NUREG - Nuclear Regulatory Commission

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NUREG--0304Vol.15, No. 4

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Regu~ atory anc Technica: Reports/ Abstract Index Journal;\ )

\ e" Annual Compilation for 1990

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Available from

Superintendent of DocumentsU.S. Government Printing Office

Post Office Box 37082Washington, D.C. 20013 7082

A year's subscription consists of 4 issues forthis publication.

Single copies of this publicationare available from National Technical

Information Service, Springfield, VA 22161

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NUREG-0304Vol.15, No. 4

Regu atory and Technical Reaorts(Abstract Inc ex Journal)

Annual Compilation for 1990.

Date Published: March 199'.

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Regulatory Publications BranchDivision of Freedom ofInformation and Publications ServicesOffice of AdministrationU.S. Nuclear Regulatoiy CommissionWashington, DC 20555

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CONTENTS

.... ........... .. . vPref ace . . . . . . . . ............. ...... .. ....... .. ...

indexTab

Main Citations and Abstracts . ........ ......... .. ...... 1......... ......... ... ..

+ Staff Reports* Conference Proceedings* Contractor Reports+ international Agreement Reports

2Secondary Report Nurnber index . . . . . . . . . . . . , .... . .. .. . . .... .. ...... .. .....

Personal Author index . . . . . . . . . . . . . . . 3............ . . ... ..... .. ..........

S ubj ect in de x . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ........ .. .. ... ........ .. ... 4

NRC Originating Organization tndex (Staff Reports) . . . 6. ... ...... .. .. ..............

NRC Originating Organization Index (international Agreernents) . .... ... ...... .. ......... 6NRC Contract Sponsor index tContractor Reports) . . . . . . . . . . . . . . . . . . . . . . . . ...... ..,.. 7

Contractor Index . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .... ......... 8......... ..... . ....

- International Organization index . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ......... ...,..... 9.

... 10Licensed Facility index . . . . . . . . . . , . . . . . ..., .... ... .... .... . . . ....

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PREFACE

This compilation consists of bibliographic data and abstracts for the formal regulatory and technicalreports issued by the U.S. Nuclear Regulatory Commission (NRC) Staff and its contractors. It is NRC'sintention to publish this compilation quarterly and to cumulate it annualty. Your comments will be op-preciated. Please send them to:

Technical Publications SectionRegulatory Publications BranchDivision of Freedom of Information

and Publications ServicesP.223U.S. Nuclear Regulatory CommissionWashington, D.C. 20555

The main citations and abstracts in this compilation are listed in NUREG number order: NUREG XXXX,NUREG/CP XXXX, NUREGICR XXXX, and NUREG/lA XXXX. These precede the following indexes:

Secondary Report Number indexPersonal Author IndexSubject indexNRC Originating Organization Index (Staff Reports)NRC Originating Organization Index (International Agreements)NRC Contract Sponsor index (Contractor Reports)Contractor IndexInternational Organization indexLicensed Facility index

A detailed explanation of the entries precedes each index,

The bibliographic elements of the main citations are the following:

Staff Report

NUREG 0808: MARK 11 CONTAINMENT PROGRAM EVALUATION AND ACCEPTANCE CRITERIA.ANDERSON, C.J. Division of Safety Technology. August 1981, 90 pp. 8109140048 09570:200.

Where the entries are (1) report number, (2) report title, (3) report author, (4) organizational unit ofauthor, (5) date report was published, (6) numbar of pages in the report, (7) the NRC Document ControlSystem accession number, (8) the microfiche address (for intemal NRC use).

Conference Report

NUREG/CP 0017: EXECUTIVE SEMINAR ON THE FUTURE ROLE OF RISK ASSESSMENT ANDREUABILIT 'NGINEERING IN NUCLEAR REGULATION, JANERP, J.S. Ar0onne NationalLaboratory. may 1081.141 pp. 8106280299 ANL 81-3. 08632:070.

Where the entries are (1) report number, (2) report title, (3) report author, (4) organization that compiledth6 proceedings, (5) date report was published, (6) number of pages in the repvrt, (7) the NRC Docu-ment Control System accession number, (8) the report number of the originating organization, (91 themicrofiche address (for NRC intemal use).

Contractor Report

NUREG/CR 1556: STUDY OF ALTERNATE DECAY HEAT REMOVAL CONCEPTS FOR LIGHT WATERREACTORS-CURRENT SYSTEMS AND PROPOSED OPTIONS. BERRY, D.L.: BENNETT, P.R.Sandia Laboratories. iday 1981.100 pp. 8107010449. SAND 800029. 08912:242.

Where the entries are (1) report number, (2) report tit!e, (3) report authors, (4) organizational unit ofauthors or publisher, (5) date report was published, (6) number of pages in the report, (7) the NRCDocument Control System accession number, (8) the report number of the originating organization (ifgiven), and (9) the microfiche address (for NRC Internal use).

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9 li-temational Agreement Report.

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NUREG/lA 0001: ASSESSMENT OF TRAC PD2 USING SUPER CANNON AND HDR EXPERIMENTALDATA. NEUMANN, U. Kraftwerk Union. August 1986. 223 pp. 8608270424. 37659:138.

Where the entries are (1) report number, (2) report title, (3) report author, (4) organizational unit of author,(5) date report was published, (6) number of pages in the report, (7) the NRC Document Control Systemaccession number, (8) the report number of the originating organization (if given), and (9) the microficheaddress (for NRC internal use).

The following abbreviations are used to identify the document status of a report:

ADD - addendumAPP - appendixDRFT - drattERR - errata

N numberR - revisionS supplementV - volume

_ Availability of NRC Publications

Copies of NRC staff and contractor reports may be purchased either from the Government Printing Office(GPO) or from the National Technical Information Service, Springfield, Virginia 22161. To purchasedocuments from the GPO, send a check of money order, payable to the Superintendent of Documents,to the following address:

Superintendent of DocumentsU.S. Government Printing OfficePost Offico Box 37082Washington, DC 20013-7082

You may charge any purchase to your GPO Deposit Account, MasterCard charge card, or VISA chargecard by calling the GPO on (2021275-2060 or (202)275-2171. Non U.S. customers must make payment inadvance either by International Postal Money Order, payable to the Superintendent of Documents, orby draft on a United States or Canadian bank, payable to the Superintendent of Documents.

NRC Report Codes

The NUREG designation, NUREG XXXX, indicates that the document is a formal NRC staff-generatedreport Contractor prepared formal NRC reports carry the report code NUREG/CR-XXXX. This type ofidentification replaces contractor-established codes such as ORNL/NUREG/TM XXX and TREE-NUREG XXXX, as well as various other numbers that could not be correlated with NRC sponsorship ofthe work being reported.

In addition to the NUREG and NUREG/CR codes, NUREG/CP is used for NRC sponsorad conferenceproceedings and NUREG/lA is used for international agreement reports,

All these report codes are controlled and assigned by the staff of the Publishing and Translations Sectionof the NRC Division of Publications Services.

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Main Citations and Abstracts

The report listings in tnis compilation are arranged by report number, whers NUREG XXXX isan NRC staff-originated report, NUREG/CP XXXX is an NRC sponsored conference report,NUREG/CR XXXX is an NRC contractor prepared report, and NUREG/lA XXXX is an inter-national agreement remrt. The bibliographic information (see Preface for details) is follOwedby a brief abstract of tais report.

NUREG-0020 VI) N11: UCENSED OPERATING REACTORS NUREG-0040 V14 N01: UCENSEE CONTRACTOR ANDSTATUS SUMMARY REPORT. Data As Of October VENDOR INSPECTON STATUS REPORT. Quarterty30,19894 Grey Book 0 LOVELACEE H Onnson of Computer & Report.JanuaTMarch 1990. * Orvison of Reactor Inspecton &Telecommurucations Services (Post 890205) January 1990 Safeguards (Post 870411). Juh 1990 213;ip 9006140499543po. 9002120335. 52579.130- 54924.276.

THE OPERATING UN!TS ST ATUS REPORT - UCENSED TNs perodical covers the resu ts of inspectons portormed byr

OPERATING REACTORS provdes data on the operaton of nu- NRC's Vendor inspecton Branch that have been $stobuted tocear uruts as timely and accurately as poststde_ TNs mfcfma' the mspected organastons durng the ponod from Januaryton is collected by the C*fice of informahon Resources Man- 1990 through March 1990.agement from the Headouarters statt of NRC's Offee of En-forcement (OE), from NRC's Regonal Offices, ard from utet>es- NUREG 0040 V14 NO2: LICENSEE CONTRACTOR ANDThe three sectons of the report are monthly hghlghts and sta. VENDOR INSPECTION STATUS REPORT. Ovariertytestes for commerciaJ operating urwts, and stata trom previousty Re@h 1M %m BwiM ' Nw -d Rmtw Wreported data; a comi#atson of detaded informaton on each specton & Safeguards (Post 870411). Octote> 1990. 125ppurut, provded by NRC's Regional Oftces, OE Headquarters and 9011090222 55661:315

nf,',je'd ) [t Tbs penodcal covers the results of inspoctons performed byy of e the NPC's Vendor inspecton Oranch *. hat have teen estnbuted

non. power reactors m the U S. It rs hoped the report is he4pfut to the espected orgarcatons dunng the penod from Apnl 1990to all agencaes and mdmduals interested m mamiairung an through June 1990.awareness of the U S. energt situaton as a wtoie.

NUREG-0020 V13 N12: UCENSED OPERATING REACTORS >8'JREG 0040 V14 H4 UCENSEE CONTRACTOR AND'

STATUS SUMMARY REPORT Data As Of November VENDOR INSPECTION STATUS REPORT. Quarteriy30,1989 gGray Book 1) LOVELACE,WM Dvtsaon of Computer & Aeport July-Septemoer 1990 (Wbte Book) * Dmson of ReactorTelecomrmnestons Senaces (Post 890205) January 1990 inspection & Safeguards (Post 870411). November 1990558pp. 9003070140. 52809125. 226pp. 9011160225. 55755 032

See NUREG-0020,V13 N11 abstract TNs penodca! covers the resotts of inspectons performed byhe a ns n ra have W d e W

NUREG-0020 V14 Not: UCENSED OPERATING REACTORS D " **P*## "98** ""9 " P"" d MSTATUS SUMMARY REPORT, Data As Of December W D b'P'* *

i 31,1989 (Gray Book 1) LOVELAvE,W H. Omson of Computer &Te4ecommuncabons Services (Post 890205). February 1990- NUREG 0090 V12 N03: REPORT TO CONGRESS ON ABNOR-

* *N EG ' N bstract ses & Eva'uaton of Operatonal Data. Drector. Janua y 1990.

| NUREG-0020 V14 N02: LICENSED OPERATING REACTORS34pp. 9003070121. 52814'186

STATUS SUMMARY 9EPORT.0ata As Of January Secton 208 of the Energy Reorganaston Act of 1974 idents'

fes an abrormal occurrence as an unscheduled medent orI 31,19904 Gray Book 0 LOVELACE,W.H Dmson of Computer &Telecommuncatons Sennees (Post 890205). Apni 1990. 564pp. event wNch the Nuclear Regulatory Commission determines to

be sagrufcant from the standpoint of pubhc health and safety9005040120. 53648:104See NUR'?G-0020,V13.N11 abstract ard requires a Quarterty report of such events to be made to

Congress. This report covers the penod July 1 tr<ough Septem-

|' HUREG-0020 V14 NO3: UCENSED OPERATING REACTORS ber 30,1989. For tNs reportng penod. there were five abnormalSTATUS SUMMARY REPORT. Data As Of F*uary occurrences. One abnormal occurrence took place at a licensed28,19904 Gray Book 0 HARTFIELD,R.A. Omson of Computer & nuclear power plant and involved sagrvficant defcencies associ-Te6ecommuncatons Services (Post 890205) May 1990. 331pp. ated with the containment recirculaton sump at the Trosan fac6-

ty. The other tour abnormal occurrences took place under otherNJREG 20*V13,N11 abstract NRC4ssued licenses: the first invoNed a med. cal diagnost>c

NUREG-0040 V13 N04: UCt:NSEE CONTRACTOR ANDmisadministraton; the second mvolved a medcal therapy mas-

VENDOR INSPECTION STATUS REPORT. Quarterty acinnistrobon; the tNrd invoNer' a radiato, overexposure of a

Report, October Decomter 1989 (White Book) * Devson of Re. radographer; and the fourth invo8ved a segnifcant breakdown

actor inspecton & Safeguards (Post 870411) January 1990. and careless csiegard of the radiaton safety program at three ;

of a bnsee's manufactunng facibt.es The Agreement States i91pp. 9003070134. 52808.208

| TNs penodcal covers tne results of inspectons performed by reported no abncer,a! occurrences dunng the reportng penod. |i

the NRC's Vendor inspecbon Branch that have been d stnbuted The report a!so contarns informabon that updates some previ-|

| to the inspected organcatsons dunng the penod from Octocer ousty reported abnormal occurrences.

1989 throuch December 1989

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2 Main Citations and Abstracts

NUREG-0090 V12 N04: REPORT TO CONGRESS ON ABNOR- TNs journal includes all formal reports in the NUREG senesMAL OCCURRENCES October December 1989. * Offee for prepared by the NRC sta'1 and contractors; proceed ngs of con-AnaWis & Evaluation of Operational Data, Director. March ferences and workshops, as well as internabonal agreement re-1990. 2tpp. 9005040046 53622.224.

