supplies for 1993Nuclear Power GeneratingStations




3939 IEEE IEEE 422 1986 Guide for the Design and glt86-010.s01 1994 R Withdrawn n/aInstallation of Cable Systems inPower Generating Stations

3940 IEEE IEEE 450 1975 Recommended Practice for inm-toc 1995 R ANS 3.2 1994Maintenance, Testing, andReplacement of Vented LeadStorage Batteries for StationaryApplications

3941 IEEE IEEE 450 N/S IEEE Recommended Practice for inm1245 App. B 1991 R IEEE 450 1995Maintenance, Testing, andReplacement of Vented Lead-AcidBatteries for Stationary

__ __ __ _ _Applications ___

4~1.U'

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Reordde Standardoc. Acetst Sndard Latest Versi on

No. Code ~ ` Sta ndard VersiW e T0l D ocu mnen t '.D a e a t C m e t re son D t

3942 IEEE IEEE 450 N/S IEEE Recommended Practice for inm7O340B 1981 R IEEE 450 1995

Maintenance, Testing, andReplacement of Vented Lead-AcidBatteries for StationaryApplications ll

3943 IEEE IEEE 450 1975 IEEE Recommended Practice for inm7O440B 1979 R IEEE 450 1995

Maintenance, Testing, andReplacement of Vented Lead-AcidBatteries for StationaryApplications

3944 IEEE IEEE 450 1975 IEEE Recommended Practice for inm81058 1984 R IEEE 450 1995


3945 IEEE IEEE 450 1975 IEEE Recommended Practice for inm9900/ IEEE 1986 R IEEE 450 1995

Maintenance, Testing, and 450Replacement of Vented Lead-AcidBatteries for StationaryApplications

3946 IEEE IEEE 450 1980 IEEE Recommended Practice for inm9900/ IEEE 1986 R IEEE 450 1995

Maintenance, Testing, and 450Replacement of Vented Lead-AcidBatteries for StationaryApplications

3947 IEEE IEEE 450 1975 IEEE Recommended Practice for not85-74 1985 R Endorsed by IEEE 450 1995

Maintenance, Testing, and Reg. Guide

Replacement of Vented Lead-Acid 1.129

Batteries for StationaryApplications -

3948 IEEE IEEE 450 1980 IEEE Recommended Practice for not85-74 1985 R IEEE 450 1995



R Stard at. A t La etes.t Standard L Ve=

io -~i, Code tadr Vrsio Title Douet Dat ably Cmet Vrsion Dt

3949 IEEE IEEE 450 1975 IEEE Recommended Practice for not89-17 1989 R Incorrectly IEEE 450 1995

Maintenance, Testing, and referenced as

Replacement of Vented Lead-Acid IEEE 540-1975Batteries for StationaryApplications

3950 IEEE IEEE 450 1980 IEEE Recommended Practice for not89-17 1989 R Incorrectly IEEE 450 1995

Maintenance, Testing, and referenced as

Replacement of Vented Lead-Acid IEEE 540-1980Batteries for StationaryApplications

3951 IEEE IEEE 450 1987 IEEE Recommended Practice for not95-21 1995 A IEEE 450 1995


3952 IEEE IEEE 450 1976 IEEE Recommended Practice for regl.128.rOl 1978 A Replaces IEEE IEEE 450 1995

Maintenance, Testing, and Standard 450-

Replacement of Vented Lead-Acid 1972

Batteries for StationaryApplications

3953 IEEE IEEE 450 1972 iEEE Recommended Practice for reg1. 1 28.rO1 1978 R Replaced by IEEE 450 1995

Maintenance, Testing, and IEEE StandardReplacement of Vented Lead-Acid 450-1975

Batteries for StationaryApplications

3954 IEEE IEEE 450 1975 IEEE Recommended Practice for regl.129.rOl 1978 P With IEEE 450 1995

Maintenance, Testing, and conditions

Replacement of Vented Lead-AcidBatteries for StationaryApplications

3955 IEEE IEEE 450 1975 IEEE Recommended Practice for reg1.32.rO2 1977 P Implied IEEE 450 1995

Maintenance, Testing, and endorsement

Replacement of Vented Lead-AcidBatteries for StationaryApplications

z

-.3

~0



Recod tianda Do. eti Latest Stadndard Latst' -'X'l_

.0 N co. u i-::~ > 5X cod St na rd., '. . Vers.io-V -l f - Dium n Dat iblt ^o m e t 'eibiDate

3956 IEEE IEEE 450 1972 IEEE Recommended Practice for reg 1.32.r02 1977 P _ 1995

Maintenance, Testing, andReplacement of Vented Lead-AcidBatteries for StationaryApplications__ _ _ _ _ _ _

IEEE IEEE 450 1975 IEEE Recommended Practice for reg5.44.rO2 1980 R Endorsed by IEEE 450 1995



Batteries for Stationary

Applications__ _ _ _ _ _

39158 IEEE IEEE 450 NIS IEEE Recommended Practice for srp8.3.2 1981 P Implied with IEEE 450 1995



Batteries for StationaryA pplications _ _ _ _ _ _ _ __

_ _ _ _ _

39 IEEE IEEE 450 1987 IEEE Recommended Practice for stsb&wB3.8.4 1992 P IEEE 450 1995

Maintenance, Testing, andReplacement of Vented Lead-AcidBatteries for StationaryApplications _ _ _ _ _ _ _

3960 IEEE IEEE 450 1980 IEEE Recommended Practice for stsb&wB3.8.6 1992 P IEEE 450 1995

Maintenance, Testing, andReplacement of Vented Lead-AcidBatteries for Stationary

-TE-E- IEE 450 1987 Applications3961 IEEE IEEE 450 1987 IEEE Recommended Practice for stsceB3.8.4 1992 P IEEE 450 1995


_ _ _ _ _ _ _

3962 IEEE IEEE 450 1980 IEEE Recommended Practice for stsceB3.8.6 1992 P IEEE 450 1995

Maintenance, Testing, andReplacement of Vented Lead-AcidBatteries for StationaryApplications .


Record tandard de. 6AcEpt, Latest St d tet V rlsodNo ode :Stah 60d Vers6 ionTi docuonet Dat bliy Cimirts. eril Date

3963 IEEE IEEE 450 N/S IEEE Recommended Practice for sts4-geB3.8.4 1992 P IEEE 450 1995Maintenance, Testing, andReplacement of Vented Lead-AcidBatteries for StationaryApplications ._.

3964 IEEE IEEE 450 1987 IEEE Recommended Practice for sts4-geB3.8.6 1992 P IEEE 450 1995Maintenance, Testing, andReplacement of Vented Lead-AcidBatteries for StationaryApplications _

3965 IEEE IEEE 450 1987 IEEE Recommended Practice for sts4-ge5.5 1992 P IEEE 450 1995Maintenance, Testing, andReplacement of Vented Lead-AcidBatteries for Stationary

.. _ Applications

3966 IEEE IEEE 450 1987 IEEE Recommended Practice for sts6-geB3.8.4 1992 P IEEE 450 1995Maintenance, Testing, andReplacement of Vented Lead-AcidBatteries for Stationary

_ _ _ __ Applications3967 IEEE IEEE 450 1987 IEEE Recommended Practice for sts6-geB3.8.6 1992 P IEEE 450 1995


3968 IEEE IEEE 450 1987 IEEE Recommended Practice for stswstB3.8.4 1992 P IEEE 450 1995Maintenance, Testing, andReplacement of Vented Lead-AcidBatteries for Stationary

X___ _ ___ __ _ __Applications ___________L __ __ .,

3969 IEEE IEEE 450 1980 IEEE Recommended Practice for stswstB3.8.6 1992 P IEEE 450 1995Maintenance, Testing, andReplacement of Vented Lead-AcidBatteries for Stationary

_________ _____________ ___________ __ A pplications . _ _

-DI\0

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Recod Sttidad '. I, '- Oe~ Acept--. LtestSthderd LatestVesn

No. ~ oe S i |/ .tandard *. :~ o :' Title'- L. .: e um n Dat abl_ Contin Xen t:s Vetal(n Datae

3970 IEEE IE .467 1980 Standard Quality Assurance regI.152.rOO 1985 R Withdrawn n/a

Program Requirements for theDesign and Manufacture of Class1 E Instrumentation and ElectricEquipment for Nuclear PowerGenerating Stations

3971 IEEE IEEE 472 1974 Standard for Relays & Relay inm52001 1995 R IEEE-C37.90 1989

Systems Associated with Electric

Power-Apparatus195-- IEC

3972 IEEE IEEE 472 1974 Standard for Relays & Relay inm52001 1995 R IEEE-C37.90 1989

Systems Associated with ElectricPower Apparatus

397 IEEE IEEE 484 N/S Recommended Practice for inm51051 1984 R IEEE 484 1987

Installation Design and Installationof Large Lead Storage Batteriesfor Generating Stations andSubstations





4�-W

�4

M00�v(!A�10

U)

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W


d Recordt- Skta .:C: Aip Latest Standard Latest ealo.0N o f. j 9 C od a S :t a n d ard V er sio n Titl D o c u m e in t Dat ... I: aB il e . - .o mm e taV r lo D a3976 IEEE IEEE 484 1975 Recommended Practice for regl,128.rQ1 1978 P With IEEE 484 1987

Installation Design and Installation conditionsof Large Lead Storage Batteriesfor Generating Stations andSubstations X

3977 IEEE IEEE 485 N/S Recommended Practice for Sizing inm2SlS/120 1993 R IEEE 485 Withdrawn n/aLarge Lead Storage Batteries for withdrawnGenerating Stations and 1993Substations

3978 IEEE IEEE 485 1983 Recommended Practice for Sizing stsb&w83.8.4 1992 P IEEE 485 Withdrawn n/aLarge Lead Storage Batteries for withdrawnGenerating Stations and 1993Substations

3979 IEEE IEEE 485 1983 Recommended Practice for Sizing stsceB3.8.4 1992 P IEEE 485 Withdrawn n/aLarge Lead Storage Batteries for withdrawnGenerating Stations and 1993Substations

3980 IEEE IEEE 485 1983 Recommended Practice for Sizing sts4-geB3.8.4 1992 P IEEE 485 Withdrawn n/aLarge Lead Storage Batteries for withdrawnGenerating Stations and 1993Substations

3981 IEEE IEEE 485 N/S Recommended Practice for Sizing sts6-geB3.8.4 1992 P IEEE 485 Withdrawn n/aLarge Lead Storage Batteries for withdrawnGenerating Stations and 1993Substations _ _,,,,_,,_,,_,_

3982 IEEE IEEE 485 1983 Recommended Practice for Sizing stswstB3.8.4 1992 P IEEE 485 Withdrawn n/aLarge Lead Storage Batteries for withdrawnGenerating Stations and 1993Substations l

3983 IEEE IEEE 489 N/S Not Found inm 245 App. B 1991 R Not found n/a

3984 IEEE IEEE 497 1981 Standard Criteria for Accident inm82102 1993 R IEEE 497 Withdrawn n/aMonitoring Instrumentation for withdrawnNuclear Power Generating 1993Stations _ _::._. _:_::. _-

z

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tF)



Ra d D o e. Aso L t s S ta n d a e V e rsio n;00-ANo. Code Standdrd

dsrs no Tit e Dot D abiit C Version . Dati

3985 IEEE IEEE 497 1977 Standard Criteria for Accident regi 1 153.rOO 1985 R IEEE 497 Withdrawn n/a

Monitoring Instrumentation for withdrawn

Nuclear Power Generating 1993

Stations

3986 IEEE IEEE 497 1977 Standard Criteria for Accident regl I97 r53 1983 R IEEE 497 Withdrawn n/a

Monitoring Instrumentation for withdrawn

Nuclear Power Generating 1993

Stations

3987 IEEE iEEE 497 1981 Standard Criteria for Accident drglO42.rOO 1995 R - Withdrawnna

Monitoring Instrumentation forNuclear Power GeneratingStations

3988 IEEE IEEE 498 1980 Standard Requirements for the inm35750 1992 R IEEE 498 1990

Calibration and Control ofMeasuring and Test EquipmentUsed in Nuclear Facilities

3989 IEEE IEEE 500 1977 Guide to the Collection and bui80-019.rO1 1980 R IEEE 500 1984 R91

Presentation of Electrical,Electronic, Sensing Component,and Mechanical EquipmentReliability Data for Nuclear PowerGenerating Stations

3990 IEEE IEEE 500 1984 Guide to the Collection and not93-64 1993 _ IEEE 5001984 R91

Presentation of Electrical,Electronic, Sensing Component,and Mechanical EquipmentReliability Data for Nuclear PowerGenerating Stations


No. - ,C . S._ X,,,.,.tndd V-rsiotiTitle Doumet :. D~te abily Comments r" D'......t.

3991 IEEE IEEE 500 1977 Guide to the Collection and nuregO933, 3.2 1992 R IEEE 500 1984 R91Presentation of Electrical,Electronic, Sensing Component,and Mechanical EquipmentReliability Data for Nuclear PowerGenerating Stations

3992 IEEE IEEE 501 1978 Standard Seismic Testing of inm25251124 1994 R IEEE C37.98 1987 R91Relays

3993 IEEE IEEE 618 1982 Installation of Electrical Equipment inm52001 1995 R IEEE 518 1982 R90to Minimize Electrical Noise Inputsto Controllers from ExternalSources, Guide for the

3994 IEEE IEEE 518 1982 Installation of Electrical Equipment inm52002 1995 R IEEE 518 1982 R90to Minimize Electrical Noise Inputsto Controllers from ExternalSources, Guide for the

3995 IEEE IEEE 535 1979 Standard for Qualification of Class not83-1 1 1983 R Referred to in IEEE 535 1986 R941 E Lead Storage Batteries for textNuclear Power GeneratingStations

3996 IEEE IEEE 535 1986 Standard for Qualification of Class reg .158.r00 1989 A IEEE 535 1986 R94.1 E Lead Storage Batteries forNuclear Power GeneratingStations

3997 IEEE IEEE 535 1979 Standard for Qualification of Class reg1.158.rOO 1989 R IEEE 535 1986 R941 E Lead Storage Batteries forNuclear Power GeneratingStations

3998 IEEE IEEE 535 N/S Standard for Qualification of Class srp3.1 1 1981 R May be used IEEE 535 1986 R941 E Lead Storage Batteries for for guidanceNuclear Power GeneratingStations

t1.)

'0

-.21

-4

(5a



Record! Sta d:r D c. 1: t ,:::i-':: L e t Sta .ndard L atE st i e- - o

NoMo e ta d r e son , T eD o um entii 0 4 at e" ab lt b l i # tersionDa e

3999 IEEE IEEE 572 1985 Standard for Qualification of Class reg1.156,rOO 1987 A Endorsed IEEE 572 1985 R92

1 E Connection Assemblies for without

Nuclear Power Generating exceptions

Stations

4000 IEEE IEEE 603 1991 Criteria for Safety Systems for drg1039.rOO 1995 R IEEE 603 1991

Nuclear Power GeneratingStations _

4001 IEEE IEEE 603 1991 Criteria for Safety Systems for drglO42.rOO 1995 A IEEE 603 1991


4002 IEEE IEEE 603 1980 Criteria for Safety Systems for drg1042.rOO 1995 R IEEE 603 1991

Nuclear Power GeneratingS tations ._..__________

4003 IEEE IEEE 603 1991 Criteria for Safety Systems for inm52001 1995 R IEEE 603 1991


4004 IEEE IEEE 603 1991 Criteria for Safety Systems for inm52002 1995 R IEEE 603 1991


4005 IEEE IEEE 603 1977 Criteria for Safety Systems for nuregO933, 1989 R IEEE 603 1991

Nuclear Power Generating 1.11.FStations

4006 IEEE IEEE 603 N/S Criteria for Safety Systems for nuregO933, 1992 R IEEE 603 1991

Nuclear Power Generating 3.110Stations

4007 IEEE IEEE 603 N/S Criteria for Safety Systems for nuregO933, 1991 R IEEE 603 1991

Nuclear Power Generating 3.128Stations

4008 IEEE IEEE 603 1991 Criteria for Safety Systems for reg I.1 18.r03 1995 R IEEE 603 1991


4009 IEEE IEEE 603 1980 Criteria for Safety Systems for reg1.1 52.rOO 1985 R IEEE 603 1991



vNo. code A Sa ndt d VtetC Version at eL

4010 IEEE IEEE 603 1980 Criteria for Safety Systems for regl.153.rOO 1985 P With IEEE 603 1991

Nuclear Power Generating modifications

Stations andsupplements

4011 IEEE IEEE 627 NIS Standard for Design Qualification srp3.1 1 1981 R May be used IEEE 627 1980 R91

of Safety Systems Equipment for guidance

Used in Nuclear Power GeneratingStations

4012 IEEE IEEE 634 1978 Standard Cable Penetration Fire drgrs809-5.rOO 1979 P IEEE 634 Withdrawn n/a

Stop Qualification Test withdrawn1990

4013 IEEE IEEE 634 NIS Standard Cable Penetration Fire inm51061 1984 R IEEE 634 Withdrawn n/a

Stop Qualification Test withdrawn...____ 1990 . _

4014 IEEE IEEE 634 N/S Standard Cable Penetration Fire inm51065 1984 R IEEE 634 Withdrawn n/a

Stop Qualification Test withdrawn._ 1990

4015 IEEE IEEE 634 N/S Standard Cable Penetration Fire not88-04 1988 P IEEE 634 Withdrawn n/a


4016 IEEE IEEE 634 N/S Standard Cable Penetration Fire regl.1 20.rO1 1977 - IEEE 634 Withdrawn n/a


4017 IEEE IEEE 645 1977 Detectors for Ionizing Radiation, reg5.9.rO2 1983 R Not found n/a

Test Procedures for High-Purity

4018 IEEE IEEE 649 N/S Standard for Qualifying Class 1 E srp3.1 1 1981 R IEEE 649 1991

Motor Control Centers for NuclearPower Generating Stations

4019 IEEE IEEE 650 NIS Standard for Qualiflcation of Class bu179-001b.s02 1980 P IEEE 650 1990

1 E Static Battery Chargers andInverters for Nuclear PowerGenerating Stations

z

U'

tjA

c

n~Mo

Q s



Re c o rd S a d rD o . A e p -L a t eist St d a d L es V e io

No o e Sai ad V ersIo Titl -Document Dalte'1~~ bilbilty - C Wmmrents VesobatO

4020 IEEE IEEE 650 N/S Standard for Qualification of Class srp3.11 1981 R iEEE 650 1990

1 E Static Battery Chargers andInverters for Nuclear PowerGenerating Stations

4021 IEEE IEEE 690 1984 Design and Installation of Cable glt86-01 .sO1 1994 R Withdrawn n/a

Systems for Class 1 E Circuits in

Nuclear Power GeneratingStations__

_ _ _ _ _

4022 IEEE IEEE 730 1984 Software Quality Assurance Plans inm37550 1995 R IEEE 730.1 1989

4023 IEEE IEEE 730 1989 Standard for Software Quality inm52001 1995 R IEEE 730 1989

Assurance Plans

4024 IEEE IEEE 730 1989 Standard for Software Quality inm52002 1995 R IEEE 730 1989

Assurance Plans

IEEE IEEE 741 N/S Standard Criteria for the gt89-010.sO1 1990 R IEEE 741 1990

Protection of Class 1 E PowerSystems and Equipment inNuclear Power GeneratingStations

4026 IEEE IEEE 741 1986 Standard Criteria for the regl.63.r03 1987 P Section 5.4 IEEE 741 1990

Protection of Class 1 E PowerSystems and Equipment inNuclear Power GeneratingStations

4027 IEEE IEEE 765 1983 Standard for Preferred Power reg l.155.rOO 1988 R IEEE 765 1995

Supply for Nuclear PowerGenerating Stations _______

4028 IEEE IEEE 803 1983 Recommended Practice for Unique 10cfr5O.73 1994 A IEEE 803 1983 R89

Identification in Power Plants andRelated Facilities - Principles andDefinitions _

4029 IEEE IEEE 828 1983 Standard for Software inm62001 1995 R IEEE 828 1990

Configuration Management Plans

.~ __ --------


Rcrdtb Steedard D-c, p Lae, Sat Verolono. Cd. Sanad .Versio 0WTitl Docwu.. ne~nt-':' Date abit. Comns Vein . De

4030 IEEE IEEE 828 1983 Standard for Software inm52002 1995 R IEEE 828 1990Configuration Management Plans l

4031 IEEE IEEE 828 1983 Standard for Software not93-57 1993 R IEEE 828 1990Configuration Management Plans

4032 IEEE IEEE 829 1983 Software Test Documentation inm52001 1995 R E_ EE 829 1983 R914033 IEEE IEEE 829 1983 Software Test Documentation inm52002 1995 R IEEE 829 1983 R914034 IEEE IEEE 830 1984 Recommended Practice for inm52001 1995 R IEEE 830 1993

Software RequirementsSpecifications

4035 IEEE IEEE 830 1984 Recommended Practice for inm52002 1995 R IEEE 830 1993Software RequirementsSpecifications

b 4036 IEEE IEEE 830 1984 Recommended Practice for not93-57 1993 R IEEE 830 1993Software RequirementsSpecifications

4037 IEEE IEEE 946 1992 IEEE Recommended Practice for not94-80 1994 R IEEE 946 1992the Design of DC Auxiliary PowerSystems for Generating Stations

4038 IEEE IEEE 1012 1986 Standard for Software Verification inm52001 1995 R IEEE 1012 1986 R92and Validation Plans

4039 IEEE IEEE 1012 1986 Standard for Software Verification inm52002 1995 R IEEE 1012 1986 R92and Validation Plans

Z 4040 IEEE IEEE 1012 1986 Standard for Software Verification not93-57 1993 R IEEE 1012 1986 R92and Validation Plans

4041 IEEE IEEE 1016 1987 Software Design Descriptions, inm52001 1995 R IEEE 1016 1987Recommended Practice for

< 4042 IEEE IEEE 1016 1987 Software Design Descriptions, inm52002 1995 R IEEE 1016 1987Recommended Practice for

-c - - - -- -

z

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-F4

t~)00



Recor D oc A c:e:t . L test S a d d Latest Version

No;: *, Code. S rd Vrsion t Documen aen l V oa

4043 IEEE IEEE 1028 1988 Software Reviews and Audits inm52001 1995 R IEEE 1028 1988

4044 IEEE IEEE 1028 1988 Software Reviews and Audits inm52002 1995 R IEEE 1028 1988

4045 IEEE IEEE 1050 1989 Guide for Instrumentation and inm52001 1995 R IEEE 1050 1989

Control Equipment Grounding inGenerating Stations

4046 IEEE IEEE 1050 1989 Guide for Instrumentation and inm52002 1995 R IEEE 1050 1989

Control Equipment Grounding InGenerating Stations

4047 IEEE IEEE 1074 1991 Developing Software Life Cycle inm52001 1995 R IEEE 1074 1992

Processes

4048 IEEE IEEE 1074 1991 Developing Software Life Cycle inm52002 1995 R IEEE 1074 1992

Processes

4049 IEEE IEEE 1228 1991 Standard for Software Safety inm52001 1995 R IEEE 1228 1994

P la n s _ _ _ _ _ _ _ _ _ _ _ _ _

4050 IEEE IEEE 1228 1991 Standard for Software Safety inm52002 1995 R IEEE 1228 1994

P la n s_ _ _ _ _ _ _ _ _ _ _ _ _ _

4051 IEEE IEEE C37.98 1978 Standard Seismic Testing of inm2525/124 1994 R IEEE C37.98 1987 R91

Relays

4052 IEEE IEEE P827 N/S A Method for Determining nuregO933, 1989 R Withdrawn Withdrawn n/a

Requirements for Instrumentation, 1.1I.FControl and Electrical SystemsImportant to Safety

4053 IEEE IEEE P848 Nt/S Procedure for the Determination of not93-40 1993 R Standard being n/a n/a

the Ampacity Derating of Fire developed, not

Protected Cables yet issued


N,. odR ' StaD of drio. Tle D'curitri Data. at..: ., .1 r Dat H4054 IEEE IEEE P848 N/S Procedure for the Determination of not94-34 1994 R Standard under Not issued n/a

the Ampacity Derating of Fire development -Protected Cables standard has

not beenpublished

4055 ISA ISA RP3.1 N/S Flowmeter Installations, Seal and Inm52051 1984 R Out of Print n/aCondensate Chambers

4056 ISA ISA RP3.2 N/S Flange Mounted Sharp Edged inm52053 1984 R Out of Print n/aOrifice Plates for FlowMeasurement

4057 ISA ISA RP4.2 N/S Control Valve Manifold Designs, inm52051 1984 R ISA RP75.06 1981Recommended Practice

4058 ISA ISA RP4.2 N/S Control Valve Manifold Designs, inm52053 1984 R ISA RP75.06 1981Recommended Practice

4059 ISA ISA RP7.3 N/S Quality Standard for Instrument inm52051 1984 R ISA S7.3 1975 R81Air

4060 ISA ISA RP7.3 N/S Quality Standard for Instrument inm52053 1984 R ISA S7.3 1975 R81Air._ _ _

4061 ISA ISA RP25.1 N/S Materials for Instruments in inm52053 1984 R Out of Print n/aRadiation Service

4062 ISA ISA RP60.9 N/S Piping Guide for Control Centers, inm52051 1984 R ISA RP60.9 1981Recommended Practice

4063 ISA ISA S5.1 N/S Instrumentation Symbols and inm52051 1984 R ISA S551 1984 R92Identification X

4064 ISA ISA S7.3 1975 Quality Standard for Instrument regl.68.3.rOO 1982 P Endorsement ISA S7.3 1975 R81Air with respect to

oil, water, andparticularmatter

z

c.4

z

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N o . i .C ode: - I Standa rdD V e s o Til D oLm n D.. ab lt C.m n sV t lD t

4065 ISA ISA S7.3 N/S Quality Standard for Instrument srp9.3.1 1981 P Implied ISA S7.3 1975 R81

Air endorsement

4066 ISA ISA 57.4 NIS Air Pressures for Pneumatic inm52053 1984 R ISA S7.4 1981

Controllers, Transmitters, andTransmission Systems l

4067 ISA ISA S26 NIS Dynamic Response Testing of inm52051 1984 R ISA S26 1968

Process Control Instrumentation

4068 ISA ISA S37.1 NIS Electrical Transducer Inm52051 1984 R Withdrawn n/a

Nomenclature and Terminology

4069 ISA ISA S50.1 N/S Compatibility of Analog Signals inm52051 1984 R ISA S50.1 1982 R92

for Electronic Industrial ProcessInstruments _

4070 ISA ISA S51.1 N/S Process Instrumentation inm52051 1984 R ISA S51.1 1979 R93

Terminology

4071 ISA ISA S67.01 1979 Transducer and Transmitter drgicl31-5.rOO 1982 P -SA 1994

Installation For Nuclear SafetyApplications

4072 ISA ISA S67.01 N/S Transducer and Transmitter inm52051 1984 - ISA S67.01 1994


4073 ISA ISA S67.01 N/S Transducer and Transmitter inm52053 1984 R ISA S67.01 1994


4074 ISA ISA S67.02 N/S Nuclear-Safety-Related Instrument inm52051 1984 8R ISA S67.02 1980

Sensing Line Piping and TubingStandards for Use in NuclearPower Plants

4075 ISA ISA S67.02 N/S Nuclear-Safety-Related Instrument inm52053 1984 R ISA S67.02 1980



Record,..f~,.,tl St7tadd Doe Accopt-7fT.2.7 LatestEi.E Stndr Laes Version t...:00-;C;E ! 0..

No Code Standard V ol Document Date b4076 ISA ISA 567.02 NIS Nuclear-Safety-Related Instrument nuregO933, 3.64 1983 R ISA S67.02 1980


4077 ISA ISA S67.02 1980 Nuclear-Safety-Related Instrument regl .151 .rOO 1983 P Endorsed with ISA S67.02 1980Sensing Line Piping and Tubing exceptionsStandards for Use in NuclearPower Plants

4078 ISA ISA S67.02 1967 Nuclear Safety Related Instrument srp7.1.A 1984 P ISA S67.02 1980Sensing Line Piping and TubingStandard for Use in Nuclear PowerPlants

4079 ISA ISA S67.04 1982 Setpoints for Nuclear Safety- gIt91-004 1991 P ISA S67.04 1994Related Instrumentation

4080 ISA ISA S67.04 N/S Setpoints for Nuclear Safety- inm52051 1984 R ISA S67.04 1994Related Instrumentation

4081 ISA ISA S67.04 1982 Setpoints for Nuclear Safety- not89-68 1989 P ISA S67.04 1994Related Instrumentation

4082 ISA ISA S67.04 1982 Setpoints for Nuclear Safety- not91-29 1991 P Endorsed by ISA S67.04 1994.... . Related Instrumentation regl .105 .

4083 ISA ISA S67.04 1982 Setpoints for Nuclear Safety- nuregO933, 3.3 1986 R ISA S67.04 1994Related Instrumentation

4084 ISA ISA S67.04 1979 Setpoints for Nuclear Safety- nuregO933, 3.3 1986 R ISA 567.04 1994Related Instrumentation

4085 ISA ISA S67.04 1982 Setpoints for Nuclear Safety- regi.105.r02 1986 P Additional ISA 367.04 1994Related Instrumentation information

provided4086 ISA ISA- 1980 Response Time Testing of Nuclear drgicl21-5.rOO 1982 P ISA $67.06 1984

dS67.06 Safety-Related InstrumentChannels in Nuclear Power Plants

4J1.

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ReodSandWr~Dc Accpt- Latest Stanidard Latest Version

. C o d el S t n d r V n T DDo c u n D i l ta t

4087 ISO ISO 389 1975 Acoustics Standard Reference 10cfr73 1995 R ISO 389 1991

Zero for the Calibration of Pure-tone Air Conduction Audiometers

4088 ISO ISO 780 1985 Packaging - Pictorial Marking for Enforcement 1994 R NUREG/B8- ISO/DIS 780 1985

Handling of Goods Manual App. D 0195

4089 ISO ISO 1496 1978 Series 1 Freight Containers - 10cfr73 1995 R -SS 1496 1993

Specification and Testing:General Cargo Containers for

General Purposes -----_-_---

4090 ISO ISO 1496 N/S Series 1 Freight Containers - inm81370 1986 R ISO 1496 1993

Specification and Testing:General Cargo Containers forGeneral Purposes

4091 ISO ISO 2889 1975 General Principles for Sampling reg4.1 5.rOl 1979 R ISO 2889 1975

Airborne Radioactive Materials

4092 ISO ISO 2919 N/S Sealed Radioactive Sources - inm1245 App. B 1991 R Also ISO 2919 1980

Classification designatedANSI N43.6and NBSHandbook 126

4093 ISO ISO 2919 1980 Sealed Radioactive Sources - reglO.11.rOO 1987 R Also ISO 2919 1980

Classification designatedANSI N43.6and NBSHandbook 126

4094 ISO ISO Guide 6 1977 Not found reg5.58.rOl 1980 R Withdrawn n/a

4095 MIL MIL C- N/S Cleaning, Compound, Solvent, reg1.37.rOO 1973 R MIL-C-81302D 1991

81302b Trichlorotrifluoroethane


:0 t-R e td -g; ~. -. :.S. .. .. ......d d .> ..... . .. . .....t iLReod tdrdd 'Do. 'A'ct Lifteit 6tandard Lakist Version'

_: _ . .. ....

4096 MIL MIL-C- N/S Cleaning, Compound, Solvent, regl.54.rO0 1973 R MIL-C-81302D 199181302b Trichlototrifluoroethane

4097 MIL MIL-C- N/S Cleaning, Compound, Solvent, reg3.21.r00 1974 R MIL-C-813020 199181302b Trichlototrif luoroethane

4098 MIL MIL-C- N/S Cleaning, Compound, Solvent, reg3.32.rOO 1974 R MIL^C-813020 199181302b Trichlototrif luoroethane

4099 MIL MIL-F- N/S Filter, Particulate, High-Efficiency, regl.140.rO1 1979 R MIL-F-51068F 1988| 51068 Fire-Resistant

4100 MIL MIL-F- N/S Filter, Particulate, High-Efficiency, regl.52.rO2 1978 R MIL-F-51068F 198851068 Fire-Resistant

4101 MIL MIL-F- N/S Filter, Particulate, High-Efficiency, reg3.12.rOO 1973 R MIL-F-51068F 198851068C Fire-Resistant

4102 MIL MIL-F- N/S Filter, Medium, Fire Resistant, reg3.12.rOO 1973 R MIL-F-51079D 198851079A High Efficiency

4103 MIL MIL-H-6875 N/S Heat Treatment of Steel, Process not90-03 1990 R MIL-H-6875H 1988for

4104 MIL MIL-L- N/S Lock and Lock Sets, Exterior, inm81046 1984 A Cancelled n/a29151 Ordnance High Security

4105 MIL MIL-L- N/S Look and Lock Sets, Exterior, inm81046 1984 R MIL-L-29151 198729151 Ordnance High Security

4106 MIL MIL-L- N/S Lock and Lock Sets, Exterior, not82-46 1982 A n/a n/a29151 Ordnance High Security

4107 MIL MIL-P- N/S Padlock, Key Operated, High not82-46 1982 A MIL-P- 198643607 Security, Shrouded Shackle _ 43607G(3)

4108 MIL MIL-P- N/S Padlock, Key Operated, High inm81046 1984 A MIL-P-43607G 198643607D Security, Shrouded Shackle

411D9 MIL MIL-P- N/S Padlock, Key Operated, High Inm81046 1984 R MIL-P-43607G 199243607D Security, Shrouded Shackle _

4110 MIL MIL-STD- N/S Welded Joint Design cir77-05 1977 P MIL-STD-22D 197922A _

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(b)



RecordN oi. Ctie Om onlt C m n e s D ate

4111 MIL MIL-STD- NIS S ling Procedures and Tables nm81 038 1984 R MIL-STD-105E 1989

105D for Inspection by Attributes

4112 MIL MIL-STD- NIS Sampling Procedures and Tables reg696.rOO 1974 ASQC-Z1.4 1993

105D for Inspection by Attributes

4113 MIL MIL-STD- N/S Requirements for Nondestructive cir77-05 1977 P MIL-STD-271 F 1986

271A Testing Methods

4114 MIL MIL-STD- NIS Welding and Casting Standard cir77-05 1977 P TD 1987

2 7 8 _ _ _ _ _ _ _ _ _ _ _

4115 MIL MIL-ST2 - 1956 Filter Units, Protective Clothing, regl.140.r01 1979 R MIL-STD-282 1956 R89

282 Gas Mask Components andRelated Products: PerformanceTest Methods

4116 MIL MIL-STD- 1956 Filter Units, Protective Clothing, regi.52.r02 1978 R MIL-STD-282 1956

282 Gas Mask Components andRelated Products: PerformanceTest Methods

411 MIL MIL-STD- N/S Sampling Procedures and Tables reg6.6.rOO 1974 R MIL-STO-414 1957

414 for Inspection by Variables forPercent Defective

4118 ML - MIL-STD- N RS Requirements for the Control of inm52001 1995 R MIL^STD^461D 1993

461 (AB,C) Electromagnetic InterferenceEmissions & Susceptibility

4119 MIL MIL-STD- N/S Requirements for the Control of inm52002 1995 R MIL-STD-461 D 1993

461 IAB,C) Electromagnetic InterferenceEmissions & Susceptibility

4120 MIL MIL-STD N/S MeasurmentofElectromagnetic inm52001 1995 R -MIL-462D 1993

462 Interference Characteristics


Rod . ~... .'S' .,',' Stndr D;. ,co*Lts St,.ar .aes Ver....-*sion , ,..-c bi tSandrd 'Version - t.* D z t V

4121 MIL MIL-STD- N/S Measurement of Electromagnetic inm52001 1995 R MIL-STD-462D 1993462 Interference Characteristics

4122 MIL MIL-STD- NIS Interface Standard for Shipboard inmS2001 1995 R MIL-STD- 19881399 Systems, Section 300a, Electric 1399C

Power, Alternating Current

4123 MIL MIL-STD- N/S Interface Standard for Shipboard inm52002 1995 R MIL-STD- 19881399 Systems, Section 300a, Electric 1399C

Power, Alternating Current

4124 MIL MIL-V-278 NIS Electrodes, Welding, Covered, cir77-05 1977 P Standard may Withdrawn n/aAluminum Bronze be MIL-E-278 1990

4125 MSS MSS-SP-25 NIS Standard Marking System for srp3.9.4 1984 A MSS-SP-25 1993Valves, Fittings, Flanges, andUnions

4126 NACE NACE MR- NIS Sulfide Stress Cracking Resistant bui88-05.s02 1988 R NACE MR-0175 199501 Metallic Materials for Oilfield

Equipment4127 NCMA NCMA TR 1979 Masonry Designers Guide srp3.8.4 1981 R Latest Version NCMA TR 130 n/a

758 maybeincorrect

4128 NCRP NCRP 1989 Screening Techniques for reg8.37.rOO 1993 P NCRP 1989Commentary Determining Compliance with CommentaryNo. 3 Environmental Standards No. 3

4129 NCRP NCRP N/S Misadministration of Radioactive SECY94-275 1995 R NCRP 1991Commentary Material in Medicine-Scientific CommentaryNo. 7 Background No. 7

4130 NCRP NCRP N/S Misadministration of Radioactive SECY95-083 1995 R NCRP 1991Commentary Material in Medicine-Scientific CommentaryNo. 7 Background No. 7

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4�-U.)Ch



fRecod $t d Doc. Accept-, Lates pStandard Ltest Version

N o o eS ta n da r d V e s o i l o u e t D t b l t m e n sV r i nD t

4131 NCRP NCRP 1994 Considerations Regarding the drgB014,rOO 1994 R Proposed NCRP Corn- 1994

Commentary Unintended Radiation Exposure of reg8.13.rOO3 mentary No. 9

No. 9 the Embryo, Fetus, or NursingC h ild _ _ _ _ _ _ _ __

_ _ _ _ _

4132 NCRP NCRP N/S Control and Removal of inm1245 App. B 1991 R NCRP Report 8 1951

Report 8 Radioactive Contamination inLaboratories__

_ _ _ _ _ _

4133 NCRP NCRP 1951 Control and Removal of reg8,21 rol 1979 R NCRP Report 8 1951

Report 8 Radioactive Contamination inLaboratories__

_ _ _ _ _ _

4134 NCRP NCRP 1951 Control and Removal of reg8.23.rOl 1981 R NCRP Report 8 1951

Report 8 Radioactive Contamination inLaboratories

4135 NCRP NCRP 1951 Control and Removal f reg8.24.rOl 1979 R NCRP Report 8 1951

Report 8 Radioactive Contamination in

Laboratories__ _____

4136 NCRP NCRP N/S Recommendations for Waste inm1245 App. B 1991 R Out of Print n/a

Report 9 Disposal of Phosphorus-32 andlodine-131 for Medical Users

4137 NCRP NCRP 1951 Recommendations for Waste reg8.21.rOl 1979 R Out of Print n/a

Report 9 Disposal of Phosphorus-32 andlodine-1 31 for Medical Users

4138 NCRP NCRP 1951 Recommendations for Waste reg8.23.rOl 1981 R Out of Print n/a

Report 9 Disposal of Phosphorus-32 andlodine-1 31 for Medical Users

4139 NCRP NCRP N/S Instrumentation and Monitoring reg 0.7.rOl 1979 R NCRP Report 1978

Report 10 Methods for Radiation Protection 57

4140 NCRP NCRP 1952 Instrumentation and Monitoring reg8.21.rOi 1979 R NNRCP Report 1978


tJl.

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tJ


_e.cord t .Doe......... ... o A t -, 6L ate St nd i ard L, VersiNo:-. :Code . .E .:.:: ttkndad Oer-- T e Do na abilityU Ceomments * r o

4141 NCRP NCRP 1978 Instrumentation and Monitoring reg8.23.rO1 1981 R NCRP Report 1978Report 10 Methods for Radiation Protection 6 7

4142 NCRP NCRP 1954 Limitation of Exposure to Ionizing reg8.18.rO1 1982 R NCRP Report 1993Report 17 Radiation 116

4143 NCRP NCRP 1954 Limitation of Exposure to Ionizing reg8.31.rOO 1983 R NCRP Report 1993Report 17 Radiation 116

4144 NCRP NCRP N/S Maximum Permissible Body inm1245 App. 8 1991 R NCRP Report 1959Report 22 Burdens and Maximum Permissible 22

Concentrations of Radionuclides inAir and in Water for OccupationalExposure

4145 NCRP NCRP 1961 A Handbook of Radioactivity reg4.15.rOl 1979 R NCRP Report 1985Report 28 Measurements Procedures 58

4146 NCRP NCRP N/S Safe Handling of Radioactive inm1245 App. B 1991 R NCRP Report 1964Report 30 Materials 30

4147 NCRP NCRP 1964 Safe Handling of Radioactive regi 0.8.r02 1987 R NCRP Report 1964Report 30 Materials 30

4148 NCRP NCRP 1966 Radiation Protection in Educational drgop212-4.rOO 1984 R NCRP Report 1966Report 32 Institutions 32

4149 NCRP NCRP NIS Medical X-Ray, Electron Beam drgfc414-4.rOO 1986 P NCRP Report 1989Report 33 and Gamma-Ray Protection for 102

Energies up to 50 MeV(Equipment Design, Performanceand Use) ___

4150 NCRP NCRP N/S Medical X-Ray, Electron Beam regl`O.10.rOO 1987 R NCRP Report 1989Report 33 and Gamma-Ray Protection for 102

Energies up to 50 MeV(Equipment Design, Performanceand Use)

4151 NCRP NCRP N/S Medical X-Ray Electron Beam orag lo 11 .rOO 1987 R NCRP Report 1989Report 33 and Gamma-Ray Protection for 102

Energies up to 50 MeV(Equipment Design, Performanceand Use)

z

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N o o dia dri d V eUc ' . ' T t e K u c m n a e a i i y C m lo t e ae si D aft e

412 NCRP NCRP N/S Stutra Shelding Design and mini 245 App. 8 1991 R Reissued as NCRP Report 1976

Report 34 Evaluation for Medical Use of X- NCRP Report 49

Rays and Gamma Rays of 49Energies up to 1 0 MeV

4153 NCRP NCRP 1970 Structural Shielding Design and reg8.18rl 92RIesue s NCRP Report 1976

Report 34 Evaluation for Medical Use of X- NCRP Report 49

Rays and Gamma Rays of 49Energies up to 1 0 MeV

4154 NCRP NCRP 1970 Precautions in the Management of drg8O15.rOO 1994 R NCRP Report 1970

Report 37 Patients Who Have Received 37Therapeutic Amounts ofRadionuclides _ _ _ _ _ _ _ _ _ _ _ _

415 NCRP NCRP 1970 Precautions in the Management of drgop212-4.rOO 1984 R NCRP Report 1970

Report 37 Patients Who Have Received 37Therapeutic Amounts ofRadionuclides _ _ _ _ _ _ _ _ _ _

-41 56 NCRP NCRP N/S Precautions in the Management of minml 245 App. B 1991 R NCRP Report 1970

Report 37 Patients Who Have Received 37

Therapeutic Amounts ofRadionuclides

4157 NCR-P -NCRP N/S Precautions in the Management of not94-09 1994 R NCRP Report 17

Report 37 Patients Who Have Received 37Therapeutic Amounts ofRadionuclides__ _ _ _ _ _ _

4158 NCRP NCRP N/S Precautions in the Management of not94-70 1994 R NCRP Report, 1970

Report 37 Patients Who Have Received 37Therapeutic Amounts ofRadionuclides

4159 NCRP NCRP N/S Precautions in the Management of pospaper-030 1980 R NCRP Report 1970

Report 37 Patients Who Have Received 37Therapeutic Amounts ofR ad io n u clid es__ _ _ _ _ _ ___ _ _ _ _ _ _ _ _ _ _ _ _ _

tA

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LI)

Codes and Standards, and Other Guidance Cited in Regulatory DocumentsPart A - Industry Consensus Codes and Standards

R e c o d S t n d a r D o e A c e p t .L a t e t S t n d a d W a e s t V e r s i oN o o eS a d;6e s i - , T t eD c m n a e * b il t C o m e n t Ve ra io n D a te

4160 NCRP NCRP 1970 Precautions in the Management of regl0.8.r02 1987 R NCRP Report 1970Report 37 Patients Who Have Received 37


4161 NCRP NCRP 1970 Precautions in the Management of reg8.18.rO1 1982 R NCRP Report 1970Report 37 Patients Who Have Received 37


4162 NCRP NCRP 1970 Precautions in the Management of reg8.23.rOl 1981 R NCRP Report 1970Report 37 Patients Who Have Received 37


4163 NCRP NCRP 1971 Limitation of Exposure to Ionizing drgop2t2-4.rOO 1984 R NCRP Report 1993Report 39 Radiation 116

4164 NCRP NCRP 1971 Limitation of Exposure to Ionizing inm83750 1994 R NCRP Report 1993Report 39 Radiation 116

4165 NCRP NCRP 1971 Limitation of Exposure to Ionizing reg3.42.rOl 1979 R NCRP Report 1993Report 39 Radiation 116

4166 NCRP NCRP 1971 Limitation of Exposure to Ionizing reg8.13.rO2 1987 R NCRP Report 1993_ Report 39 Radiation 116

4167 NCRP NCRP N/S Limitation of Exposure to Ionizing reg8.29.r00 1981 R NCRP Report 1993'Report 39 Radiation 116

4168 NCRP NCRP 1972 Protection Against Radiation from drgop212-4.r00 1984 R NCRP Report 1972Report 40 Brachytherapy Sources 40

4169 NCRP NCRP NIS Protection Against Radiation from inm 1245 App. B 1991 R NCRP Report 1972Report 40 Brachytherapy Sources 40

4170 NCRP NCRP 1972 Protection Against Radiation from reg8. 1 9.rOl 1982 R NCRP Report 1972Report 40 Brachytherapy Sources 40

4171 NCRP NCRP 1972 Protection Against Radiation from reg8.33.r00 1991 R NCRP Report 1972Report 40 Brachytherapy Sources 40

4172 NCRP NCRP N/S Specifications of Gamma-Ray inm 1245 App. B 1991 R NCRP Report 1974Report 41 Brachytherapy Sources 41

4173 NCRP NCRP 1975 Limitation of Exposure to Ionizing reg8.18.rOl 1982 R NCRP Report 1993Report 43 Radiation 116

4174 NCRP NCRP N/S Limitation of Exposure to Ionizing reg8.31.rOO 1983 R NCRP Report 1993_ Report 43 _ Radiation _ 116 _

z

r-1

(b)



Record Standard Dec. Ae a Standard Lat st Version

4175 NCRP NCRP N/S Exposure of the Population in the drgop212-4.rOO 1984 R NCRP Report 1988

Report 45 United States and Canada from 94

Natural Background Radiation

4176 NCRP NCRP N/S Exposure of the Population in the reg4.2.r0 1976 R NCRP Report 1988



4177 NCRP NCRP 1975 Exposure of the Population in the reg8.30.rOO 1983 R NCRP Report 1988



4178 NCRP NCRP N/S Tritium Measurement Techniques inm1245 App. B 1991 R NCRP Report 1976

Report 47 _ _ _ __47

4179 NCRP NCRP 1976 Tritium Measurement Techrniques reg4.15.rOl 1979 R NCRP Report 1976

Report 47 47

4180 NCRP NCRP 1976 Radiation Protection for Medical drgop212-4.rOO 1984 R NCRP Report 1989

Report 48 and Allied Health Personnel 105

4181 NCRP NCRP 1976 Radiation Protection for Medical reg10.8.r02 1987 R NCRP Report 1989


4182 NCRP NCRP 1976 Radiation Protection for Medical reg8.18.rOl 1982 R NCRP Report 1989


4183 NCRP NCRP 1976 Radiation Protection for Medical reg8.23.rOl 1981 R NCRP Report 1989


4184 NCRP NCRP N/S Structural Shielding Design and drgfc4i 4-4.rOO 1985 R NCRP Report 1976

Report 49 Evaluation for Medical Use of X- 49

Rays and Gamma Rays ofEnergies up to 10 MeV


RecrdSt4 itd"r Do. Acet-Ltest Starndard La~testVersion;~b i | Con-

4185 NCRP NCRP 1976 Structural Shielding Design and reg8.18.rOl 1982 R NCRP Report 1976Report 49 Evaluation for Medical Use of X- 49

Rays and Gamma Rays ofEnergies up to 10 MeV

4186 NCRP NCRP 1976 Environmental Radiation reg4.15.rOl 1979 R NCRP Report 1976Report 50 Measurements 50

4187 NCRP NCRP NIS Review of NCRP Radiation Dose inm1245 App. B 1991 R NCRP Report 1977Report 53 Limit for Embryo and Fetus in 53

Occupationally Exposed Women

4188 NCRP NCRP 1977 Review of NCRP Radiation Dose inm 302 1994 R NCRP Report 1977Report 53 Limit for Embryo and Fetus in 53

Occupationally Exposed Women

4189 NCRP NCRP NIS Protection of the Thyroid Gland in inm1245 App. B 1991 R NCRP Report 1977Report 55 the Event of Releases of 55

Radioiodine4190 NCRP NCRP 1977 Protection of the Thyroid Gland in not88-15 1988 R NCRP Report 1977

Report 55 the Event of Releases of 55Radioiodine

4191 NCRP NCRP 1977 Protection of the Thyroid Gland in regS.20.rOl 1979 R NCRP Report 1977Report 55 the Event of Releases of 55

Radioiodine4192 NCRP NCRP 1977 Radiation Exposure of the U.$S drgop212-4.r00 1984 R NCRP Report 1988

Report 56 Population from Consumer 95Products and MiscellaneousSources

4193 NCRP NCRP NIS Instrumentation and Monitoring Inm1 245 App. B 1991 R NCRP Report 1978Report 57 Methods for Radiation Protection 57

4194 NCRP NCRP 1978 Instrumentation and Monitoring inm83525 1984 R NCRP Report 1978Report 57 Methods for Radiation Protection 57

?U)

(b



.Record .t......De. A;cept- Latet- Standard .Laet.- V.erin

No. Cda' 8Stan- i { n 'itle - Di Ve e 6h ,i Date

4195 NCRP NCRP 1978 Instrumentation and Monitoring inm83526 1984 R NCRP Report 1978

Report 57 Methods for Radiation Protection S7





4198 NCRP NCRP 1978 Instrumentation and Monitoring reg10.8.r02 1987 R NCRP Report 1978


4199 NCRP NCRP 1978 instrumentation and Monitoring reg8.21,rO1 1979 R NCRP Report 1978


4200 NCRP NCRP 1978 Instrumentation and Monitoring reg8.23.r01 1981 R NCRP Report 1978


4201 NCRP NCRP 1978 Instrumentation and Monitoring reg8.24.rOl 1979 R NCRP Report 1978


4202 NCRP NCRP N/S A Handbook of Radioactivity inm 1245 App. 8 1991 R NCRP Report 1985

Report 58 Measurements Procedures 58

4203 NCRP NCRP 1985 A Handbook of Radioactivity reg10.8.r02 1987 R NCRP Report 1985


4204 NCRP NCRP 1978 A Handbook of Radioactivity reg4.1 5.rOl 1979 P NCRP Report 1985


4205 NCRP NCRP 1978 A Handbook of Radioactivity reg4.16.rOl 1985 R NCRP Report 1985


4206 NCRP NCRP 1978 A Handbook of Radioactivity reg8.21.rOl 1979 R NCRP Report 1985


4207 NCRP NCRP 1978 andbook of Radioactivity reg8.23.rOl 1981 R NCRP Report 1985


4208 NCRP NCRP 1978 A Handbook of Radioactivity reg8.24.rOl 1979 A NCRP Report 1985

Report 58 Measurements Procedures _ 58


R5o~rdg: Standrd Doe. Accept. Latestitadad tt_ ..... V..s..ioNo.Cde.ana..Vr.o.Ti Doumn Dat VOomets Vrsoont

4209 NCRP NCRP N/S Operational Radiation Safety minml 245 App. B 1991 R NCRP Report 1978______Report 59 Program ._.____ 59

4210 NCRP NCRP 1978 Operational Radiation Safety reg8.23.rOl 1981 R NCRP Report 1978Report 59 Program _ 59

4211 NCRP NCRP N/S Radiation Safety Training Criteria minm 245 App. B 1991 R NCRP Report 1978Report 61 for Industrial Radiography 61

4212 NCRP NCRP N/S Management of Persons inml 245 App. B 1991 R NCRP Report 1980Report 65 Accidentally Contaminated with 65

Radionuclides __. _

4213 NCRP NCRP 1980 Management of Persons inr83526 1984 R NCRP Report 1980Report 65 Accidentally Contaminated with 65

Radionuclides

4214 NCRP NCRP 1980 Management of Persons inm83726 1991 R NCRP Report 1980Report 65 Accidentally Contaminated with 65

Radionuclides4215 NCRP NCRP 1980 Management of Persons inm83750 1994 R NCRP Report 1980

Report 65 Accidentally Contaminated with 65Radionuclides _-

4216 NCRP NCRP N/S Dosimetry of X-Ray and Gamma- inm1245 App. B 1991 R NCRP Report 1981Report 69 Ray Beams for Radiation Therapy 69

in the Energy Range 1 OkeV to50MeV

4217 NCRP NCRP N/S Nuclear Medicine - Factors inm 1245 App. B 1991 R NCRP Report 1982Report 70 Influencing the Choice and Use of 70

Radionuclides in Diagnosis andTherapy .

4218 NCRP NCRP 1983 Operational Radiation Safety- drgfc414-4.rOO 1985 R NCRP Report 1983Report 71 Training 71

4219 NCRP NCRP N/S Operational Radiation Safety- inm1245 App. B 1991 R NCRP Report 1983Report 71 _ Training ______71

4220 NCRP NCRP 1983 Operational Radiation Safety- inm83523 1984 R NCRP Report 1983Report 71 Training 71

4221 NCRP NCRP 1983 Operational Radiation Safety- inm83750 1994 R NCRP Report 1983_ Report 71 Training _ _ 71 _

z

'0

f1j1

zt_1

tJI



422 NCRP NCR 198 O}-rdr 0......Q...perational Radiation Safet; Ireglo .8.rO2 1987 R NCRP...... Repo... rt| 198

4223 i NCRP jNeCPRPt 1 1 9 8 3 Poeto nNcerMdcn reg8.13.rOZ 1987 h NCRP Report 1983

Report 73 and Ultrasound DiagnostiC 73

Procedures in Children

4224 NCRP NCRP N/S Radiological Assessment: minml245 App. 8 1991 R .NR eot18

Report 76 Predicting the Transport, 76

Bioaccumulation, and Uptake byMan of Radionuclidds Released to

4225 NCRP NCRP N/S Genal ronepts ft inml245 App. 1991 R NCRP Report 1985

Report 84 Dosimetry of Internally Deposited 84

Opradionulde71______

4226 NC RP NCRP N7S nior5 A 1991 R NCRP Report 1987

Report 87 Assessment of internal 8

4227 NCRP 1987 Ureofioas isay P edur nes reg8.9r1O 1993 P-NCRP Report 1997

Report 87 Assessment of Internal 87

Radonu--d Dpostio _Report___ _________

4228 NCRP NCRP 1986 Radiatonucal Alsession drg3003.rOO 1990 R NCRP Report 1987

Report 88 Prdcintro SythemTasport,_______ ______8 ____

_:NS neoratl Conf cepts or8 tO ionizing inm1 245 App. B 1991 R NCRP Report 1993

4225 116 ..

4229 NCRPF NC;HP MwO - � 1. -1- - - - -, -- -- - - - - - 116IReport 91 _ __ aa n I. 1aq NCRP Renort - 1993

Limitation of Exposure to.. .._rn I4230 NCRP NCRP

ReportN/S Limitation of Exposure to ionizing inm I -zuz I :0- I I

116914 _ _ Radiation 4 ,r 1 o - NCRP Re-ort 1993

Limtaio ofM_ Exosr to _on__n

4231 1 NCRP

4232 1 NCRP

NCRPReport 91

CRPReport 92

1987 Limitation of Exposure to Ionizing pol55J1-HZ/-/0ZZ 1 Y7UV n1

1164Radiation I~~5.nr fR

1987 Pbliic Radiation Exposure fromNuclear Power Generation in theUnited States

drg8012,~rOO 1 YY4+ n regS.29.rOl 92. _

-----. I -- I t I l 1Prowosed NCRP Report 1 1 987Ion-zing g.... -a -u 0' IA

4233 NCRP NCRPReport 93

1987 Ponizing oaftheUon txposurtes O teIPopulation of the United States

U190V I -- . vi7 ..

regS.29,rOlI'

93

L I1 - I ___I -__ I________3 . I_______ -______


R..cod d | De Ac. Wdatd Latest Veion

4234 NCRP NCRP N/S Ionizing Radiation Exposure of the inm1245 App. B 1991 R NCRP Report 1987

Report 93 Population of the United States, 93

4235 NCRP NCRP N/S Ionizing Radiation Exposure of the pol55FR27522 1990 R NCRP Report 1987

Report 93 Population of the United States 93

4236 NCRP NCRP 1987 Exposure of the Population in the drg8012.rOO 1994 R Proposed NCRP Report 1988

Report 94 United States and Canada from reg8.29.r01 94Natural Background Radiation

4237 NCRP NCRP N/S Exposure of the Population in the inm1245 App. B 1991 R NCRP Report 1988

Report 94 United States and Canada from 94Natural Background Radiation

4238 NCRP NCRP N/S Radiation Exposure of the U.S. inm1245 App. B 1991 R NCRP Report 1988


4239 NCRP NCRP N/S Radiation Exposure of the U.S. pol55FR27522 1990 R NCRP Report 1988


4240 NCRP NCRP 1989 Comparative Carcinogenicity of drg8012.rOO 1994 R Proposed NCRP Report 1988

Report 96 Ionizing Radiation and Chemicals reg8.29.rOl 96

4241 NCRP NCRP N/S Quality Assurance for Diagnostic inm1 245 App. B 1991 R NCRP Report 1988

Report 99 Imaging _ 99

4242 NCRP NCRP N/S Exposure of the U.S. Population inm 1245 App. B 1991 R NCRP Report 1989

Report 100 from Diagnostic Medical Radiation 100

4243 NCRP NCRP 1989 Exposure of the U.S. Population drg8012.rOO 1994 R Proposed NCRP Report 1989

Report 101 from Occupational Radiation reg8.29.rOl 101

4244 NCRP NCRP N/S Exposure of the U.S. Population inm1245 App. B 1991 R NCRP Report 1989

Report 101 from Occupational Radiation 101

z

-4n

Is0

z

'0



R e o dS a in d a rd D e . A c p -L t s t n a d l a t s t V ~ s

4245 NCRP NCRP N/S Radiation Protection for Medical |inm 245 App. B 1991 R 5NCRPReport 9


4246 NCRP NCRP 1989 Limits for Exposure to Hot not90-48 1990 A 10RP Report 1989

Report 106 Particles' on the Skin 106

4247 NCRP NCRP 1990 Implementation of the Principle of drgOO02.rOO 1991 A Appendix X to NCRP Report 1990

Report 107 As Low As Is Reasonably Reg Guide 107

Achievable (ALARA) for Medical 10.8

and Dental Personnel

4248 NCRP NCRP N/S Implementation of the Principle of inml 245 App. B 1991 R NCRP Report 1990

Report 107 As Low As Is Reasonably 107

Achievable (ALARA) for Medicaland Dental Personnel

4249 NCRP NCRP 1990 Implementation of the Principle of reg10.8 App. X 1992 R NCRP Report 1990

Report 107 As Low As Is Reasonably 107

Achievable (ALARA) for Medicaland Dental Personnel

4250 NCRP NCRP N/S Calibration of Survey Instruments not93-30 1993 R NCRP Report 1991

Report 112 Used in Radiation Protection for 112

the Assessment of IonizingRadiation Fields and RadioactiveSurface Contamination

. .1 A I QQA R Prnnostd NCRP Report 1993


I 1993 Risk testimates or onaulatoProtection

urys V-. vv_ * vv . .

reg8.29.rO1 115

199 ,,,.-. -! I yi- R tpronnsed I NCRP Report I 99UI t1993..


1993 LRmitation ot txposure lu 'nIVIRadiation

U[uoV . <., vv , ovs . . I . -r- ---

reg8.29.rO1 116

.. I_______ 1 _____ ________ I______________I__ I I________ ~ _ _ _ _ ---- I ----___ - -----_____ - _______


Reod tndr e.s Accept-~V~ aes tdard Letei Versioni

kNo- Code 9 oStandad "Tement Date :-if ,t C Vrsion Date4253 NEI NEI 94-01 1995 Industry Guideline for regl.163.rOO 1995 P NEI 94-01 1995

Implementing Performance-BasedOption of 10 CFR 50 Appendix J

4254 NEMA NEMA N/S National Electrical Manufacturers bul79-001 8 1980 R Generic n/a n/aAssociation reference to

NEMA

4255 NEMA NEMA N/S National Electrical Manufacturers bu188-010.s01 1989 R Generic nWa n/aAssociation reference to

INEMA

4256 NEMA NEMA AB-1 N/S Molded-Case Circuit Breakers and bu188-01 0 1988 P Implied NEMA AB 1 1993Molded Case Switches endorsement

4257 NEMA NEMA AB-2 N/S UL Standard for Safety Molded- bu188-01 0 1988 P Latest Version UL 489 1995Case Circuit Breakers and Circuit maybeBreaker Enclosures incorrect.

4258 NEMA NEMA AB-2 N/S UL Standard for Safety Molded- not85-16 1985 P Latest Version UL 489 1995Case Circuit Breakers and Circuit maybeBreaker Enclosures incorrect.