Section 208 of the Energy ReorgaN2aton Act of 1974 identh ports The entnes in this compilaton are indexed for access by

fies an abnormal occunence as an unscheduled inc6 dent ortrtle and abstract, secondary report number, personal author,subect, NRC organizaton for staff and intomabonal agree.fevent wNch the Nuefw Regulatory Commission determnes to

be significant from the standpoint of pubhc hea!th and safety ments, contractor, internabonal organtraton, and beensed facileyand reqvwes a quartedy report of auch events to be made to

Congress. TNs report covers the penod October 1 through De-NUREO-0304 V16 N01: REGULATORY AND TECHNICAL RE-cember 01,1989 For tNs reporting ponod, there were three ab-

normal occurrerres, none involving a bcentsd nuclear power PORTS (ABSTRACT INDEX JOURNAL) Compdabon For Fast

plant Two of the abnorma! occunences took place under othe' Quarter 1990, January. March. ' Dwision of Freedom of Informa-

NRC4ssued bcenses The fvst indved a medical diagnosuc tron & Publicabons Services (Post 890205) May 1990. 53pp.9006080185.54074:156misadmnstraton and the second involved a medcal therapy

misadmarsatratort The thrd abnorma: occunence was reported See NUREG 0304N14,N04 abstract.

by an Agreement State (Louisiana) and involved an overexpo".sure to an industrial radiographer. The report also contains in NUREG 0304 V15 N02: Rt:GULATORY AND TECHNICAL RE-PORTS (ABSTRACT INDEX JOURNAL) Compdabon Forformaton that updates a provously reported abnormal occur-

" Sec nd Oum MAmu * De of Fme d e-maton & Putshcations Servces (Post 890205). August 1990-

NUREG-0090 V13 N01: REPORT TO CONGRESS ON ABNOR. 49pp. 9010240391. 55495:277.MAL OCCURRENCESJanuary March 1990. * Offce for Analy, See NUREG 03C4.V14,N04 abstract.srs & Evaluaton of Operatonal Data, Dvector. July 1990,42pp.9008160096. 54947.261. NUREG-3304 V15 NO3: REGULATORY AND TECHNICAL RE.

Sectoi 206 of the Energy Reorgantzston Act of 1974 6denti. PORTS (ABSTRACT INDEX JOURNAL) Compilaton For TNrdfies an abnormal occunenco as an unscheduled incident or Quarter 1990, July-September. * Divison of Freedom of Informa-event wNch the Nuclear Regulatory Commiston determ nes to ton & Pubhcahons Services (Post 890205)- December 1990.be sigruficant from the standpoint of pubhc health and safety 44pp. 9012280235. 56257.334.and requires a quartetty report of such events to be made to See NURE3 0304,V14,N04 abstractCongress. This report covers the period January 1 throughMarch 31,1990. For tNs reporting penod, there were 10 abnor- NUREO-0?25 R '3: U.S. NUCLEAR REGULATORY COMMISSIONmal occurrences One involved the loss of vital ac power with a FUNCTIONAL ORGANt2ATION CHARTS Apnl 1,199n * Otc ofsubsequent reactor coolant system heat up at the Vogtle Unit 1 Personnel (Tost 870413) Apnl 1990. 64pp. WO5070012,power plant donng shutdown. The event was Irwesbgated by an 53656.347.NRC incident investigabon Team (in). The other rune abnormal

Functional organ 2aton charts for the U.S Nuclear Regulatoryoccunences involved nuclear malenal heensees and are de- Comnusson offcos, dwiscos, and branches are presented.scnbed in detail under other NRO4ssood hcenses: eight ofthese involved modcal therapy trusadministrabons; the other in-

NUREG 0325 R14: U S. NUCLEAR REGULATORY COMMtSSLONvolved the receipt of an LnsNelded radoactNe source at Amer-FUNCTIONAL ORGANt2ATION CHARTS August 15, 1990. 'sham Corporation in Buriington, Massachusetts. The latter eventOfc of Personnel (Post 870413) September 1990. 62pp.was also investigated by an NRC llT. No abnormal occurrences9010090054. 55333 027.were reported by the Agreement States. The report also cord

lains informabon that updates a previously reported abnormal See NUREG.0325,R13 abstract

occurrence.NUREG 0343 V01 R13: DIRECTORY OF CERTIFICATES OF

NUREG 0090 V13 N02: REPORT TO CONGRESS ON ABNOR. COMPLIANCE FOR RADIOACTIVE MATERIALSMAL OCCURRENCE &Apni-June 1990. * Office for Analysis & A S.Repod d NRC Approwd Packages. , Owison ofEvaluation of Operational Data, Drector. October 1990. 34pp. Safeguards & Transportabon (Post 870413) October 1990.9011200187. 55791:044. 475pp. 9011060134. 55624.341.

Section 208 of the Energy Reorganizaton Act of 1974 identi. This dwectory contains a Report of NRC Approved Packagesfies an abnormal occurrence as an unscheduled incident or (Volume 1), Certihcates of Comphance (Volume 2), and aevent wNch the Nuclear Regulatory Commisson deterrrunes to Report of NRC Approved Quahty Assurance Programs for Ra-be ogruficant from the standpoint of pubis health and safety doactive Matena's Packages (Volume 3). The purpose of thisand requtres a quarterly report of such events to be made to drectory is to make available a convervent source of informa-Congress This report covers the penod Aprd 1 through June tion on Quality Assurance Programs and Packagings wNch30,1990 The report discusses sis abnormal occurrences, none have been approved by the U S. Nuclear Regulatory Commis-invoNing a nuclear power plant. There were five abnormal oc- sion. SNpments of radioactwe matenal utihang these packag-'

currences at NRC licensees: (1) deficiencies in brachytherapy ings must be in accordance with the provtssons of 49 CFRprogram; (2) a radabon overexposure of a radographer; (3) a 173.471 and 10 CFR Part 71, as apphcable. In satisfying the re-medical diagnosbc misadministratiort (4) admirustrabon of I 131to a lactatng female with uptake by her infant; and-(5) a medi- quirements of Secton 71.12, it is the responsabihty of the bcens-

cal therapy misadmirustration. An Agreement State (Artzona) re- ees to insure themseNes that they have a copy of the current

pr fted an abnormal occurrence involving a medical diagnoste approval and conduct their transportabon activities in accord.

misadministrabon. The report also contains informahon that up- ance wih an NRC approved quahty assurance program.dates a previously reported abnorrnal occurrence

NUREG-0383 V02 R13: DIRECTORY OF CERTirlCATES OFNUREG-0304 'V14 N04: REGULATORY AND TECHNICAL RE-

A e ams O Co@anca Nson of Sa4- PORTS (ABSTRACT INDEX JOURN.\L) Annual CompilatonFor 1989. * Division of Freedom of Information & Pubhcations guards & Transponabon (Post 870413) October 1990. 634pp.

es (Post 890205). March 1990.152pp. 9004030145' 9AE 383 Vo ,R13 abstract-

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NUREG4363 V03 R10: DIRECTORY OF CERTIFICATES OFThe Safeguards Summary Event List provides bret summa-

COMPUANCE FOR RADIOACTIVE MATERIALS ries of hundreds of safeguards related events involving nuclear

PACKAGES Report or NRC Approved Oukity Assurance Pro- matenal or facilities regulated by the U S. Nuclear Regulatory

grams For Radudactive Materials Packages. * Dvison of Safe-Comtmssion. Events are desertbed under the categories: tomb-

guards & Transportaten (Post 870413). October 1990.177pp.related, 6ntrusion, missing / allegedly stol4A transportation relat-ed, tampering / vandalism, arson, firearms-related, radiologeal

9011060128. 55624:164- sabotage, non-radological sabotage, alcohol and drug related, iSee NUREG 0383,V01,R13 abstract. and miscellaneous. Because of puohc interest, the mescoltane, I

NUREG 0386 005 R05: UNITED STATES NUCLEAR REGULA, ous section also includes events reported involving source ma-TORY COMMISSION STAFF PRACTICE AND PROCEDURE teria; byproduct matenal, and natural uranium which areDIGEST. Commission, Appeal Board And L6 censing Board exempt from safeguards requirements. Informaton in the eventDecisions. July 1972. September 1989. * Offee of the General desenptons were obtained from onicial NRC roportsCounsel (Post 860701). March 1990, 660pp. 9004110232.

NUREG-0540 V11 N10: TITLE LIST OF DOCUMENTS MADE$3351:319' son number 5 of the fifth editon of the NRC Prac-PUBUCLY AVAILABLE. October 1-01,1989 * Dvtsson of Free-This Revitce and Procedure Dgest contains a digest of a number of dom of Informaton & Pubhcatons Servees (Post 890205) Jan-Commisson, Atomic Safety and Licensing Appeal Board, and uary 1990. 326pp. 9002120142. 52581:253.Atoms Safety and UCensing Board decissons issued dunng the This document is a monthly subhcator containing desenp-penod July 1,1972 to September 30, 1989, Interpreting the tions of informaton recetved anc generated by the U.S. NuclearNRC a Rules of Practice in 10 CFR Part 2. Regulatory Commisson (NRC). This information includes (1)

NUREG4386 D05 R06: UNITED STATES NUCLEAR REGULA-docketed maternal associated wih crvilian nuclear power plants

TORY COMMISSION STAFF PRACTICE AND PROCEDUREand other uses of radoactive natonals, and (2) nondocketed

DIGEST.Commsssson, Appeal Board And Licensing Board matenal recetved and generatec by NRC pertinent to its role as

Decisons.Jufy 1972 Docember 1989. * Office of the General a regulatory agency The folcong indexes are included Per-Counse) (Post 860701). June 1990. 672pp. 9007120220. sonal Author, Corporate Sour.:e, Report Number, and Cron

Reference to Pnncipal DocurNnts.54473.203

This Revision 6 of the fifth editon of the NRC Practee and NUREG-0540 V11 N11: TIS.E UST OF DOCUMENTd MADEProcedure D: gest contains a digest of a number of Comtmssion, PUBLICLY AVAILABLE. NOVEMBER 1 30, 1989 * Dvision ofAtomic Safety and Licensing Appeal Board, and Atomic Safety Freedom of Information & Pubhcatione Sonnees (Post 890205).and Licensing Board decissons assued dunng the penod Jufy 1, March 1990. 335pp. 9004000177, 53309.2361972 to December 31,1989, interpreting the NRC's Rules of See NUREG 0540,V11,N10 ?bstract.Practce in 10 CFR Part 2.

NUREG4386 005 R07: UNITED STATES NUCLEAR REGULA- HUNEG-0540 V11 N12: TITLE LIST OF DOCUMENTS MADE

TORY COMMISSION STAFF PRACTICE AND PROCEDUREPUBLICLY AVAILABLE. DECEMBER 1 31,1989 * Divison of

DIGEST.Commiss#on, Appeal Board And ucensing Board Freedom of information & Pubhcatons Sennees (Post 890205).Decisions. July 1972 . March 1990. * Office of the General Apdl 1990. 230pp. 9005210149. 53887.204,

Counsel (Post 860701). August 1990. 655pp. 9009120095. See NUREG 0540,V11,N10 abstract.

55125:145 NUREG4540 V12 N01: TITLE LIST OF DOCUMENTS MADEThis Revision Number 7 of the fifth edition of the NRC Prac- PUBLICLY AVAILABLE January 1 31,1990. * Dvision of Frec-

tee and Procedure Dgest contains a digest of a number of dom of Information & Pubhcations Services (Post 890205). ApnlCominssion. Atomac Safety ar". Leensing Appeal Board, and 1990. 332pp. 9005210255. 53889:146Atomic Safety and Licensing Board decisons lasued dunng the See NUREG-0540,V11,N10 abstract.penod July 1,1972 to March 31,1990, interpreting the NRC'sRules of Practice in 10 CFR Part 2. NUREG4540 V12 NO2: TITLE LIST OF DOCUMENTS MADE

NUREG4386 005 R08: UNITED STATES NUCLEAR REGULA-PUBUCLY AVAILABLE. February 1 28, 1990 * Dvision of Frae-

TORY COMMISSION STAFF PRACTICE AND PROCEDUREdom of information & Pubhcations Services (Post 890205), June

DIGEST. Commission. Appeal Board And Licensing Board 1990. 304pp. 9006290112, 54324:008.

Decisons.Jdy 1972 June 1990, * Office of the General Coun- See NUREG 0540,V11,N10 abstract.

set (Post 860701). November 1990. 682pp. 9012280169. NUREG4540 V12 NO3: TITLE LIST OF DOCUMENTS MADE56226:027. PUBUCLY AVAILABLE March 1 31, 1990. * Dvision of Freo-

This Revision 8 of the fifth edition of the NRC Practice and dom of information & Pubhcations Services (Post 800205). JufyProcedure Dgest contains a digest of a numoer of Comrmssion, 1990. 453pp. 9008070384. 5484 h012.AtorWe Safety and Ucensirg Appeaf Board, and Atomic Safety See NUREG4540,V11,Nt0 abstract.and Licensing Board decisions lasued dunng the pered July 1,1972; to June 30,1990, interpreting the NRC's Rules of Prac- NUREG4540 V12 N04: TITLE LIST OF DOCUMENTS MADEtce in 10 CFR Part 2' PUBLICLY AVAILABLE.Apol 130,1990 * Division of Freedom

NUREG4430 V09 N02: LICENSED FUEL FACluTY STATUSof informaton & Publicatens Services (Post 690205) July 1990.

REPORT. inventory Otterence Data. July 1988 June 1989.(Gray 322pp. 9008160107. 54049.0 f 6.

Book II) * Office of Nuclear Matenal Safety & Safeguards. Apnl See NUREG4540,VI1,N10 abstract.

1990.18pp. 9005210145 53861'.345. NUREG4540 Vl2 N05: TITLE LIST OF DOCUMENTS MADENRC is committed to the pedodic pubhcation of licensed fuel PUBUCLY AVAILABLE.May 1 31,1990.* Dmson of Freedomfa$ ties inventory difference data, following agency review of of Informaton & Pubbcations Services (Post 890205). July 1990.the information and complet>on of any related NRC investiga. 4 f 4p0. 0008160102. 54947.322.tions. Information in this report includes inventory difference See NUREG 0540,V11,N10 abstract.data for active fuel fabncation facihties possessing more thanone effective kilogram of lugh ennched uranium, low enriched NUREG4540 V12 N06: TITLE UST OF DOCUMENTS MADEuranium, plutonium, or uranium 233. PUBLICLY AVAILABLE. June 1 30, 1990. * DMson of Freedom

NUREG-0525 R16: SAFEGUARDS SUMMARY EVENT USTof Informaton & Publications Sennces (Post 890205). August

(SSEL). Dvision of Safeguards & Transportation (Post 1990. 3J3pp. 9009040041. 55050:227.*

870413). July 1990. 369pp. 9009070011. 55070:128 See NUREG.0540,V t 1,N IO abstract.