4259 NEMA NEMA AB-3 1984 Molded Case Circuit Breakers and not92-51.sO1 1994 R NEMA AB 3 1991_ _ Their Application

4260 NEMA NEMA AB-4 1991 Guidelines for the Inspection and not92-51 1992 R NEMA AB 4 1991Preventive Maintenance of MoldedCase Circuit Breakers Used inCommercial and Industrial

_ _Applications

4261 NEMA NEMA AB-4 1991 Guidelines for the Inspection and not92-51.sO1 1q94 R NEMA AB 4 1991Preventive Maintenance of MoldedCase Circuit Breakers Used inCommercial and Industrial

:_ _ __ | :Applications :

z

t.~)

z

'IO40



R '| A t-4 dat d Dec. Ascept- Lt|Cst Stadrd Ltest Ver6le

No oe Standard :eau il Ddcument Dt aiiy omet" erinat-

-4-262-- NEMA NEMA AB-4 1991 Guidelines for the Inspection and not93-6 4 1993 R NEMA AB 4 1991

Preventive Maintenance of MoldedCase Circuit Breakers Used inCommercial and Industrial

Applications nt15191 RNMMG195

4263 NEMA NEMA MG 1 1978 Motors and Generators not9l-5s 1991 R NEMA MG 1 1995

4264 NEMA NEMA MG 1 1988 Motors and Generators not92-51.s01 1994 R NEMA MG 1995

4265 NEMA NEMA WC N/S Ampacitles of Cables in Open-Top not92-46 1992 R Same as ICEA NEMA WC51 1986 R91

51 Cable Trays Publication P-54-440

4266 NETA NETA STD 1987 National Electrical Testing bu188-010 1988 P Implied NIETA STD ATS 1993

ATS Association Acceptance Testing endorsement

Specifications ______

4267 NFPA NFPA 1991 Fire ProtectionsHandbook drg3006.rOO 1993 R Not found n/a

4268 NFPA NFPA 1976 Fire Protection Handbook inm81054 1984 R j Not found na

___ -- -. . _ i Na.t;,ni F Prntection agt83-033 1983 R Generic n/a n/a4269 NFPA NFIJA Veto

Association Standards7 '

NIFPA

.__ _ ____I = I-_. , - -4 1 v-,77 R I F tNFPA 1201 1 1994Develop.ng Fire Protection

4270 NFPA NFPA 4 1977 Developing Fire Protection reg 1.I zu.rv. I I 7, I/ .. I

I ___________ IServices Tor me rTno _-NFPAut20l1NI I I*- I 1. if'A *1 qiR R !NKP 1201 I - -1994

427

427

427

427

F]

NFPA NFPA 4 N/IS Developing Fire Protectiul,- - - - I ..

-1,1 . svs . .

__I__I_ _ ._ 1 1 1 9 seRvicestort -7eruoi I 1NFPA 1201 t l 994NFPJ

NFP~

A-- NFPA 4 1977 Developing Fire Proxection s,~Ju:w.>, , vv - . .

IServices for the Public I .,m I, -s Withdrawn Withdrawn n/a.- I I - -- - . .. k -wvv z .. . _ A . _---- - ihd a n - ! ih r w

A iFPA 4A 19 69 Fire Department organization reg 1 . 14J- zV I I.II, / ,

out of print

__ _ _ _ _ .. - -- - f.- I - 4 -in1 11 I 1AA R t!td aw W ithdraw n 1 n/a4

75-

NFPA NFPA 4A SN/S are Departmem VFqdF114d%1V11 Ie V I., -v1- . .

Iou t of nrint-

srpI-.I. I -JOFire Depatmet uraniztio iou.of orintNFPA NFPA 4A 19g69 IFire Department Organization slpv.u. I I-

Io 'u t ,o ,f , p r~i'n t I -

I _ __ _ _ I _ _ _ _ __ _ _ _ _I__ _. __ _ __ _ _ -A I ___ ___


RFcord Sadt Do. t a Stndrd L

4276 NFPA NFPA 6 1974 Recommendations for regl.120.rO1 1977 R Withdrawn - Withdrawn n/aOrganization of Industrial Fire Loss out of printPrevention

4277 NFPA NFPA 6 N/S Recommendations for regl.70.rO3 1978 R Withdrawn - Withdrawn n/aOrganization of Industrial Fite Loss out of printPrevention

4278 NFPA NFPA 6 1974 Recommendations for srp9.5.1 1981 P Withdrawn - Withdrawn n/aOrganization of Industrial Fire Loss out of printPrevention

4279 NFPA NFPA 7 1974 Management of Fire Emergencies regl.120.rOl 1977 R Withdrawn - Withdrawn n/aout of print

4280 NFPA NFPA 7 N/S Management of Fire Emergencies reg .70.r03 1978 R Withdrawn - Withdrawn n/aout of print

4281 NFPA NFPA 7 1974 Management of Fire Emergencies srp9.5.1 1981 R Withdrawn - Withdrawn n/aout of print

4282 NFPA NFPA 8 1974 Effects of Fire on Operations regl.120.rOl 1977 R Withdrawn - Withdrawn n/aManagement Responsibility out of print

4283 NFPA NFPA 8 N/S Effects of Fire on Operations regi.7003 1978 R Withdrawn - Withdrawn n/aManagement Responsibility out of print

4284 NFPA NFPA 8 .1974 Effects of Fire on Operations srp9.5.1 1981 R Withdrawn - Withdrawn n/aManagement Responsibility out of print

4285 NFPA NFPA 1O 1984 Portable Fire Extinguishers inm64704 1994 R NFPA 10 1994

4286 NFPA NFPA 10 N/S Portable Fire Extinguishers inm88055 1991 R NFPA 10 1994

4287 NFPA NFPA 10 1975 Portable Fire Extinguishers reg1.1 20.rO1 1977 R NFPA 10 1994

4288 NFPA NFPA 10 1975 Portable Fire Extinguishers srp9.5.1 1981 P NFPA 10 1994

4289 NFPA NFPA 11 N/S Low-Expansion Foam inm88055 1991 R NFPA 11 1994

4290 NFPA NFPA 11 1975 Low-Expansion Foam regl.120.rOl 1977 R NFPA 11 1994

4291 NFPA NFPA 11 1975 Low-Expansion Foam srp9.5.1 1981 P NFPA 11 1994

4292 NFPA NFPA 1 1A NIS Medium- and High-Expansion inm88055 1991 R NFPA 1 1A 1994Foam Systems ....

4293 NFPA NFPA 1 1A 1970 Medium- and High-Expansion regl.120.rO1 1977 R NFPA 1 1A 1994Foam Systems

z

txI

%0

z

'a

0



N o ..c d S a d w e s k iT t eD c m n D t a n i l o m n sV r i nD t

4294 NFPA NFPA 11A 1970 Medium- and High-Expansion srp9.5.1 1981 P NFPA 11A 1994

Foam System s __________|___

4295 NFPA NFPA 11 B 1974 Low-Expansion Foam regi .i 20.r01 1977 R _ NFPA 11 1994

4296 NFPA NFPA 118 1974 Low-ExpansionFoam srp9.5.1 1981 P NFPA 11B NFPA t1 1994combined withN PA 19

4297 NFPA NFPA 12 N/S Carbon Dioxide Extinguishing nnm88-55 1991 R NFPA 12 1993

Systems _ _ _ _ _ _ _

4298 NFPA NFPA 12 N/S Carbon Dioxide Extinguishing not92-14 1992 R NFPA 12 1993

Systemrs

4299 NFPA NFPA 12 1973 Carbon Dioxide Extinguishing not92-28 1992 R NFPA 12 1993

Systems _ _ _ _ _ _

4300 NFPA NFPA 12 1973 Carbon Dioxide Extinguishing re.g.120.r 1977 P NFPA 12 1993

Systems _ _ _ _ _ _ _

4301 NFPA NFPA 12A N/S Carbon Dioxide Extinguishing srp9.5.1 1981 P NFPA 12 1993

Systems _ _ _ _ _ _ _

4302 NFPA NFPA 12A N/S Halon 1301 Fire Extinguishing inm880o 5 1991 R NFPA 12A 1992

Systems__ _ _ _ _ _

4303 NFPA NFPA 12A 1973 Halon 1301 Fire Extinguishing not92-28 1992 R NFPA 12A 1992

Systems !F A 1 A1 9

4304 NFPA NFPA 12A 1989 Halon 1301 Fire Extinguishing not92-28 1992 -N FP A 12A 1992System s__ _ _ __ _ _ _ _ _

4305 NFPA NFPA 12A 1973 Halon 1301 Fire Extinguishing regi .1 20.rO5 1977 P NFPA 12A 1992

Systems withdrawn

4306 NFPA NFPA 12A 1973 Halon 1301 Fire Extinguishing srp9.5.1 1981 P NFPA 12A 1992

Systems

4307 NFPA NFPA 128 N/S Halon 1211 Fire Extinguishing inm88r5. 1991 R NFPA 12B withdrawn n/a

Systems withdrawn1995 _ _

4308 NFPA NFPA 128 1973 Halon 1211 Fire ExigihnRel. 0r1 17 NFPA 128 withdrawn n/a

Systems withdrawn1995

4309 NFPA NFPA 128 1973 Halon 1211 Fire Extinguishing srp9.5.1 1981 P NFPA 12B withdrawn n/a

Systems withdrawn11 9 9 5 _ _ _ _ _ _ _ _ _ _ _


... .. _ ............................. ..... ....... _ ............ . . . . . . . . . . . ._

.Refordnt- tSt .Standard Latet Versn 1No oe Sedr eso ieDcmn.D at. abiity, Commen~ts - Version Dt

4310 NFPA NFPA 13 N/S Installation of Sprinkler Systems gIt80-100 1980 R NFPA 13 1994

4311 NFPA NFPA 13 N/S Installationof Sprinkler Systems g:t86-01 0 1986 8 NFPA 13 1994

4312 NFPA NFPA 13 NIS Installation of Sprinkler Systems inm88055 1991 - NFPA 13 1994

4313 NFPA NFPA 13 NIS Installation of Sprinkler Systems not84-09 1984 P NFPA 13 1994

4314 NFPA NFPA 13 1976 Installation of Sprinkler Systems regl.120.rOl 1977 P NFPA 13 1994

4316 NFPA NFPA 13 1976 Installation of Sprinkler Systems srp9.5.1 1981 P NFPA 13 1994

4316 NFPA NFPA 14 1983 Installation, of Standpipe and Hose inm64704 1994 R NFPA 14 1993_ __ Systems

4317 NFPA NFPA 14 NIS Installation of Standpipe and Hose inm88055 1991 R NFPA 14 1993_____________ ~System s_ _ _ _ _ _ _

4318 NFPA NFPA 14 1974 Installation of Standpipe and Hose regl.120.rOl 1977 R NFPA 14 1993_ _ Systems

4319 NFPA NFPA 14 1974 Installation of Standpipe and Hose srp9i5.1 1981 P NFPA 14 1993Systems

4320 NFPA NFPA 15 N/S Water Spray Fixed Systems for gpt86-01 0 1986 P NFPA 15 1990Fire Protection

4321 NFPA NFPA 15 N/S Water Spray Fixed Systems for inm88055 1991 R NFPA 15 1990Fire Protection

4322 NFPA NFPA 15 1973 Water Spray Fixed Systems for regl.120.rOl 1977 R NFPA 15 1990Fire Protection

4323 NFPA NFPA 15 1973 Water Spray Fixed Systems for srp9g.5.11 1981 P NFPA 15 1990Fire Protection

4324 NFPA NFPA 16 N5S Installation Of Deluge Foam-Water inm88055 1991 8 NFPA 16 1995Sprinkler and Foam-Water SpraySystems I_ _

4325 NFPA NFPA 16 1973 Installation Of Deluge Foam-Water srp9.5.1 1981 P NFPA 16 1995Sprinkler and Foam-Water SpraySystems

4326 NFPA NFPA 20 N/S Installation of Centrifugal Fire g1t80-100 1980 R NFPA 20 1993Pumps _

z

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-3

0

ItJ

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- I f~ -- ..-- 7 : ;-..iE-E.E:T:~. N~.0:~;zCI ..S :4-f.: 11(-:X tr- X:j j.,'~,~ -e : . : 7 777-777771.

|Recd SS dr|V rd|

Doe. ~ Accept~ Lat~st St~nWarj Uiesit versio.icument.~LDate j abiity Commets, esnDt.. WDC

4327

i4328

NFPA

WNFPA

NFPA 20

NFPA 20 N/S

Installation ol Uenmmu-w, I 11-PumpsInstallation of Centrifugal Fire

Iim6405 3B 1979 R NFPA 20 I UU0

I II _____I_ .~ .. -.-- I h. ----. 4 n tinm8805 199inm88055 1991 R NFITA ZU I UUo

IPumps __a________2_199

4329 NFPA NFPA 20 1973 Installation of Centrifugal Fire reg1.120.r0l 1977 P NFPA20 19g3

_________________ _____________ ______________ Pumps Fire________________________1981______________ P_____20____1993____

4330 NF NFPA 20 1973 Installation of Centrifugal Fire srp9.5.1 1981 P NFPA20 1993

Pumps Prvae___e________179 R FP 2 19

4331 NFPA NFPA 22 N/S Water Tanks for Private Fire in 3 1979 8 NFPA22 1993

Protection ________179___PA24_99

4332 NFPA NFPA 24 N/S Installation of Private Fire ServiceNFPA24 1995Mains and Their Appurtenances

43 NFPA NFPA 24 N/S Installation of Private re Service inm89055 1991 R NFPA24 1995

Mains and Their Appurtenances

4334 NFPA NFPA 24 1973 installation of Private Fire Service reg1.120.rO1 1977 R NFPA 24 1995


Q_-A -

Q .P Fi' S 1 1981 P NFPA 24 1995insiejiejivas Fir~o.

4335 NFPA NFPA 24 1YJ3

4336 I NFPA -NFPA 26 1958

Installatflln0 rtVI~ t F-- t ,~ " VI--


Supervision of Valves ControllingWater Supplies for Fire Protection

_ _ .r A zt, 1 QOOreg1.1I20.rO1 1977 P NtFPA ZO t Yt50

. - I I ---- k-~ i 0' MP 9 t -1988

4337 i NFPA NFPA 26 1958 Supervision of Valves Controlling

Water Supplies for Fire Protectionsrp9.5.1I -I Zia I r- {xi g A �

. _ I I I. I on I t-NFPA 500 t 1992NFPA600 199

4338433943404341

4342

4343

NFPA NFPA27NFPA NFPA 27

NFPA NFPA 27NFPA NFPA 27

NFPA NFPA 30

NFPA NFPA 30

~-i Qa7 I1-4-trini Firr HfInaASs Irw 1. IzV.I I JI {

I . I .L - I -. .Fire Brig des ____ ____ ___ NFPA 600 r- 1992 ----N/S -- Industrial Fire Brigades Irea I -I 0A. I 992

-

--. 0 1 I l. -- tF -m I rw -vv975 jlndustrial Fire Brigades Ib4rptyII ri D. 1 99

-- , j u! .dI rhO UFJ 'O_ _ _ _ _ _ _ _ _ I I. i - Im: A o 7 1 9 9 3.. M_., .: -c a-s: A-.>^ crD9.5 .31 I Zia n *-l z ra vv

. _ _

I U 0 jjUU5E~dI -II U-j. . . I-'-dr -- - ! =00 MrPAi4) 1 9

NIS

IN/S

Flammable and CombustibleLiquids CodeFlammable and Combustible

drguuuj.rWv l Z;U4 n% EM. . ,5 van

I -ti Irt- L-g - -t8 I6I D0I1 0Iglt86-01 0 I u96b I r - I - -v s _v

I _Liquids Code -_


Recod Stnd~r Do~ Acept-- Ltet Stalndard LetestVersion_ _ ...__. ... ..

No -6 Code Standard Doc-m.t........a.. : i m i .er..o DatI4344 NFPA NFPA 30 N/S Flammable and Combustible inm88055 1991 R Typo in NFPA 30 1993

Liquids Code inm88055-wasNFPA3O9

4345 NFPA NFPA 30 1973 Flammable and Combustible reg1.120.rOl 1977 P NFPA 30 1993Liquids Code

4346 NFPA NFPA 30 1973 Flammable and Combustible srp9.5.1 1981 P NFPA 30 1993Liquids Code

4347 NFPA NFPA 31 N/S Installation of Oil-Burning inm88055 1991 R NFPA 31 1992Equipment __. _.

4348 NFPA NFPA 37 NIS Stationary Combustion Engines inm88055 1991 R NFPA 37 1994and Gas Turbines

4349 NFPA NFPA 45 NIS Fire Protection for Laboratories inm88055 1991 R NFPA 45 1991Using Chemicals

4350 NFPA NFPA 50 N/S Bulk Oxygen Systems at inm88055 1991 R NFPA 50 1990Consumer Sites

4351 NFPA NFPA 50A 1976 Gaseous Hydrogen Systems at srp9.5.1 1981 P NFPA 50A 1994Consumer Sites

4352 NFPA NFPA 50B N/S Liquefied Hydrogen Systems at inm88055 1991 R NFPA 50B 1994Consumer Sites

4353 NFPA NFPA 518 1984 Fire Prevention in Use of Cutting inm64704 1994 R NFPA 518 1994and Welding Processes

4354 NFPA NFPA 51B N/S Fire Prevention in Use of Cutting inm88055 1991 R NFPA 51B 1994and Welding Processes

4355 NFPA NFPA 51B 1976 Fire Prevention in Use of Cutting regl,120.rOl 1977 A NFPA 51B 1994and Welding Processes

4356 NFPA NFPA 51B 1976 Fire Prevention in Use of Cutting srp9.5.1 1981 R NFPA 51B 1994and Welding Processes

4357 NFPA NFPA 54 N/S National Fuel Gas Code inm88055 1991 R ANSI Z223.1/ 1992/ 1992NFPA 54

LA

z

C)

LA

(-b

zC)

a

4:~



ftecrd Sandtd Dc. Acep- LaestSt~andard Latet Vears~o

N00 C o de V io ..ite Docum Dat a i C om m ents Valtoonn D

4358 NFPA NFPA 69 N/S Explosion Prevention Systems inm88055 1991 R NFPA69 1992

--NFPA 69 1992

4359 NFPA NFPA 69 1973 Explosion Prevention Systems regl .1 20.r0l 1977 R NFPA_99_1992

4360 NFPA NFPA 69 1973 Explosion Prevention Systems srp9.5.1 1981 _ NFPA_69

4361 NFPA NFPA 70 1978 National Electrical Code inm51063 1985 AR NFPA 70 1996

4362 NFPA NFPA 70 N/S National Electrical Code inm88055 1991 R . NFPA7 1996

_ o9- 1994 R - - NFPA70 199670 NIS i'JavlO idI EAw I.O4363 I

4364

4365

4366

4367

NFPA

NFPA

NFPA

NFPA

NFPA

NFPA

NFPA

70a

70 1975 National Electrical CodeI I 1 A_ -7 - I I non

reg1.1 20.rO1 1977 R1 Nt4`11A /V I :7-

, . I ___n taNFPA 7 1996....... I . . . .. 99

NFPA 70

NFPA 70B

NFPA 70B

1975 National Electrical Code stpu.n.I lvOI r

I_ - 4I-_t 1:%J1 FPA 70R 1994Elecirical~~~., Eqimn Mantnac .mU.. . 'N/S Electrical Equipment MaintenanceIinmMSUDD 1 UV n

I __ _ _ _ _ _ _ _ _ _ _ _I - I f~{t ricPa -7or I 1994

990 Electrical Equipment Maintenance Inot93-64 1 vUUY n ,., ,E, vv . _ _ .

[-4316I___ I_ ---1 L. . . . n. 4Ik.Ienn I 188 --fw -- INFPA7E 18

F NFPA NFPA 70E 1974 Elmctpcal WoyeeyWrequklplaes *uEmployee Workplaces

uulvv-v, w ---

________- I. . tsnl.s I 19q() A TNFPA 70E 1 9884369 NFPA NFPA 70E NIS E mecpncal W rpaTe lY acest7r4U1 1 L- UI

Employee Workplaces.. " ------- . .

I__I___I__ I I . 1nr1 i 7I1-F I NFPA'7OE-- 1 1988- -.- - ectr cai oa. - -. n- r- quni 119 71-- P - -

43.

43'

43,

70 NFPA NFPA 70E N/Si Electmpal oee WrkesEmployee Workplaces

,. Ipfiy . . E. ,.v . - - -

I_! _ !___I -t. ... - ; I- 1 qf44I R I FPA 72 | 993Na.oa rir ,grr I s. _u.

71

,72

NFPA NFPA 72D 1979 National Fire Alkillf, Go-

_I = I._.___ I . - .. _ -. I- -- 9 1 INFPQ72 1R13NationalvU .-r __,muor

NFPA NFPA 72D N/S National Hre, Alarm UfJuu MM--

_ _ l

___ .... . . A T INFPA 72 1 1993

re- .. J .- ,

£ .i.

NFPA 72D 1975 INational Fire Alarm L;0d0 leg 1. 14V.1 V - I . I I

I

4374

1

NFPA NFPA 72D -- 1975 INational Fire Alarm Code srpu. D. I_ _ _ _ I- I . 1. - 0a I -- IN FPA 72 1 1 9

1.7v v I...... ....

I ________I_________________ I ________


Record Sth'6iiDO.AcetiiLtstSadard Latest Version

No. Code Stadard Version . tl Documet -te t o e

4375 NFPA NFPA 72E N/S National Fire Alarm Code inm8S055 1991 R NFPA 72 1993

4NFPA NFPA 72E 1974 National Fire Alarm Code reg_.120.r0l 1977 P NFPA 72 1993

4377 NFPA NFPA 72E 1974 National Fire Alarm Code srp9e5.1 1981 P NFPA 72 1993

4378 NFPA NFPA 75 N/S Protection of Electronic inm88055 1991 R NFPA 75 1995Computer/Data ProcessingEqulipment

4379 NFPA NFPA 77 NIS Static Electricity inm88055 1991 R NFPA 77 1993

4380 NFPA NFPA 78 1968 Lightning Protection Code drgrs7O5-4.rOO 1979 P NFPA 780 1992

4381 NFPA NFPA 78 1975 Lightning Protection Code drgrs705-4.rOO 1979 P NFPA 780 1992

u 4382 NFPA NFPA 78 N/S Lightning Protection Code inm88055 1991 R NFPA 780 1992

4383 NFPA NFPA 79 N/S Electrical Standard for Industrial inm88055 1991 R NFPA 79 1994

_ _ _ Machinery4384 NFPA NFPA 80 N/S Fire Doors and Fire Windows inm88055 1991 R NFPA 80 1995

4385 NFPA NFPA 80 1975 Fire Doors and Fire Windows reg1.120.rOl 1977 R NNFPA 80 1995

4386 NFPA NFPA 80 1975 Fire Doors and Fire Windows srp9.5.1 1981 R NFPA 80 1995

4387 NFPA NFPA 80A N/S Protection of Buildings from inm88055 1991 R NFPA 80A 1993

Exterior Fire Exposures

4388 NFPA NFPA 85D N/S Prevention of Furnace inm88055 1991 R NFPA 8502 1995Explosions/Implosions in MultipleBurner Boiler-Furnaces

z

4389 NFPA NFPA 86C N/S Industrial Furnaces Using a Special inm88055 1991 _ NFPA 86C 1995

Processing Atmosphere

v 4390 NFPA NFPA 90A N/S Installation of Air Conditioning inm88055 1991 R NFPA 90A 1993and Ventilating Systems

4391 NFPA NFPA 90A NIS Installation of Air Conditioning not83-69 1983 P NFPA 90A 1993

xa _and Ventilating Systems

fr

;0


d IRecttLst Standard Latbst. Versi|n

dNo. C o e. St da V ers o .n t D ability C: m m entS . . i n te

4392 NFPA NFPA 90A NIS Installation of Air Conditioning srp9.5.1 1981 P NFPA 90A 1993

and Ventilating Systems

4393 NFPA NFPA 90B N/S Installation of Warm Air Heating inm88055 1991 R NFPA 90B 1993

and Air Conditioning Systems

4394 NFPA NFPA 92 1972 Waterproofing and Draining of regi.120.rOl 1977 P Withdrawn - Withdrawn n/a

Floors out of print

4395 NFPA NFPA 92 1972 Waterproofing and Draining of srp9.5.1 1981 P Withdrawn, Withdrawn n/a

Floors Typo insrp9.5.1 -NFPA 92M

4396 NFPA NFPA 101 N/S Life Safety Code bu177-008 1977 R NFPA 101 1994

4397 NFPA NFPA 101 NIS Life Safety Code inm88055 1991 R NFPA 101 1994

4398 NFPA NFPA 197 1966 Training for Initial Fire Attack regl.120.rOi 1977 P NFPA 1410 1995

4399 NFPA NFPA 197 1966 Training for Initial Fire Attack srp9.5.1 1981 P NFPA 1410 1995

4400 NFPA NFPA 204 1968 Smoke and Heat Venting reg_.120.rOl 1977 R NFPA 204M 1991

4401 NFPA NFPA 204 1968 Smoke and Heat Venting srp9.2.rO1 1981 R NFPA 204M 1991

4402 NFPA NFPA 204M N/S Smoke and Heat Venting inm88055 1991 R NFPA 204M 1991

4403 NFPA NFPA 220 NIS Types of Building Construction inm88055 1991 R NFPA 220 1995

4404 NFPA NFPA 220 N/S Types of Building Construction not95-27 1995 R NFPA 220 1995

4405 NFPA NFPA 220 1975 Types of Building Construction regl.120.rOl 1977 R NFPA 220 1995

4406 NFPA NFPA 220 N/S Types of Building Construction srp9.5.1 1981 P NFPA 220 1995

4407 NFPA NFPA 232 1975 Protection of Records inm39701 1992 R NFPA 232 1995

4408 NFPA NFPA 232 NIS Protection of Records inm4529 1980 R NFPA 232 1995

4409 NFPA NFPA 232 1975 Protection of Records regl.88.rO2 1976 A _ NFPA 232 1995


. ...r........r........A... ... .. atest Standard Latest VerlonNo. ;Coda | Stqndtid Ve n | T t. D Coment Vers on: a

4410 NFPA NFPA 232 N/S Protection of Records srpl 7.1 1981 P NFPA 232 1995

4411 NFPA NFPA 251 N/S Fire Tests of Building Construction glt86-01 0 1986 R NFPA 251 1995and Materials

4412 NFPA NFPA 251 NIS Fire Tests of Building Construction glt86-010.sO1 1994 R NFPA 251 1995and Materials

4413 NFPA NFPA 251 N/S Fire Tests of Building Construction git92-008 1992 A NFPA 251 1995and Materials ____

4414 NFPA NFPA 251 N/S Fire Tests of Building Construction inm88065 1991 R NFPA 251 1995and Materials

4415 NFPA NFPA 251 N/S Fire Tests of Building Construction not92-46 1992 R NFPA 251 1995and Materials

4416 NFPA NFPA 251 NIS Fire Tests of Building Construction not92-55 1992 R NFPA 251 1995and Materials

4417 NFPA NFPA 251 1975 Fire Tests of Building Construction not95-52 1995 R NFPA 251 1995and Materials

4418 NFPA NFPA 251 1975 Fire Tests of Building Construction regl.120.rO1 1977 R NFPA 251 1995and Materials

4419 NFPA NFPA 251 1971 Fire Tests of Building Construction srp9.5.1 1981 P NFPA 251 1995and Materials

4420 NFPA NFPA 252 NIS Fire Tests of Door Assemblies nuregO933, 1992 R NFPA 252 19953.149 _ _

4421 NFPA NFPA 259 NIS Standard Test Method for glt86^010.sO1 1994 R NFPA 259 1993Potential Heat of BuildingMaterials

4422 NFPA NFPA 259 1976 Standard Test Method for regl.120.rOl 1977 P NFPA 259 1993Potential Heat of BuildingMaterials

4423 NFPA NFPA 259 1976 Standard Test Method for srp9.5.1 1981 R NFPA 259 1993Potential Heat of BuildingMaterials

4424 NFPA NFPA 321 NIS Basic Classification of Flammable inm88055 1991 R NFPA 321 1991and Combustible Liquids

z

U)

U)

zCsi

PO

100



Record S D cept L e S d rd La iest Verslon

442 NFPA- NFPA .25 N/eS i F T :ire Hazar Poeriesi of drg OO3rO 199 R NFP 32 1994 i.' '

Flammable Liquids, Gases, sndVoltil Solid

442P8 NFPA 4825 19948

and Storage of Zirconium

4427 NFPA NFPA 600 N/S Industrial Fire Brigades inm88055 1991 R _ NFPA 600 1992

4428 NFPA NFPA 801 N/S Facilities Handling Radioactive inm88055 1991 R NFPA 801 1995

Materials ____ ____ ____ __197_R_ NFA_80

4429 NFPA NFPA 802 1974 Nuclear Research and Production reg1.1 20.rOl 1977 . NFPA 802 1993

Reactors

-,4430 ~NFP~A NF-PA 802 N/S Nuclear Re-search and Production regil.70.r03 1978 R NFPA 802 1993

R eactors _ _ _ _ _ _ _ __ _ _ _ _ _ _

4431 NFPA NFPA 802 1974 Nuclear Research and Production srp9.5.1 1981 R NFPA 802 1993

Reactors Nl P e as m 71RA59

4432 NFPA NFPA 803 1983 Light Water Nuclear Power Plants inm64704 1994 R NFPA 803 1993

-4-433 NFPA N~FPA 803 ~ N/S Light Water Nuclear Power Plants inmiiIOS5 1991 8RFA 0 1993

4434 NNFPA FPA 1962 N/S Care, Use, and Service Testing of srp9.5.1 1981 P NFPA 1962 1993

Fire Hose Including Couplings and

Nozzles NBSGR_____198

4435 NIST NBS GCR 80 1981 The Directory of Commercial drgopO32-5.rOO 1984 R NBa GCR 80- 1981

296 Calibration Services for Ionizing 296

Radiation Survey Instruments

4436 NIST NBS N/S Permissible Dose From External inm9900/20 1970 R NCRP Report 1993

Handbook Sources of Ionizing Radiation 116

59 NR eot 19

4437 NIST 59 1966 Permissible Dose From External not86-23 1986 A NCRP Report 1993


4438 NIST NB5 1954 Permissible Dose From External reg8.18.r01 1982 R NCRP Report 1993


59 _ _

Codes and Standards. and Other Guidance Cited in Regulatory DocumentsPart A - Industry Consensus Codes and Standards

Recd Otrd .d Ltst WonNo oe .Sadr eso il ocumednt:!] .. Dt abit Comnt Version DateSt n a d Tilial hk Cod _0Itnad

4439 NIST NBS 1959 Maximum Permissible Body I 0cfrlOO 1994 R NCRP Report 1959Handbook Burdens and Maximum Permissible 2269 Concentrations of Radionuclides in

Air and in Water for OccupationalExposure

4440 NIST NBS 1959 Maximum Permissible Body not84-40 1984 R NCRP Report 1959Handbook Burdens and Maximum Permissible 2269 Concentrations of Radionuclides in

Air and in Water for OccupationalExposure

4441 NIST NBS N/S A Handbook of Radioactivity reg4.15.rOl 1979 R NCRP Report 1985Handbook Measurements Procedures 588080 _ __ _ _ _ _ __ _ _ _ __ _ _ _

4442 NIST NBS 1966 Experimental Statistics reg5.37.rOl 1983 R NBS Handbook 1966Handbook 9191 ___

4443 NIST NBS 1975 Classification of Radioactive Self- reg6.4.rO2 1980 R Also ANSI N43.4 1975 R89Handbook Luminous Light Sources designated116 NBS 116

4444 NIST NBS 1977 Classification of Sealed reg6.4.rO2 1980 R Also ANSI N43.6 1977 R89Handbook Radioactive Sources designated ISO126 2919 and NBS

Handbook 126

4445 NIST NBS 1979 Classification of Industrial Ionizing drgtpl 02-5.rOO 1980 A Also ANSI N43.8 1979 R88Handbook Radiation Gauging Devices designated129 __adiogNBS 129

4446 NIST NBS 1981 Gamma Radiography - 10cfr34 1994 A ANSI N43.9 ANSI N43.9 1991Handbook Specifications for Design and Test also designated136 of Apparatus as NBS

Handbook 136

Z

90n;111Uh%.O

IU.)

�0

I

w

Zcl.�Mq)rI-I'l�40w



Recd SDetndard Late4t

TersAnyNo oe Sadr winTte Doumn Da aiiy Comments" Veon' Dat

4447 NiST NBS 1976 Problems in Sample Treatmen reg4.1rO 1979 R Pl 1976

Publication 4 Trace Analysis 4-22

22 ___1984__ ____ ____ ____ ____ ____ __ _ ___1980_

4448 NIST NBS 1978 Neutr ion Counting for reg5.34.rt l 1984 R N2S Publication 1980

Publication the Nondestructive Analysis of 528

528 _ a_ n i__ .Nuclear Materials eg.8O19 R.___1S

4449 NIST NBS 1980 Neto orrelation Counting for re53.1 1983 R NBS Publication 1980

Publication the Nondestructive Analysis of 528

528 Nuclear Materials _______

rd. ~'..~~inCtintina for 1reu5.38.r01 19831 R NBS Publication 1 9804450 NIS I

Publication---

I OVp

the Nondestructive Analysis ofKI-1-na Material

52

5Z8I . t ' inR207 1986 out of print ln-easur- ni u;-'vu

a8

n/a4451 NIST NBS

Publication1980U Measurement lech,10,00 -

I

4452 NIST NOS 1980 Measurement Technology inm85407 ; 1 out of print n/a n/a

Publication 6

_ 582 t1 tss

-_}{~ NBS Spncialf daD025.O 98 _ _ i 19g81I~~ ~ ~ ~ _ -n9..0 94

4453

4454

NIST

NIST

NBSPublication603NBSPublication

I 98 tiequirelienmb ror a" Fl~tNational Ionizing Radiation[Maueet . rga -

Publication 6031�1.

Measuremnts vrogampI l 1-7-ruv. ._ . - . I T --- _:

1981 Requirements for an EffectiveNational Ionizing RadiationMhi.nearamcintq Proaram

drgopZ I Z-4.ruv I "01+ n

ffov I-I ________ ._ - _.

44a55--- NIST NIS 1982 1ocedures for Calibrating Neutron drgop32-5.rO _

Publication Personnel Dosimeters

4455 63ST t 1982 Procer , orCaibrting Neutron inm8375.r0 1988 R___________ 63jeralosn1rL roceauresT~ ivi511dl% .VGU~.JlE_

_

NBS SpecialiPublication 603

NBS SpecialPublication 633

NBS SpecialPublication 633

I 1982

1982

1982

4456

4457

4458

NIST NBS 1 UtizPersonnel DosimetersPublication

1633 1 1 . ,nn 1 4 iwi tNISTSP810 1 1994

NIST

NIST

NISTPubiication

N/S National Voluntary LabmorayAccreditation Prograrn, 1994

urgUVV0.1VU I. .J . I �

81 0 1 _-----_I .__r ctory .. = ..7;7 i INBSIR 73-107 1 1973NBSIR 73-107

1973 iElproved Point Karnels forElectron and Beta-Ray Dosimetry

reg Il 10.-1ru I *:,,, I . .

zCr'

Vi


Record Sta dard o Latest Standard LI test .ersioNo Cod e St ndard> Ve'rslon tleDt at ility Co ment Version Das

4459 NIST NBSIR 76- 1976 Tornado-Borne Missile Speeds srp3.5.1.4 1981 P NBSIR 76-1050 1976

1050

4460 NIST NBSIR 85- 1985 Principles of Quality Assurance of inm79701 1988 R NBSIR 85-3105 1985

3105 Chemical Measure- ments

4461 NIST NBSIR 85- 1985 Principles of Quality Assurance of inm84750 1988 R NBSIR 85-3105 19853105 Chemical Measure- ments

4462 NIST NBSIR 85- 1986 Compendium of Benchmark drg1025.rOO 1993 R NBSIR 85-3151 19863151 Neutron Fields for Reactor

Dosimetry

4463 NIST NSRDS-NBS 1969 Photon Cross Sections, reg5.21.rO1 1983 R NSRDS-NBS 29 196929 Attenuation Coeffluents, and

Energy Absorption Coefficientsfrom 10 keV to 100 GeV

4464 NRA NRA 1976 High Power Rifle Rules Book 1 Ocfr73 1995 P NRA High 1993Power RifleRules Book

4465 NRA NRA N/S NRA Target Manufacturers Index 1 Ocfr73 19 95 A NRA Target 1992ManufacturersIndex

4466 NRA NRA 1976 High Power Rifle Rules Book inm81501 1984 A NRA High 1993Power Rifle

____ ___ ___ Rules Book

4467 NRA NRA NIS NRA Target Manufacturers Index inm8l 501 1984 A NRA Target 1992Manufacturers

_ _ _ _ _ _ _ _ _ _ _ In d e x _ _ _ _ _ _

4468 NRA NRA NIS NRA Target Manufacturers Index reg5.20.rOO 1974 A NRA Target 1992ManufacturersIndex

4469 UL UL 94 N/S Tests for Flammability of Plastic cir77-03 1977 R UL 94 1995Materials for Parts in Devices andAppliances

4470 UL UL 437 NIS Key Locks inm1245 App. B 1991 R UL 437 1994

z

0~



R c0 "d OtK; d:"t o A ^t- L St dard L.Ats i r o

iNo. -Cad Sttnda Ve.so . . t o t il. o V i - at

4471 UL UL 555 N/S Safety Fire Dampers inm88055 1991 R UL 555 1990

4472 LU L UL 586 N/S Safety High-Efficiency, inm88055 1991 R UL 586 also UL 586 1990

Particulate, Air Filter Units designatedANSI B132.1

4473 L UL 752 N/S Safety Bullet-Resisting Equipment inm1245 App. B 1991 R UL 752 1991 R93

4474 UL UL 752 N/S SafetyBullet-Resisting Equipment inm81084 1984 R UL 752 1991 R93

4475 UL UL 768 NIS Combination Locks inm1245 App. B 1991 R UL 768 1994

4476 UL UL 768 NIS Combination Locks inm81046 1984 R UL 768 1994

4477 UL UL Subject 1991 iire Tests for Electrical Circuit glt86-10.01 1994 P UL Outline of 1991

1724 Protective Systems Investigation1724

4478 UL UL Subject 1984 Fire Tests for Electrical Circuit not93-40 1993 R UL Outline of 1991

1724 Protective Systems Investigation1724

c c) E

Codes and Standards and Other Guidance Cited in Regulatory DocumentsPart B - Other Guidance

Record : Stadard boe Aent- Laes :e.s. -No' - 0dde et VStandard0 Vrsl t t t t o

4479 ACI ACI Journal 1960 Corrosion of Prestressed Wire in reg 1.107.rO1 1977 R ACI Journal 1960Concrete

4480 ACI ACI Journal 1969 Corrosion and Corrosion regl.107.rOl 1977 R Paper ACI Journal 1969Protection of Tendons inPrestressed Concrete Bridges ___ _

4481 ACI ACI Journal 1966 Influence of Size and Shape of reg1.35.1.rOO 1990 R ACI Journal 1966Member on the Shrinkage andCreep of Concrete

4482 ACI ACI Journal 1975 Concrete Quality Control reg1.90.rOl 1977 R ACI Journal 1975Instruments

4483 ACI ACI Journal 1949 An Ultrasonic Method of Studying regl.90.rOl 1977 R ACI Journal 1949Deterioration and Cracking inConcrete Structures

4484 ACI ACI N/S Evaluation of Concrete Properties reg1.90.rOl 1977 R ACI Monograph Not foundMonograph from Sonic Tests No 2No 2

4485 ACI ACI Paper 1972 Effect of Temperature on Creep of regl.35.1.rOO 1990 R ACI Paper 31 of 197231 of ACI Concrete, A Literature Review ACI SP 34SP 34

4486 ACS ACS Journal 1949 High Temperature Heat Contents reg1.77.rOO 1974 R ACS Journal 1949of Uranium, Uranium Dioxide andUranium Trioxide

4487 ACS ACS 1971 Time to Chemical Steady-States in reg1.113.rO1 1977 R ACS 1971Symposium Lakes and Oceans

4488 AEC 28 F.R. 1963 Notice Regarding Need for reg8.3.rOO 1973 R 28 F.R. 9678 19639678 Establishment of Film Dosimetry

Calibration Laboratory

4489 AEC AEC 1968 Meteorology and Atomic Energy reg3.33.rOO 1977 R AEC TID-24190 1968

4490 AEC AEC 1968 Meteoroiogy and Atomic Energy reg3.34.rOl 1979 R AEC TID-24190 1968

4491 AEC AEC 1968 Meteorology and Atomic Energy reg3.35.rOl 1979 R AEC TID-24190 1968

C)~

Vi

(A

U10

z

0

~0a~

W~


R c dStan dard boeb A'M OPt~L t s e so

o Codbe Stanidard:: V e io T0tle Doc men D D ate ab t Com ments L tet Version D at

4492 AEC AEC N/S Guide for Economic Evaluation of reg4.2.rO2 1976 R AEC Report 1969

Nuclear Reactor Plant Designs NUS-531

4493 AEC AEC 1971 Guide to the Preparation of reg4.2.rO2 1976 R AEC 1971

Environmental Reports for NuclearPower Plants

4494 AEC AEC Air 1974 Nuclear Power Plant Control Roorn nuregO737 1980 R AEC Air 1974

Cleaning Ventilation System Design for Cleaning

Conference Meeting General Design Criterion Conference19

4495 AEC AEC 1972 Soil Behavior Under Earthquake srp2.5.5 1981 R AEC Contract 1972

Contract W- Loading Conditions - State-of-the- W-7405-eng-26

7405-eng- Art Evaluation of Characteristics26 for Seismic Responses Analyses

4496 AEC AEC HASL N/S Procedure Manual reg4.3,rOO 1973 R AEC HASL 300 Not Found

3004497 AEC AEC Paper 1967 Your Body and Radiation drgop212-4.rOO 1984 R AEC Paper 1967

4498 AEC AEC 1980 Medical Aspects of Radiation inm87103 1994 R AEC Publication 1980

Publication Accidents

4499 AEC AEC R&D 1964 Two-Phase Pressure Drop in reg1.157.rOO 1989 R AEC R&D 1964

Report GEAP Straight Pipes and Channels: Report GEAP

4616 Water-Steam Mixtures at 600 to 4616

1400 psia4500 AEC AEC R&D 1970 Two-Phase Flow and Heat regl.157r00 1989 R AEC R&D 1970

Report GEA Transfer in Multirod Geometries: Report GEAP-

13049 Subchannel and Pressure Drop 13049Measurements in a Nine-RodBundle for Diabatic and AdiabaticConditions


. t Late _t VeNo. di0 S tandard Vate ab:it Comnment ; LAt Veion Date

4501 AEC AEC R&D 1964 Two-Phase Pressure Drop Across reg1.157.rOO 1989 R AEC R&D 1964Report GEAP Contractions and Expansions: Report GEAP-4622 Water-Steam Mixtures at 600 to 4622

1400 psia4502 AEC AEC Report 1972 Soi Behavior Under Earthquake reg 1.1 38.rOO 1978 R AEC Report 1972

Loading Conditions; State-of-the-Art Evaluation of SoilCharacteristics for SeismicResponse Analyses

4503 AEC AEC Report 1969 Guide for Economic Evatuation of regl .110.rOO 1996 R AEC Report 1969NUS-531 Nuclear Reactor Plant Designs NUS-531

4504 AEC AEC Report 1971 Amchitka Tsunami Study srp2.4.6 1981 R AEC Report 1971NVO-289-7 NVO-289-7

4505 AEC AEC Report 1971 Rat Island Tsunami Model: srp2.4.6 1981 R AEC Report 1971NVO-289-10 Generation and Open-Sea NVO-289-10

Characteristics

4506 AEC AEC Report 1968 Prediction of the Maximum reg3.51.rOO 1982 R AEC Report 1968UCRL- Dosage to Man from the Fallout of UCRL-5016350163 Nuclear Devices, Handbook for

Estimating the Maximum InternalDose from Radionuclides Releasedto the Biosphere

4507 AEC AEC Report, 1972 Basic Properties of Ice as Related srp6.5.4 1988 R AEC Report, 1972WASH-1232 to the Performance of Ice WASH-1 232

Condensers

4508 AEC AEC TID- 1963 Nuclear Reactors and Earthquakes srp3.7.3 1989 R TID-7024 196317024 _ _ _.. .__

4-3

z

(.A-- 3

LA

z

~0

00


Part B - Other Guidance

R o StBnd rd - - Doct d 9Accept -I LlateDth IonN o o e , S te d r V r i nT i l o u m e n t :~ : Da te a l l y C m e t L a t st : V e s o nD t

4509 AAEC EC TI- 1962 Calculation of Distance Factors for nuregO933, AEC TID-14844 1962

14844 Power and Test Reactor Sites 2.C.8

4510 AEC AEC TID- 1962 Calculation of Distance Factors for nureg0933, 1992 R AEC TID-14844 1962

14844 Power and Test Reactor Sites 3.155

4511 AEC AEC TID- 1962 Calculation of Distance Factors for stsb&w1.1 1991 A AEC TID-14844 1962

14844 Power and Test Reactor Sites

4512 AEC AEC TID- 1962 Calculation of Distance Factors for stscel.1 1991 A AEC TID-14844 1962


4513 AEC AEC TID- 1962 Calculation of Distance Factors for stsge-41.1 1991 A AEC TID-1 4844 1962


4514 AEC AEC TID- 1962 Calculation of Distance Factors for stsge-61 .1 1991 A AEC TID-14844 1962


4515 AEC AEC TID- 1962 Calculation of Distance Factors for stswstl .1 1991 A Provides AEC TID-14844 1962

14844 Power and Test Reactor Sites guidance forshieldingdesign _ _ _ _ _ _ _

4516 AEC AEC TID- 1969 Standard Nuclear Instrument reg5.9.02 1983 R AEC TID-20893 1969

20893 Modules

4517 AEC AEC TID- 1968 Meteorology and Atomic Energy regl.77.rOO 1974 R AEC TID-24190 1968

24190 _ _ _ __ __ _ _

4518 AEC AECTID- 1969 PlumeRise reg1.111.rO1 1977 R AEC-TID-25075 1969

2 5 0 7 5 _ _ _ _ _ __ _ _ _ _ _ _

4519 AEC AEC TID- 1974 Statistical Methods in Nuclear reg5.34.rOl 1984 R AEC TID-26298 1974

26298 __ _ _ _ _ Material Control_ _ _ _ _ _

4520 AEC AEC TID- 1974 Statistical Methods in Nuclear reg5.38.rOl 1983 R AEC TiD-26298 1974

. 26298 Material Control

4521 AEC AEC TiD- N/S Reactor Shielding for Nuclear srp6.4 1981 R TID-75951 Not found

7 5951 __ _ _ _ _ Engineers_ _ _ _ _ _ _

4522 AEC AEC WASH- 1975 Operational Accidents and reg8.29.rOO 1981 R WASH-1 192 1975

1192 Radiation Exposure Experience

4.5.

z

Ci

~0

.10

Cs


Record: San ar e. e L . VeNo.~, Code:: Stende'rd V ri nTteD cu ment Dae bliy Co mn ts L atest Version Date:

4523 AEC AEC WASH- 1974 Applications of Bioassay for reg8.22.rOl 1988 R AEC WASH- 19741251 Uranium 1251

4524 AEC AEC-OIS 1973 Reactor Shielding for Nuclear srpl2.3 1981 R AEC-OIS 1973Engineers

4525 AICHE AICHE 1965 The Corrosion Potential of Wetted reg1.36.rOO 1973 R AICHE 1965Conference Thermal Insulation Conference

4526 AICHE AICHE 1971 Design and Siting Criteria for Once reg1.113.rO1 1977 R AICHE Meeting 1971Meeting Through Cooling Systems

4527 AICHE AICHE 1965 Mathematical Analysis of reg1.1 13.r01 1977 R AICHE Meeting 1965Meeting Estuarine Pollution

4528 ANS ANS Letter 1985 Determination of Crack Leakage gIt89-1 0.sO3 1990 R ANS Letter 1985Rates in BWRs _

4529 ANS ANS 1979 Gamma Ray Measurements for regs537.rOl 1983 R ANS Meeting 1979Meeting Uranium Enrichment Standards

4530 ANS ANS 1980 The Detection of Fissionable reg5.1 1.rO1 1984 R ANS 1980Monograph Materials by Nondestructive Monograph.

Means4531 ANS ANS 1980 The Detection of Fissionable reg5.21.rOl 1983 R ANS 1980

Monograph Materials by Nondestructive MonographMeans

4532 ANS ANS 1980 The Detection of Fissionable reg5.38.rO1 1983 R ANS 1980Monograph Materials by Nondestructive Monograph

Means4533 ANS ANS 1980 The Detection of Fissionable reg5.53.rO1 1984 R ANS 1980

Monograph Materials by Nondestructive MonographMeans

4534 ANS ANS 1980 The Detection of Fissionable reg5.9.rO2 1983 R ANS 1980Monograph Materials by Nondestructive Monograph

Means4535 ANS ANS Paper 1975 On-Line Power Distribution inm61702 1980 R ANS Paper 1975

Monitoring With In-Core Detectors

z

C-4

0M


R eO rdOan a dDo , Ac e t Latest V r io

Nte o.dd C ode 0 0 tStandard- Verion Til Document Date tbfility; Comments0 Laes Versn Date

4536 ANS ANS Paper 1973 Reactor Siting in the Vicinity of srp3.5.1.6 1981 R ANS Paper 1973

A irfie ld s _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

4537 ANS ANS 1989 1989 National Heat Transfer glt88-20.sO3 1990 R ANS 1989

Proceedings Conference, August 6-9, 1989, Proceedings

Philadelphia, PA, Page 233-241

4538 ANS ANS Topical 1989 Potential Underestimation of Test nuregO933, 1990 R ANS Topical 1989

Meeting and Maintenance Unavailabilities 3.117 Meeting

in Probabilistic Risk Assessments

4539 ANS ANS 1984 Evaluation of Selected drgl 025rOO 1993 R ANS 1984

Transactions Approximations Used in Pressure Transactions

Vessel Fluence Calculations

4540 ANS ANS 1983 Reduction in Reactor Vessel drg 025r00 1993 R ANS 1983

Transactions Irradiation Through Fuel Transactions

Management

4541 ANS ANS 1983 Pressure Vessel Fluence Reduction drgiO25rOO 1993 R ANS 1983

Transactions Through Selective Fuel Assembly Transactions

Replacement

4542 ANS ANS 1983 Pressure Vessel Damage Fluence drg1025rOO 1993 R ANS 1983

Transactions Reduction by Low-Leakage Fuel Transactions

Management

4543 ANS ANS 1991 Reactor Cavity Dosimetry - A drgl 25rOO 1993 R ANS 1991

Transactions Regulatory Perspective Transactions

4544 ANS ANS 1984 Benchmarking of Pressure Vessel drgl 025rOO 1993 R ANS 1984

Transactions Fluence Calculations Transactions

4545 ANS ANS 1979 Shielding Benchmarks drgtO25rOO 1993 R ANS 1979

Transactions Transactions

4546 ANS ANS 1983 Trends in Chemical Analysis inm79501 1989 R ANS 1976

Transactions Procedures at Nuclear Power TransactionsPlants _ _


WM tQ '.,-- _ -i, .... ................ .. A :t ~ i0iX .0'::0Xff: ,.BRecor Stadr t. i...t . .... iStandard |oe Accep-: La ;tet Vrion: 0

No, odeVeridnoduet Date ~abilt COMMnts LatestfVersion Date4547 ANS ANS 1973 Transactions of the American regI.70.rO3 1978 R ANS 1973

Transactions Nuclear Society 1973 Winter TransactionsMeeting

4548 ANS ANS 1976 Engineering Evaluation of regl.89.rOl 1984 R ANS 1976Transactions Radiation Environment in LWR Transactions

Containments4549 ANS ANS 1974 Calculation of Accident Doses to regi .89,rOl 1984 R ANS 1974

Transactions Equipment Inside Containment of TransactionsPower Reactors

4550 ANS ANS 1976 A Simple Algorithm to Calculate regl.89.rOl 1984 R ANS 1976Transactions the Immersion Dose Transactions

1

4551 ANS ANS 1974 Empirical Model to Estimate reg3.33.rOO 1977 R ANS 1974Transactions Energy Releases from Accidental Transactions

Criticality

4552 ANS ANS 1974 Empirical Model to Estimate reg3.34.rO1 1979 R ANS 1974Transactions Energy Releases from Accidental Transactions

.____ ____ ____C riticality _ _ _____________::

4553 ANS ANS 1974 Empirical Model to Estimate reg3.35.rOl 1979 R ANS 1974Transactions Energy Releases from Accidental Transactions

_ . _ _ Criticality4554 ANS ANS-58.2 1985 Determination of Crack Leakage g1t89-1 O.sO3 1990 R n/a n/a

Working Rates in BWRsGroup _______ ___

4555 ASCE ASCE 1974 Inspection, Maintenance, and reg1.127.rOl 1978 R ASCE 1974Rehabilitation of Old Dams

4556 ASCE ASCE N/S Suggested Specification for srp3;8.4 1981 R ASCE Not foundStructures of Aluminum Alloys6061 -T6 and 6067-T6

4557 ASCE ASCE 12th 1970 Analysis of Hurricane Tides at srp2.4.5 1981 R Implied ASCE 12th 1970Engineering Padre Island, Texas endorsement EngineeringConference for specific Conference

model

4558 ASCE E 1988 Analysis of Gradual Earth-Dam nuregO933, 1989 R ASCE Journal 1988_ Joural _ Failure 2.B.31 .

z

(!h

Zci90

�Vt!h

�40W

;VI

W


R ecrd StandI rd D c. A ce pt- t Ve.sion

N ot : bCo d e S .: t ttandadrrd i it D m D t a t e t V r i te-

4559 ASCE ASCE 1972 Hydrothermal Analysis by Finite reg1.1 13.rOl 1977 P Implied ASCE Journal 1972

Journal Element Method endorsementfor specificm odel__ _ _ _ _ _

4560 ASCE ASCE 1971 Diffusion of Sewage Effluent from reg1.113.rOl 1977 P ASCE Journal 1971

Journal Ocean Outfall

4561 ASCE ASCE 1967 The Mechanics of Dispersion in reg 1.1 13.rOl 1977 P ASCE Journal 1967

Journal Natural Streams

4562 ASCE ASCE 1971 Sediment Discharge Formulas regl.1 13.rOl 1977 R ASCE Journal 1971

Journal4563 ASCE ASCE 1967 Waco Dam Slide reg1.127.rOl 1978 R ASCE Journal 1967

Journal4564 ASCE ASCE 1972 Analyses of Waco Dam Slide reg 1.127.rO 1 1978 8 ASCE Journal 1972

Journal4565 ASCE ASCE 1967 Electro Osmotic Stabilization of reg1.127.rOl 1978 R ASCE Journal 1967

Journal West Branch Dam

4566 ASCE ASCE 1967 Slide in the Siburus Dam regl.127.rOl 1978 R ASCE Journal 1967

Journal __.__. -

4567 ASCE ASCE 1967 Investigation of Embankment regy.1 27.rO1 1978 R Implied ASCE Journal 1967

Journal Performance endorsement

4568 ASCE ASCE 1976 Cyclic Triaxial Strength of reg 1.1 38.rOO 1978 P ASCE Journal 1976

Journal Standard Test Sand

4569 ASCE ASCE 1976 Pinhole Test for Identifying reg1.1 38.rOO 1978 R ASCE Journal 1976

Journal Dispersive Spills,4570 ASCE ASCE 1976 Identification and Nature of reg1.1 38.rOO 1978 R ASCE Journal 1976

Journal Dispersive Soils

4571 ASCE ASCE 1968 Cyclic Stress Strain regl.138.rOO 1978 R ASCEJournal 1968

Journal Characteristics of Clay .

4572 ASCE ASCE 1971 Deformation Characteristics of regl.138.rOO 1978 R ASCE Journal 1971

Journal Sand Under Cyclic Loading

4573 ASCE ASCE 1971 Sand Liquefaction in Triaxial and reg1.1 38.rOO 1978 R ASCE Journal 1971

Journal Simple Shear Tests

4574 ASCE ASCE 1975 Testing Procedure Effects on reg1.1 38.rOO 1978 R ASCE Journal 1975

Journal Dynamic Soil Behavior

-4N

z

V-

-4

Cs


Recd .. . Stand'dard D oc. Acept- Latest erson.No. C de 0 St d ad V 0 sion Tite D ocum ent: :D bl C m t L st VeSionDa

4575 ASCE ASCE 1977 Creep of Concrete A Consistent regl.35.1.rOO 1990 P Implied ASCE Journal 1977Journal Engineering Approach endorsement

as acceptablescientificmethod

4576 ASCE ASCE 1977 Stochastic Process for regl.35.1.rOO 1990 P ASCE Journal 1977Journal Extrapolating Concrete Creep

4577 ASCE ASCE 1975 Definition of Statistically regl.92.rOl 1976 R ASCE Journal 1975Journal Independent Time Histories

4578 ASCE ASCE 1974 Inspection, Maintenance, and reg3.11.1.r01 1980 R ASCE Journal 1974Journal Rehabilitation of Old Dams

4579 ASCE ASCE 1967 Seismic Failures of. Chilean reg3. 11.1 rO1 1980 R ASCE Journal 1967Journal Tailings Dams

4580 ASCE ASCE 1967 Seismic Failures of Chilean reg3.1 1.r02 1977 R ASCE Journal 1967Journal Tailings Dams

4581 ASCE ASCE 1967 Stability Analysis of Embankments reg3.11.r02 1977 R ASCE Journal 1967Journal

4582 ASCE ASCE 1967 Use of Computers for Slope reg3.1 1.r02 1977 R ASCE Journal 1967Journal Stability Analysis

4583 ASCE ASCE 1965 Earthquake Induced Displacement reg3.1 1.r02 1977 R ASCE Journal 1965Journal in Sand Embankments

4584 ASCE ASCE 1971 The Slides in the San Fernando reg3.1 1.r02 1977 R ASCE Journal 1971Journal Dam During the Earthquake of

February 9, 1971

4585 ASCE ASCE 1967 Slope Stability During Earthquakes reg3.11.r02 1977 R ASCE Journal 1967Journal

4586 ASCE ASCE 1971 Dynamic Analysis of the Slide in reg3.1 1.r02 1977 R ASCE Journal 1971Journal the Lower San

4587 ASCE ASCE 1882 Estimating Soil Water Retention reg3.64.rOl 1989 R ASCE Journal 1982Journal From Soil Properties

4588 ASCE ASCE 1972 Hydrothermal Analysis by the reg4.4.rOO 1975 R ASCE Journal 1972Journal Finite Element Method

z

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Record Latest Ve ;sio

ItNoI Code Stand rtd OVri - Titl D Dat b tC m t L V Dat

4589 ASCE ASCE 1968 New Distribution of Extreme srp2.3.1 1981 R Endorsed on a ASCE Journal 1968

Journal Winds case by casebasis

4590 ASCE ASCE 1967 Darcy's Flow Solutions with a srp2.4.13 1981 P ASCE Journal 1967

Journal Free Surface

4591 ASCE ASCE 1968 New Distribution of Extreme srp2.4.3 1989 R ASCE Journal 1968

Journal Winds in the United States

4592 ASCE ASCE N/S Journal of the Geotechnical srp2.6.4 1981 R Acceptable for ASCE Journal Not found

Journal Engineering Division threedimensionalearthquakeeffects

4593 ASCE ASCE 1973 Design Response Spectra for srp3.9.2 1981 A ASCE Journal 1973

Journal Nuclear Power Plants

4594 ASCE ASCE 1975 Definition of Statistically srp3.9.2 1981 R Acceptable ASCE Journal 1975

journal Independent Time Histories model

4595 ASCE ASCE Paper 1981 Consequences of Earthquakes in srp2.5.2 1989 R ASCE Paper 1981

the Mississippi Valley

4596 ASCE ASCE Paper 1974 i Motion Computsrp2.5.2 1989 R Implied ASCE Paper 1974

Characteristics Methods endorsementon a case bycase basis

4597 ASCE ASCE Paper 1971 Regional Water Supply Systems reg1.1 13.rOl 1977 P ASCE Paper 1971

Analysis for a Megalopolis

4598 ASCE ASCE Paper 1961 Wind Forces on Structures srp3.3.1 1981 P Implied ASCE Paper 1961

3269 endorsement 3269on a case bycase basis

4599 ASCE ASCE Paper 1961 Wind Forces on Structures srp3.3.2 1981 P ASCE Paper 1961

3269 3269

4600 ASCE ASCE Power 1971 Testing for Large Curved reg1.107.rOl 1977 R ASCE Power 1971

Division Prestressing Tendons Division


Record :Sta D Accpt- Latest Version. .... __.__._ ... ...No oe Standard VrinTteoc en te aliy C met Ltateson Date

4601 ASCE ASCE Soil 1972 Investigation for Design and regl.132.rOl 1979 R ASCE Soil 1972Mechanics Construction of Foundations of MechanicsFoundation Buildings FoundationDivision Division

4602 ASCE ASCE Soil 1967 ASCE Soil Mechanics and srp2.5.5 1981 i Acceptable ASCE Soil 1967Mechanics Foundation Division Conference model MechanicsFoundation on Stability and Performance of FoundationDivision Slopes and Embankments Division

4603 ASCE ASCE 1969 Delaware River Basin Modeling reg1.1 13.rOl 1977 P Implied ASCE Specialty 1969Specialty endorsement ConferenceConference

4604 ASCE ASCE 1975 Seismic eld Methodsfor nSitu regl.132.rO1 1979 P ASCE paper ASCE Specialty 1975Specialty Moduli ConferenceConference

4605 ASCE ASCE 1970 Technique for Study of Granular reg1.1 32.rOl 1979 R Implied ASCE Specialty 1970Specialty Materials endorsement ConferenceConference

4606 ASCE ASCE 1973 Generation of Seismic Floor reg1.143.rO1 1979 P ASCE Specialty 1973Specialty Response Spectra for Equipment ConferenceConference Design

4607 ASCE ASCE 1972 A Method for Analyzing Effects of srp2.4.4 1981 R ASCE Specialty 1972Specialty Dim Failures in Design Studies ConferenceConference

4608 ASCE ASCE 1973 Dynamic Analysis of Structural srp3.9.2 1981 R ASCE Specialty 1973Specialty Systems Excited at Multiple ConferenceConference Support Locations

(1

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1.4


R eco d 'Standr d D ec. A ccept- ... t..t.V..r....