-- - - - . . . _ _ - _ _ _ - - --

4 M:In Citations and Abstracts

NURE04540 V12 N07: TITLE LIST OF DOCUMENTS MADE NUREG-0750 C102: INDEXES TO NUCLEAR REGULATORYPUBLICLY AVAILABLE. July 131,19% * Dmsion of Freedom COMMISSION ISSUANCES. January 1,1980 Through Decemberof Informatm & Pubicabons Servces (Post 890205). Septem- 31.1985, * D# vision of Freedom of Informaton & Pubhcatonsber 1990. 364pp. 9009210224. 55232.198.

Services (Post 890205). November 1989.1,080pp. 9003160045.See NUREG 0540,V11,N10 abstract 52958.212.Digests and endexes for issuances of the Comrwssm, the

NUREG 0540 Vit Hos: TITLE UST OF DOCUMENTS MADE Atome Safety and Lconsing Appeal Panel, the Atomc SafetyPUBLICLY AVAILABLE. August 1 31,1990. * Dmseon o: Free-and ucensing Board Panet, the Administrabve Law Judges, the

dom of Informaton & Pubhcatons Seryces (Post 890205). Oe- Dwators' Decisions, and the Dervals of Pettsons for Rulomak-tober 1990. 319pp,9010300245. 5555h001, ing are presented."

NUREG4750 V30101: INDEXES TO NUCLEAR REGULATORYNUREG 0540 V12 N09: TITLE LIST OF DOCUMENTS MADE COMMISSON ISSUANCESJuly-September 1989= ' Desion of

PUBLICLY AVAILABLE. September 1 30,1990. Dmson of Freedom of information & Pubhcatons Servces (Post 890205).*

Freedom of Informaton & Publicatons Servees (Post 890205). February 1990. 50pp. 9004100439. 53350:238.November 1990. 254pp. 9011270230. 55855:109 See NUREG 0750.C102 abstract

See NUREG.0540,V11,N10 abstract.NUREG4750 V30102; INDEXES TO NUCLEAR REGULATORY

NUREG 0540 V12 N10: TITLE LIST OF DOCUMENTS MADE COMMISSION ISSUANCES. July December 1989. * Dmsion ofPUBLICLY AVAllABLE. Octote 1 31, 1990. * Dvision of Free. Freedom of Informaton & Pubhcatons Servees (Post 890205).dom of Informaton & Pubhcabons ScMces (Post 890205). Do, W N 87pp M120163. W86:237.cember 1990. 266pp. 9012280250. 56269.270. See NUREG 0750,C102 abstract

See NUREG-0540,V11,N10 abstractNURE04750 V30 N01: NUCLEAR REGULATORY COMMISSON

NUREG 0650 R01: PUBLISHING DOCUMENTS IN THE NUREG" '

APo 8 205)m f In ma &P at s rvSERIES. * Dmsion of Freedom of informabon & Pub 8cabonsServices (Post 890205). December 1990.150pp, 9101110201. vary 1990. 89pp. 9004030109. 53229:208.56344:148. Legalissuances of the Commission, the Atomic Safety and U.

This report provides guidelines to staff, contractors, and censing Appeal Panel, the Atoms Safety and Ucensing Boardgrantees who prepare documents to be pubhsned in the Panel, the Admstvstrahve Law Judges, and NRC Program Of-

fees are presented.NUREG series for the U.S. Nuclear Regulatory Comrwason(NRC). Adhering to these guidelines wdl improve the readabihtyand promote the uniformity of NRC pubhcates. In additort ad- NUREO.0750 V30 NO2: NUCLEAR REGULATORY COMMISSION

henng to these guidehnes wdl ensure these authors comply with|SSUANCES FOR AUGUST 1989. Pages 85-165. * Dvison ofFreedom of Informaton & Pubications Sennces (Post 890205),the NRC's pubicatons poicy and procedures. This report re- January 1990. 85pp. 9004030047. 53230.007,

vises and supersedes NUREG 0650, "Techrvcal Wrtbng Style See NUREG4750,V30,N01 abstract.Guede," originally pubbshed in November 1979. For the convorysence of users, it repeats informacon about NRC's preferred NUREG4750 V30 NO3: NUCLEAR REGULATORY COMMISSONstyne for hsting references, with minor changos, that was pub. ISSUANCES FOR SEPTEMBER 1989. Pages 107 229. * Dvbthed in NUREG 1379, "NRC Editonal Style Guide." NUREG.

soon of Freeoom of Informaton & Pubhcatons Servtces (Post1379 superseded Supplement I to NUREG-0650. 800205). January 1990. 68pp. 9004030101. 53229.299.See NUREG 0750,V30,N01 abstract

NUREG-0713 V09: OCCUPATIONAL RADtATION EXPOSURE ATCOMMERCIAL NUCLEAR POWER REACTORS AND OTNER NUREG-0750 V30 N04: NUCLEAR REGULATORY COMMISSIONFACILITIES 1987, Twentieth Annual Report BROOKS,0.G. Orvi. ISSUANCES FOR OCTOBER 1989. Pages 231323. * Derisionsun of Regulatory Apphcations (Post 870413). HAGEMEYER,0. of Freedom of Information & Pubhcatons Services (PostScience Apphcations Internabonal Corp. (formerly Science Ap. 890205). January 1990.100PP,9004030044. 53230:096.phcabons, Inc.). November 1990. 275pp. 9011270235. See NUREG-0750,V30,N01 abstract.5585 N

This report summanzes the occupatonal radiabon exposure NUREG4750 V30 N05: NUCLEAR REGULATORY COMMISSONbiormaton that has been reported to the NRC a Radiation Ex- ISSUANCES FOR NOVEMBER 1989. Pages 325-708. * Dmstonposure informabon Reporong System (REIRS) by nuclear power of Freedom of inhabon & Pub 6cabons Services (Postfacihbes and certain other categones of NRC hcensees dunng 890205). March 1990. 393pp. 9004100444. 53350-280.the years 'iD69 through 1987. The bulk of the data presented in See NUREG-0750,V30,N01 abstract

the report was obtained from annual radiabon exposure reportssubrntted in accordance with the requirements of 10 CFR NUREG4750 V30 N06: NUCLEAR REGULATORY COMMISSION20,407 and the techrucal specificabons of nuclear power plants- ISSUANCES FOR DECEMBER 1989. Pages 709-811. ' Dvision

of Freedom of Informabon & Publicabons Services (PostD:ta on workers terminabng ther employment at certain NRCAcensed facihties were obtained from reports submitted pursu' 890205). Apnl 1990.105pp. 9007120158. 54486.310.

ant to 10 CFR 20.408 The 1987 annual reports nubrntted by See NUREG-0750,V30,N01 abstract., about 460 bcensees indicated that approximately 23G00 inde

NUREG-0750 V31101: INDEXES TO NUCLEAR REGULATORYi-viduals were morvtored, 211,000 of whom were monitored by

( nuclear power facihbes. They incurred an average indMdual COMMISSON ISSUANCES. January March 1990. * Dvison ofFreedom of Informabon & Pubhcatons Services (Post 890205).l dose of 0,19 rem (cSv) and an average measurable dose of July 1990. 53pp. 9009170093. 55202.102.

| 0.39 rem (cSv). Termination radiation exposure reports were See NUREG-0750,Cl02 abstract(nalyzed to reveal that about 86,300 indmduals completed theiremployment with one or more of the 460 covered hcensees

NUREG 0750 V31102: INDEXES TO NUCLEAR REGULATORYduring 1987. Some 81,600 of these indmduals terrnnated from COMMISSION ISSUANCES. January June 1990. * Dmsion ofpower reactor facihtaes, and about 8,700 of them were consid-

Freedom of informaton & Pubhcabons Services (Post 890205).ered to be transient workers who received an average dose of September 1990. 8 tpp. 9010230091. 55470:048.0.60 rem (cSv). See NUREG-0750,C102 abstract.

_ . . - .- ._ - .


NUREG4760 V31 N01: NUCLEAR REGULATORY COMMISSONproJm wty 40 maes southwest of Fort Worth, Texas. This sup-

ISSUANCES FOR JANUARY 1990. Pa9es 1130 * Divison ofpiemW reports the status of certain issues that had not been

Fromhm of Informaton & Pubicatons Servees (Post 890205)resolved at the time of pubhcaten of the Safety EvaluabonReport and Supplements 1,2,3,4,6,12, and 21 to that report.

April 1990,135pp. 9007 f 20154. 54487:064. This supplemont also includes the evaluatons for leonsingSee NUREG-0750,V30,N01 abstract ttems res tved since Supplement 21 was issued Supplement 5

NUREG 0750 V31 N02: NUCLEAR REGULATORY COMMISSION has been cancelled Supplements 7 through 11 were kmtted toISSUANCES FOR FEBRUARY 1990. Pages 131+195. * Omsson N staH wabay of anegatcos inveshgated by N NRCof Freedom of Informabon & Publications Servces (Post Technical Reve team. Supplement 13 presented the staff's890205). Apnl 1990. 70pp, 9007120148. 54487:199. evaluaton of * - amanche Peak Response Team (CPRT) Pro-

See NUREG4750,V30,N01 abstract gram Plan, m , was formulated by the apphcant to resolve

NUR G 076a V31 NO3: NUCLEAR REGULATORY COMMISSONvarcus constructen and des gn issues raised by sources exter-

(SSUANCES FOR MARCH 1990,Pages 197 332. ' Dmrdon of nal to the apphcant. Supplements 14 through 20 presented the

Freedom of Information & Pubhcatens Services (Post 890205).staff's evaluaton of the applicant's Conective Action Programand CPRT actrvit>es. Items identified in Supploments 7,8,9, io,

May 1990.139pp. 9007'20122. 54487:268. 11,13,14, and 15 through 20 are not included in thF supple-See NUREG 0750,V30,N01 abstract. ment, except to me ecent mat my aNect me agave FoafNUREG 0750 V31 N04: NUCLEAR REGULATORY COMMISSION Safety Anatysis Report

ISSUANCES FOR APRit.1990 Pages 333-370. * Dmsson ofFreedom of informaton & Puhhcations Servces (Post 890205)- NUREG 0797 S23: SAFET) EVALUATION RENAT RELATEDJune 1990. 44pp. 9007120119. 54488:047. TO THE OPERATION Of COMANCHE PE sK STEAM ELEC-

See NVREG 0750,V30,N01 abstract TRIC STATION, UNITS 1 AND 2. Docket Ns. 50-445 And 50-446.(Texas Utihties Electnc Company,et af.) * Comanche Peak

HUREG-0750 V31 N05: NUCLEAR REGULATORY COMMISSIONISSUANCES FOR MAY 1990.Pages 371481. * Dmsion of

Project Dmsson (890101 400602). February 1990. 102pp.

Freedom of informabon & Pubhcatons Services (Post 890205)9003070170. 52808.299.

Supp6ement 23 to the Safety Evaluaten Report related to theJuly 1990.117pp. 9008070350. 54863:075. operabon of the Comanche Peak Steam Electnc Stabon. Units

See NUREG-0750,V30,N01 abstract. 1 and 2 (NUREG 0797), has been prepared by the Office of Nu-

NUREG-0750 V31 N06: NUCLEAR REGULATORY COMMISSION clear Reactor Regutabon of the U.S. Nuclear Regulatory Com-ISSUANCES FOR JUNE 1990.Pages 483 604. * Division of missen. The facility is located in Somervell County, Texas, ap-

Freedom of informaton & Pubhcatons Sevees (Post 890205)- proximately 40 miles southwest of Fort Worth, Texas. This sup-August 1990.133pp. 9009040088. 55046.178- piement reports the status of certain lasues that had rot been

See NURES0750,V30,N01 abstract resoNed at the bme of pubhcation of the Safety Evaluation

NUREG 0750 V32101: INDEXES TO NUCLEAR REGULATORYReport and Supplements 1, 2, 3, 4, 6,12, 21, and 22 to thatrepet This supplement also includes the evaluatons for Igons-

COMMISSION ISSUANCES. July-September 1990. * Omsion of mg items resoNed since Supplement 22 was issued. Supple-Freedom of informaton & Pubhcahons Services (Post 890205). ment 5 has been cancelled. Supplements 7 through 11 wereDecember 1990.3600. 9101110235. 56342:204. hm: led to the staff evaluaton of allegatons investgated by the

See NUREG-0750,Cl02 abstract NRC Technical Review Team. Supplement 13 presented the

NUREG-0750 V32 N01: NUCLEAR REGULATORY COMMISSION staff's evaluabon of the Comanche Peak Res6cnse TeamISSUANCES FOR JULY 1E 10.Pages 155. * Dmson of Free- (CPRT) Program Plan, wnich was lomulated by the appbcant to

dom of information & Pubhcahons Sennces (Post 890205) ress tve vanous construction and design issues raised byAugust 1990. 62pp. 9009130045. 55194:041. sources extemal to the appicant. Supplements 14 through 20

See NUREG-0750,VW N01 abstract. presented the staff's evaluation of the appncants CorrectiveActon Program and CPRT actmbes. Items identified in Supple-

NUREG-0750 V32 NO2: NUCLEAR REGUt.ATORY COMMISSION ments 7,8,9,10,11,13, and 15 through 20 are not included inISSUANCES FOR AUGUST 1990 Pages 56-120. * Dmson of this supplenent, except to the extent that they affect the apph-Freedom of informabon & Pubhcatons Services (Post 890205), cant's F6ra Safety Analysis ReportOctober 1990. 8000. 9010310170. $$579-263.

See NUREG-0750,V30,N01 abstract. NUREG-0797 S24: SMETY EVALUATION REPORT RELATED

NUREG-0750 V32 N03: NUCLEAR REGULATORY COMMISSION TO THE OPERATION OF COMANCHE PEAK STEAM ELEC-ISSUANCES FOR SEPTEMBER 1p90. Pages 129199. * DivL TRIC STATION UNITS 1 AND 2. Docket Nos. 50445 And 50-

son of Freedom of Informaten & Pubhcatons Services (Post446.(Texas 'Mttes Electnc Company.et al.) * Comanche Peak

890205). November 1990. 77pp. 9011290035. 55880:02R Protect Dmsion (890101 900602). Apnl 1990, - 174pp.

9005180159. 53861:137,See NUREG-0750,V30,N01 abstract. - Supplement 24 to the Safety Evaluabon Report related to theNUREG-0750 V32 N04: NUCLEAR REGULATORY COMMISSION operation of the Comanche Peak Steam Electric Stabon, Units

ISSUANCES FOR OCTOBER 1990 Pages 201331. * DMson 1 and 2 (NUREG 0797), has been prepared by the Offee of Nu-of Freedom of Informaton & Publicabons Servces (Post clear Reactor Regulaten of the U.S. Nuclear Regulatory Com-890205). December 1990.140pp. 9101110238. 56342:064. me h fac% 4 WM m hM hny Nas, am

See NUREG4750,V30,N01 abstract, proximately 40 miles southwest of Fort Worth, Texas. This sup-

NUREG-0797 S22: SAFETY EVALUATION REPORT RELATEDpiement reports the status of certain issues that had not been

TO THE OPERATION OF COMANCHE PEAK STE/ M ELEC-resoNed at the bme of pubhcabon of the Safety Evaluauon

TRIC STATION, UNITS 1 AND 2. Docket Nos. 50 445 And 50- Report and Supplements 1, 2, 3, 4, 6,12, 21, 22, and 23 to that

446 (Texas Utihties Electric Company,et al.) ' Comanche Peak report This supplement also includes the evaluatons for hcens-

Project OMson (890101 900602). January 1990 369pp. Ing items resoNed since Supplement 23 was issued. Supple-ment 5 has been cancellod. Supplements 7 through 11 were

9003070163. 52814:220. hmited to the staff evaluaton of altogations invest > gated by theSupplement 22 to the Safety Evaluaton Reoort related to the

operaton of the Comanche Peak Steam Electnc Stabon, UnitsNRR Technscal Review Team Supplement 13 presented the

1 and 2 (NUREG-0797), has been prepared by the Office of Nu-staff's evaluaton of the Comanche Peak Response Team(CPRT) Program Plan, which was formulatad by the hcensee toclear Roactor Regulabon of the U.S. Nuclear Regulatory Com. resolve vanous constructon and design issues raised byrnsssion. The facihty is located in Somervelt County, Texas, ap-

. - - - _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ - _ - _ _ _ - _ _ _ - _ _ _ _ _ _ _ _

1I


sources extemal to the bconsee. Supplements 14 through 20 NURE0 0837 Viv M3: NRC ILD DIRECT RADIATION MONbpresented the staff's evaluation of the beensee's Corrective TORNG NETWOR(.Prryess Report Jufy-September 1990.Action Program and CPRT activities. hems identified in Supple-

STRUCKMEYER,R ; WNAMARA,N= Hegion 1 (Post 820201)-ments 7,8,9,10,11,13, and 15 through 20 are not included in Decembet 1990, 230pp. 9101110198. 56356'001.thrs supplement, except to the extent that they affect the bcens-ee's hnal Safety AnaYsts Report. This report provides the status and resutts of the NRC Ther.

motuminescent Dosimeter (TLD) Direct Ra$aton MonitonngNUREG-0800 03.6.1 R2: STANDARD REVIEW PLAN FOR THE Network. It presents the radiabon levels measat in the vicinity

REVIEW OF SAFETY ANALYSIS REPORTS FOR NUCLEAR of NRC heensed facilities throughout the country for the thirdPOWER PLANTS LWR EditiortRevision 2 To SRP Secte quarter of 1990.3.6.1,%nt Design For Protection Auros in Fluid Splems Outside..~ pinst Postulated Pong FaibOffice of Nuclear Reactor NUREG 0847 S05: SAFETY EVALUATION REPORT RELATEDRegulaton, Drector (Post 870411). October 1990. 29pp TO THE OPERATION OF WATTS BAR NUCLEAR9010310161. 55629.063, PLANT, UNITS 1 AND 2. Docket Nos. 50-390 And 50-391.(Terv

The revis#on of SAP Section 3.8.1 (Revision 2), Plant Design nessee Valley Authonty) TAM,P.S. Divtsion of Reactor Projects -for Protecton Against Postulated Pong Failures in Fluid Sys. 1/II (Post 870411). November 1990. 109pp. 9011260026.tems Outside Containment, ehmnated jet impengement offects 55798.146.On essential equipment associated with the artHtrary one square Supplement No. 5 to the Safety Evaluation Report for the ap-foot break in the break exclusion (superpipe) tone of main phcabon filed by the Tennessee Valley Authonty for hcense tosteam and feedwater knes outside the containment, modified operate Watts Bar Nuclear Plant, Units 1 and 2. Docket Nos.the background section of SPLB 31 to bnng the background up 50-390 and 50-391, located in Rhea County, Tennessee, hasto date, and claathed the staff's posttron on postulated single been prepared by the Office of Nuclear Reactor Regulation ofactive failures concurrent with a postulated pipang failure in one the Nuclear Regulatory Commisson The purpose of this sup-of two or more redundant trarns of dual-purpose moderate- piement is to update the Safety Evaluaton of (1) aMtonal in-energy essenbal system as defined in BTP SLPB 3-1. formaton submitted by the apphcant since Supplement No. 4

NUREO-080017,3 R30: STANDARD REVIEW PLAN FOR THE $ns 'e "nent fo$a)ssuREVIEW OF SAFETY ANALYSIS REPORTS FOR NUCLEARPOWER PLANTS. LWR EditortRevision 0 To SRP Sect 6on 17.3,

NUREO 0496 SO9: SAFETY EVALUATION REPORT RELATED 'p" Quality Assurance Program Desenpton." ' Division of Licens-TO THE OPERATION OF SEABROOK STATION, UNITS 1 ANDee Performance & Quahty Evaluabon (Post 870411). August

1990. 20pp. 9009070001. 55071:137 2 Docket Nos. STN-50-443 And STN 50-444.(Pubhc ServiceSRP Secton 17.3, "Quallty Assurance Program Desenpton," Company Of New Hampshire) * Division of Reactor Protects t/

4

io a new section in Chapter 17. it puts in place a performance' || (Post 870411). March 1990.166pp 9004030159 53229.042.oriented quality assurance program review plan that (1) mini- This report is Supplement No 9 to the Safety Eva untons

mires the current fragmentation and overtap of the self-assess- Repo*t (SER) (NUREG 0896, March 1983) for the apphcat>onment funcbon responsMiities, including safety comrnittee activb filed by the Pubhc Service Company of New Hampshire, et ai,ties, audits, and other independent assessments, (2) semphfss for heenses to operate Seabrook Station, Units 1 and 2 (Docketthe formal clanfies the Intent, and consondates the text of the Nos STN 50-443 and STN 50-444) It has been prepared bypresent SRP Sectons 17.1 and 17.2, (3) places emphasis on the Office of Nuclear Reactor Regulation of the U.S Nuclearmanagement, portormance/venficaton, and self-assessment, Regulatory Commission and provides recent informaton onthe three components of quahty assurance, and (4) permits the o en items id.wstifwxt in the SER The facihTY is located in Sea-use of up to-date industry consonvus standards, w HampMre Subect to f avoratde resolution of thet

items discussed in this eport, the staff concludes that the facsh-NUREG-0837 V09 N04: NRC TLD DIRECT RADIATION MONI. ty can be operated by 'he apphcant withcM endangenng theTORtNG NETWORK. Progress Report. October December 1989 health and safety of the pubhc,

STRUCKMEYER,R; MCNAMARA,N. Regon 1 (Post 820201tMarch 1990. 326pp. 9004100322. 53343 076

NUREO-0933 S11: A PRIORITIZATION OF GENERIC SAFETY'

This report provides the status and results of the NRC Ther. ISSUES. EMRIT,R.; RIGGS R.; MILSTEAD,Wa et at Dmston ofmolurnnescent Dosimeter (TLD) Direct Radiabon Monitonng Regulatory Apphcatons (Post 870413). July 1990. 180pp.Network. It presents the radiation levels measured in the viciruty 9008070346. 54862:255.of NRC heensed facihty sites throughout the country for the The report presents the pnonty rankirigs for genene safotyfourth quarter of 1989.

issues related to rvxtear power plants. The purpose of theseNUREG4837 V10 N01: NRC TLD DIRECT RADIATION MONI- " ** '# " ##" * *

TORING NETWORK. Progress Report. January-March 199p # ** * * " " * #8 "STRUCKMEYER,k; MCNAMARA,N Region 1 (Post 820201f signahcant potent al for reducing nsk. The safety pnonty rankingsJune 1990. 227pp. 9007120185. 54470-336. am W , aM N and han been assigmd,

Thes report provides the status and results of the NRC 'her- n me a f ns sig ance eshmates, t% rato of nsk tomotuminescent Dosmeter (TLD) Duect Racaton Monitonng costs and other 6mpacts estimated te result if resolutions of theNetwork. It presents the radiaton lei eis measured in the vienty safety issues were implemented, and the consideration of un-of NRC licensed facilites throughout the country for the first certaintaes and other quantitative or Quahtative factors. To the

. quarW of 1990. extent practical, estimates are quantitative

NUREG-0837 V10 N02: NRC TLD DIRECT RADIATION MONI. NUREG 0936 V08 N04: NRC REGULATORY AGENDA.OuartertyTORING NETWORK. Progress - Report. Apnt-June 1990, Report. October December 1989 ' Division of Freedom of infor,STRUCKMEYER.R; MCNAMARA,N. Region 1 (Post 820201). mation & Pubhcanons Services (Post 890205) January 1990.Seotember 1990. 227pp. 9010090064. 55319 345. 134pp 9003070131. 52808 074.,

Thts report provides the status and resutts of the NRC Ther- The NRC Regulatory Agenda is a compilation of all rules onmoluminescent Dosimeter (TLD) Dweet Radiation MonitonngNetwork, it presents the radiaton levels measured in the vienty

which the NRC has proposed or is considenng action and a

of NRC heensed facihtses throughout the country for the second petitions for rutomaking which have been received by the Com-quarter of 1990. masson and are pending dispositiori by the Commission. The

Regulatory Agonda is updated and issued each quarter.

__ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ . _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ ___ _ . . _ _ _ _

. . - -- -. ._ - . . - - -


NUREO 0936 V09 N01: NHC REGULATORY AGENDA.Ouarterty with respect to these enforcement actons. It is antcipated that

Report. January March 1990. * Drvison of Freedom of informa.the information 6n tNs pubication will be widety disseminated to

ton & Pubhcatons Sennees (Post 890205). April 1990.145pp. managers and employees engaged in actMties konsod by theNRC, so that actions can be taken to improve safety by avoid-

9005210250. 53889 001.See NUREG-0936,V08.N04 abstract. ing future violat ons similar to those described in this pubhca- )

*NUREG-0936 V09 N02: NRC REGULATORY AGENDAQuarterly

Report,AprilJune 1990. * Dmsion of Freedom of Informaton & NUREG 1021 R06: OPERATOR LICENSING EXAMINER ST AND-Pubhcations Services (Post 890205) July 1990 153pp- ARDS DEAN.W. Division of Licensee Performance & Quahty

9008140487. 54925 129- Evaluaton (Poet 870411) June 1990. 315pp. 9006290065.See NUREG 0936,V08,N04 abstract. 54321:339.

The Operator Licensing Examiner Standards provide poleyNUREG-0836 V09 N03: NRC REGULATORY AGENDAOua-terty and guidance to NRC examiners and estabhsh the procedures

Report,JuySeptember 1990. ' Devtsion of Freedom of informa-ton & Pubications Services (Post 890205) October 1990.

and practicos for examening and hcensing of apphcants for NRCoperator heensos pursuant to Part 55 of Title 10 of the Code of

151pp. 9011090217. 55661:164 Federal Regulatons (10 CFR 55) They are intended to assistSee NUREG 0936,V08,N04 abstract. mam a fa@ osees s e mam

NUREO.0940 V06 N04: ENFORCEMENT ACTIONS. SIGNIFbing process better and to provide for equitable and consistentCAN ACTIONS RECOL Progress adm6nistration of exam 6natone to all apphcants by NRC examin-ReportOctober. December 1989. ,VED.QuartertyOle of Enforcem90t (Post ers These standards are not a substtuto for the operator h-970413) March 1990. 289pp,9005040056. 53623.190. censing regulatona and are subject to revision or other intemal

This conplation summarizes significant enforcement actions o erator licensing program changes. As appropnate, thesethat have been resolved dunng one quarterty penod (October - ggg g g gg ggg g g, ,December 1989) and includes copies of letters, Notees, and ed mm mawOrders sent by the Nuclear Regulatory Commesson to bconsees we operator hconsing activnes.with respect to these enforcement actons. Also included are anumber of enforcement actions that had been previously re- NUREO 1100 V06: DVDGET ESTIMATES Fiscal Year 1991. * De-solved but not published in this NUREG. It is anteipated that vison of Budget & Analysis (Post 890205). January 1990.the informaaon in tNs pubhcation will be widely disseminated to 208pp. 9002120028. 52610:231.managers and employees engaged in actmties heensed by the This report contains the fiscal year budget justificebons toNRC, so that actions can be taken to improve safety by avoid- Congress. The budget provides estimates for salanes and ex-ing isture violations samnar to those described in tNs pubhca- penses and for the Office of the inspector General for fiscalton. year 1991.

NUREG 0940 V09 N01: ENFORCEMENT ACTIONS. SIGNIFl' NUREO 1125 V11: A COUPILATION OF REPORTS OF THE AD-CANT ACTIONS RESOLVED.Ouarterty Progress VISORY COMMITTEE ON REACTOR SAFEGUARDS.1989Report. January March 1990. Ofc of Enforcement (Post Annual. * ACRS Advisory Committee on Reactor Safeguards.870413). May 1990, 403pp. 9006290085. 54320'263 April 1990.150pp. 9005210245. 53888.210.