No. Codea: Standar VersionP Tite Documet Date. ablity Comments Laest etshn Date

4609 ASCE ASCE 1973 Influence of Closely Spaced srp3.9.2 1981 R Implied ASCE Specialty 1973

Specialty Modes in Response Spectrum endorsement Conference

Conference Method of Analysis

4610 ASCE ASCE 1973 Design Response Spectra for regl.61,rOO 1973 P Implied ASCE Structural 173

Structural Nuclear Power Plants endorsement Engineering

Engineering Meeting

Meeting

4611 ASCE ASCE 1973 Design Response Spectra for regl .6O.rOl 1973 P ASCE Structural 1973

Structural Nuclear Power Plants Engineering

Engineering Meeting

Meeting ____ _

4612 ASME ASME 1969 Correlation of Critical Heat Flux in 10cfr50 App. K 1994 A ASME Paper 1969

a Bundle Cooled by Pressurized

Water ____..

4613 ASME ASME Paper 1969 Prediction of Blowdown and Jet srp3.6.2 1981 R . ASME Paper 1969

HT-31 Thrust Forces HT-31

4614 ASME ASME 1990 Validation of the Deformation regl.161.rOO 1995 R ASME 1990

Transactions Plasticity Failure Assessment Transactions

Diagram (DPFAD) Approach - TheCase of An Axial Flaw in aPressurized Cylinder

4615 ASME Journal of 1965 Maximum Flow Rate of a Single 1 Ocfr5O App. K 1994 A Journal of Heat 1965

Heat Component, Two-Phase Mixture Transfer

Transfer__ _ _ _ _ _ _

4616 ASME Nuclear 1991 A Review of the ASME Low Upper drg1023.rOO 1993 R Nuclear 1991

Engineering Shelf Toughness Evaluation Engineering and

and Design Procedures for Nuclear Reactor Design

Pressure Vessels

4617 ASME Transactions 1948 Prediction of Pressure Drop During 1 Ocfr50 App. K 1994 A certification Transactions of 1948

of ASME, Forced Circulation Boiling of required by ASME, 695 -

695 - 702 Water ASNT-IRRSP 702


. . . . E. . . . . . ... . t . i : W.. ............ ....... d..i.i-.x; E

t Record ~~~~~~~. |- -; i l-- -....... ...eor ,Xta--rdti OoaAc tl --Lat.t e lri on

No Cde Stndrd Vesin ite ocmet at ailty Comets Laest Version Date.:

4618 ASTM ASTM 1957 Stress Corrosion Cracking of reg1 .36.r00 1973 R ASTM Bulletin 1957Bulletin Insulated Austenitic Stainless

._._____ ____ Steel4619 ASTM ASTM Fifth 1980 Burst Criterion of Zircaloy Fuel srp4.2 1981 R Current version ASTM Fifth 1980

International Claddings in a LOCA and date not InternationalConference found Conference

4620 ASTM ASTM- 1985 Solid-State Track Recorder drg1025.r00 1993 R ASTM- 1985EURATOM Neutron Dosimetry in Light-Water EURATOMSymposium Reactor Pressure Vessel Symposium

Surveillance Mockups in Reactor___________ Dosimetry __

4621 ASTM ASTM- 1990 Contributions of the Venus- drg1025.rO0 1993 R ASTM- 1990EURATOM Engineering Mock-Up Experiments EURATOMSymposium to the LWR-PV Surveillance Symposium

4622 ATC ATC132A 1981 Radwaste Solidification not89-27 1989 R ATC 132A 1981

4623 ATC ATC N/S Tentative Provisions for the srp3.8.4 1981 R Also titled NBS ATC-3-06 1984Publication 3 Development of Seismic Special


4624 ATC ATC 1978 Tentative Provisions for the drgce406-4.rO0 1986 R Also titled NBS ATC-3-06 1984Publication 3 Development of Seismic Special06 Regulations for Buildings Publication

510 and NSFPublication 78-8

4625 ATC ATC-8019-1 1985 ATCOR AVRS-80 Volume not89-27 1989 R ATC_8009-1 1985

I Reduction Process 8_ _ _ _

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00


Rec rdStandard De . ,'A Cc00pt L ates6t Verslonn/aon/a

4626 AWWA AWWA N/S Standard Methods for the reg1.1 37.rOO 1978 Rna /

Examination of Water and

W astew ater __ _ _ __ _ _ _ _ _ __ _ _ _

467 AWWA AWWA 1971 Standard Methods for the regi .138.rOO 1978 R n/a n/a

Examination of Water andWastewater

4628 AWWA AWWA 1965 Corrosion Protec-tion Properties of regil.1 07.r01 1977 R Current version AWWA Journal 1965

Journal Portland Cement Concrete and date notfound

469 DOE DOE Bulletin N/S Filter Unit Inspection and Testing regl .52.r02 1978 R n/a n/a

Service__ _ _ _ _ _

4630- DOE DOE Order N/S Protection Program Operations l0cfr73 1994 R DOE Order 1992

5632.1 5632.18B

4631 DOE DOE Order N/S Physical Protection of Special 10cfr73 1994 R DOE Order 1989

5632.2 Nuclear Material and Vital 6632.2A

Equipment _ _ _ _ _ _

4632 DOE DOE ORO- N/S Uranium Hexaflouride: Handling not8O-27 1990 R ANSI N14.1 1990

651 Rev 5 Procedures and ContainerDescriptions

______

4633 DOE DOE-/DO/00 1 987 DOE Evaluation Document for drgOOO8.r00 1995 R DOE/DO/0053- 1987

53-Hi DOT 7A Type A Packaging H

4634 DOE DOE/DO/00 N/S DOE Evaluation Document for not90-35 1990 B DOE/DO/0053- 1987

53-H.1 (MLM DOT 7A-Type A Packaging Hi (MLM-3245)

3245)

4635 DOE DOE/EV/1 83 1980 A Guide to Reducing Radiation drgop61 8-4.rOO 1982 R DOE/EV/1 830- 1980

O.T5 Exposure to As Low As T5

Reasonably Achievable (ALARA)


.. .. . ... .. . .. . .. ....... . ..,8>---0__

lco S t a C ds onrd . e t eri

4636 DOE UMTRA- 1981 Radon Attenuation Effectiveness reg3.64.rOo 1989 R i UMTRA- 1981DOE/ALO and Cost Optimization for Uranium DOEIALO 165165 Mill Tailings and Composite

Covers

4637 DOE UMTRA- 1982 Engineering Guides for Estimating reg3.64.rOO 1989 R VMTRA- 1982DOE/ALO- Cover Material Thickness and DOE/ALO-193193 Volume _ .,

4638 DOT 10 CFR 71 NIS Packaging and Transportation of drgOOO8.rO0 1995 R 10 CFR 71 1995Radioactive Material

4639 DOT 10 CFR N/S Packaging and Transportation of glt8O-09 1980 R 10 CFR 71 199571.3 Radioactive Material

4640 DOT 10 CFR NIS Packaging and Transportation of reg7.7rOr 1977 RF 10 CFR 71 199571.5(b) Radioactive Material

4641 DOT 10 CFR N/S Physical Protection of Plants and 1Ocfr2O 1994 RF 10 CFR 73.421 199573.421 -424 Materials 424

4642 DOT 49 CFR 1973 Transportation cir81-007 1981 R 49 CFR 1973

4643 DOT 49 CFR 100- N/S Hazardous Materials Regulations inm86740 1992 l 49 CFR 100- 1994177 _ _ 177

4644 DOT 49 CFR 100- NIS Hazardous Materials Regulations inm86740 1992 R 49 CFR 100- 1994177 177

4645 DOT 49 CFR 1 00- 1983 Hazardous Materials Regulations not84-14 1984 Fl Implied 49 CFR 100- 1994177 endorsement 177

4646 DOT 49 CFR 100- N/S Hazardous Materials Regulations not90-56 1990 P 49 CFR 100- 1994180 ,IS,,O __________ 180

4647 DOT 49 CFR 100- N/S Research and Special Programs not92-62 1992 R 49 CFR 100- 1994199 _ Administration 199

4648 DOT 49 CFR 100- N/S Research and Special Programs not92-72 1992 R 49 CFR 100- 1994199 Administration 199

4649 DOT 49 CFR 170- N/S Hazardous Materials Regulations inm1232 1986 F Implied 49 CtR 170- 1994178 endorsement 178

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od ur66t i Me Clu ,.ty7:-- ~ ~CbMM C;tt.: . aiZed -i ..7 -EEESiS.-X~ .iiRecord id Standard Do V. A.....epti ite sition

4650 DOT 49 CFR 170- 1979 Hazardous Materials Regulations not81-02 1981 P Implied 49 CFR 170- 1994

178 endorsement 178

4651 DOT 49 CFR 170- NIS Hazardous Materials Reguations not82-47 1982 P Implied 49 CFR 170- 1994

178 endorsement 178

4652 DOT 49 CFR 170- N/S Hazardous Materials Regulations not84-14 1984 P Implied 49 CFR 170- 1994

178 endorsement 178

4653 DOT 49 CFR 170- N/S Hazardous Materials Regulations not9O- 3 5 1990 P Implied 49 CFR 170- 1994

178 endorsement 178

4654 DOT 49 CNR 170- N/S Hazardous Materials Regulations bu179-19 1979 P Implied 49 CFR 170- 1994

179 endorsement 179

4655 DOT 49 CFR 170 N/S Hazardous Materials Regulations bu179-20 1979 P Implied 49 CFR 170- 1994

179 . endorsement 179

4656 DOT 49 CFR 170- N/S Hazardous Materials Regulations bu179-20 1979 P Implied 49 CFR 170- 1994

179 endorsement 179

4657 DOT 49 CFR 170- NIS Hazardous Materials Regulations not79-21 1979 P Implied 49 CFR 170- 1994

179 endorsement 179

4658 DOT 49 CFR 170 N/S Hazardous Materials Regulations not89-74 1989 P Implied 49 CFR 170- 1994

179 endorsement 179

4659 DOT 49 CFR 170- N/S Hazardous Materials Regulations 1 Ocf r71 1994 A 49 CFR 170- 1994

189 189

4660 DOT 49 CFR 170 NIS Hazardous Materials Regulations cir78-03 1978 P 49 CFR 170- 1994

189 . 189

4661 DOT 49 CFR 170- NIS Hazardous Materials Regulations drgO008.rOO 1995 R 49 CFR 170- 1995

189 _ -_____.189

4662 DOT 49 CFR 170- NIS Hazardous Materials Regulations drgfc410-4.rOO 1985 A Implied 49 CFR 170- 1994

189 endorsement 189

4663 DOT 49 CFR 170- N/S Hazardous Materials Regulations Enforcement 1994 R NURiG/8R- 49 CFR 170- 1994

189 Manual, App. D 0195 189

4664 DOT 49 CFR 170. N/S Hazardous Materials Regulations not80-32 1980 P Implied 49 CFR 170- 1994

189 endorsement 189

4665 DOT 49 CFR 170- NIS Hazardous Materials Regulations not8b-67 1986 P implied 49 CFR 170- 1994

189 _ endorsement 189

4666 DOT 49 CFR 170 NIS Hazardous Materials Regulations not87-47 1987 P 49 CFR 170- 1994

189 _ 189

4667 DOT 49 CFR 170- N/S Hazardous Materials Regulations not93-086 1993 R 49 CFR 170- 1994

189 9_ _ _ _ _.

Codes and Standards and Other Guidance Cited in Regulatory DocumentsPart B Other Guidance

> > TE f ~~~~~~~~. .q. ... ., ...;:C. i --*

R cord Stri dard Doc- Accept- Latest VersionNo: Code Standard&&: V" ersIon Tite Docuent:; :Date .bilit on ate

4668 DOT 49 CFR 170- N/S Hazardous Materials Regulations reg10.06.rOl 1981 R 49 CFR 170- 1994

189 189

4669 DOT 49 CFR 171 NIS General information, Regulations, inm1 245 App. B 1991 R 49 CFR 171 1994

and Definitions

4670 DOT 49 CFR 171- N/S Hazardous Materials Regulations Enforcement 1979 R 49 CFR 171- 1994

173 Manual, App. G 173

4671 DOT 49 CFR 171- N/S Hazardous Materials Regulations inm86740 1992 R 49 CFR 171- 1994

178 __ _ _ _ _ _ _ _178

4672 DOT 49 CFR NIS Immediate Notice of Certain 49 FR 12335 1984 R 49 CFR 171.15 1994

171.15 Hazardous Material Incidents andDetailed Hazardous MaterialIncident Reports

4673 DOT 49 CFR N/S Immediate Notice of Certain inml330 1984 R 49 CFR 171.15 1994

171.15 Hazardous Material Incidents andDetailed Hazardous MaterialIncident Reports

4674 DOT 49 CFR NIS Immediate Notice of Certain inm9900/ 1980 R Implied 49 CFR 171.15 1994

171.15 and Hazardous Material Incidents and 10CFR20 endorsement and 171.16

171.16 Detailed Hazardous MaterialIncident Reports .

4675 DOT 49 CfR N/S Immediate Notice of Certain not90-56 1990 P 49 CFR 171.15 1994

171.15 and Hazardous Material Incidents and and 171.16

171.16 Detailed Hazardous MaterialIncident Reports

4676 DOT 49 CFR N/S Immediate Notice of Certain inm871 00 App. 1991 R 49 CFR 171.15 1994

171.15-16 Hazardous Material Incidents and C 16

Detailed Hazardous MaterialIncident Reports

4677 DOT 49 CFR N/S Immediate Notice of Certain inm87100 App. 1994 R 49 CFR 171.15 1994

171.15-16 Hazardous Material Incidents and D 16


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R e c rd t D e c; ' " - '. ; .A e pt ;--- L a ;te s t V e r sitn

t -No.- i

- C ode " St n ard Versio i D Dat i i ots Latest V ion D ate

4678 DOT 49 CFR N/S Immediate Notice of Certain inm87100 App. 1994 R 49 CFR 171.15 1994

171 .1 5-16 Hazardous Material Incidents and E 16

Detailed Hazardous Materint

Incident Reports_

4679 DOT 49 CFR NIS Immediate Notice of Certain inm87100 App. 1994 R 49 CFR 171.15 1994

171.15-16 Hazardous Material Incidents and F 16


4680 DOT 49 CFR N/S Detailed Hazardous Material Enforcement 1979 R 49 CFR 171.16 1994

171.16 Incident Reports Manual, App. G

4681 DOT 49 CFR 172 N/S Hazardous Materials Tables, inm99750 1994 R 49CR 7 1994

Hazardous MaterialsCommunications Requirements.and Emergency ResponseInformation Requirements

4682 DOT 49 CFR 1979 Purpose Hazardous M not82-47 1982 Implied 49 CFR 1994

172.101 1979___ Material Table _______ __980_ endorsement 172.101 1994___

172.101 172.101 and

and 173.21 (b)

1 7 3 . 21 (b ) _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

4684 DOT 49 CFR N/S Description of Hazardous Material 1 Ocfr73 1994 A 49 CFR 1994

4685 DOT 49 CFR N/S Hazardous Materials Tables, not91-35 1991 A Implied 492.2R 1994

172.400 Hazardous Materials endorsement 172.400

Communications Requirementsand Emergency ResponseInformation Requirements

4686 DOT 49 CFR Nti ing not90-35 1990 P Implied 49 CFR 1994

1720.436 M T endorsement 172.436-440

4 4 .. _ _ _ _ .__ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

____ _


Record itandard Dok Acet Latest VersionNo. Coe Standar VesonTtl ouen ated aIRVy omet LaestyVeslon bate

4687 DOT 49 CFR N/S Various Titles not87-47 1987 P Implied 49 CFR 1994172.500- endorsement 172.500-519,519, & & 172.556172.556 .

4688 DOT 49 CFR 1979 Vehicle Placards not82-47 1982 P 49 CFR 1994172.506 172.506 and

and 172.508172.508

4689 DOT 49 CFR N/S Emrergency Response Information inm86750 1994 R 49 CFR 1994172.600- 172.600-172.604 172.604

4690 DOT 49 CFR 173 N/S Shippers General Requirements for l Ocfr7 1994 A Implied 49 CFR 173 1994Shipments and Packaging endorsement

4691 DOT 49 CFR 173 N/S Shippers General Requirements for 55 FR 27522 1990 R 49 CFR 173 1994Shipments and Packaging

4692 DOT 49 CFR 173 N/S Shippers General Requirements for gIt80-09 1980 R 49 CFR 173 1994Shipments and Packaging

4693 DOT 49 CFR 173- N/S Various Titles inm2600 1990 R 49 CFR 173- 1994178 __ _ _ _ _ 178 _ _ _ _

4694 DOT 49 CFR N/S Shippers General Requirements for inm83723 1991 R Implied 49 CFR 1994173.1 (b) Shipments and Packaging endorsement 173.1 (b)

4695 DOT 49 CFR 1979 Requirements for Exclusive Use not80-32 1980 P Implied 49 CFR 1994173.389(o) Shipments endorsement 173.389(o)

4696 DOT 49 CFR N/S Shippers - General Requirements not80-32.rO1 1982 P Implied 49 CFR 1994173.393 (i) for Shipments and Packages endorsement 173.393 (i) &

& (ii __ _ _ _ _ W

4697 DOT 49 CFR 1979 DOT Specification 55 not81-02 1981 P Implied 49 CFR 1994173.394 (a) endorsement 173.394 (a) (2)(2) and and 178.250178.250 _ _ _ _

4:h.00

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Rcotd Stdrd .'Doci Accept- .. Latest ersion

N o . C o eS:d r e r i nT t eD c u e t I a Illity C o m e t o o t V r i n D.a t e :

4698 DOT 49 CFR 1979 DOT Specification 55 not82-47 1982 P 49 CFR 1994

173.394 (a) 173.394 (a) (2)

(2) and and 178.250

1 7 8 .2 5 0 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

4699 DOT 49 CFR 1979 Specification 7A, General not81-02 1981 P Packages not 49 CFR 1994

173.394(a) Packaging, Type A authorized 173.394(a) (1)

11) and after 6/30/85. and 178.350

178.350

4700 DOT 49 CFR N/S Shippers - General Requirements g9t8l-38 1981 P 49 CFR 1994

173.397 for Shipments and Packages 173.397

4701 DOT 49 CFR N/S Shippers - General Requirements reg8.30.rOO 1983 R 49 CFR 1994

173.397 for Shipments and Packages 173.397

4702 DOT 49 CFR N/S Shippers -General Requirements 10cfr20 1994 R 49 CFR 1994

173.403 (m) for Shipments and Packages 173.403 (m)

and Iw) and (w)

4703 DOT 49 CFR N/S Shippers General Requirements 1 Ocfr2O 1994 R Implied 49 CFR 1994

173.403 (m) for Shipments and Packages Subparts A-O endorsement 173.403 (Im)

and Iw) and (w)

4704 DOT 49 CFR N/S Authorized Type A Packages inm87100 App. 1994 R 49 CFR 1994

173.415(a) B 173.415a


173.415(a) C 173.415a

4706 DOT 49 CFR N/S Authorized Type A Packages inrn87 100 App. 1994 R 49 CFR 1994

173.415(a) D 173.415a


173.415(a) E 173.415a

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. C sReC ord S t a n d a r . D ec. A c c e p t-L atdst V e r io no .C eS t d a d V r o nT t eo c e nD t e a b i y C m ~ n s a e t V r i n D a t e

4708 DOT 49 CFR NIS Authorized Type A Packages inm87100 App. 1994 R 49 CFR 1994173.415(a) F 173.415a

4709 DOT 49 CFR N/S Authorized Type A Packages inm87100 App. 1994 R 49 CFR 1994173.415(a) G 173.415a

4710 DOT 49 CFR NIS Authorized Type A Packages not90-35 1990 P Implied 49 CFR 1994173.415(a) endorsement 173.415a

4711 DOT 49 CFR NIS Authorized Type A Packages regl o.08.ro2 1987 R 49 CFR 1994173.415(a) 173.415(a)

4712 DOT 49 CFR 1983 Authorized Type A and Type B not84-14 1984 R Implied 49 CFR 1994173.415(b) Packages endorsement 173.415(b) andand 173.416 (a)173.416 (a)

4713 DOT 49 CFR N/S Authorized Type B Packages inmm7100 App. 1991 R 49 CFR 1994173.416(a) C 173.416a

4714 DOT 49 CFR NIS Authorized Type B Packages inm87100 App. 1994 R 49 CFR 1994173.416(a) F 173.416a

4715 DOT 49 CFR NIS Authorized Packaging - Fissile not86-86 1986 P Implied 49 CFR 1994173.417 Materials endorsement 173.417

4716 DOT 49 CFR 1989 UF6 Cylinder Packing not90-27 1990 P 49 CFR 1994173.420 Requirements 173.420

4717 DOT 49 CFR NIS Shippers General Requirements not92-58 1992 R 49 CFR 173 1994173.420 for Shipments and Packages

4718 DOT 49 CFR NIS Shippers - General Requirements 1 Ocfr2O 1994 R Implied 49 CFR 1994173.421- for Shipments and Packages Subparts A-O endorsement 173.421-424424 _

4719 DOT 49 CFR N/S Radiation Level Limitations not88-101 1988 P Implied 49 CFR 1994173.441 (a) endorsement 173.441 (a)and(b) and(b_

3

9-4

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00


Re ord Stand d Do. 00. r ccep.t Latest rslon

. .. ..No .. K

0 i C o d e . t ; V-t

S t a n d r d V e r si o n t i t l . o cn t a t C t e

4720 DOT 49 CFR N/S Contamination Controls not85-46 1985 P Implied 49 CFR 1994

173.443 endorsement 173.443

4721 DOT 49 CFR 1983 Type A Packaging Tests and not84-14 1984 P Implied 49 CFR 1994

173.465 Specification 7A, General endorsement 173.465 and

and Packaging, Type A 178.350

118.350 _ . _ _ _

4722 DOT 49 CFR N/S Requirements for USNRC not88-33 1988 P Implied 49 CFR 1994

173.471 Approved Packages endorsement 173.471

4723 DOT 49 CFR NlS Requirements for Exporting DOT not87-47 1987 P Typo - was 49 CFR 1994

173.472 Specification Type B and Fissile 40CFR173- 173.472

Packages 178

4724 DOT 49 CFR 174 N/s Hazardous Materials Regulations Enforcement 1979 R Implied 49 CFR 174 1994

- 177 Manual, App. G endorsement 177

4725 DOT 49 CFR N/S Carriage by Public Highway not87-55 1987 P 49 CFR 1994

177.842(d) 177.842(d)

4726 DOT 49 CFR N/S Carriage by Public Highway reg7.3.rOO 1975 R 49CFR 1994

177.853 49 178194177.853

4727 DOT 49 CFR 178 N/S Shipping Container Specifications 49 FR 12335 1984 R 49CFR 178 1994

4728 DOT 49 CFR 178 N/S Shipping Container Specifications Enforcement 1979 R Implied 49 CFR 178 1994

Manual, App. G endorsement

4729 DOT 49 CFR NIS DOT Specifications 2OPF or 21 PF not90-27 1990 implied 49 CFR 1994

178.120 & Series endorsement 178.120 &

178.121 178.121

4730 DOT 49 CFR N/S DOT Specification 21 PF-1A, not9O-27 1990 P Implied 49 CFR 1994

178.121 Specifications for Protective endorsement 178.121

Overpacks

4731 DOT 49 CFR 1 983 Specification 20 WC - Wooden not84-14 1984 P Implied 49 CFR 1994

178.194 Protective Jackets endorsement 178.194

4732 DOT 49 CFR N/S Specification 20 WC - Wooden not87-47 1987 P Specification 49 CFR 1994

178.194 Protective Jackets disqualified by 178.19449CFR173.469

-P.

00

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e. d Dc. Ac c Latest VersionoSt n d ,d Version T tle Do um D ate ability CLatle AVersiona Date

4733 DOT 49 CFR 1983 Specification 2R not84-14 1984 R Implied 49 CFR 178.34 1994178.34 endorsement

4734 DOT 49 CFR N/S DOT Specification 7A, Type A not85-46 1985 P Implied 49 CFR 1994178.350 Packaging endorsement 178.350

4735 DOT 49 CFR N/S DOT Specification 7A, Type A not87-47 1987 P Implied 49 CFR 1994178.350 Packaging endorsement 178,350

4736 DOT 49 CFR N/S DOT Specification 7A, Type A not9O-27 1990 P Implied 49 CFR 1994178.350 Packaging endorsement 178.350

4737 DOT 49 CFR 1979 DOT Specification 7A, Type A not82-47 1982 P 49 CFR 1994178.350 & Packaging 178.350 &173.395 (al 173,395 (a) (1)

__________ _ ..(1 ) _

4738 DOT 49 CFR 390- N/S Federal Motor Carrier Safety Enforcement 1979 R 49 CFR 390- 1994397 Regulations Manual, App. G 397

4739 DOT 49 CFR 390- N/S Federal Motor Carrier Safety reg10.06.rO1 1981 R Implied 49 CFR 390- 1994397 Regulations endorsement 397

4740 DOT 49 CFR N/S Federal Motor Carrier Safety not87-31 1987 P 49 CFR 1994393.100, Regulations 393.100,393.102, 393.102,393.104 393.104

4741 DOT DOT 1983 A Review of the Department of drgOO08.rOO 1995 R DOT 1983Transportation Regulations forTransportation of RadioactiveMaterials

4742 DOT DOT 1989 Transportation Regulations: drgOOO8.rOO 1995 A DOT 1989Compatibility with Regulations ofthe International Atomic EnergyAgency: Notice of Proposed Rule

4743 DOT DOT 1990 1990 Emergency Response inm86740 1992 R 49 CFR 1994__________ Guidebook _ _ _ _

4744 DOT DOT 1983 A Review of the DOT Regulations not84-14 1984 R Packages not 49 CFR 1994for Transportation of Radioactive authorizedMaterial after 6/30/85.

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R ecBC rd otndard . D c Ac e t Latest Version

. C St nd d V s n Titlel D um e t D ate atV rto R D ate

4745 DOT DOT N/S DOT Specification 55 not87T47 1987 P Deals with 49 CFR 1994Medical Waste

4746 DOT DOT NIS DOT 17H Steel Drums not89-85 1989 f 49 CFR 1994

4747 DOT DOT Class 1989 Specifications for Multi-Unit Tank not9O-27 1990 R Medical Usage 49 CFR 1994

106A Cars

4748 DOT DOT E 7060 N/S DOT Exemption DOT E 7060 not89-74 1989 R Air Cylinder 49 CFR 1994Exemption ____Eemtin_._

4749 DOT DOT E 7235 N/S DOT Exemption DOT E 7235 not84-34 1984 R Air Cylinder 49 CFR 1994Exemption

4750 DOT DOT E 7235 N/S DOT Exemption DOT E 7235 not85-48 1985 R Air Cylinder 49 CFR 1994.Exemption _ _ _ _ _ _ _

4751 DOT DOT E 7235 N/S DOT Exemption DOT E 7235 not86-24 1986 R Air Cylinder 49 CFR 1994Exemption

4752 DOT DOT E 8059 N/S DOT Exemption DOT E 8059 not86-24 1986 R Medical Usage 49 CFR 1994

4753 DOT DOT E 8308 N/S DOT Exemption DOT E 8308 not89-74 1989 R Implied 49 CFR 1994endorsement

4754 DOT DOT 1973 Truck Top Markings for Visual reg5.t7.r00 1974 P 49 CFR 1994

P5200.8 Identification

4755 DOT DOT 1983 A Review of the DOT Regulations inm86740 1992 R DOT Pamphlet 1983

Pamphlet for Transportation of RadioactiveMaterials

4756 DOT DOT 1983 A Review of the DOT Regulations Inm86740 1992 R DOT Publication 1983

Publication for Transportation of RadioactiveMaterials

4757 DOT DOT 190mergency Respose inm86740 1992 R DOT Publication 1990

Publication Guidebook

4~100

\0

U'

(5


Recoadt S ;c pt ndad - -- A L VersionNo- C de Standard V - .... D tersion. Til l. c-men hate S bi Cemments Latest V ate

4758 DOT DOT N/S Radioactive Materials inm86740 1992 R DOT Publication 1981Publication Transportation Information and DOT/RSPAlMtDOT/RSPA/ Incident Guidance 81-4MTB-81 -4

4759 DOT DOT N/S Authorized Type A Packages 1 0cfr2, App. C 1994 A 49 CFR 173 1994Specification7A ___

4760 DOT DOT N/S Authorized Type A Packages Enforcement 1994 R NUREG/BR- 49 CFR 173 1994Specification Manual, App. D 01957A _

4761 DOT DOT N/S Authorized Type A Packages inm86740 1992 A Cited as a 49 CFR 173 1994Specification reference7A

4762 EPA 38 FR 1973 Memorandum of Understanding 1 Ocfr2O 1994 A 10 CFR 20 199524936 between the Environmental

Protection Agency and the AtomicEnergy Commission

4763 EPA 40 CFR 141 N/S National Primary Drinking Water inm2602 1995 R 40 CFR 141 1995Regulations

4764 EPA 40 CFR 190 N/S Environmental Radiation 10cfr2, App. C 1994 R 40 CFR 1994Protection Standards for NuclearPower Operations _ ____

4765 EPA 40 CFR 190 N/S Environmental Radiation git79-41 1979 R 40 CFR 1994Protection Standards for NuclearPower Operations ________

4766 EPA 40 CFR 190 1985 Einvironmental Radiation policy6/95 1995 R 40 CFR 190 1995Protection Standards for NuclearPower Operations

4767 EPA 40 CFR 190 1985 Environmental Radiation policy8/95 1995 R 40 CFR 190 1995Protection Standards for NuclearPower Operations

4768 EPA 40 CFR 190 N/S Environmental Radiation reg3.51.rOO 1982 R 40 CFR 1994Protection Standards for NuclearPower Operations _ _ _

Z

-.1

Cs



R eco rda n D c A cce pt te V ersio n

'No. Cod Standard- . Versioi Mcm n Dat y Comments Latest Ve sOn Date

4769 EPA 40 CFR 191 N/S Environmental Radiation drg3003.rOO 1990 R 40 CFR 1994

Protection Standards forManagement and Disposal ofSpent Nuclear Fuel, High-level andTransuranic Radioactive Wastes

4770 EPA 40 CFR 192 N/S Health and Environmental inm280010 26 1995 R 40 CFR Part 1994

Protection Standards for Uranium 192

and Thorium Mill Tailings

4771 EPA 40 CFR 192 N/S Health and Environmental reg3.64.rOO 1989 R 40 CFR 1994

Protection Standards for Uraniumand Thorium Mill Tailings

4772 EPA 40 CFR 192 N/S Health and Environmental SECY95-155 1995 R 40 CFR 192 1995

Protection Standards for Uraniumand Thorium Mill Tailings

4773 EPA 40 CFR N/S Health and Environmental 1 Ocfr4O 1994 P 40 CFR 1994

192, Protection Standards for Uranium

Subparts D and Thorium Mill Tailings

and E

4774 EPA 40 CFR 259 NIS Standards for the Tracking and not89-85 1989 P Current Part

Management of Medical Waste, 259

Interim Final Rule and Request forComments

4775 EPA 4 CFR 261 N/S Identification and Listing of 1Ocfr6l 1994 R Not in EPA On- 40 CFR 261 1994

Hazardous Waste line LibrarySystem

4776 EPA 40 CFR 261 N/S Identification an Listing of 55 FR 27522 1990 R 40 CFR 1994

Hazardous Waste

4777 EPA 40 CFR N/S Worker Protection not92-72 1992 R 40 CFR 311.1 1994

31 . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

4P.