This compilation summan7es significant enforcement actions This compitabon contains 54 ACRS reports submitted to thethat have been resolved dunn0 one quarterfy penod (January - Commission or to the Executrve Director for Operations during

; March 1990) and inciudes copies of letters, Notices, and Orders calendar year 1989. It also includes a report to the Cong ess onsent by the Nuclear Regulatory Commission to hcensees with the NRC Safety Research Program. All reports have been made

| respect to these enforcement actons. Also included are e available to the pubhc through the NRC Pubhc Document Roomt

number of enforcement actions that had been previously re- and the U.S. Library of Congress. The reports are divided intosoMJ but not published in tNs NUREG. It is antcipated that two roups: Part 1: ACRS Reports on Project Reviews, and Partthe informabon in (NS pubhcation will be wdely disseminated to 2: ACRS Reports on Genenc Subjects Part 1 contains ACRSmanagers and employees engaged in actmties heensed by the reports alphabetized by project name and witNn project name

j NRC, so that actions can be taken to improve safety by avoid- m M ordet PM 2 Men h p h ht future violatons similar to those desenbod 'i this pubhca- e d m W e MW m

by chronologscal order.

NUREO 0940 V09 NC2: ENFORCEMENT ACTIONS: SIGNIFI- NUREO-1145 V06: U S. NUCLEAR REGULATORY COMMISSIONCANT ACTIONS RESOLVED.Ouarterty Progress Report,Apnp 1989 ANNUAL REPORT. * Office of Administrabon (PostJune.1990. * Ofc of Enforcement (Post 870413), September 890205). July 1990. 248pp. 9000040001, 55017.155.1990. SC2pp. 9009250082. 55242:170. TNs report covers the major actmtses, events, decisions, and

TNs compilation summanzes significant enforcement actions planning that took place dunng fiscal year 1989 witNn the U.S.that have been resolved dunng one quarterly period (April - Nuclear Regulatory Commission (NRC) or involving the NRC.June 1990) and includes copies of letters, Nobces, and Orderssent by the Nuclear Regulatory Commission to hcensees with NUREG 1150 V01: SEVERE ACCIDENT RISKS.AN ASSESS-respect to these enforcement actions it is anticipated that the MENT FOR FIVE U S. NUCLEAR POWER PLANTS. Final Sum-6nformabon in tnis pubhcation will be widely diseeminated to mary Report. * Division of Systems Research (Post 880717)-managers and employees engaged in actmt es beensed by the December 1990. 287pp. 9101110232. 56342:237.NRC, so that act6ons can be taken to improve safety by avoid- TNs report summari2es an assessment of the risks fromtng future vioiations similar to those desenbod in this pubhca- severo accidents in f ve commercial nuclear power plants in thetea United States These nska are measured in a number of ways,

NUREG-0940 V09 N03: ENFORCEMENT ACTIONS: SIGNIFl-includong: the estimated frequencies of core damage accident.

CANT ACTIONS RESOLVED Ouarterty Progress Report July- from intomally initiated accidents, and externally tnetaated accb

September 1990. * Ofc of Enforcement (Post 870413) Novem- dents for two of the plants, the performance of containment

ber 1990 382pp 9012110322 56044'308. structures under severe accident loadings; the potent al magni-

TNs compilation summarizes significant enforcement actions tude of radionucide releases and offsite consequences of such

that have been resolved dunng one quarteriy penod (Juty Sep- accidents, and the overall risk (the product of accident frequen-

tember 1990) and includes coptes of letters, Notees, and cies and consequences) Supporting tNs summary report are a

Orders sent by the Nuclear Regulatory Cornmission to hcensees large number of reports written under contract to NRC whch

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. - _ _ _ -. .. - -- . - - -- -


provde the detailed d:scussion of the methods used and resultsNUREG 1232 V04: SAFETY EVALUATION REPORT ON TEN.obtained in these risk studes Volume 1 of tNs report has three

NESSEE VALLEY AUTHORITY: WATTS BAR NUCLEAR PER-parts Part i provides the background and objectives of the as-FORMANCE PLAN AULUCK.R. TVA Protects thvision (890101sessment and summanzes the methods used to perform the D00602L January 1990 84pp 9003070159. 52807041.

nsk studies. Part il provdes a summary of results obtained forTNs safety evaluaton report on the information subtrutted bycach of the five plants studied Part til provdes perspectives on the Tennesson Valley Authortty in its Nuclear Perioimance Plan

the results and discusses the role of tNs work in the larger con + for the Watts Bar Nuclear Plant and in supporting documentstext of the NRC staff's work. has been prepared by the U.S. Nuclear Regulatory Commisson

NUREG 1150 V02: SEVERE ACCIDENT RISKSAN ASSESS-staff. The plan addresses the plant 4pecife corrective actons

MENT FOR FIVE U.S. NUCLEAR POWER PLANTS. Appendices as pa t of the recovery program for leensing of Unit 1. The staff

A,0 And C. Final Report. * Divison of Systems Research (Post will be munitonng and inspocting the implementaten of the pro.680717), December 1990. 313pp. 9101110227, 56343.164 grams The plan does not address alllicensin0 matters that will. TNs report summartres an assessment of the nsks from be required for tuel load and operabon of Urut 1. Those remain-

severe accidents in five commercial nuclear power piams in the ing heensing matters have been addressed in previous safetyUruted States. These naks are measured in a number of ways. evaluatons or will be addressed 'n accordance with routinei

NRC heensing practices.including the oshmated frequencies of core damage acedentsfrom intomally Initiated scedenta, and externalty Irvtiated acc5 NUREG 1266 V04: NRC SAFETY RESEARCH IN SUPPORT OFdents for two of the plants, the performance of containment REGULATION FY 1989 * Othee of Nuclear Regulatory Re-structures under severe accdent loadings, the potential magng tearch (Post 860720). April 1900, 61pp. 9005040092.tude of radonucide releases and offstte consequences of such 53622.113cecidents; and the otorall nsk (the product of accdent frequen. TNs report, the fifth in a senes of annual reports, was pre-cies and consequencest Supporting tNs summary report are a pared in response to congressona, inquinos concerrung howlarge number of reports wntten under contract to NRC which nuclear regulatory research is used. It summartres the accom-provde the detalled dscussen of the methods used and results phshments of the Office of Nuclear Regulatory Research donngobtained in these nsk stu6es. Volume 2 of this report Contains FY 1D89. The goal of this office is to ensure that safety relatedthree appendices, providing greater detail on the methods used, research provdas the techrucal bases for rutomaking and for re-an example nsk calculaton, and more detailed discusson of lated decisions in support of NRC bconsing and inspection ac.perticular techn# cal issues found important in tne nok stud es. trvities. This research is necessary to make certain that the reg-

ulatons that are irnposed on hconsees provide an adequateNUIEG 1214 R05: HISTORICAL DATA SUMMARY OF THE SYS- margin of safety so as to protect the health and safety of the

TEMATIC ASSESSMENT OF LICENSEE PERFORMANCE. pubhc. This report descobes both the direct contobubons to scoALLENSPACH.F.; NEASE.R. Division of Licensee Performance snufic and technical knowtedge with regard to nuclear safety& Quahty Evaluaton (Post 870411L February 1990. 11 %'y and their regulatory apphcabons.9003070137. 52807.320.

The Histoncal Data Summary of the Systematic Assessment NUREG 1272 V04 N01: OFFICE FOR ANALYSIS AND EVALUA-of Licensee Performance (SALP) is produced penodically by the TION OF OPERATIONAL DATA 1989 ANNUAL REPORT. PowerU.S. Nuclear Regulatory Commissco. This summary provides Reactors * Office for Analysis & Evaluabon of Operationalthe results of the assessment for each facihty by NRC region Data, Director, July 1990. 264pp. 9009040081. 55048.295.end is further divided into the following sectons: Secten 1 pre- e annual mpet of the U.S. Nuclear Regulatory Commis-sents the most recent SALP report ratings for facihties in oper, sows Office fu AMysis and Evaluabon of Operabonal Dataation and under constructort These tabngs are grouped by (AEOD)is devoted to the activities performod dunng 1989, TheRegen showing rahng based on the revised Manual Chapter report le pubbshed in two separate parts. NUREG 1272, Vol 4,0516 functional areas, then the pre-revised Manual Chapter No.1, covers power reactors and presents an overview of the0516 functonal areas and then for reactors unoer constructon- operabng expenence of the nuclear power industry from theSecten 2 presents a chronological hatng of all SALP report rat. NRC perspective, including comments about the trends of someings for each operating facihty, These rabngs are also grouped key portormance measures The report albo includes the pnnebby Region showing ratings based on the sevised Manual Chap- pal findings and issues idenbhed in AEOD studes over the pastter 0516 funcbonal areas and then the pre revised Manual year and summan20s informabon from such sources as hcenseeChapter functional areas Section 3 presents a chronological event reports, diagnostc evaluabons, and reports to the NRC'sbshno of all SALP report rabngs for each facihty under construc- Operatons Center. This report also compdes the status of staffton. For histoncal purposes, past construebon raungs for facih- actons mswing from pmvous incident investgaton Team (IIT)bes that recently have been hcensed also are hated in Secuon reports NUREG 1272, Vol 4, No. 2, covers nonreactors and3' presents a review of the events and concerns dunno 1989 as.

sociated with the use of heensed matenalin norveactor apphca-NUREG-1214 R06: HISTORICAL DATA SUMMARY OF THE SYS. tions, such as personnel overexposures and med cal misadmirs

TEMATIC ASSESSMENT OF LICENSEE PERFORMANCE. istratons. Eact, volume contains a kst of the AEOO reportsALLENSPACH.F.; WHARTON,R, Orvison of Licensee Perform. issued for 1980 1989ance & Quality Evaluaton (Post 870411). August 1990.114pp-9008310213.55043.056. NUREG-1272 V04 N02: OFFICE FOR ANALYSIS ANC EVALUA.

TlON OF OPERATIONAL DATA 1989 ANNUALThe Histoncal Data Summary of the Systemauc Assessmentof Licensee Performance (SALP) is produced penodically by the REPORT.Nonreactors ' Othce for Ana!ysis & Evaluation of

Operabonal Data, Director. July 1990. 68pp. 9000040059.U.S. Nuclear Regulatory Commissiort This summary provides55048.199the results of the assessment for each facihty by NRC regon

and is further drvided into the following sections: Section 1 pre- See NUREG 1272,V04,N01 abstract.

sents the most recent SALP report raungs for facitibes in oper- HUREG 1299 DRFT FC: STANDARD REVIEW PLAN FOR THEaton and under constructort Secten 2 presents a chronologs REVIEW OF LICENSE RENEWAL APPLICATIONS FOR NU.cd hsung of all SALP report rabngs for each operabng facihty. CLEAR POWER PLANTS Draft Report For Comment. * OthceSection 3 presents a chronological hshng of all SALP report rat- of Nuclear Reacter Regulabon, Director (Post 870411) Novem-ings for each facihty under construction. For histoncal purposes, ber 1990. 347pp. 9012110326. 56060-001.past construction rahngs for fac:hties that recently have been D. The SRP LR is to be used by the NRC staff when performingcensed also are hsted in Section 3. safety reviews of apphcations for the renewal of power reactor

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Main Citations and Abstrccts 9

licensss The use of the SRP LR when reviewing heense renew- tory Commiss6on, its regulatory responsibihbes, atid areas li-

al apphcations prov. des a framework for the staff to determine censed ty the Comrnsseort TNs is ar, annual pubhcaton for the

whether or riot (1) the appleation is sufficient to allow the timely general use of the NRC Staff and is availatWe to the pubhc. Thedigest is divided into two parts; the first presents an overview ofrenews proviseons of 10 CFR 2.109 to appiy, (2) systems, struc- the U S. Nuclear Regulatory Commswon and the second pro.tu*es, and components important to hconse renewal have been

dentified, (3) sign:feani *gs-related degradation has been iden- vides data on NRC commercial nuclear reactor hconsees andtified and its effects evaluatea and (4) programs for age related commercial nuclear poww reactors worldwide.

degradabon management have been or will be Imptomented NUREG 1352: ACTION PLANS FOR MOTOR OPERATEDsuch that the current hcensing bas.s will be maintained dunng VALVES AND CHECK VALVES SCAR 0 ROUGH,T.G. Divsonthe renewal term The draft SRP LR has been developed to of Engsreenng Technology (Post 890827). June 1990 34pp.enable the staff to dentify areas and issues requinng review, 9006290061. 54318.321and provides acceptance critena to assast the reviewers. The proper performance of motorwerated valves (MOVs)

NUREG 1316: TECHNICAL FINDINGS AND REGULATORY and check vanes is necessary for the safe operaton of a nucle-

AN ALYSIS RELATED TO GENERIC ISSUE 70 Evaluaton Of ar power plant Probioms have been expenonced with thesePower Operated Rehet VaNo And Block Vane Rehabiltty in vatves for many years. Currentfy, the U S. Nuclear RegulatoryPWR Nuclear Power Plants KIRKWOOD.R. Dtviason of Safety Commisson (NRC) and the nuclear endustry have a number ofIssue Resolubon (Post 880717). December 1989. 26pp- actmbes under way to provide assurance that MOVs and check

9002120148. 52611:263. vanes will successfully perform their safefy functons whenThis report summartres work performed by the Nuc6 ear Reg * needed The MecMnecal Engineenng Branch (EMEB) of the

latory Commisson statt to resolve Genene l$ sue 70 " Technical Office of Nuclear Reactor Asgulabon has been assigned the re-Findings and Regulatory Ahalysis Related to Genenc issue 70 - sponsibility of coordinating NRC activibes and nonstonng 6ndus-Power Operated Rehet Valve and Block VaNo Rehatahty. The try actmtros regarding MOVs and check valves To moet this re-report evaluates the rehabihty of PORVs and blo;k vaNet and spons4tuty, EMEB has prepared action plens to provide assur-their safety signdicance in PWR nuclear power plants. The ance d the propw performance of Nse vaNa Through thereport centsfies those safety related functons that may be per- acton plans, the NRC staff will have an orgencred approach toformed by PORVs and describes ways in which PORVs and resoNo the concoms regarding the operatdty of MOVs andblock vanes may be improved. This report also presents the check vanes in a timety manner.regulatory analysis for Genenc issue 70.

NUREG-1362 DRFT FC: REGULATORY ANALYSIS FOR PRO-NUREG-1333: MAINTENANCE APPROACHES AND PRACTICES POSED RULE ON NUCLEAR POWER PLANT LICENSEIN SELECTED FOREIGN NUCLEAR POWER PROGRAMS AND RENEWALDraft Report For Comment. * Dmsson of SafetyOTHER U.S INDUSTRIES: REVIEW AND LESSONS 1ssac Resoluton (Post 880717) Juiy 1990. 213pp. 9008070329LEARNED. DEY.M Dmsson of Regulatory Apptecatons (Post 54862:04287013) Apni 1990.111pp 9005070010. 53657:05t. This requistury anatysis provides the supporting informabon

The Commisson published a Notice of Proposed Rulemaking for a proposed rule bat wtit define the Nuclear Regulatory Com-or Maintenance of Nuclear Power Plants on November 28, messon's requirements for renewing the operatng bconses of1988, spelhng out NRC's expectabons in maintenance. In pro. comercial nuclear power plants A set of lour specific attema.

! panng the proposed rule, the NRC reviewed maintenance prac, hvos for the safety review of heense renewal apphcations is de-I bees in other countnes and considered maintenance approach, fined and evaluated. These are: Alternative A-current beensing

es in other industnes in tNs country. As a result of the review of basis; Afternatrve B-extension of Altematrve A to require as-maintenance practices, it was cuncluded that certan practices sessant and managing of aging; Attemative C--extenson ofin the following areas have been found to contotr'te significant. A%matrve B to requwe assessment of design differencesly to effective maintenance- (1) systems approach; (2) effeebve. against selected new plant standards using probatAstic nsk as-ness monitonng; (3) technician Quahfications and motivaton; sessment; and Attematsve D--extenson of Alternative B to re-!

and (4) maintenance organizatiott guire comphanca with all new-plant standa ds. A quantitative

NUREG 1339: RESOLUTION OF GENERIC SAFETY ISSUE companson of the four alternatrves in terms of impact-to-value

29 BOLTING DEGRADATION OR FAILURE IN NUCLEAR ratos *s presented, and Alternative B 6s the most cost-benefictalPOWER PLANTS JOHNSON R.E. Dmsson of Safety issue Res- safety review themattveoluton (Post 880717) June 1990. 23pp. 9008140466. ATOMIC SAFETY AND LICENSING BOARDNUREG 1363 V02:54927:158. PANEL ANNUAL REPORT FISCAL YEAR 1989. COTTER,0.P.

Ths report desenbes tne U.S. Nuclear Regulatory Comrras. Atomec Safety and Ucensing Board Panel. My 1990. 63ppsoon's (NRC's) Genenc Safety issue 29. "Boiting Degradation or

9008070082. 54845.098.Failure in Nuclear Power Plants," including the bases for estab- In Fiscal Year 1989, the Atomic Safety and Licensing Boardhshing the issue and its histoncal higNights. The report also de. Panel (ASLDP) handled 40 proceedings invoNing the construc-scribes the actmties of tne Atorne Industnal Forum (AIF) reie- bon, operaton and maintenance of commercial nuclear powervant to tNs issue, including its cooperahon with the Matenals reactors or other actmbes requinng a hconse from the NuclearProperties Courcil (MPC) to organize a task group to help re- Regulatory Commission. This report summanzes, highhghts andsone the issue. The Electnc Power Research Institute, support. analy7es how the wide-ranging issues raised in these procee4ed by the AIF/MPC task group, prepared and issued a two- ings were addressed by the Judges and Licensing Boards ofvolume document that provides, in part, the technical basas for

the ASLBP dunng the year.resoNing Genere Safety lasue 29. This report presenta theNRC's review and evaluaton of the two volume document and NUREG 1372: REGULATORY ANALYSIS FOR THE RESOLU-NRC's concluson that "its document in conjunction with other TION OF GENERIC ISSUE 0 9, " MAIN STEAM ISOLATIONinfcrmaton from both industry and NRC, provides the bases for VALVE LEAKAGE ANO LCS FAILURE." GRAVES,C.C. Omsonr og Ws ssa of Safety issue Resolution (Pos 880717). June 1990. 29pp-

NUREG 1350 V02: NUCLEAR REGULATORY COMMISSION IN-9006290054 6C2f:306.

FORMATION DIGEST.1990 Edstort OUVE.K L. Omson ofGenenc issue C-8 deals with staff concerns about pubhc nsk

Budget & Anatysis (Post 890205) March 1990. 117pp. because of the incidence of leak test f ailures reported for mainsteam isolaton vatves (MSIVs) at boihng water reactors and the

9004090296. 53315:278.The Nuclear RegJatory Commission information Digest pro- hrntations of the leakage control systems (LCS) for mitigating

vides summary information regarding the U.S. Nuclear Regula- the consequences of leakage from these vanes. If the MSiv

.__ _ _. _ __ _ _ __ . . . -_ _ _ _ _ _


leakage is Greatly in excess of the allowable value in the techrw-NUREG 1390: SAFETY EVALUATION REPORT RELATED TOcat specifcations, the LCS would be unavailable because of

THE RENEWAL OF THE OPERATING LICENSE FOR THEdesign hmitations. The issue was arvtiated in 1983 to assess (1) TRIGA TRAINING AND RESEARCH REACTOR AT THE uni-the causes of MSIV leakage failures, (2) the effectiveness of the VERSITY OF ARIZONA Docket No 50113. (Untversity of Anto.LCS and afternative mitigation paths, and (3) the need for adde na) * Division of Reactor Projects IllfV,V & Special rNotectshonal regulatory action to reduce pubic risk. This report pre- (870411901215). May 1990. 74pp 9006080200,54074:200sents the regulatory analysis for Genenc leave C-8 and con. This Safety Evaluation Report for the application filed D* theciudes that no new regulatory requirements are warranted, University of Antona for the renewal of Operating License P. 52

to continue operabng its research teactor at an increased oper-NUREG 1377 R01: NRC RESEARCH PROGRAM ON PLANT ating power level has been prepared by the Office of Nuclear

GGING. LISTINGS AND SUMMAP:ES OF REPORTS ISSUED Reactor Regulation of the U S Nuclear Regulatory Comtnssion.THROUGH MAY 1990. KONDIC.N.N4 HILL.EL Dutsson of En- The facihty is located on the Uruversity of Art 2ona campus ingineenng (Post 870413). July 1990. 62pp. 9008070371. Tucson, Antona. The staff concludes that the reactor can con-54B45:036. tinue to be operated by the University of Anzona without endar>

The U.S. Nuclear Regulatory Comrnsalon is conducting the genng the health and safety of the pubhc.Nuclear Plant Aging Research (NPAR) Program. T his is a com-prehensive hardware onented engineenng research program fo. NUREG 1391 DRFT FC: CHEMICAL TOXICITY OF URANIUMcused on understardng the aging mechanisms of components ,

and systems in nuclear plants. The NPAR program also focuses Report For Comment. MCGUIRE,S A Offee of Nuclear Regula-on methods for simulating and (nonitonn0 the aging related dog- tory Research (Post 860720). April 1990 16pp 9005210238.todation of these components and systems. In additon, it pro- 5380 32v6 des recommendations for effective maintenance to (nanageagmg and for the implementation of the research results in the hexafluoride are compared to the effects from a^ute radiationregulatory process. This document contains a listing and inder doses of 25 rems to the whole body and of 300 rems to theof reports generated in the NPAR program that were issued g g , gthrough May 1990 and summanes of those reports. Each sum- 500 mg min /m(3) of hydrogen fluoride is roughty equivasert, inmary describes the elements of the research covered in the M b an d 25 mreport and outhnes the signifcant results. For tM convensence Similarty, an intake of about 10 mr1 of uranium in soluble form isof the u r he a are indexed by personal or, corpo. roughly equivalent, in terms of earfy effects, to an acute whole,

body dose of 25 rems. The purpose of these analyses 6s to pro-vxte information for developing siting entena for uranium ennch-

NUREG 1381: TECHNICAL SPECIFICATIONS, W MANCHE ment plants based on chenical torcity. These sitino criteria arePEAK STEAM ELECTRIC ST ATION. UNIT 1. Docket No. 50- 'O D' 8'milar, in terms of health aad safety irnr* an workers445,Appendtx *A" To Ucense No. NPF 28, * Comanche Peak and memWs d the pubhc, to N seg cnw . A NRC r$a-Project Division (890101900602). February 1990. 354pp. tons for nuclear power plants, wtuch are based on radiation9003120703, 52883.015. doses.

The- Techn6cai Specifications for Comanche Peak SteamElectric Station, Urvt 1 were prepared oy the U.S. Nuclear Re9- NUREG 1392: LEAKAGE OF AN IRRADIATOR SOURCE THEufatory Commission. They set forth the htmts, operat ng condF JUNE 1988 GEORGIA RS) INCIDENT. * Office of Governmentaltions, and other requirements apphcable to a nuclear reactor fa- & Pubhc Affairs (Post 870413). SETSER.J L Georgia, State of.cihty, as net forth in Section 50.3e of Title 10 of the Code of February 1990. 45pp. 9003190259. 53005.245.

. Federal Regulations Part 50, for the protection of the health and On June 6,1988, operators of a pool ertadiator in Decatur,safety of the public- Georgia were prevented by a safety system from rasseng

sources from the pool. Radiation levels of 60 millitem por hour

NUREG 1383: GUIDANCE ON THE APPLICATION OF QUALITY at the surface of the pool water were found,irdcative of a leak

ASSURANCE FOR CHARACTERIZING A LOW. LEVEL RADIO. of one or more of the 252 Cs.137 source capsules used et theACTIVE WASTE DISPOSAL SITE. Final Report. PITilGLtO.CL; rradiator. Because of the concerns which arose out of this inct-STARMER,R.Ja HEDGES D. Division of Low. Level Waste Man- dent, the State of Georgia and the Conference of Radiation

Control Program Drectors, Inc. decided it should be reviewed inagement & Decommissiorvng (Post 870413). October 1990-17pp. 9010240396. 55495.259. depth. Geo'gia G?vernor, The Honorable Joe Frank Hams, cro-

This document provides Guidance to an applicant on meeting ated an incident Evaluation Task Force and charged it with col-

the Quahty Control (OC) requirements of 10 CFit Part 61.12 for lecting information on the incident, maintaining communicatons

a Low-Leve! Weste (LLW) disposal factirty. The OC requre- with the DOE invest;gative Board and prepanng a wntten report

ments combined with the requirements for managertal controls of lessons learned. Since the incident and responses to it are

and audits are the basis for developing a Quality Assurance stdl ongoing, a hr-al report of the task force is expected at a(OA) program and for the guidance provided herein. The docu- later date. A summary of the Task Force's First interim Report

j ment specifically estabhshed OA guidance for site charactenza. has been propered for persons needing an overvtow of the ince.

| tion activities necessary to meet the performance objectrves of dent and lessons leamed to date. The Conference estabbshedl 10 CFR Part of and to hmit exposure to or release of radioac. an Incident Review Team which agreed to assume the responsel trvity. bihty from the Georgia task force to decuss the role of the

States in regulating trradiators Its intenm Report provides a| NUREG 1386: TECHNICAL SPECIFICATIONS FOR SEABROOK

summary of Agreement States' vmws and recommendations an| STATION, UNTT 1. Appendix "A" To Ucense No. NPF-86. * Di- some of the issues raised by the incident.

mson of Reactor Protects 1/11 (Post 870411) March 1990. NUREG-1393: THE INCINERATION OF LOW. LEVEL RADICAC-419pp. 9004090200. 53307:001.TIVE WASTE.A Report For The Advisory Committee On Nuclear

The Seabrook Staton, Unit 1 Technical Spectftcations were Waste. LONG,S.W. Advisory Committee on Nuclear Wasteprepared by the U S. Nuclear Regulatory Commission to set June 1990. 75pp. 9007120183. 54469 05'lforth the limits, operating conditions, and other requirements ap- This report is a summe<y of the contemporary use of incinor.piscable to a nuclear reector facility as set forth in Sect nn 50 36 ation technology as a memod for volume reducton of LLW. It isof 10 CFR Part 50 for the protection of the health and safety of intended pnmanly to servo as an overview of the technology forthe public. -

waste managernent professionais invoNed in the use or regula-

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M:In Citstions and Abstrsets 11

This document is an enmronmantal assessment of a systemton or LLW incineraton. It is also expect +xt that organtzahons designed to detect the presence of emlostves 6n checked alt-presently considenng the use of incineraton as part of thest re- hne baggage or cargo. The system is meant to be installed atdioactive waste management programs will benefit by gaining a the concourse or lotty ticketing areas of U S. commercial air-general knowledge of incinerator operating exponence SpeciftC ports and use* a scaled radcactive source of cahtornium-252 totypes of incinerabon technologies are addressed in tNs report, irrad4 ate taggage tiems The major 6mpact of the use of thiaincluding desgnahon of the kinds of wastes that can be proc- Wstem anses from direct exposure of the public to scattered oressed, the magnitudes of volume reduction that are achievable leakage radtaten from the source and to induced radioactrvtty inin typical operahon, and requiremeLs for ash handung and off- baggage items. Under normal operation and the most hkely ac-gas fdteeng and scrubbing A status fisting of both U S. and for- cident acenanos, the environmental impacts that woWd be cro-egn incinerators provides hightshts of actmtes at government, ated by the proposed heensing action would not t>e sgnificant.Industry, nnstnutonal, and comme cial nuciou power plant sites

NUREG 1394: EMERGENCY RESPONSE bATA SYSTEM (ERDS)NUREO 1398 DRFT FC: ENVIRONMENTAL ASSESSMENT FOR

PROPOSED RULE ON NUCLt!AR FOWER PLANT LICENSEIMPLEMENT /, TION JOUCOEUR.J R Office for Analysis &Evaluation of Ocoratonal Data. Director. AprW 1990. 53pp

RENEWAL. Draft Report for Comment * Divison of Saietyissue Resolution (Post 880717) July 1990 57pp, 9006070358

9006060154. 54077.3t tThe U S Nuclear Regulatory Commission has begun imple- 54845 250

The possible environmental effects of promulgating nuclearmentation of the Emergency Response Data System (ERDS) to power plant license renewat standards by the propc.ed rule.10upgrade its abdity to acquae data from nuclear power plants an CFR Part $4, rather than applying requvementa in an ad hocthe event of an emergency at the piant ERDS providea a direct minner in indvdual heensing actions, are asswsori The rulereal-timii trensfer of data from bcensee p(ant coinputers to the requires the development of enformation and anatyses to identifyNRC CF6 bons Center. The system has been desgned to be aging problems of systems structures, and components that willactivatet ay the hcensee dunng an emergency wNch has beenclassified at an ALERT or hegher level, The NRC pwtson of

be of concern donng the renewal term and will not be controlled

EROS will receive the data stream. sort and fue the data. Theby ensting regulatory programs, Required actions may be