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tJA


Record. St.nidardD Accept-, - Lts'.t Vers on

4778 EPA 40 CFR 61, N/S National Emission Standards for inm87102 1994 R 40 CFR 61, 1994Subpart I Hazardous Air Pollutants Subpart I

4779 EPA 40 CFR N/S National Emission Standards for inm4O750 1995 6 40 CFR 61.103 199461.103 Hazardous Air Pollutants

4780 EPA 40 CFR NIS National Emission Standards for inm80745 1995 R 40 CFR 61 .103 199461.103 Hazardous Air Pollutants

4781 EPA 40 CFR NiS National Emission Standards for not89-37 1989 R 40 CFR 61.15 199461.15 Hazardous Air Pollutants

4782 EPA 40 FR 1975 Second Memorandum of 1 Ocfr51 1994 R 40 FR 60115 197560115 Understanding Regarding

Implementation of Certain NRCand EPA Responsibilities andPolicy Statement onImplementation of Section 511 ofthe Federal Water PollutionControl Act (FWPCA)

4783 EPA EPA N/S Emergency Worker and Life 1 Ocfr60.47 1994 P Not in EPA On- n/a n/aSaving Activity Protective Action line LibraryGuides System

4784 EPA EPA N/S Emergency Workers and not84-40 1984 P n/a n/aLifesaving Activity ProtectiveAction Guides

4785| EPA EPA N/S Manual of Protective Action not86-18 1986 R EPA-520/1-75- 1990Guides and Protective Actions for 001ANuclear Incidents

4786 EPA EPA N/S Manual of Protective Action not92-38 1992 R published EPA-400/R- 1991Guides and Protective Actions for monthly 92/001Nuclear Incidents

4787 EPA EPA N/S Radiological Health Data and regl.113.rO1 1977 R n/a n/aReports

4788 EPA EPA 1978 Consideration of Environmental reg3.8.rO2 1982 R EPA P882- 1978Criteria for Radioactive Waste 185182

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Record tandar Dec. ccept-LatestVerslo

W~~~~~~ ~~~ ~ ~ ~ ~ i |to S fSl0| 16 *m| D6iet00 W nNoSoe San ad V riond~ T...o.m...t biiy Co m ns et eson D t

479 EPA EPA 1969 Mathmt a Ioes for regi1.1 13.rOl 1977 R EPA-WQO- 1969

Prediction of Thermal Energy 16130-EXT-

Changes in Impoundments _ __1111_1 197_ 12/69 1 97 1

47790 EPA EPA 1971 A Particle in Cell Method for regl.1 11.rol 1977 R EPA APTD- 17

Contracts Numerical Solution of the 0952

68-02-0006 Atmospheric Diffusion Equationand Applications to Air PollutionProblems

4791 EPA EPA ORP/LV 1976 Sampling and Data Reporting reg4.16.rOl 1985 R EPA ORP/LV-76 1976

76-9 Considerations for Airborne 9

Particulate Radioactivity

4792 EPA EPA 1972 Environmenta Raoactivity reg4.14.rOl 1980 R EPA ORP/SID- 1972

ORP/SID-72- Surveillance Guide 72-2

4793 EPA EPA N/S Environmental Radioactivity reg4.2.rO2 1976 R EPA ORP/SID- 1972

ORP/SID-72- Surveillance Guide 72-2

4794 EPA EPA Project 1971 Estuarine Modeling. An regl. 13.r01 1977 R EPA-WQO- 1971

No. Assessment 16070-DZV-

160700ZV, 02/71

Contract 14-12-551

4795 EPA EPA Report 1971 One-Dimensional Real Time Model reg1.1 13.rOl 1977 R n/ana

16070DGW for Estuarine Water QualityPrediction

4796 EPA EPA 400-R- 1992 Manual of Protective Action drg8012.rOO 1994 R Proposed EPA-400-R-92- 1992

92-001 Guides and Protective Actions for reg8.29.rOl 001

Nuclear Incidents

4797 EPA EPA-440/9- 1973 Auto-Qual Modeling System reg1 .113.rOl 1977 R EPA TR-54 1973

73-003

4798 EPA EPA-520/1 - N/S Manual of Protective Action not91-72 1991 R EPA-520/1 -75- 1990

75-001 Guides and Protective Actions for 001A

Nuclear Incidents __


. . t . .. .. ., ,. .. ....-..Record Standard& Doe Accept- Late Vers Ion

No. Code Standard VersIonTit:e Doc:ument Dae ability Comments Latest Vslon Date4799 EPA EPA-52011- N/S Manual of Protective Action not92-08 1992 P EPA-520/1-75- 1990

75-001 Guides and Protective Actions for 001ANuclear Incidents

4800 EPA EPA-52011- 1975 Manual of Protective Action reg3.42.rOl 1979 R EPA-520/1-75- 199075-001 Guides and Protective Actions for 001A

Nuclear Incidents4801 EPA EPA-520/1- 1990 Manual of Protective Action inm 1302 1994 R EPA-520/1-75- 1990

75-001-A Guides and Protective Actions for 001ANuclear Incidents

4802 EPA EPA-520/1- 1990 Manual of Protective Action inm82202 1993 R EPA-520/1-75- 199075-001-A Guides and Protective Actions for 001A

Nuclear Incidents4803 EPA EPA-520/1- 1990 Manual of Protective Action inm82206 1993 R EPA-520/1 -75- 1990


4804 EPA EPA-520/1 - 1990 Manual of Protective Action inm82206 1993 R EPA-520/1-75- 199075-001-A Guides and Protective Actions for 001A

Nuclear Incidents4805 EPA EPA-520/1 - 1990 Manual of Protective Action inm82207 1993 R EPA-520/1 -75- 1990

75-001 -A Guides and Protective Actions for 001ANuclear Incidents

4806 EPA EPA-520/1- 1990 Manual of Protective Action inm822202 1993 R EPA-520/1 -75- 199075-001 -A Guides and Protective Actions for 001 A

Nuclear Incidents4807 EPA EPA-520/1- 1990 Manual of Protective Action inm82301 1993 EPA-520/1 -75- 1990


4808 EPA EPA-520/1 - 1990 Manual of Protective Action inm82701 1994 R EPA-520/1-75- 199075-001-A Guides and Protective Actions for 001A

Nuclear Incidents4809 EPA EPA-520/1 - 1990 Manual of Protective Action reg3,67.rOO 1992 R EPA-520/1 -75- 1990


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- eord San d .l: t; atet Vertitn

N o C d S a d a d V e si nT i l D c m e t a e b li y C o m m n t s L a te s t V er nD t ei

4810 EPA EPA-520/1 - 1976 Potential Radiological Impact of reg3.51.r0 1982 D EPA-520/1 -76- 1976

76-001 Airborne Releases and Direct 001

Gamma Radiation to IndividualsLiving Near Inactive Uranium MillTailings Piles

4811 EPA E -520/1- 1978 Planning Basis for the lOcfr5O App. E 1994 R EPA-520/1 -78- 1978

78-016 Development of State and Local 016

Government RadiologicalEmergency Response Plans inSupport of Light-Water NuclearPower Plants

4812 EPA EPA-520/1- 1978 Planning Basis for the lOcfr5O.33 1994 R EPA-520/1-78- 1978



4813 EPA EPA-52011- 1978 Planning Basis for the 10cfrS0.54 1994 R EPA-520/1-78- 1978



4814 EPA EPA-520/1- 1978 Planning Bass for the 44 FR 61123 1979 R EPA-520/1-78- 1978


Government RadiologicalEmergency Response Plans inSupport of Light Water NuclearPower Plants


ReodStanfdard Do. Acp-Latest: Vers 6ntic.%% ::iI Code Standard VNer$1on - ltetOCUM nt Date, aly C met Latest Vrerson Dat0~i

4815 EPA EPA-520/1 - 1978 Planning Basis for the 45 FR 2893 1980 R EPA-520/1-78- 197878-016 Development of State and Local 016

Government RadiologicalEmergency Response Plans inSupport of Light Water NuclearPower Plants

4816 EPA EPA-520/1- 1980 Upgrading Environmental drg8004.rOO 1991 R EPA-520/1-80- 198080-012 Radiation Data: Health Physics 012

Society Committee Report HPSR-1

4817 EPA EPA-520/1- N/S Radionuclies: Background reg8.13.rO2 1987 R EPA-520/1- 198484-022-1 Information Document for Final 84/022-1

Rules. Volume 1 .

4818 EPA EPA-520/1- 1988 Limiting Values of Radionuclide drg801O.rOO 1992 R EPA-520/1-88- 198888-020 Intake and Air Concentration and 020

Dose Conversion Factors forInhalation, Submersion, andIngestion

4819 EPA EPA-520/1 - 1988 Limiting Values of Radionuclide drg801 1.rOO 1992 R EPA-520/1 -88- 198888-020 Intake and Air Concentration and 020


4820 EPA EPA-520/1- 1988 Limiting Values of Radionuclide inm87103 1994 R EPA-520/1-88- 198888-020 Intake and Air Concentration and 020


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48 1E PA E A -52 /1 19 88 Lim iting V alues of R d io u l d e 8 3 . O 9 2 R EP - 20 -8 -1 8

88-020 Intake and Air Concentration and 020

Dose Conversion Factors forInhalation, Submersion, andIngestion.

4822 EPA EPA-520/1- 1988 Limiting Values of Radionuclide reg8.34.rOO 1992 Typo in EPA-520/1-88- 1988

88-020 Intake and Air Concentration and inm82207 in 020

Dose Conversion Factors for Standard

Inhalation, Submersion, andIngestion

4823 EPA EPA-5201- 1989 Bakgroun IfoRation li inm87 1 02 1 994 R EPA-520/1 -89- 1989

89-001 Document; Procedures Approved . 001

for Demonstrating Compliancewith 40 CFR Part 61, Subpart I

4824 EPA EPA-520/1- 1989 EPA Guidance Document for inm87102 1994 8 EPA-520/1 -89- 1989

89-002 Facilities Subject to 40 CFR Part 002

61, Subpart I: Procedures forDetermining Compliance with theStandard and Qualification forExemption from Reporting

4825 EPA EPA-520/1- 1989 User's Guide for COMPLY inm87102 1994 R EPA-520/1-89- 1989

89-003 003

4826 EPA EPA-620/3- 1974 Storage of Low-Level Radioactive drgesl 15-4.rOO 1983 R EPA-52013-74- 1974

74-009 Wastes in the Ground: 009

Hydrogeologic and HydrochemicalFactors

4827 EPA EPA-520/4- 1974 Environmental Radiation Dose reg3.51.r0l 1982 R EPA-520-4-73- 1974

73-002 Commitment: An Application to 002

the Nuclear Power Industry


_ .. ....... . i ' f : : 0 t ' V i i ~ i ' S ' t i "t'-'X-~o ws 'i iiN 0 1a..................-t .t,.o -- nRecord Standard - t. Accet te VersNo oe standard Verelo Title Douetamt blt C an nont Laest VeWson Dt

4828 EPA EPA-520/4- 1975 Occupational Exposures to reg8.29.rOO 1981 R EPA-520/4-80- 198080-001 ionizing Radiation in the United 001

States: A ComprehensiveSummary for 1975

4829 EPA EPA-520/4- 1980 Occupational Exposure to ionizing reg8.29.rOO 1981 R EPA-520/4-80- 198080-001 Radiation in the United States: A 001

Comprehensive Summary for1975

4830 EPA EPA-520/5- 1984 Eastern Environmental Radiation inm84725 1991 R EPA-520/5-84- 198484-006 Facility Radiochemistry Procedures 006

Manual

4831 EPA EPA-520/5- 1984 Eastern Environmental Radiation inm84850 1988 R EPA-520/5-84- 19844> 84-006 Facility Radiochemistry Procedures 006

Manual

4832 EPA EPA-520/6- 1974 Evacuation Risks - An Evaluation glt80-60 1980 R EPA-52016-74- 197474-002 002

4833 EPA EPA-52018- N/S Evacuation Risks - An Evaluation gIt79-067 1979 R EPA-520/8-74- 197474-002 002

4834 EPA EPA-520/9- 1973 Environmental Analysis of the reg3.51.rOO 1982 R EPA-520/9-73- 197373-003-B Uranium Fuel Cycle, Part I -- Fuel 003-B

Supplyz 4835 EPA EPA-520/9- 1973 Environmental Analysis of the reg3.51.r0l 1982 R EPA-520/9-73- 1973

73-003-B Uranium Fuel Cycle, Part I -- Fuel 0038_ Supply I

) 4836 EPA EPA-520/9- 1973 Environmental Analysis of the reg3.51.rOO 1982 R EPA-520/9-73- 197373-003-C Uranium Fuel Cycle, Part l! - 003-C

Nuclear Power Reactors4837 EPA EPA-S20/9- 1973 Environmental Analysis of the reg3.51.rO1 1982 R EPA-520/9-73- 1973

73-003-C Uranium Fuel Cycle, Part II - 003-CNuclear Power Reactors

z

00


Iror S a d a rd! D do k A c pt a e t e s o

r oC d eS ta n d d V e soA ll o u e n a e o l l y C m m n ~ L t s e s o D a t e :

4838 EPA EPA- 1977 Procedures Manual for Ground- drgesl 14-4rOO 1 983 R EPA-530/SW- 1977

530/SW- Water Monitoring at Solid Waste 611

611 Disposal Facilities

4839 EPA EPA-550/9- 1974 Information on Levels of reg4.2.rO2 1976 R EPA-550/9-74- 1974

74-004 Environmental Noise Requisite to 004

Protect Public Health and Welfarewith an Adequate Margin ofSafety

_ _ _ _ _ _ _

4840 EPA EPA-57019- 1976 Manual of Water Well drgesl 14-4,rO0 1983 R EPA-570/9-75- 1976

75-001 Construction Practices 001

4841 EPA EPA-60012- 1981 Mnal of Gro ateruality drgesl14-4.rOO 1983 R EPA-600/2-81 - 1981

81-160 Sampling Procedures 160

4842 EPA EPA-600/3- 1977 Impact of Abandoned Wells on drgesl 14-4.rOO 1983 R EPA-600/3-77- 1977

77-095 Ground Water 095

4843 EPA EPA-600/4- 1975 Interim Radiochemical drgesl 14-4.rOO 1983 R EPA-600-4-75- 1975

75-008 Methodology for Drinking Water 008

4844 EPA EPA-60014- 1976 Atmospheric Dispersion srp2.3.4 1981 R EPA-600/4-76- 1976

76-030-A Parameters in Gaussian Plume 030a

Modeling

4845 EPA EPA-600/4- 1976 Handbook for Sampling and reg4.15.rOl 1979 R EPA-600/4-82- 1982

76-049 Sample Preservation of Water and 029

Wastewater

4846 EPA EPA-60014- 1977 Environmental Radioactivity reg4.1 5.rOl 1979 8 EPA-600/4-81 - 1981

77-001 Laboratory Intercomparison 004

Studies Program

4847 EPA EPA-600/4- 1977 Reference Method for the reg4.15.rOl 1979 R EPA-600/4-77- 1977

77-027-A Determination of Suspended 027A

Particulates in the Atmosphere(High Volume Method)

'IO

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'0


Rec Sta drd Doci A a itest VersionoC od e St n ar d V rs io Ti l a ' u en a t a b l t C m nt L a e t V ersio n :D t

4848 EPA EPA-600/4- 1977 Sampling of Water and reg4.15.rOl 1979 R EPA-600/4-77- 197777-039 Wastewater 039

4849 EPA EPA-600M4- 1979 Handbook for Anaiytical Quality drgesl 14-4.rOO 1983 R EPA-600/4-79- 197979-019 Control in Water and Waste Water 019

Laboratories ........ _ __ . _. _ ___

4850 EPA EPA-600/4- 1979 Handbook for Analytical Quality inm79501 1989 R EPA-600/4-79- 197979-019 Control in Water and Waste Water 019

Laboratories_ _

4851 EPA EPA-600/4- 1979 Methods for Chemical Analysis of drgesl 14-4.rOO 1983 R EPA-600/4-79- 197979-020 Water and Wastes 020

4852 EPA EPA-600/4- 1983 Methods for Chemical Analysis of inm79501 1989 R EPA-600/4-79- 197979-020 Water and Wastes 020

4853 EPA EPA-600/4- 1983 Quality Assurance Handbook for inm80521 1984 R EPA-600/4-82- 198282-062 Air Pollution Measurement 062

Systems: Volume IV,_______ Meteorological Measurements _


Systems: Volume IV,Meteorological Measurements


Systems: Volume IV,Meteorological Measurements

4856 EPA EPA-600/7- 1977 Handbook for Analytical Quality reg4.1 5.rO1 1979 R EPA-600/7-77- 197777-088 Control in Radioanalytical 088

Laboratories4857 EPA EPA-600/D- 1980 National Secondary Drinking drgesl 14-4.rOO 1983 R EPA-600/D-80- 1980

80-003 Water Regulations 003

4858 EPA EPA-625/6- 1974 Methods for Chemical Analysis of reg4.15.rOl 1979 R EPA-625/4- 197974-003 Water and Wastes 7 9/020

C.

'-'


| Reco rd Sta nCd a dit h o A c e t L at4!0est Ve rsi >:Cggo n li

4859 EPA EPA-62516- 1978 Industrial Guide for Air Pollution reg3,56.r00 1986 R EPA-625/ 6-78- 1978

78-004 Control 004

4860 EPA EPA-d6017- 1977 Quality Control for Environmental reg4.15.r01 1979 R-EPA-600/7-77- 1977

7 7-14 Measurements Gamma-Ray 144

_Spectroietry

4861 EPA EPA-670/4- 1973 BIologial Fidel nd Labroraltry reg415.rOl 1979 R EPA-670/4-73 1973

73-001 Methods for Measuring the 001

.Quality of Surface Waters and

4862 EPA EPA-66-01- 190 Dto mnt of Euresman rges14-4.rOO 1983 R Not listed in EPA-66-01- 1980

5971 Costs for Proper Abandonment EPA On-line 5971

and Plugging of Injection Wells Library System

4863 EPA EPA-680/4- 1975 Hiadook oF Rad iEmicat reg4.14.rOl 1980 R EPA-670/4-75 1975

75-001 Analytical Methods 001

4864 EPA EPA-660/4 1975 Handbook of Radiochemical reg4A15rOl 1979 R -EPA-66014-75- 1975

75-001 Analytical Methods 001

4865 EPA EPA-69-03- 1982 MINTEQ: A Computer Program for drgesl 15-4,rOO 1983 R - EPA-60013-64- 1984

3089 Calculating Aqueous Geochemical 032

Equilibria

4866 EPA EPA-905/2- 1979 Management and Technical reg34.1.r0O 1986 R EPA-9051/2-79- 1979

79-e 002 Procedures for Operation and 002

Maintenance of Air PollutionControl Equipment

4867 EPA EPA-AP-101 1972 Mixing Heights, Wind Speeds, and srp2o.l 1981 R EPA AP-804 1972

Potential for Urban Air Pollution3Throughout the Contiguous UnitedStates

4866 EPA EPA-APTD- 1972 accident EidecMnual reg1386.rOO 1974 R EPA9APT2- 1972

1114 .1114

.- 00 Prcdue fo Oprton 0


RecrdStndard.. Dec 'Accept-: Latest versionoo. Code Standard eitDocumetr Date ability Comenntse.: Latest VeMSon

4869 EPA EPA-NC N/S Valley Model Computer Program reg1 .111,r01 1977 R EPA DF-78/002 1978_ 27711 (Model-Simulation)

4870 EPA EPA-ORP/LV 1976 Sampling and Data Reporting reg4.15.rOl 1979 R EPA ORP/LV-76 197676-9 Considerations for Airborne 9

Particulate Radioactivity4871 EPA EPA-ORP/LV 1976 Sampling and Data Reporting reg4.16.rO1 1985 R EPA ORP/LV-76 1976

76-9 Considerations for Airborne 9Particulate Radioactivity

4872 EPA EPA- 1972 Analytical Quality Control reg4.1 5r01 1979 R Not listed in EPA ORPISID 1972ORPISID 72- Methods EPA On-line 72-22 Library System

4873 EPA EPA- 1972 Analytical Quality Control reg4.15.r01 1979 R EPA ORP/SID- 1972ORP/SID 72- Methods 72-22

4874 EPA EPA- 1972 Analytical Quality Control reg4.14.rO1 1980 R EPA ORP/SID- 1972ORP/SID-72- Methods 72-22

4875 EPA EPA-PAGs N/A EPA Protective Action Guidelines inm82206 1993 R Not listed in n/a n/a(PAGs) EPA On-line

Library System

4876 EPA EPA-PB-275- 1977 Compilation of Air Pollutant reg3.59.rO0 1987 R n/a n/a525 Emission Factors

4877 EPA EPA-R2-72- 1974 Workbook on Thermal Plume reg1.1 13.rO1 1977 R EPA PB 235841 1974005b Prediction Vol. 2-Surface

Discharge4878 EPA EPA-RD No. 1971 Radiological Surveillance Studies reg1.1 13.rOl 1977 R EPA-RD-71-1 1971

71-1 at a Pressurized Water NuclearPower Reactor

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.~. .... _ _.....7

R ec d ' 'oSt a n d ar D ec. Acc e p t:.: L t e t V ersio;

0 N o. i ~ i;;4 0 Ci0:i ~ t~ode ; 0 000XiS S tandard Version Title D c e t D ate i ity C atest i D

4879 EPA EPA/NRC N/S Joint EPA/NRC Guidance on the not90-31 1990 R EPA OSWER 1988

Definition and Identification of #943200-2

Commercial Mixed Low-LevelRadioactive and Hazardous Wasteand Answers to AnticipatedQuestions

4880 EPA NEPA 1969 National Environmental Policy Act reg4.7.r01 1975 R NEPA 1969

of 1969

4881 EPA NPDES NIS National Pollutant Discharge g1t89-13 1989 R Computer Clean Water 1977

Elimination System Code Act

4882 ERDA ERDA 76-21 1976 Nuclear Air Cleaning Handbook regl.140.rOl 1979 P ERDA 76-21 1976

4883 ERDA ERDA 76-21 1976 Nuclear Air Cleaning Handbook regl.52.rO2 1978 P ERDA 76-21 1976

4884 ERDA ERDA 76-21 1976 Nuclear Air Cleaning Handbook srp6.5.1 1981 P ERDA 76-21 1976

4885 ERDA ERDA 77-24 1977 A Guide for Environmental reg4.14.r01 1980 R ERDA 77-24 1977

Radiological Surveillance at ERDA

Installations

4886 ERDA ERDA 77-24 1977 A Guide for Environmental reg4.15.rOl 1979 R_ ERDA 77-24 1977

Radiological Surveillance at ERDAInstallations _ _ _ _ _ _ _ _

4887 ERDA ERDA CONF 1975 The Dosimetry of the Radioactive regl.109.rOl 1977 R ERDA CONF. 1975

730 015 Noble Gases 730 015

4888 ERDA ERDA 1975 certification of ERDA Contractors inm86740 1992 R ERDA Report 1975

Report MLM- Packaging with Respect to DOT MLM-2228

2228 Specification 7A PerformanceRequirements

4889 ERDA ERDA 1974 Wind as Related to Critical reg8.30.rOl 1983 R ERDA 1974

Symposium Flushing Speed Versus Reflotation Symposium

Series 38 Speed by High-Volume Sampler Series 38

Particulate Loading


Record S tandard D .. Ace:t- .atet.rAio :.

No, Code, S tndard Vso 19 e tcment DatI Al Commenwt LE atest. .Veriont4890 ERDA ERDA X- 1976 Bulk Sample Self-Attenuation reg5.1 1.rOI 1984 R ERDA X- and 1976

and Gamma- Correction by Transmission Gamma-RayRay Measurement SymposiumSymposium

4891 ERDA ERDA X- 1976 Bulk Sample Self-Attenuation reg5.23r01 1984 R ERDA X- and 1976and Gamma- Correction by Transmission Gamma-RayRay Measurement SymposiumSymposium

4892 ERDA ERDA X- 1976 Bulk Sample Self-Attenuation reg5.37.rO1 1983 R ERDA X- and 1976and Gamma- Correction by Transmission Gamma-RayRay Measurement SymposiumSymposium

4893 ERDA ERDA X- 1976 Bulk Sample Self-Attenuation reg5.38.rOl 1983 R ERDA X- and 1976and Gamma- Correction by Transmission Gamma-RayRay Measurement SymposiumSymposium

4894 ERDA HASL-300 1972 Environmental Measurements reg4.15.rOl 1979 R HASL-300 1990Laboratory Procedures Manual

4895 ERDA HASL-312 1976 Guidance for Air Sampling at reg4.15.r01 1979 R Cancelled HASL-312 1976Nuclear Facilities 1985

4896 Fed Spec Federal N/S Fuel Oil, Diesel not94-19 1994 R Federal 1987Specification SpecificationVV-F-800 VV-F-800D

0

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0


e cord San da d Do e, ACCe t Latest Verslon

f XNo. " ''l...-.Cor e .S V ion.. ... D c e D e b Commer .ft ......s Latest Version D

4897 Fed Spec Federal NIS Components for Interior Security 10cfr73 1994 A Federal 1990

Specification Alarm Systems Specification W

W-A-00450 A-450C

4898 Fed Spec Federal N/S Components for Interior Security 1 Ocfr73 1994 A Federal 1990


W-A- A-450C

00450B , . _ _

4899 Fed Spec Federal N/S Components for Interior Security inm1245 App. B 1991 R Federal 1990


W-A-450B A-450C

4900 Fed Spec Federal NIS Components for Interior Alarm inm1245 App. B 1991 R Federal 1990

Specification Systems, Balanced Magnetic Specification W

W-A-450C/1 Switches A-450/1

4901 FFPR FF-P- N/S Padlock, Key Operated not82-46 1982 A Cancelled n/a n/a

001480 1985 .

4902 FFPR FF-P- N/S Padlock, Key Operated reg5.1 2.rOO 1973 A n/a n/a

001480 _ _

4903 FFPR FF-P-1 10 NIS Padlock, changeable combination not82-46 1982 A FF-P-1 1 OD 1966

4904 FFPR FF-P- 1 1 OF N/S Padlock, changeable combination reg5.1 2.rOO 1973 A Cancelled FF-P- 1 1 OG 19871987 _ _ _ _ _

4905 FFPR W-A-00450 N/S Components for Interior Alarm regl.17,rOl 1973 A W-A-004508 1973

A _Systems __

4906 FFPR W-A-00450 1973 Components for Interior Alarm regl .70.rO3 1978 A W-A-00450B 1973

B Systems

4907 FM FM N/S Factory Mutual System Approval inm88055 1991 R FM Approval 1993

Guide Guide

4908 FM FM N/S Factory Mutual System Approval regl .1 20.rOl 1977 P FM Approval 1993

Guide Guide

4909 FM FM NIS Factory Mutual System Approval srp9.5.1 1977 P FM Approval 1993

Guide _ _ Guide

4910 FWPCA FWPCA NIS Federal Water Pollution Control lOcfr5l 1994 R n/a n/a

Lf 0LAct ___________


.. . . .. .. ... . . . ..._._Record S1tandr 06m:: Accept Lates Verio

No. Cods Stnad VrlnTtl ouhrt Dt biiy Cm t ~ t Veslon, Dt4911 GS of A Geological 1984 Chronology and Rates of Faulting drg 1015.rOO 1992 R Geological 1984

Society of Ventura River Terraces, Society BulletinBulletin California

4912 GS of A Geological 1984 Holocene Activity of the San drg 101 5.rOO 1992 R Geological 1984Society Andreas Fault at Wallace Creek, Society BulletinBulletin California

4913 GS of A Geological 1985 Holocene Rate of Slip and drglO15.rOO 1992 R Geological 1985Society Tentative Recurrence Interval for Society BulletinBulletin Large Earthquakes on the San

Andreas Fault, Cajon Pass,Southern California

4914 GS of A Geological 1977 Profiles and Ages of Young Fault drg1015.rOO 1992 R Geological 1977Society Scarps, North-Central Nevada Society BulletinBulletin _

4915 GS of A Geological 1970 Dating Episodes of Faulting from drgl015.rOO 1992 8 Geological 1970Society Tree Rings: Effects of the 1958 Society BulletinBulletin Rupture of the Fairweather Fault

on the Tree Growth

4916 GS of A Geological 1982 Soil Profile Development in Xeric drg1015.rOO 1992 R Geological 1982Society Climates: A Summary Society BulletinBulletin .

4917 GS of A Geological 1982 Holocene Faulting History as drg1015.rOO 1992 _ Geological 1982Society Recorded by Alluvial Stratigraphy Society BulletinBulletin Within the Cucamonga Fault

Zone; A Preliminary View

4918 GS of A Geological 1982 Tectonic Geomorphology of the drgl015.rO0 1992 R Geological 1982Society San Andreas Fault Zone in the Society BulletinBulletin Southern Indio Hills, Coachella

Valley, California

4919 GS of A Geological 1984 Chronology and Rates of Faulting drg1032.rOO 1995 R Geological 1984Society of Ventura River Terraces, Society BulletinBulletin California _ _ _ _

zC:

-4nno

I

z

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I0'



c i tandard Doe. A c e t-| L t Verio

4920 GS of A Geological 1984 Holocene Activity of the San drg1032.rOO 1995 R Geological 1984

Society Andreas Fault at Wallace Creek, Society Bulletin

Bulletin California

4921 GS of A Geological 1985 Holocene Rate ofSlip and drg1032.rOO 1995 R Geological 1985

Society Tentative Recurrence Interval for Society Bulletin

Bulletin Large Earthquakes on the SanAndreas Fault, Cajon Pass,Southern California

4922 GS of A Geological 1977 Profiles and Ages of Young Fault drg1032.rOO 1995 R Geological 1977

Society Scarps, North-Central Nevada Society Bulletin

Bulletin4923 GS of A Geological 1970 Dating Episodes of Faulting from drg1032.r00 1995 R Geological 1970

Society Tree Rings: Effects of the 1958 Society Bulletin

Bulletin Rupture of the Fairweather Faulton the Tree Growth

4924 GS of A Geological 1982 Soil Profile Development in Xeric drgl032.rOO 1995 R Geological 1982

Society Climates: A Summary Society Bulletin

Bulletin G eological__

_ __ __ _ __ __ _ __ _ __ _1982__ _ __ _

4925 GS of A Geological 1982 Holocene Faulting History as dr91032.rOO 1995 R Geologicat 1982

Society Recorded by Alluvial Stratigraphy Society Bulletin

Bulletin Within the Cucamonga FaultZone; A Preliminary View

4926 GS of A Geological 1951 Classification and a Scheme for reg1.138.rOO 1978 R Golieoygcal 1951

Society the Identification of Layer Silicates Society Bulletin

Bulletin __Gelogcal199

4927 GS of A Geological 1993 Holocene Climatic and Limnologic drg1032.rOO 1995 R Goloiocal 1993

Society History of the North-Central Society Special

Special United States as Recorded in the Paper 276

Paper 276 Varved Sediments of Elk Lake,Minnesota: A Synthesis


Record. tA Latest Versi oN. code" Stnad eso <il ouet Dt abi~y Cmet aetVrin Dte!300No 0 ... .. da Il t~ a ' 00. -. .0

4928 HHS FDA 81- 1981 Background Material for the not88-015 1988 R FDA 81-8158 19818158 Development of the Food and

Drug Administration'sRecommendations on Thyroid-Blocking with Potassium Iodide

4929 HHS HHS N/S Mandatory Guidelines for Federal 1Ocfr26 1994 A HHS Guidelines 1993Workplace Drug Testing Programs(63 FR 970).

4930 HHS HHS N/S Mandatory Guidelines for Federal adm94-09 1994 R HHS Guidelines 1993Guidelines Workplace Drug Testing Programs

4931 HHS HHS 1990 Alcohol, Tobacco, and Other drg8.14.rOO 1994 R HHS Publication 1990Publication Drugs May Harm the Unborn No. IADM)92-(ADM)92- 17111711

4932 HHS HHS 1981 Radiation Safety in Nuclear reg10.8.r02 1987 R HHS Publication 1981Publication Medicine: A Practical Guide FDA 82-8180FDA 82-8180

4933 HHS HHS 1984 Recommendations for Quality reg10.8.r02 1987 R HHS Publication 1984Publication Assurance Programs in Nuclear FDA 85- 8227FDA 85- Medicine Facilities8227

4934 HPS HPS Topical 1970 Health Physics Aspects of Nuclear reg1.1 13.rOl 1977 R HPS Topical 1970Symposium Facility Siting Symposium

4935 HPS HPS Topical 1976 Operational Health Physics reg4.14.rOl 1980 R HPS 1976Symposium

I,)

\0-'I

z

'JI

-I

z

9k0-3

(A

U'00


4936 1-PS Publication 1972 Health Physics in the Healing Arts ........ reg8.18.r01 ..... ... 1982 R Publication No. 1972

No. (FDA) (FDA) 73-8029

73-8029.

4937 ICRP ICRP 1991 Annals of the ICAP, Risks . ....... drg8Ol 2.rOO ..... .. .1994 R Proposed ICRP 1991

Associated with Ionizingn.29.rORadiation, Volume 22, No.1 ____tt___

4938 IEEE IEEE Catalog 1980 Reaord of the WrngCnferec reg0933r 1 1989 R IeE ocatalorkng 1980

No. TH0073 on Advanced Electrotechnology No. TH0073-7

7 Applications to Nucltear PowerPlants

4939 IEEE IEEE No. 1978 Jont fre Dist i drgrs705-4.rOO 1979 R -IEEE No. 1978

F77017-7 Stroke Current Rise and Crest F77017-7

Magnitude to Transmission Lines

4940 IEEE IEEE Paper 1979 Radon Monitoring: Uranium Mill reg4.14.rO1 1980 R IEEE Paper 1979

Field Experience with a Passive

N TH 73o Adetector le trotchn_____N. _TH _73-

4941 IEEE IEEE Paper X 1974 New Seismic Requirements for srp3.10 1981 R IEEE Paper T 74 1974

74 048-5 Class 1 Electrical Equipment 048-5

4942 IEEE IEEE Power 1969 Comparison o ishrsus drgrs705-4.rOO 1979 R IEEE Power 1969

Engineering American Lightning Records EngineerngMagnitude tCommittee Vol.

5Vol. 88, No, .88, No. 5

4943 IEEE IEEE Power 1978 Transient Lightning Overvoltage drgrs7e5-4.rOO 1979 R IEEE Power 1978

Engineering Protection RequiRements for a 500 Engineering

Committee kV Gas-insulated Substation Committee Vol.

Vol. 97, No. 97, No. 1

1


.~M h .:~D r ,;l y...L...... _ _

ecod tandd a rd DC.- Acep- La tet Vrion hNo~ Code4t;t 0:0i.til;t0 00;t Stndr Ves- 'T ^<.i ;t le 'Dcmn Dat abt:t Comet Laes Verio Da

4944 IEEE IEEE 1972 CdTe Gamma Spectrometers for reg5.37.rO1 1983 R IEEE 1972Transactions Nondestructive Analysis of Transactions

Nuclear Fuels4945 IEEE IEEE 1974 Advances in CdTe Gamma Ray reg5.37.rO1 1983 R IEEE 1974

Transactions Detectors Transactions

4946 IEEE IEEE 1976 IAEA Experience in the reg5.37.rOl 1983 R IEEE 1976Transactions Development and Use of CdTe Transactions

Gamma Spectrometric Systemsfor Safeguards Applica- tion

4947 IEEE IEEE 1978 Lightning Performance - I drgrs7O5-4.rOO 1979 R IEEE 1978Transactions Shielding Failures Simplified TransactionsVol. PAS- Vol. PAS-97,97, No. 1 No. 1

4948 IEEE IEEE 1985 Understanding Asymmetry not92-51.s01 1994 R IEEE 1985Transactions Transactions,, Volume iA- Volume IA-21,

21, No. 4 No. 4

4949 IEEE IEEE 1975 Design of a Continuous Digital reg4.14.rO1 1980 R IEEE 1975Transactions Output Environmental Radon Transactions-NS-22 Monitor NS-22

4950 IEEE Pulp and N/S Addressing Nuisance Tripping of not92-51.sO1 1994 R Pulp and Paper 1989Paper Instantaneous Trip Breakers in Conference, 89-Conference, High Efficiency Motor Applications 0789-07

4951 ISA ISA N/S Response Time Testing of srp7,1 1984 R iSA Transaction 1991Transaction Pressure Transmitters in Nuclear 91-72091-720 Power Plants

4952 NCRP NCRP 1960 Somatic Radiation Dose for the drgop618-4.rOO 1982 R NCRP 1960Committee General Population Committee

4953 NCRP NCRP 1960 Somatic Radiation Dose for the reg8.8.r01 1978 R n/a n/aCommittee General Population _ _ _

LA0%0

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.4


Part B - Other Guidance_1R - l .7 s . Ve.son

Racord.^I I . �:� � 1:�� 'j �I1, , ,I 1-1-

I...

': -1, ;z �: �., � a., � I

.. ta darid ,..TL.aA

Documeat '.Dk.Date.

Accept! ~~ `abii ..II-P~ktt

.'.X: , ',,,'"sW ,......

". 1. _,,o LatetstV. ;L -z S0

No.IMFCo-e1t1ngara rVIchim and IdraoB012.r00 1 I 41 R 1 INCRP

taln DatesVelo

1988

954954 NCRPProceedings

I U00 e-jw u az*tY .. .... ,o - - -.

Nagasaki and Its Implications for

Risk Estimates

,

Proceedin(

I I --- ! I I.CA r 1983 -I4955 N1EA INtA

, _

1983

1985

Assessing Human Reliability inNuclear Power PlantsExpert Judgment of HumanReliability

regl . I b4a UV 1U0 .l. ._. .

,_t ssA.nn I lqR'7 1S l8u .___

I -fAf J

49561 NEA NEA CSNIReport No.

Te- 1. s5. G 1987 R NEtA uNo.8Report No. 88

I ::,.

[8 11 I..oa Ir i l~t; t INI j 93__I IUI.Q_ I "NEI

4957 NEI NEI 1993 Thermo-Lag 3JU- I t,0m~UU5UU ImY

Evaluation Methodology PlantScreening Guide

11VL7;}-Vz . -V_

1985___________________I. - t 1rhMI h A.

4958 NEMA NEMAPresentation

1985 IMotor Inrush Currents not92-51.sO1 199U4 M

Presentation

0h

C)

_______ .1 .t~I---t-'-i IIl~cfr2O 19A

4959 NIOSH 130CFR 1 I N/S National Institute for OccupationalSafety and Health

National Institute for OccupationalSafety and Health

1 Ocfr20 1994 R 15u %rn 1 1 l oo

4960 N 30 CFR 1N1 NS not84-60 R t30 CFR 1 | 1994

I~O I_.'__h -

4961~ NIOSH 1NIOSH 1974 Certified Personal ProtectiveIEquipment List

drgop61I8-4.roo 1 UU/ /A sv<s .

I -4_ _ _ It- t I R-5~.-nr.I imnc~u -- 1 Q7S1 Toxic Substances List rey1l.78.rOO 191/4 1`DSH

4ubz~N/ I1fvt 4-,II I I.,ertme resr-~

4963 NIOSH NIOSH N/Si U61`1117e8 rersonne1l vluttulvr:-

Equipment ListCertified Personnel ProtectiveC-'; --- nt IList

.,.I - . .

II

4964 1NIOSH NIOSH N/S reg3.55 .rOO 198t5 h Il l/

1974

1973

n/a

n/a

n/a

1 979

A.4.--t

4g65 i NIOSH

NIOSH

NIOSH 1974 Certified Personnel ProtectiveEquipment List

NIOSH 80- 1979 Criteria for a Recommended

106 Standard... Working in ConfinedSpaces

reg8.8.rO3J I U/ 0_ 1 n n Q rQrq

-IIt~~- -

not8 1-26 1981I

n/a

NI S 0-106

I ----


ftRecoird Standard Do - Le Versiona atWNo ht ... y.Coe ab-. .nt .it, a V . .

4967 NIOSH NIOSH 80- 1979 Criteria for a Recommended not81 -26Part4 1981 R NIOSH 80-106 1979106 Standard ..Working in Confined

Spaces

4968 NIOSH NIOSH 82- 1981 Supplement to the NIOSH inm83100 1991 R NIOSH 92-101 1991106 Certified Equipment List




4972 NIST NBS N/S National Voluntary Laboratory 1Ocfr2O 1994 R n/a n/aAccreditation Program (NVLAP)

4973. NIST NIST NIS National Voluntary Laboratory 10cfr20 1994 A n/a n/aAccreditation Program (NVLAPI Subparts A-O

4974 NOAA NOAA 1968 Climatic Atlas of the United srp2.3.1 1981 R NOAA Not foundStates

4975 NOAA NOAA N/S Local Climatological Data - Annual srp2.3.1 1981 R NOAA Not foundSummary with Comparative Data

4976 NOAA NOAA NIS State Climatological Summary srp2.3.1 1981 R NOAA Annual

4977 NOAA NOAA NiS Storm Data srp2.3.1 1981 R NOAA Annual

4978 NOAA NOAA N/S Local Climatological Data - Annual srp2.3.2 1981 R NOAA AnnualSummary with Comparative Data

4979 NOAA NOAA N/S State Climatological Summary srp2.3.2 1981 R NOAA Annual

4980 NOAA NOAA N/S Tide Tables srp2.4.2 1989 R NOAA Not found

4981 NOAA NOAA 1973 Numerical Simulation of Tsunamis srp2.4.6 1981 R NOAA 1973

4982 NOAA NOAA 1971 Recent Tsunami Theory srp2.4.6 1981 R NOAA 1971

z4

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W


Veor tandr oc cet- LOtest Verlbn

No.cri X $ Code Standard V| r io - . his Doc| u' nt l Date ability Comm e t La s |Version l |at4983 NOAA NOAA 1972 A Package Program for Time- stp2.4.6 1981 R NOAA 1972

Stepping Long Waves into CoastalRegions with Application toHaleiwa Harbor, Oahu

4984 NOAA NOAA Draft 1972 Probable Maximum Precipitation reg1.59.r02 1977 R NOAA Hydro- 1978

Report Estimates, -- United States East of meteorological

the 105th Meridian Report No. 51

4985 NOAA NOAA HUR 1968 Meteorological Characteristics of regl.59.r02 1977 R NOAA HUR 7- 1968

7-97 the Probable Maximum Hurricane, 97A

Atlantic and Gulf Coasts of theUnited States

4986 NOAA NOAA HUR N/S Meteorological Characteristics of reg3.26.rOO 1975 R NOAA HUR 7- 1968



4987 6NOAA NOAA HUR N/S Meteorological Characteristics of reg3.39.rO0 1976 R NOAA HUR 7- 1968



4988 N A NOAA HUR 1968 Meteorological Characteristics of reg3.40.rOl 1977 R NQAAHUR 7- 1968



4989 NOAA NOAA HUR 1968 Meteorological Characteristics of srp2.4.5 1981 R N-AA HUR 7- 1968


Atlantic and Gulf Coasts of the

United States l

4990 NOAA NOAA HUR 1968 Meteorological Characteristics of regl.59.rO2 1977 R NOAA HUR 7- 1968

7-97A the Probable Maximum Hurricane, 97A



ND Ei ... -E 0 i .... ; d W_ .=............... . ... _ - i: - :; t V-.Xi fTgf:-ntRe ord:00 ::it i ;::i:; ..00t0-; Sta d r Dec A.e t Laes Vers00000 ::to; t oVn;;

No ode Sanad Veo Tttl Oounmnt Dateiliy omments, Ltst Version Dt;0i0 o.f t;.0s 0 i C I i 0; t - i~. -1 1 ... t .Il .1it:buett

4991 NOAA NOAA HUR 1968 Meteorological Characteristics of reg3.40.rOl 1977 R NOAA HUR 7- 1968

7-97A the Probable Maximum Hurricane, 97A


4992 NOAA NOAA 1950 Rappahannock River above Salem srp2.4.3 1989 R Not published n/a

Hydro- Church Dam Site, Va.meteorological Report

4993 NOAA NOAA 1956 Potomac River, Va., Md., W. Va. srp2.4.3 1989 R Not published n/a

Hydro- (12 sub-basins)meteorological Report

4994 NOAA NOAA 1956 Delaware River above Trenton, srp2.4.3 1989 R Not published n/a

Hydro- Chestnut Hill, and Belvedere Dammeteorologic Sitesal Report

4995 NOAA NOAA 1965 Delaware River above Tock's srp2.4.3 1989 R Not published n/a

Hydro- Island Dam Sitemeteorological Report

4996 NOAA NOAA 1966 St. John River above Dickey Dam srp2.4.3 1989 R Not published n/a

Hydro- Site, and Between Dicky andmeteorologic Lincoln School Dam Sites, Maineal Report

4997 NOAA NOAA 1950 Coosa River above Howell Mill srp2.4.3 1989 R Not published n/a

Hydro- Shoals Dam Site, Ala.meteorological Report

ti

Wi

'.0

zCi

MJ'0


ec dSt d a dD o c A ce t L ate st V e s c

No. Code Stanndad V rio -, O Title ae f lDoumtnt st a t cts Late t V esion, D te

4998 NOAA NOAA 1950 Cape Fear River above Smiley srp2.4.3 1989 R Not published n/a

Hydro- Falls Dam Site, N.C.meteorological Report

4999 NOAA NoAA 1951 Savannah River above Hartwell srp2.4.3 1989 R Not published n/a

Hydro- Dam Site. N.C.meteorological Report

5000 NOAA NOAA 1952 Alabama and Apalachicola Rivers, srp2.4.3 1989 Not publisheda

Hydro- Ala. and Fla.meteorological Report

5001 OAA NOAA 1959 Black Warrior River above Holt srp2.4.3 1989 R Not published n/a

Hydro- Lock Dam Site, Ala,meteorological Report

5002 NOAA NOAA 1950 South Fork of Holston River above srp2.4.3 1989 R Not published nfa

Hydro- Boone Dam Site, Tenn.meteorologial Report

5003 NOAA NOAA 1956 Allegheny River above Allegheny srp2.4.3 1989 R Not published n/a

Hydro- River Reservoir, Pa.meteorological Report

5004 NOAA NOAA 1958 Kentucky River, Ky. (2 basins) srp2.4.3 1989 R Not published n/a

Hydro-meteorological Report


Recod Sandad -Doe. Accpt-Latet Version

5005 NOAA NOAA 1963 New River above Moores Ferry srp2.4.3 1989 R Not published n|aHydro- Dam Site, Va.meteorologicat Report

5006 NOAA NOAA 1964 Licking River, Ky, and White River, srp2.4.3 1989 R Not published n/a

Hydro- Ind.meteorologicat Report

5007 NOAA NOAA 1947 Iowa River above Coralville Dam srp2.4.3 1989 R Not published n/a

Hydro- Site, Iowameteorologicat Report

5008 NOAA NOAA 1948 Des Moines River above srp2.4.3 1989 R Not published n/a

Hydro- Saylorville, Iowa and Howell Dam

meteorologic Site, lowaat Report

5009 NOAA NOAA 1955 Salt River, Mo. srp2.4.3 1989 R Not published n/a

Hlydro-meteorological Report

5010 NOAA NOAA 1948 James River above Jamestown srp2.4.3 1989 R Not published n/a

Hydro- Dam Site, N. Dak.

7- meteorological Report

M 5011 NOAA NOAA 1951 Big Blue River above Tuttle Creek srp2.4.3 1989 _ Not published n/a

Hydro- Dam Site, Kans.meteorologicat Report

U _.)

z

U'

U'



0eo dS a d rdO o c e t L b ates V ere o n

N o.C o d eS a d r e s o ~l o u s t D t a b ilIty , C o m t L at s t V e s onat

5012 NOAA NOAA 1958 Republican River at (a) above srp.4.3 1989 R Not publirshed n/a

Hydro- proposed Milford Dam Site, Kans.;

meteorologic and lb) between Harlan Co. Dam

at Report and proposed Milford Dam Site,

Kans

5013 NOA AA 1961 Meramec River Basin, Missouri srp2.4.3 1989 R Not published n/a

Hydro-meteorologicat Report

d NOAA NOAA 1969 Republican River above Harlan Co. srp2.4.3 1989 R Not published n/a

Hydro- Res., Neb.

meteorologicat Report

5015 NOAA NOAA 1947 Canadian River above Eufaula srp2.4.3 1989 R Not published n/a

Hydro- Dam Site, Okla.


5016 NOAA NOAA 1948 able Rock srp2.4.3 1989 R Not published n/a

Hydro- Dam Site, Mo.


5017 NOAA NOAA 1948 Eleven Point River above Water srp2.4.3 1989 R Not published n/a

Hydro- Valley Dam Site, Ark,


5018 NOAA NOAA 1948 Kiamichi River above Hugo Dam srp2.4.3 1989 R N n/a

Hydro- Site, Okla.



t RecordC taa Dk Accept- Lat V er .i . e on

5019 NOAA NOAA 1948 Boggy Creek above Boswell Dam srp2.4.3 1989 R Not published n/a

Hydro- Site, Okla.meteorological Report

5020 NOAA NOAA 1949 North Canadian River above srp2.4.3 1989 R Not published n/a

Hydro- Optima (Hardesty) Dam Site, Okla.meteorological Report

5021 NOAA NOAA 1948 Lower Canadian River, Okla. srp2.4.3 1989 R Not published n/a


5022 NOAA NOAA 1948 Gaines Creek Dam Site, Okla. srp2.4.3 1989 R Not published n/a


5023 NOAA NOAA 1948 Onapa-Canadian (combined) Dam srp2.4.3 1989 R Not published n/a

Hydro- Site, Okla.meteorological Report

5024 NOAA NOAA 1950 Verdigris River above Oologah srp2.4.3 1989 R Not published n/a,

Hydro- Dam Site, Okla.meteorological Report

5025 NOAA NOAA 1950 Little Red River above Green srp2.4.3 1989 R Not published n/a

Hydro- Ferry, Ark.meteorological Report

U'o

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--4W,

zC,

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(5

tj)



ieodStadadDe Acet Lstfst Version'

5026 NOAA NOAA 1951 Grand (Neosho) River aboe srp24.3 1989 R p hd nla

Hydro- Strawn Dam Site, Kans.

meteorological Report

5027 NOAA NOAA 1952 Pinon Canyon above Trinidad, srp2.4.3 1989 R Not published nWa

Hydro- Colo.meteorological Report

5028 NOAA NOAA 1955 Beaver Reservoir, White River, srp2.4.3 1989 R Not published n/a

Hydro- Ark.meteorological Report

5029 NOAA NOAA 1956 Kisatchie Dam Site on Kisatchie srp2.4.3 1989 R Not published n/a

Hydro- Bayou, La.meteorological Report

5030 NOAA NOAA 1956 Cypress Creek above srp2.4.3 1989 R Not published n/a

Hydro- Mooringsport, La.meteorological Report

__ .I. ilwod sro24.3 1989 - Not published n/aNOAA R}

oo

00

5031 NOAA NOAA


I tot) UUMtl rlvtg 00v-e -- Ia *- sVV

Dam Site, Ark.; and (b) BrokenBoW, Okla.

_I . A 1 -- _-I n/a

5032 NOAA NOAAHydro-meteorological Report

1966 White River Drainage above k.ltBayou, Ark.

srpz4.4.,3 I nroz I �

I_ _ _ _ _ I ______ --___ _ __ _ I _ _ _ _ - - - - - - - ._ _ _ _-_ _


eor t D A .atest Vrsion0No 'Code ... c StanWr Ve tseon Ton:tle c bat a C L V

5033 NOAA NOAA 1967 Upper Arkansas River, Colorado srp2.4.3 1989 R Not published n/aHydro- (sub-basins)meteorological Report

5034 NOAA NOAA 1969 Arkansas River Drainage Between srp2.4.3 1989 R Not published n/aHydro- John Martin Dam, Colo., andmeteorologic Great Bend, Kans.al Report

5035 NOAA NOAA 1947 Leon River above Belton Dam srp2.4.3 1989 R Not published n/aHydro- Site, Tex.meteorological Report

5036 NOAA NOAA 1949 Jemez Creek, N. Mex. srp2.4.3 1989 R Not published n/aHydro-meteorological Report

5037 NOAA NOAA 1950 Chama River above Chamita Dam srp2.4.3 1989 R Not published n/aHydro- Site, N. Mex.meteorological Report

5038 NOAA NOAA 1 956 Rio Hondo above Two Rivers srp2.4.3 1989 R Not published n/aHydro- Reservoir, N. Mex.meteorological Report

5039 NOAA NOAA 1956 Richland Creek, Tex. srp2.4.3 1989 R Not published n/aHydro-meteorological Report

LA

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-.4

(k)

z

tit

IJ


Reco d St. andard D c Accept- Latet .Vers on

N oE0,i. ; 0200: C od e i L S tnd ardl | rs i r-T0i|:0 - . it le00 D ocu m ent D ate abiit C o m m ent Da s V eruo Date

5040 NOAA NOAA 1956 Basque River above Waco srp2.4.3 1989 R Not published nla

Hydro- Reservoir, Tex.meteorological Report

5041 NOAA NOAA 1956 Leon River above Proctor srp2.4.3 1989 R Not published n/a

Hydro- Reservoir Project near Hasse, Tex.meteorological Report

5042 NOAA NOAA 1957 Pecos River above Alamogordo srp2.4.3 1989 R Not published n/a

Hydro- Reservoir, N. Mex.meteorological Report

5043 NOAA NOAA 1957 Pecos River above los Esteros, N. srp2.4.3 1989 R Not published n/a

Hydro- Mex .meteorological Report

5044 NOAA NOAA 1957 Intervening Drainage between Los srp2.4,3 1989 R Not published n/a

Hydro- Esteros and Alamogordo, N. Mex.meteorological Report

5045 NOAA NOAA 1958 Rio Grande between Cerro and srp2.4.3 1989 R Not published n/a

Hydro- Cochiti Darn Site, N. Mex.

meteorological Report

5046 NOAA NOAA 1958 Combined Drainage of Santa Fe srp2.4.3 1989 R Not published n/a

Hydro- Creek and Rio Galisto abovemeteorologic Galisto Dam Site, N. Mex.

al Report


ec d ,00a00ndar ;o:. Acet Lat. t VerDWoMN i Ce Standad.- Verion. Tit t C me -r Dat t

5047 NOAA NOAA 1958 Lamposas River above proposed srp2.4.3 1989 R Not published n/aHydro- Lamposas Dam Site, Tex.meteorological Report

5048 NOAA NOAA 1959 Navasota River, Tex. (7 sub- srp2.4.3 1989 R Not published n/aHydro- basins)meteorological Report

5049 NOAA NOAA 1963 Colorado River above Fox srp2.4.3 1989 R Not published n/aHydro- Crossing, Tex.meteorological Report

5050 NOAA NOAA 1968 Lower Rio Grande, United States srp2.4.3 1989 R Not published n/aHydro- and Mexico (between Falcon andmeteorologic Anzalduas Dams)al Report

5051 NOAA NOAA 1953 Gila River above Coolidge Dam srp2.4.3 1989 R Not published n/aHydro- Site, Ariz.meteorological Report

5052 NOAA NOAA 1955 Queens Creek, Gila River Basin, srp2.4.3 1989 R Not published n/aHydro- Ariz.meteorological Report

5053 NOAA NOAA 1958 Bill Williams River above proposed srp2.4.3 1989 R Not published n/aHydro- Alamo Dam Site, Ariz.meteorological Report

t'

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I

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(a

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Reor StndrdDt. ccpt Ltet erio|o. Code Standard Veso Tia; tW e Docum n bt abilit C e La st V t

5054 NOAA NOAA 1968 Santa Rosa Wash Basin, Ariz. srp2.4.3 1989 R Not published n/a


5055 NOAA NOAA 1969 Black Creek, Ariz. srp2.4.3 1989 R Not published n/


5056 NOAA NOAA 1972 Preliminary Estimate for Drainages srp2.4.3 1989 R Not published n/a

Hydro- North of Phoenix, Ariz.meteorological Report

5057 NOAA NOAA 1951 Humboldt River, Devils Gate Dam srp2.4.3 1989 R Not published n/a

Hydro- Site, Nev.meteorological Report

5058 NOAA NOAA 1954 Mathews Canyon Dam Site (Virgin srp2.4.3 1989 R Not published n/a

Hydro- River), Nev. and Pine Canyon Dam

mneteorologic Site (Virgin River), Nev.al Report

5059 NOAA NOAA 1957 Dell Canyon Reservoir, Utah srp2.4.3 1989 R Not published n/a


5060 NOAA NOA/A 1960 Las Vegas Wash, Nev. srp2.4.3 1989 Not pubiished n/



_. .. . . . . . . .

RodSadadDcc Acet Latest versionNo . Code. Standard Vee Version .eate

5061 NOAA NOAA 1960 Henderson Wash, Nev. srp2.4.3 1989 R Not published n/aHydro-meteorological Report

5062 NOAA NOAA 1960 West Fork (Mojave River), Calif. srp2.4.3 1989 R Not published n/aHydro-meteorological Report

5063 NOAA NOAA 1960 Tahchevah Creek, Calif. srp2.4.3 1989 R Not published n/aHydro-meteorological Report

5064 NOAA NOAA 1962 Whitewater River above Garnet srp2.4.3 1989 R Not published n/aHydro- Dam Site, Calif.meteorological Report

5065 NOAA NOAA 1962 San Gorgonio River above srp2.4.3 1989 R Not published n/aHydro- Cabazon Dam Site, Calif.meteorological Report

5066 NOAA NOAA 1964 Martis Creek, Calif. srp2.4.3 1989 R Not published n/aHydro-meteorological Report

5067 NOAA NOAA 1962 Merced River, Calif. srp2.4.3 1989 R Not published n/aHydro-meteorological Report

z

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Cs

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tN)4.



R:ecor Standard D c Accept .a .... -:...V ert

neo.u ; i t:0Code . 0l054 StandardX ; Versio T0l Document Da;te09 abil0 0itl Commnte 0Latt Vsin Dte

5068 NOAA NOAA 1968 American River above Folsorn srp2.4.3 1989 R Not published n/s

Hydro- Dam, Calif.meteorologial Report

5069 NOAA NOAA 1968 Northan Middle Forsof srp2.4.3 1989 R Not published n/a

Hydro- American River above Auburnmeteorologic Dam Site, Califal Report

5070 NOAA NOAA 1968 Intervening Drainage between srp2.4.3 1989 R_ Not published n/a

Hydro- Auburn Dam Site and Folsom Dammeteorological Report

5071 NOAA NOAA 1968 Yuba River above Iarysville, srp2.4.3 1989 R Not published n/a

Hydro- Calif .meteorological Report

5072 NOAA NOAA 1968 Los Angeles District, Calif. (18 srp2.4.3 1989 R Not published n/a

Hydro- basins In Calif., Nev., and Ariz.lmeteorologial Report

5073 NOAA NOAA 1973 San Diego River Watershed, Calif. srp2.4.3 1989 R Not published n/a

Hydro- (13 sub-basins)meteorological Report

5074 NOAA NOAA 1947 Sagwni River Aatska srp2.4.3 1989 R Not published n/a

. Hydro-meteorologicai Report

__ _'~_.4 NA OA147 SawyRvr Al.k rp.4. 198 _ o ulse


er Standar D oc.Accpt' Latest esIon0o6oe Sadrd VrinTte ouet Dt ability Cmets Lts Version Dt

5075 NOAA NOAA 1961 Bradley Lake Basin, Alaska srp2.4.3 1989 R Not published n/aHydro-meteorological Report

5076 NOAA NOAA 1962 Chena River, Alaska srp2.4.3 1989 R Not published n/aHydro-meteorological Report

5077 NOAA NOAA 1965 Long Lake Portion of the srp2.4.3 1989 R Not published n/aHydro- Snettisham Projectmeteorological Report

5078 NOAA NOAA 1967 Takatz Creek, Baranof Island, srp2.4.3 1989 R Not published n/aHydro- Alaskameteorological Report

5079 NOAA NOAA 1969 Tanana River Basin for (a) Chena srp2.4.3 1989 R Not published n/aHydro- River above Chena Dam Site, ib)meteorologic Little Chena River above Littleal Report Chena Dam, and (c) Tana River

between Tanacross and Nenana,Alaska

5080 NOAA NOAA 1969 Preliminary Estimates, Vicinity of srp2.4.3 1989 R Not published n/aHydro- Juneau: Mendenhall River, Lemonmeteorologic Creek, and Montana Creekal Report

Lii

Lii

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M-Qi

(b

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c)

-4

(5


Part B - Other Guidance._

I : , ,, I

Record L

5081 NOAA

5082 NOAA

i..

5083 NOAA

LAh~

:-Standardi -

NOAAHydro-meteorological Report

NOAAHydro-meteorologicat Report

NOAAHydro-meteorologicat Report

NOAAydro-


NOAAHydro-meteorologicaI Report 1

NqOAAHydro-neteorologic

at Report

10

-Standard I.Vrsio n .

1974

1 96

1967

1973

1943

.:Thile

Preliminary Estimates, Vicinity of

Ketchikan: Whipple Creek nearWards Cove, Carlanna Creek near

Ketchikan, Hoadley Creek nearKetchikan, and Ketchikan Creek

near Ketchikan

Eastern Panama and NorthwestColombia

Hypothetical Rainstorms over RioAtrato Basin, Colombia, SouthAmerica

Probable Maximum ThunderstormPrecipitation Estimates SouthwestStates

Maximum Possible PrecipitationOver the Ompompanoosuc Basin

above Union Village, Vt.