,0-

users will 6nclude the NRC Operatons Center, the NRC Region-placement, returtushmerr sospection, test ng or monitoring

at Office of the affected plant, and if requested, the Statessuch schons will generali se within the range of similar actronstaken for plants dunng the inibal operating term They would be

wmch are withir) the ten mee EPZ of the site. The currently to- pnmanty confined witNn the plants with potential for only minorstalled EmergeNy Notificaten System will be used to supple- disruction to the environment. It is unhkely that these actionsment EADS data TNs report provides the rNnimum guidance would change the operatsng condihons of plants in ways thatfor implementahon of EROS at hcensee sites it is intended to would change the environmental effects already being exper6-be esed for planning implementation under the current voluntary enced The promulgaton of 10 CFR Part $4 has clear advan-program as well for providing the minimum Standards for imple- tages relahve to regulatory stabihty and administrative effc6ency.menting the proposed ERDS rule. However, it will not result in environenental effects significantly

NUREG-1395 DRFT: INDUSTRY PERCEPTIONS OF THEdifferent from those ansing from ekcensing under existmo regu-

!MPACT OF THE U S NUCLEAR REGULATORY COMMISSIONlations. The NRC concludes that promulgaton of 10 CFR Part

ON NUCLEAR POWER PLANT ACTMTIES Draft Report 54 would not egnihcantly affect the environment and. therefore,

DAVIS.A S ; PEDERSON C D Rogion 3 (Post 820201) March a fuil environmental impact statement is not requwed and a

1990.180pp 9004000218.53313 M0 Findng of No Sgnihcant impact can be madeTeor % of senior managers from the NRC surveyed hcensee

NUREO 1399: TECHNtCAL SPECIFICATIONS. COMANCHE PEAKstaff members representng 13 nuclear power utsties from STEAM ELECTRIC ST ATION. UNIT 1. Docket No. 50 445.Appen-across the country to obtain their can.hd views of the effechve-

dix "A" To Lscense NPF 8E(Tetas UtAtes Electnc) * Coman-nos , and smpact of NRC requiatsry acteties Ltcensee com- che Peak Proscet Drvison (890101900602). Apnl 1990. 360pp,rra.nts addressed the full scope of NRC activebes and the

9006080f 50. 54081:109irrpact of agency acbons on hcensee rewrces. steff perform- The Techn$ cal Specificatens for Comanche Peak Steamence, p'anning and scheduhng, and organtrabonal effective- Electnc Staten. Unit 1 were prepared by the U S Nuclear Reg-nus The pnncipa! themes of th s survey respondents' com- ulatory Commisson. They set forth the hmsts cperabng condoments are that (1) licensees acquiesco to NRC requests to tions, and other requuements apphcablo to a nuclear reactor la.avom poor rabngs on NRC Systemahc Assessment of Uccesee et! sty, as set forth in Sect on 50.36 of Title 10 of the Code ofFvformance (SALP) reports and the consequent unancial and Federal Regulations Part Srt, for the protection of the health andpubhc Dercepton problems that result ev1n 6f the requests re-quvo the expendture of significant resources on matters of mar-

Safety of the pubhc.

gina! sa'ety sgnif4ance, and (2) NRC so dominates hconsee re- NUREG 1402: CLOSEOUT OF NRC BULLETIN 8845 NONCON.sources through its existing and changing formM and informal FORMING MATERIALS SUPPLIED BY PIPING

squirements that hcensees behove tnat their plants, though not SUPPUES,1NC,AT FOLSOM.NEW JERSEY,AND WESTunsafe, would have better reliabil,ty, and may even achieve a JERSEY M ANUF ACTURING COMPANY AT

Ngher degree of safety, if heensees were freer to manage their WILLIAMSTOWN,NEW JERSEY. Divnen of Engineenno'

own resources This draft report does not attempt to defend any Technology (Post 800827) May 1990 79pp 9006110010. IEB-NRC pomtion, endorse or refute hcensee perceptions; or explain 88-005. 54083.185 |any acton taken by NRC in tulfdhog its responsibilit es to protect TNs report documents the actmtics that led to the Closeout ;

the health and t.afety of the pubhc Senor NRC managers have of U.S Nuclear Regulatory Commisson (NRC) Bullet n 88-05,made a prehmanary evaluabon of the informahon in tNs report wNch was issued on May 6.1988. The bulletin requwod that h-

ianJ have made recommendabons to address licensee concerns consees submit information on matenals supphed by Pipingin some araas The final evaluaton and recommenoations WHI Supries, Inc (PSI) and Wer Jersey Manufactunng Companybe pubhshed at a later dato as the final NUREG (WJM), and requested that they (1) ensure that these matenais

NUREG 1396: ENVIRONMENTAL ASSESSMENT OF THE THER-comphed with the Amenean Society of Mechanical Engineers.

MAL NEUTRON ACTMTATION EXPLOSfvE DETECTIONBoder and Pressure Vessel Code (ASME Code) and design

SYSTEM FOR CONCOURSE USE AT U .S AIRPORTS. Specificahons or wwe *.uitable for their intended service or (2)

JONES,CG Otvison of Industnal & Medical Nuclear Safety replace such matenais Supplements I and 2 were issued onJune 15 and August 3,1988. respectively In Supplement 2. an-

(Post 870729). August 1990 160pp. 9010090050. 55322 003 |

I

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-. _ - _ _ . .-~ _ . - .- . . _. - . - -

12 Main Citations cnd Abstracts

other affikated supphor, Chms Landing Metal Manufacturers,NUREO 1407 DRFT FC: PROCEDURAL AND SUBMITTAL GUID-Incorporated (CLM), was identified. The staff concluded that (1)

ANCE FOR INDIVIDUAL PL. ANT EXAMINATION OF EXTER,the awytical procedures used to quahfy the nonconforming NAL EVENTS (IPEEE) FOR SEVERE ACCIDENTparta and the analysis results provido an adequate basis for re- VULNERABILITIES Draft Report For Comment * Dmson ofsolving the staff's concerns regarding fittings and flanges, f2) Safety issue Resoluton (Post 880717). July 1990. 41pp.even though the materials suppled t3 PSI, WJM, and CLM with 9008070367. 54A45'307.festfied cerbfied matenal test reports do not meet the ASME Based on a Policy Statement on Severe Accdonts, the toCode, their use is an acceptable attemative in accordance with consee of each nuc6 ear power plant is requested to periorm anSection 50,55a(a)(3)(si) of Title 10 of the Code of Federal Regu. rdividual plant examinaton. The plant examinabon systematblabons (3) acbytties in response to Bulletin 88 05 regarding fit- cally looks for vulnerabihties to severe accidents and cost effec-tings and flanges can be closed for all operating plants, and (4) tive safety improvements that reduce or ehminate the importantheensees should evaluate the use of product forms other than vulnerabikties. This document presents gudance for performing!stbngs and ,langet and reporting the results of the indmdual plant examinaton of

external events OPEEE) The gudance for reporting the resultsNUREO 1403; SAFETY EVALUATION REPORT RELATED TO of me individual plant examinaton of internal events (tPE) is

THE FULL. TERM OPERATING LICENSE FOR DRESDEN NU- presented in NUREG-1335.

CLEAR POWER STATION UNIT 2 Docket No. 50-237.(Com-NUREG 1409: BACKFITTING OUIDELINES. ALLISON.D.P.;monweattn Edison Company) * Division of Rea: tor Protects .

CONRAN.J H.; TROTTtER,C A. Office for Analysis & Evaluatonlitly,V & Specia! Protects (6704 1901215). October 1990.39pp. 0010230057. 55472 277, of Operabonal Data Dvector. July 1990.102pp 9008070378.

54846 270.The Safety Evaluation Report for the full term operating h- The bacutting process is the process by which the U.S Nu-

conse application feed by Commonwealth Edison Company for clear Regulatory Commission (NRC) oecedes whether to issuethe Dresden Nuclear Power Stabon, Unit 2, has been prepared new or revised requuements or staff possions to hcensees ofby the Office of Nuclear Reactor Regulabon of the U S. Nuclearnuc6 ear power reactor facilibes Requirements for proper justifi-

Regulatory Commisson. The facihty is located in GrundyCounty, Ilknots. Subject to favorable resoluton of the items dis.

cation of backfits and information requests are provded by twoNRC rules (Title 10 Code of Federal Reguistons, Sections

cussed in this report the staff concludes that the facility can 50109 and 50.54(f)). NRC procedures include the charter of theconunue to be operated without endangenng the heatth and committee to Review Genenc Requwements, NRC Manualbately of the pubhc. Chapter 0514, and individual office procedures Three types of

backtits are recognized. Cost lustified substanbal safety srn-NUREO 1404: LfCENSEE USE OF TACTICAL EXERCISE RE- provements require backfit anatyses and findings of (1) substan-

SULTS SAWYER.04 BROWN,C Devision of Safeguards & tial safety improvement and (2) }ustified costs Comphance ex.Transportation (Post 870413). Apnl 1990 lipp 9005210234. coptons and adequate protecton exceptons do not requnoSM61M fridings of substantal safety improvements and costs are not

On November 10, 1988 the Nuclear Regulatory Commisson cons Howw tNy am W bacWs and que dow(NRC) amended fts physical secunty requvements in 10 CFR mentod evaluatono to support the use of the exceptions. Infor.Part 73 for fuel facilitics possessi"9 formula quantibes of strate- msu as e t e an a@ sis ofgee special nucioar matenal. The amendments to 10 CFR the burden to be imposed to ensure that they are justfiod in73 46(b) requee, among other tnings, that hconsees carry out view of the potential safety significance of the informaton re-performance evaluations through tactical response exercises quested

Tho exercises are intended to demonstrate the guard forceNUREO 1410: LOSS OF VITAL AC F9WER AND THE RESIDUALstaie of readiness and to test the effectiveness of delay mecha.HEAT REMOVAL SYSTEM DURING M!D LOOP OPERATIONSnaams, alarm and communicabon systems, resoor'se times, de. AT VOGTLE UNIT 1 ON MARCH 20,1990.' Ofc of the Execu-

ployment of response forces, finng SUls (simulated), tactical tive Dwector for Operabona, June 1990, 522pp. 9006290080-maneuvers, etc. The purpose of this documront is to set forth 5431910Lcritena, acceptable to the NRC staff, which will enable a ficens. On March 20,1990, the Vogtle Electnc Generating Plant Unitce to use the results of an exercise to determine whethor adde 1 located in Burke Counr/, Georg4a, about 25 miles southeasttonai training or secunty improvements are needed. of Augusta, exponenced a loss of all safety (vital) ac power.

TN plant was in cold shutdown with reactor coolant level low.NURCO 1405; INADVERTENT SHIPMENT OF A RADIOGRAPHIC ered to "meloop" for vanous maintenance tasks. Both theSOURCE FROM KOREA TO AMERSHAM rantainment building personnel hatch and equipment hatchCORPOR ATION.B U R LING TON, MASS ACH U S ETTS * NRC were m One emergay desel gene <ator and one reserveNo Detailed Aff:bation Grven. May 1990.177pp. 9006110005. audary transformer were out of sennce for maintenance, withgg7 the remaining reserve audary transformer supplying both Urut

Amersham Corporahon, Burkngton, Massachusetts, a hcensee 1 saW W A M m N b Mage sw%ad WWof the U S. Nuclear Regulatory Cofnmission (NRC), authonzed "" 0 *

- to manufacture and distnbute indium-102 and cobalt-60 source* * * *** N ** ##

assembhos for use in radography equipment, received a ship- sulator broke, a phase-to. ground fault occurred. and the feedetment of 14 source changers on March 8,1990, that were being cirevit breaisers for the safety buses opened. The operablereturned from their product distnbutor, NOI Corporation in Seoul, emergency diesel generator started automabcany becausa ofKorea. One source changer contained a small sealed source in the undervoltage conditon on the safety bus, but inpped offan unshioided location. Amersham employees retneved the after about 1 minute. About 20 minutes later the diesel genera-source, secured it in a hot cell and rytfed NRC's Region L. tor load sequencer was reset, causing the d,esef generator toSubsequently, NRC dispatched an Incident investgabon Team start a second time The diesel generator started again, operat-to per'orm a comprehensive review of this inc6 dent and deter- ed 1or about 1 minute, and tnpped off. The diesel generator wasmine the potentla! for esposure to those who handled the restarted in the manual emergency mode 36 minutes after the

source chanDer and to members of the general pubhc. This loss of power. The generator remained on hne and provided

report desCnbos the Incident and the methodology used in the power to its safety bus Dunng th9 36 minutes without safetybus power. the reactor coolant system temperature rose frominvestigation and presents the Teats Inndings and Conclusions about 90"F to 136'F. This report documents the results of an

- - - - -_ _______


incident Investgaton Team sent to Vogtle by the Executwo Dn tegnty is maintained The purpose of tNs report is to provide

rector for Operatons of the U S. Nuclear Regulatory Commis- regulatory guidance to licensees with Mark 111 containments with

aion to determine what happened, identify the probable causes, regard to demonstrating comphance with 10 CFR 50 44, Sec-tions (c)(3)(vi) and (c)(3)(vii) in tNs report, the staff provides its

and make appiopriate f ndine and conclusions. evaluaton of the genonc methodology proposed by the Hydro-NUREG 1411: RESPONSE TO PUBLIC COMMENTS RESULTING gen Comrol Owners Gwp ma genc methodology is docu-

FROM THE PUBLIC WORKSHOP ON NUCtEAR POWER nwnted n Topcal Roomt HGNM2E Gnent gy%gonPLANT LICENSE RENEWAL ' Office of Nuclear Regulatory Control informaton for OWR /6 Mark 111 Containments in addeResearch (Post 860720). July 1990. 75pp 9006070323 ton, the statt hcs recommended that the vulnerabihty to inter-S4845 348 rupton of poww to me h* men ignitors be evaluated farther

On October 13, 1989. the U.S Nuclear Regu atory Commis- on a pla@specihc basis Na part oi Or aevidual plant exarrana-r

tuon (NRC) issuet an Advance Notice of Proposed Rutemaking ton of the plants with M ark I" rmininmen,aon nuclear powe+ plant heense renewal The nobce presentedthe NRC's prehr innary regulatory philosophy and approach for NUREG 1418: CHARAC ErilSTCS V LOW LEVEL RADIOAC-developing beens) rene*al tegutahons and solicited comments TlVE WASTE DiSPOoED OURING 1987 THROUGH 1989on a number of 'schnical and pohey issues it also announced ROLES,G W. Divison of Low level Waste Management & De-plans for a oubis workshop to discuss the issues and to recorve comm6ssoring (Post 870413) December 1990 629ppcomments and informatort The workshop was held on Novem. W 2 N M 8001bor 1314,1989, in Reston, Virginia. This document reports on This report presents the volume, actMty, and radonuclide dis-the NRC's response to the pubhc comrnents from the workshop gg ggand wntten comments on the workshop topics recerved shortly ggg g ,gafter the workshop. (The proceedngs of the workshop were re- near Bamwell. SC, Richland, WA, and Deatty, NV. The reportported in NUREG/CP-0108)' has been entrely assembled from desenptons of waste prove

NUREG 1412 DRFT FC: FOUNDAT60N FOR THt: ADEOVACYed in LLW sNpment mandests Indmdual redonuclide dstnbu-

OF THE UCENSING BASES A Supplement To U e Statement tons are hsted as a functon of waste class, Uf general industry.