Document-~rp2.4. 3

;t Doc.g,

Date1989

itEAccept-l0Rablity8- A --

C.m. . t s

s-srp2.4.3 119891 R Not published | n/a

srp2.4.3 1 R Not published nla

m::; :D t :: - -:0f , I

Latest 'v riNot published

Latest VersionI - I Daten/a

srp2.4

. 11 989 R -. Not published /nla

50841 NOAA

srp2.4.3 R5085 NOAA

5086 v iNOAA

L-

1939 Maximum Possible Rainfallover sp2.4.3

the Arkansas River Basin above

Caddoa, Colo.

1989TR

NOAA Hydro-meteorologicalReport 1


1943

193

t')

'0

(a


: e c o rd S t n d r D c c AVe t d L ae- V e rs__ionLi -d ar t Le - i : t t A -- 0.S- i- -f H

N o.c.. S a.d d V: e orsionn it e D m at i ' its L t . D ate5087 NOAA NOAA 1939 A Preliminary Report on the srp2.4.3 1989 R NOAA Hydro- 1939

Hydro- Maximum Possible Precipitation meteorologicalmeteorologic over the Dorena, Cottage Grove, Report 11al Report and Fern Ridge Basins in the11 Willamette Basin, Oreg.

5088 NOAA NOAA 1939 Maximum Possible Precipitation srp2.4.3 1989 R NOAA Hydro- 1939Hydro- over the Red River Basin above meteorologicalmeteorologic Denison, Tex. Report 12al Report12

5089 NOAA NOAA 1940 A Report on the Maximum srp2.4.3 1989 R NOAA Hydro- 1940Hydro- Possible Precipitation over Cherry meteorologicalmeteorologic Creek Basin in Colorado Report 13al Report

5090 NOAA NOAA 1940 The Frequency of Flood-Producing srp2.4.3 1989 R NOAA Hydro- 1940Hydro- Rainfall over the Pajaro River meteorologicalmeteorologic Basin in California Report 14al Report14

5091 NOAA NOAA 1941 A Report on Depth-Frequency srp2.4.3 1989 R NOAA Hydro- 1941Hydro- Relations of Thunderstorm Rainfall meteorologicalmeteorologic on the Sevier Basin, Utah Report 15al Report1 5

5092 NOAA NOAA 1943 A Preliminary Report on the srp2.4.3 1989 R NOAA Hydro- 1943Hydro- Maximum Possible Precipitation meteorologicalmeteorologic over the Potomac and Report 16al Report Rappahannock River Basins16

5093 NOAA NOAA 1944 Maximum Possible Precipitation srp2.4.3 1989 R NOAA Hydro- 1944Hydro- over the Pecos Basin of New meteorologicalmeteorologic Mexico Report 17al Report17 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

t-I

LuI

00


X .c .o.. A c tiL v e r s i o n

tnr St ndardV

5094 NOAA NOAA 1 945 Tentative Estimates of Maximum srp2.4.3 1989 R NOAA Hydro- 1945

Hydro- Possible Flood-Producing meteorological

meteorologic Meteorological Conditions in the Report 18

al Report Columbia River Basin

1 8 ------_ _

5095 NOAA NOAA 1945 Preliminary Report on Depth- srp2.4.3 1989 R NOAA Hydro- 1945

Hydro- Duration-Frequency meteorological

meteorologic Characteristics of Precipitation Report 19

al Report over the Muskingum Basin for 1-

19 to 9-Week Periods

5096 NOAA NOAA 1942 Maximum Possible Precipitation srp2.4.3 1989 R NOAA Hydro- 1942

Hydro- over the Ohio River Basin above meteorological

meteorologic Pittsburgh, Pa. Report 2

al Report 2

5097 NOAA NOAA 1945 An Estimate of Maximum Possible srp2.4.3 1989 R NOAA Hydro- 1945

Hydro- Flood-Producing Meteorological meteorological

meteorologic Conditions in the Missouri River Report 20

al Report Basin above Garrison Dam Site

20

5098 NOAA NOAA 1939 Revised Report on Maximum srp2.4.3 1989 R NOAA Hydro- 1945

Hydro- Possible Precipitation, Los Angeles meteorological

meteorologic Area, California Report 21B

al Report

5099 NOAA NOAA 1944 Revised Report on Maximum srp2.4.3 1989 R NOAA Hydro- 1945

Hydro- Pdssible Precipitation, Los Angeles meteorological

meteorologic Area, California Report 218

al Report21A


oReco d ta r D Ac t Latest Version

No Code Standard X ..Versio n .It Document Dat e a bility Comments Latest Version Date5100 NOAA NOAA 1945 Revised Report on Maximum srp2.4.3 1989 R NOAA Hydro- 1945

Hydro- Possible Precipitation, Los Angeles meteorologicalmeteorologic Area, California Report 21 Bal Report21 B

5101 NOAA NOAA 1946 An Estimate of Maximum Possible srp2.4.3 1989 R NOAA Hydro- 1946Hydro- Flood-Producing Meteorological meteorologicalmeteorologic Conditions in the Missouri River Report 22al Report Basin Between Garrison and Fort22 Randall

5102 NOAA NOAA 1947 Probable Maximum Precipitation srp2.4.3 1989 R NOAA Hydro- 1978Hydro- Estimates, United States East Or meteorologicalmeteorologic the 105th Meridian Report 51al Report23

5103 NOAA NOAA 1947 Maximum Possible Precipitation srp2.4.3 1989 R NOAA Hydro- 1947Hydro- over the San Joaquin Basin, Calif. meteorologicalmeteorologic Report 24al Report24

5104 NOAA NOAA 1947 Representative 12-Hour srp2.4.3 1989 R NOAA Hydro- 1949Hydro- Dewpoints in Major United States meteorologicalmeteorologic Storms East of the Continental Report 25Aal Report Divide, 2nd edition252 5 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

5105 NOAA NOAA 1949 Representative 1 2-Hour srp2.4.3 1989 R NOAA Hydro- 1949Hydro- Dewpoints in Major United States meteorologicalmeteorologic Storms East of the Continental Report 25Aal Report Divide, 2nd edition25A

- ---- ---

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Part B - Other GuidanceAccept-~ ;I. I

-X.or-,e 1 :�:� : :: : � � II I 'I �1:�: I. .. .:. . . . . . .. . .:: �; .... ...1 �� I.:1 X. - Standard ..., a- ..-... Doecd.

:: .1 . . .

.-d.: -

ILatest VerseonDate !: o

ii"; imm~t8:_ ...:

:N . Code [-1 A Standard .V nI { -. ^. . . i~n~ R NAA Hyro- 951

5106 NOAA

51071 NOAA

5108 1 NOAA

LA

05109 NOAA

NOAAHydro-meteorological Report26NOAAHydro-meteorological Report27NOAAHydro-meteorological Report28

NOAAHydro-meteorological Report29NOAAHydro-meteorologial Report 3

NOAAHydro-meteorological Report30NOAAHydro-meteorological Report31

I UVOkeechobee during Tropical Stormof August 26-27, 1949

a _ -.. I

1951

1952

1953

FS-i;;;7-~aiur ossiblePrecipitation, Rio Grande Basin,Fort Quitman to Zapata

Generalized Estimate of Maximum

Possible Precipitation over NewEngland and New York

Seasonal Variation of theStandard Project Storm for Areasof 200 and 1,000 Square MilesEast of the 105th Meridian

srpz.-+.o .I---owes A q I 1 F4HFX

-.- ,{-

R

Report 26

srp2.4.3 R

meteorological

srp2.4.3 1989 R _ .:ydr.--._ 1953srp2.4.3 1 989 R NOAA Hydro-

meteorologicalReport 29


1953

1 943

-- _



1951

1952

I- :' ... _ ..... ___4 A. e -r51 10 1 NOAA 1943 -Maximnum Possible Precipitation

over the Sacramento Basin ofCalifornia

srpz.4,3i I YIOU I

511 1 NOAA 1953 ]Meteorology of Floods at St. Louislsrp2.4.3 1989 R Not published n/a

5112 1 NOAA 1954 Analysis and Synthesis ofHurricane Wind Patterns over Lake

Okeechobee, Florida

srp2.4. 3 tT~~ R

L�� L��


1954

..1 _______________


..cord S . -tandar -::, Acceptg Lot Version

No. Coe Standar Verso tItle- Dument Dt ablomments L

5113 NOAA NOAA 1954 Characteristics of United States srp2.4.3 1989 R NOAA Hydro- 1954

Hydro- Hurricanes Pertinent to Levee meteorological

meteorologic Design for Lake Okeechobee, Report 32

al Report Florida32

5114 NOAA NOAA 1956 Seasonal Variation of the Probable regl .59.rO2 1977 R NOAA Hydro- 1956

Hydro- Maximum Precipitation East of the meteorological

meteorologic 105th Meridian Report 33al Report33 ____

5115 NOAA NOAA 1956 Seasonal Variation of the Probable srp2.4.3 1989 R NOAA Hydro- 1956

Hydro- Maximum Precipitation East of the meteorologicalmeteorologic 105th Meridian Report 33al Report33

5116 NOAA NOAA 1956 Meteorology of Flood-Producing srp2.4.3 1989 R NOAA Hydro- 1956

Hydro- Storms in the Mississippi River meteorological

meteorologic Basin Report 34al Report34

5117 NOAA NOAA 1959 Meteorology of Hypothetical Flood srp2.4.3 1989 R NOAA Hydro- 1959

Hydro- Sequences in the Mississippi River meteorological

meteorologic Basin Report 35al Report356

5118 NOAA NOAA 1969 Interim Report, Probable Maximum srp2.4.3 1989 R NOAA Hydro- 1969

Hydro- Precipitation in California meteorological

meteorologic Report 36al Report36

5119 NOAA NOAA 1962 Meteorology of Hydrologically srp2.4.3 1989 R NOAA Hydro- 1962

Hydro- Critical Storms in California meteorological

meteorologic Report 37

al Report37

U'

(A)

U'

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CD


Part B - Other Guidance_ .._______ I

---. v

Ii , . . .

'-Recordb-5 12 '0'' C, - ' odeii ̀

NOAA

5121 NOAA

5122 1 NOAA

tL 5123 NOAA

.Standard _

NOAAHydro-meteorologicai Report38NOAAHydro-meteorologicaI Report39NOAAHydro-meteorologicat Report 4

NOAAHydro-meteorologicat Report40

NOAAHydro-meteorologicat Report41NOAAHydro-meteorologicat Report42NOAAHydro-meteorological Report43

I : i i,' idi j.~ f ...Sta-nda'rd

Versip~on,~,,~1961

1963

1943

1965

1965

1966

Meteorology of Flood-Producing

Storms in the Ohio River Basin

Probable Maximum Precipitation in

he Hawaiian Islands

Maximum Possible Precipitation

over the Panama Canal Basin

Probable Maximum Precipitation,

Susquehanna River Drainage

above Harrisburg, Pa,

Probable Maximum and TVA

Precipitation over the Tennessee

River Basin above Chattanooga

Meteorological Conditions for the

Probable Maximum Flood on the

Yukon River above Rampart,

Alaska

,'t'- ,' z ;' ,; ' , '; : L.

Documentsrp2.4.3

dI ... ',, :

'Date989 ~A..et'

:~abilltiY..

, . :

. r,- h.e.. litti " v .A~Co-mmets' I

--- ---- -- -- -- .

Latest Verslon

Latest Verslon. , .'Dat e:f . ,",

U .'

1 989 R NiOAA Hydro-meteorologicalReport 38

OAA Hydro-


I Z20 a

srp2.4.3 1989 R 1963

_ 4 A -

srp2.4.3 F j98 If- R NOAA Hydro-meteorologicalReport 4

I1943

I I I _ _ _ _ _ 1199 . _~~ _9 6A-

srp2.4.3 1989 R

srp2.4.3 R5124 1 NOAA

srp2.4.3 1989 R

I OA1.


NOAA Hydro-




_

1965

1965

19665125 t NOAA

5126 1 NOAA

I

L��

1966 Probable Maximum Precipitation, 1Northwest States

L-

srp2.4.3 ---- "989 R


< i~gh.\ . T- ..E. iE700EREE iREiRE~iD: ifsCE 3. . .... ..... ... ..i i W. : .- E,.... , .. ii . .....

SRecod .tandard Do Acpt La V .iNo. Cod ~ Stanidard '.Vrson Tte ,Dc en Dte aity, omns: aetVrin Dt

5127 NOAA NOAA 1981 Probable Maximum Precipitation, srp2.4.3 1989 R NOAA Hydro- 1981Hydro- Northwest States meteorologicalmeteorologic Report 43al Report43Addendum

5128 NOAA NOAA 1969 Probable Maximum Precipitation srp2.4.3 1989 R NOAA Hydro- 1969Hydro- over South Platte River, Colorado, meteorologicalmeteorologic and Minnesota River, Minnesota Report 44al Report44

5129 NOAA NOAA 1969 Probable Maximum and TVA srp2.4.3 1989 R NOAA Hydro- 1969Hydro- Precipitation for Tennessee River meteorologicalmeteorologic Basin up to 3,000 Square Miles in Report 45al Report Area and Durations to 72 Hours45 _ _ _ _ _ _ _ _ _ _ _

5130 NOAA NOAA 1970 Probable Maximum Precipitation, srp2.4.3 1989 R NOAA Hydro- 1970Hydro- Mekong River Basin meteorologicalmeteorologic Report 46al Report46 _ _ _ _ _ _

5131 NOAA NOAA 1973 Meteorological Criteria for srp2.4.3 1989 R NOAA Hydro- 1973Hydro- Extreme Floods for Four Basins in meteorologicalmeteorologic the Tennessee and Cumberland Report 47al Report River Basins47 _____ _

5132 NOAA NOAA 1973 Probable Maximum Precipitation srp2.4.3 1989 R NOAA Hydro- 1973Hydro- and Snowmelt Criteria for Red meteorologicalmeteorologic River of the North Above Pembinz, Report 48al Report and Souris River Above Minot,48 North Dakota

LA3

0

(!A

-4

Cb

z

C-4

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Coe Standar d ydrlr il Dcuet Dt blt Cnnet eetVrson D9t7

53 NOA NA197 PoaeMaimumn Precipitation srp2.4.3 1989 R NOAA Hdr- 1751NA NOAA 1r 977 Pron: bable IV, ax

meteorologrd* 0 |ical

Hydro- Estimates, Colorado River and meteorological

meteorologic Great Basin Drainages Report 49

al Report

49 ___989__NAAHyd___94

5134 NOAA NOAA 1947 Thunderstorm Rainfall srp2.4.3 1989 R -NOAA Hdro-l1947

Hydro- Reporto5

meteorological Report 5

5136 NOAA NOAA 1982 The Meteorology of Important srp2.4.3 1989 R meteHro-g1982

Hydro- Rainstorms in the Colorado River meteorological

meteorologic and Great Basin Drainages Report 50

al Report50 ___ __ ___ __19___ _8

6136 NOAA NOAA N/S Probable Maximum Precipitation regil59.rO2 1977 R NOAA Hydroa

Hydro- Estimates, United States East of meteorological

meteorologic the 105th Meridian Report 51

al Report51__ _ _ _ __

_ _ _ _ _

5137 NOAA 51 1978 Probable Maximum Precipitation srp2.4.2 1989 R NOAA Hydro- 1978


meteorologic the 105th Meridianal Report

5138 NOAA 1978 Probable Maximum Precipitation srp2.4.3 1989 R NOAA Hydro- 1978


meteorologic 105th Meridian Report 51

al Report

_ nf Probahle Maximum sro2.4.2 1989 R NOAA Hydro- 1982NOAAlatu}w T.........--o

5139 NOAA NUAAHydro-meteorological Report

I 1cow

Precipitation Estimates, UnitedStates East of the 105th Meridian


152 _ ___ __ _I


: 0No. . :.; 00 Code :Standard Vet: .Yrsioni m ~ le - : ec~oument Date.. abX.t ComE nt 0sX4 Lates version D:t

5140 NOAA NOAA 1982 Application of Probable Maximum srp2.4.3 1989 R NOAA Hydra- 1982

Hydro-Precipitation Estimates, United meteorological

meteorologic States East of the 105th Meridian .Report 52al Report52 _ _ _ _ _

5141 NOAA NOAA 1980 Seasonal Variation of 10-Square- srp2.4.2 1989 R NOAA Hydro- 1980

Hydra- Mile Probable Maximum meteorologicalmeteorologic Precipitation Estimates, United Report 53al Report States East of the 105th Meridian53 _ _ _ _ _

5142 NOAA NOAA 1980 Seasonal Variation of 10-Square- srp2.4.3 1989 R NOAA Hydra- 1980Hydra- Mile Probable Maximum meteorological

meteorologic Precipitation Estimates, United Report 53

al Report States East of the 105th Meridian_53 _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ _ _ _ _ ___ _ _ _ _ _

5143 NOAA NOAA 1983 Probable Maximum Precipitation srp2.4.3 1989 R NOAA Hydro- 1983

Hydro- and Snowmelt Criteria for meteorological

meteorologic Southeast Alaska Report 54

al Report

54


Hydro- Estimates, United States Between meteorological

meteorologic thecContin ental Divid e and the Report 55

al Report 103rd Meridian

53


Hydro- Estimates, United States Between meteorological

meteorologic the Contin ental Divid e and the Report 55al Report 103rd Meridian55

5146 NOAA NOAA 1938 A Preliminary Report on the srp2.4.3 1989 R -NOAA Hydro- 1938

Hydro- Probable Occurence of Excessive meteorological

meteorologic Precipitation over Fort Supply Report 6

al Report 6 Basin, Okla X

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UtA


N o . C o d e~ St n d r e s o nT t eo u m t D a e b li y C o m m en n ts L ate st Ver sio n :D t

5147 NOAA NOAA 1938 Worst Probable Meteorological srp2.4.3 1989 R NOAA Hydro- 1938

Hydro- Condition on Mill Creek, Butler meteorological

meteorologic and Hamilton Counties, Ohio Report 7

at Report 7

5148 NOAA NOAA 1938 A Hydrometeorological Analysis of srp2.4.3 1989 R NOAA Hydro- 1938

Hydro- Possible Maximum Precipitation meteorological

meteorologic over St. Francis River Basin above Report 8

at Report 8 Wappapello, Mo.

5141939 A Report on the Possible srp2.4.3 1989 R NOAA Hydro- 1939

Hydro- Occurrence of Maximum meteorological

meteorologic Precipitation over White River Report 9

at Report 9 Basin above Mud Mountain DamSite, Wash.

5150 NOAA NOAA 1982 Earthquake History of the United srp2.5.2 1989 R NOAA 1982

Publication States Publication 41-

41-1 1 _ _ _ _

5151 NOAA NOAA Tech. 1976 Diffusion Under Low Windspeed regl.145.rO1 1982 R NOAA Tech. 1976

Memo ERL Conditions Near Oak Ridge, Memo ERL ARL-

ARL-61 Tennessee 61

5152 NOAA NOAA Tech. 1977 Rancho Seco Building Wake regl.145.rOl 1982 R NOAA Tech. 1977

Memo ERL Effects on Atmospheric Diffusion Memo ERL ARL-

ARL-69 69

5153 NOAA Tech. 1974 A Program for Evaluating reg1.111.rO1 1977 . R NOAA Tech. 1974

Memo ERL- Atmospheric Dispersion From a Memo ERL-ARL-

ARL-42 Nuclear Power Station 42

-j.


Record StAndard o A.cept- Lte V lonNo. Code Stndardi Vro "Ti iocmet i bate blity Comment Laes: ,tt Versoate

5154 NOAA NOAA Tech. 1974 A Program for Evaluating srp2.3.4 1981 R NOAA Tech. 1974Memo ERL- Atmospheric Dispersion From a Memo ERL-ARL-ARL-42 Nuclear Power Station 42

5155 NOAA NOAA Tech. 1974 Regional Effluent Dispersion reg1.111 .r01 1977 R NOAA Tech. 1974Memo ERL- Calculations Considering Spatial Memo ERL-ARL-ARL-44 and Temporal Meteorological 44

Variations

5156 NOAA NOAA 1960 Generalized Estimates of Probable srp2.4.2 1989 R NOAA 1960Technical Maximum Precipitation for the Technical PaperPaper No. United States West of the 105th No. 3838 Meridian for Areas to 400 Square

Miles and Durations to 24 Hours

5157 NOAA NOAA 1970 The March-April 1969 Snowmelt srp2.4.3 1989 R NOAA 1970Technical Floods in the Red River of the TechnicalReport NWS North, Upper Mississippi, and Report NWS 1313 Missouri Basins

5158 NOAA NOAA 1971 Weekly Synoptic Analyses, 5-, 2-, srp2.4.3 1989 R NOAA 1971Technical and 0.4-Millibar Surfaces for 1968 TechnicalReport NWS Report NWS 1414

5159 NOAA NOAA 1975 Some Climatological srp2.4.3 1989 R NOAA 1975Technical Characteristics of Hurricanes and TechnicalReport NWS Tropical Storms, Gulf and East Report NWS 1515 Coasts of the United States

5160 NOAA NOAA 1975 Storm Tide Frequencies on the srp2.4.3 1989 R NOAA 1975Technical South Carolina Coast TechnicalReport NWS Report NWS 161 6 _ _ _ _ __ _ _ _ _ __ _ _ _ _ _ _ _ _ _ _ _ _ _

U.)

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Record Stand Dc. :|xAccept- Latest Version.

No Cde Sanar erio ite ocmnt Dae abliy Commients - Laotes Verin Date

5161 NOAA' NONA 1975 Estimation of Hurricane Storm srp2.4.3 1989 R NOAA 1975

Technical Surge in Apalachicola Bay, Florida Technical

Report NWS Report NWS 17

175 1989 R NOAA 1975___ __ __ __ __ __ __ __ _

5162 NOAA NOAA 1975 Point Probability Method of Tide srp2.4.3 1989 R NOAA 1975

Technical Frequency Analysis Applied to technical

Report NWS Apalachicola Bay and St. George Report NWS 18

18 Sound, Florida

5163 NOAA NOAA 1979 Interduration Precipitation srp2.4.3 1989 R NOAA 1979

Technical Relations for Storms - Southeast Technical

Report NWS States Report NWS 21

2 1 _ _ _ _ __ _ _ _

5164 NOAA NOAA N/S teorological Criteria for the drgce4O6-4. rO 1986 R NOAA 1979

Technical Standard Project Hurricane and Technical

Report NWS Probable Maximum Hurricane Report NWS 23

23 Windfields, Gulf and East Coastsof the United States

5165 NOAA NOAA N/S Meteorological Criteria for the reg3.44.rO2 1989 R NOAA 1979

Technical Standard Project Hurricane and echnica



5166 NOAA NOAA N/S Meteorological Criteria for the reg3.48.rOl 1989 R NOAA 1979

Technical Standard Project Hurricane and Technical




Record Standard Doc .... ce.- L...s Vor.Xo.A0 No.i: Cde Standard Verssoa Toin tleocmet te aiita

5167 NOAA NOAA 1979 Meteorological Criteria for the srp2.4.3 1989 R NOAA 1979Technical Standard Project Hurricane and TechnicalReport NWS Probable Maximum Hurricane Report NWS 2323 Windfields, Gulf and East Coasts

of the United States

5168 NOAA NOAA 1980 A Methodology for Point-to-Area srp2,4,3 1989 R NOAA 1980Technical Rainfall Frequency Ratios TechnicalReport NWS Report NWS 2424

5169 NOAA NOAA 1980 Comparison of Generalized srp2.4.3 1989 R NOAA 1980Technical Estimates of Probable Maximum TechnicalReport NWS Precipitation with Greatest Report NWS 2525 Observed Rainfalls

5170 NOAA NOAA 1981 Frequency and Motion of Atlantic srp2.4.3 1989 R NOAA 1981Technical Tropical Cyclones TechnicalReport NWS Report NWS 2626

5171 NOAA NOAA 1981 Interduration Precipitation srp2.4.3 1989 R NOAA 1981Technical Relations for Storms-Western TechnicalReport NWS United States Report NWS 2727

5172 NOAA NOAA 1982 A Monthly Averaged Climatology srp2.4.3 1989 R NOAA 1982Technical of Sea Surface Temperature TechnicalReport NWS Report NWS 3131

5173 NOAA NOAA N/S Pertinent Meteorological and srp2.4.3 1989 R Not published n/aTechnical Hurricane Tide Data for HurricaneReport NWS Carla3232 _ _ . _ __ __ _ _ _ _ _ _ _ _

5174 NOAA NOAA 1982 Evaporation Atlas for the srp2.4.3 1989 R NOAA 1982Technical Contiguous 48 United States TechnicalReport NWS Report NWS 3333 _ _ ___ _

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5176

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5178

5179

OsHA

UL

UL

USGS



~,S t a n drdo V e S to W .l D c m nt D t a b l t C m e t s

NSF Tentative Provisions for the dr*ce406- 4 .tOO 1986 R Also titled NBS

Publication Development of Seismic Special

78-8 Regulations for Buildings Publication510

29 CFR N/S Hazardous Waste Operations and not92-7 2 1992 R

1910.120 ___ _ Emergency Response 994

UL Subject -1991 Fire Tests for Electrical Circ'uit g~t86-1 0.sl 1994 P

1724 Protective Systems

UL Subject 1984 FireTests for Electrical Circuit not93-40 1993 _

1724 Protective Systems

USGS 1951 Cl a and a Scheme for regI.138.rOO 1978 R

Bulletin the Identification of Layer Silicates

1910.120

: Q;Xnu:? ::::1;;:! X: Latest: Versloa

LatestVeson , 8DateATC-3-06 1984

.~ Utlir1QQI 991

_ . _

UL Outline ofInvestigation1724UL Outline of

Investigation1724USGS Bulletin

1991

1991

LA4~.0

Appendix A

Summation of Code and Standard Citationsin Regulatory Documents (Part A)

A-1 NUREG/CR-5973 Rev. 3

Appendix A


Citations

Acoustical Society of America (ASA) 1American Concrete Institute (ACI) 81American Institute of Steel Construction (AISC) 13American National Standards Institute (ANSI) 962American Nuclear Society (ANS) 255American Petroleum Institute (API) 8American Public Health Association (APHA) 13American Society of Civil Engineers (ASCE) 5American Society of Heating, Refrigerating, and Air Conditioning Engineers (ASHRAE) 1American Society of Mechanical Engineers (ASME) 1756American Society for Nondestructive Testing (ASNT) 16American Society. for Quality Control (ASQC) 2American Society for Testing and Materials (ASTM) 355Applied Technology Council (ATC) 9American Water Works Association (AWWA) 6American Welding Society (AWS) 19Crane Manufacturers Association of America (CMAA) 3Diesel Engine Manufacturers Association (DEMA) 5Factory Mutual (FM) 2Health Physics Society (HPS) 10Heat Exchanger Institute (HEI) 1Insulated Cable Engineers Association (ICEA) 3Institute of Electrical and Electronics Engineers (IEEE) 448Instrument Society of America (ISA) 32International Commission on Radiological Protection (ICRP) 72International Commission on Radiological Units and Measurements (ICRU) 11International Conference of Building Officials (ICBO) 7International Standards Organization (ISO) 8Manufacturers Standards Society (MSS) 1Military Standards (MIL) 30National Concrete and Masonry Association (NCMA) 1National Association of Corrosion Engineers (NACE) 1National Council on Radiation Protection (NCRP) 126

A-3 NUREG/CR-5973 Rev. 3

Appendix A


Citations

National Electrical Manufacturers Association (NEMA) 12

National Electrical Testing Association (NETA) I

National Fire Protection Association (NFPA) 163

National Institute of Standards and Technology (NIST) 30

National Rifle Association (NRA) 5

Nuclear Energy Institute (NEI) 1

Underwriters Laboratory (UL) 10

NUREG/CR-5973 Rev. 3 A-4

Appendix B

Summation of Other Government and Industry GuidanceCitations in Regulatory Documents (Part B)

B-1 NUREG/CR-5973 Rev. 3

Appendix B

Summation of Other Government and Industry GuidanceCitations in Regulatory Documents (Part B)

Citations

American Chemical Society (ACS) 2American Concrete Institute (ACI) 7Atomic Energy Commission (AEC) 37American Institute of Chemical Engineers (AICHE) 3American Nuclear Society (ANS) 27American Society of Civil Engineers (ASCE) 57American Society of Mechanical Engineers (ASME) 6American Society for Testing and Materials (ASTM) 4Applied Technology Council (ATC) 10American Water Works Association (AWWA) 3Department of Energy (DOE) 9Department of Health and Human Services (HHS) 6Department of Transportation (DOT) 125Energy Research and Development Administration (ERDA) 14Environmental Protection Agency (EPA) 128Factory Mutual (FM) 3Federal Specification (FFPR) 11Federal Water Pollution Control Act (FWPCA) 1Geological Society of America (GS of A) 17Health Physics Society (HPS) 3Institute of Electrical and Electronics Engineers (IEEE) 13Instrument Society of America (ISA) 1International Commission on Radiological Protection (ICRP) 1National Council on Radiation Protection (NCRP) 3National Electrical Manufacturers Association (NEMA) 1National Institute for Occupational Health and Safety (NIOSH) 13National Institute of Standards and Technology (NIST) 2National Oceanic and Atmospheric Administration (NOAA) 201National Science Foundation (NSF) 1Nuclear Energy Agency (NEA) 2Nuclear Energy Institute (NEI) IOccupational Safety and Health Administration (OSHA) 1Underwriters Laboratory (UL) 2United States Geological Survey (USGS) 1

B-3 NUREG/CR-5973 Rev. 3

NUREG/CR-5973PNL-8462

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2. TITLE AND SUBTITLE NUREG/CR-5973

PNL - 8462Codes and Standards and Other Guidance Cited in Regulatory Documents Revision 3

5. Date Report Published

MONTH YEAR

August 19965. AUTHOR(S) 4. FIN OR GRANT NUMBER

J2328J. R. Nickolaus, K. L. Bohlander 6. TYPE OF REPORT

Technical7. PERIOD COVERED (Inclusive

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10. SUPPLEMENTARY NOTES

11 ABSTRACT (200 words or ess)

As part of the U.S. Nuclear Regulatory Commission (NRC) Standard Review Plan Update and Development Program(SRP-UDP), Pacific Northwest National Laboratory developed a listing of industry consensus codes and standards andother government and industry guidance referred to in regulatory documents. The SRP-UDP has been completed and theSRP-Maintenance Program (SRP-MP) is now maintaining this listing. Besides updating previous information, Revision 3adds approximately 80 citations. This listing identifies the version of the code or standard cited in the regulatory document,the regulatory document, and the current version of the code or standard. It also provides a summary characterizationof the nature of the citation. This listing was developed from electronic searches of the Code of Federal Regulations andthe NRC's Bulletins, Information Notices, Circulars, Enforcement Manual, Generic Letters, Inspection Manual, PolicyStatements, Regulatory Guides, Standard Technical Specifications and the Standard Review Plan (NUREG-0800).

12. KEY WORDSIDESCR1PTIONS (List words orphrases that will assist researchers in locating this report.)

Code, Standard, Standard Review Plan (SRP)

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