Of Cons #deratons For The Proposed Rule On huclear Power and of waste stream, in addition, enlormaton is presented about

Plant License Renewal (10 CFR Part 54) Draft Repet For Com- Gsposal of wastes containing chelatng agents, about use of so-ment. * Offce of Nuclear Reactor Regulation, Direce (Post hdificaton media, about the distnbuton of raduaton levels at the

870411), July 1990.106pp. 9008070326. 54860:125 surfaces of waste containers, and about the distribubon of

in order to hmit the Commisson's beense renewal deciscr' to waste container sizes. Considerably move informaton is pre-considersbon of whether age-related degradaten nas been ( # sonted about waste disposed at the RicNand and Beatty drs-

quately addressed, the Part 54 rulemaking must make a genene posal f ac at es than at the Bamwelt esposal facilityfinding for all nuclear power plants that the findngs of reasona-

NUREG-1420: SPECIAL COMMl1 TEE REVIEW OF THE NUCLE.ble assurance of adequate protecton for issuance of an operat-ing hcense continue to be true at the time of the renewal appli- AR REGULATORY COMM!$SION'S SE P E ACCIDENTcaton and accoringly need not be made anew at the time of RISKS REPORT (NUREG 1150) KOUT S,H.J C.;

hcense renewal. TNs analy,,is desenbes the regalatory process- APOSTOLAKIS G; BIRKHOFER.ER; et al Offee of Nuclear

es that form the basis for auch a focng. TNs document $s- Regulatory Research (Post 660720t August 1990. 90ppcusses how the hcensing process has evolved in mator 5, 'eti 9009110129 55t24136.issue areas under existing regulatory processes that have eru in Aprii 1989, the Nuclear Repatory Comm3sson's (NRC)

aured conhnued adequacy of the hcenseg bases of all operat- Office of Nuclear Regulatory Research (RES) published a draft

ing plants The document presents the desenbod regulatory report " Severe Accident Risks An Assessment for Five L1

processes as the Comfrisson's reasons for considenng it un-Nuclear Power Plants," NUREG 1150 TNs report updated, ex-

necessary to re-review an operahng plant's hcensing basis. tended and improved upon the information presented in the

except for age-related degradaten concems, at the time of IF 1974 " Reactor Safety Study," WASH 1400. Because the infor-

cense renewal. TNs report is a supplement to the Statement of mawn in NUREG 1150 wdl play a significant role in implement-

Considerabons for the Nuclear Regulatory Commisson's pro- ing the NRC's Severe Accident Pohcy, its quality and cradibihty

posed rule (10 CFR Part 54) that would estabush the entena are of cntical importance Accordingry, the Commisson request-

and standards governsng nuclear power plant hcense renew 3L ed that RES conduct a peer revsew of NUREG 1150 to ensurethat the methods, safety insqhts and conclusons presented are

NUREG 1416 V03 N01: OF nJE OF THE fNSPECTOR approonate and adequately reflect the current state of knowi-GENERALSemtannual FwportApni-September 1990,

edge witn respect to reactor safety To tNs end, RES formed uGLENN.W.L; WATKINS,R.A Office of Inspector General (Post special committee 6n ' ol 069 under the provisions of the890417). October 1990. 30pp. 9101110208. 56344:117. Federal Adesory Ca imittee Act The Committee, composed of

inspectors General are required, by the LG Act of 1978. as a group of recognin j natonal and internoonal emperts in nu-amended, to prepare semiannual reports wNch summanze the Clear reactor safety, was charged with propanng a report reflect-significant investgabve and audt actetes of the othee The 6- ing tneir review of NUREG 1150 with respect to the adequacymonth reportng penod ends March 31 and September 30 The of the methods. data, analysis and conclusons it set forth Thereport is submitted to the Chairman not later than Apni 30 and report wNch precedes reflects the results of tNs peer revmw.October 31, respecbvely, of each year The Chawman preparescomments as required by the IG Act, and transmits the report to NUREG 1423 V01: A COMPILATION Of REPORTS OF THE AD-Congress' VISORY COMMITTEE ON NUCLEAR WASTE. July 1988 June

NUREG 1417: SAFETY EVALUATION REPORT RELATED TO1990 * Adwsory Committee on Nuclear Waste August 1990

HYDROGEN CONTROL OWNERS GROUP ASSESSMENT OF115pp. 9010230048. 554 72 352.

MARK fil CONTAINMENT Ll,C.Y.; KUDRICK.J.A. Omsion of Ths compelabon contains 37 reports issued by the Adasory

Systems Technoiogy ; Post 890827). October 1990 44pp Committee on Nuclear Waste (ACNW) dunng the first two yearsof its operaton. The reports were submitted to the Chairman of

9010300241. 55629 017. to the Executwe Director for Operatons. t .S Nuclear Regula-Title 10 of the Code of Foderal Regulations (10 CFR), Secten50 44," Standards for Combustbie Ges Control System in ught- tory Commission (NRC) Topics include thr NRC analysis of the

Water. Cooled Power Ree: tors," requires that systems be pro- U.S Department of Energy Site Charamenzabon Psn for the

vided to controf hydrogen concentiabon in the containment at- highaevel radoactNo waste repository, the standards promul-

mosphere fonowing an accident to ensure that containment in- gated by the U S Ermronmenta! Protecten Agency for the cis.

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_ _ _ __ __


posal of Ngh level waste, the NRC pohey statement on DeewNUREG/CP 0105 V03: PROCEEDINGS OF THE SEVENTEENTHRegulatory Concern, tech,wcal documents prepared by the NRC

WATER REACTOR SAFETY INFORMATION MEETINGstaff relative to the decommesseorwng of nuclear power plants, WEISS,AJ Drookhaven Natonal Laboratory March 1990the stabilgabon of uranium mill taihngs piles, and environmental 536pp 9004090193 53398 OMmonitoring All reports prepared by the Comnetee have been See NUREG/CP 0106,V01 abstract-made available to the pubhc through the NRC Pubhc DocumentRoom and the U S. Lityary of Congress. Included in an appen. NUREG/CP 0107: PROCEEDINGS OF THE UNITED STATESdix is a listing of references to related reports on nuclear waste NUCLEAR PEGULATORY COMMISSION SECURITY TRAIN.matters that were issued by the Advisory Commettee on Reactor ING SYMPOSIUM Meeting The Cha!!Safeguards pnor to the estabhshment of the ACNW. "'Ws Hocogniton And Detecten , enge Frearms And Expio.Namn of Safeguards &

Transportaton (Post 870413) September 1990 308ppNUREG 1424: SAFETY EVALUATION REPORT RELATED TO 9010230103. 55470.272

THE FULL TERM OPERATING LICENSE FOR PALISADES NU- These conference proceedings have been prepared in sup-CLEAR PLMT. Docket No 50 255. (Consumers Power Compa. port of the U.S Nuclear Regulatory Commesson's Secuntyny) MASCtANTONIO A. Drvtsson of Reactor Protects lit,lV,V & hamg Sympowm on hng N Challengef vearms andSpecial Projects (870411001215L November 1990. 43pp. EQosws Recogmon and Nem. Noweer 20 thrwgh

30, 1989 in Bethesda, Marytanct TNs document contains thes sa et a t repnrt re:ates to the issuance of a full-

term operating Icese (FTOL) for the Palisades Nuclear Gene'' o h a f sta s suabng Plant in respo, 'e to an application filed by the Consumers of the shoes that were shown at the syrnposium (Appendix A)Power Company. The sport provides an update of the status ofthe Systemate Evaluaten Program (SEP) lasues that were not NUREG/CP-0108: PUBLIC WORKSHOP ON NUCLEAR POWER

PLANT UCENSE HENEWAL. HUGHE S.A. A; LlGON,0 Mafuity resolved 6n the SEP Integrated Plant Safe'y AssessmentSETH.S S. MITRE Corp April 1990 7Dpp 9005020348, MTR.Report (NUREG 0820 and NUREG-0820 Supplement 1). TNs90W00013 S3580136

report also addresses the status of requirements stemming from On 13 October 1989, the U S Nuclear Regulatory Commis-the accident at Three Mile island Unit 2, unresolved safetybues, and other important plant specific issues that have not son (NRC) issued an Advance Notice of Propnsed Rulemakingytt been resolved The staff has evaluated the #ssues related to on nuclear power plant Scense renewal The notice presented

the NRC's prehmnary regulatory phdosophy and approach forthe converson of the provtsonal operat ng hcense to a futhterm developing license renewa! regulabons, and Sohctied commentsoperahng license and concluded that the facility can conbnue to on a number of technical and pokey issues it also announcedtn operated without endangenng the health and safety cf the plans for a pubhc workshoo to discuss the issues and to recevopubic,

comments and information Representatives from 80 organga-tons attended the wontshop, held on 1314 November 1989, in

NUREG 1425: WELDING AND NONDESTRUCTIVE EXAMINA. Reston, Vaginia Subsequentry,12 organnations sut>mitted wnt.TION ISSUE 9 AT SEABROOK NUCLEAR STATION An inde- ten comments to the NRC. This report provides a summary ofpendent Review Team Report. SPESSARD,R.L; COLEY,J.; both workshop and wotten commentsCROWLEY,W.; et al. Ofc of the tc scutive Director for Oper-abons. Jufy 1990, 404pp. 9008140491. 54925.282.

NUREG/CP 0109: PROCEEDINGS OF THE SEMINAR ON LEAK-In response to congressunal concerns about the adequacy of BEFORE-BREAK Further Developments in Regulatory Pohcies

tM welding and nondestructrve examinaton (NDE) programs at And Supporbng Research WILKOWSKI,0 M Battelle Memonalthe Seabrook Nuclear Staten, NRC senor management estab- Inshtute, Columbus Laboratones CHAO.K,S Ta:wan Power CoIched an independent review team (lRT) to conduct an assess- February 1900. 352pp. 9003100303 S'043 231.ment The IRT focused on the quality of the hnished hardware The fourth h a sones of Intwnatonal LoaWwe Breaktrd associated records, as well as on the adequacy of the (LDB) Seminars supported in part by the U S Nuclear Roguta-onraft quahty assurance program as apphed to the fabricaton % mason was W at N Wonal hal Waq Mcnd NDE programs for pipe wolds Ths report documents the Taspos, Taiwan on May 11 and 12,1989 The seminar updatedhodings of that investigatort unaW $m aM supng ma@ @ W 4

tendees included representatives from regulatory agenctos,NUREG/CP 0105 V01: PROCEEDINGS OF THE SEVENTEENTH doctnc u% representabves, nuclear poww plant fabocators,

WATER REACTOR SAFETY INFORMATION MEETING research organuations, and acadamic inst tutons RegulatoryWEISS AJ Brookhaven Natonal Laboratory. March 1990. pohcy was the sutaect of presentaunns by Mr. G Artotto (U S,493pp. 9004030082. 53226.322' NRC, U SA), Dr. D Jarman (AECB, Canadal Dr. P, Miteha

TNs threo volume report contains 84 papers out of the 111 (ENEA DISP, naly) Dr. C. Faidy (EDF/Septon, France), and Dr.that were presented at the Seventeenth Water Reactor Safety K Takumi (NUPEC, Japan). A paper by Mr K. Wichman and Mr.Information Moebng huu .. .he Hohday Inn Crowne Pla2a, S Lee of the U S. NRC Office of Nuclear Reactor Regulaton isRockville, Maryland, dunng the week of October 23-25, 1989' tncluded as background matenal to these proccodngs; it dis-The papers are pnnted in the order of t!wur presentabon en each cusses the history and status of LDB appbcations in U S nucle-sesson and desenbe progress and results of programs in nucle' at power plants in add: ton, several papers on the supportingcr safety research conducted in this country and abroad For- research programs descnbod regulatory pohcy or industry stand.eegn participaton in tne meeting included ten differer' papers ards for flaw evaluations, e g-, the ASVE secton x1 code pro.

cedures. Supporting research programs were reviewed on theprssented by researchers from France, Germare Japan,Norway and the United Kingdom. The titles of the r wers and first and second day tr/ several participants from Taiwan. U S.,the names of the authors have been updated and may differ Japan, Canada, Idy, and France

from those that appeared in the final program of the meetingNUREG/CP 0110: PROCEEDINGS OF THE INTERNATIONAL

NUREG/CP4105 V02: PROCEEDtNGS OF THE SEVENTEENTH WORKSHOP ON NEW DEVELOPMENTS IN OCCUPATIONALDOSE CONTROL AND ALARA IMPLEMENTATION AT NUCLE-WATER REACTOR SAFETY !NFORMATION MEETING.AR POWER PLANTS AND SIMILAR FACILITIES DAUM.J W_WEISS,AJ Brookhaven Nabonal Laboratory. March 1990.

$25pp. 9004000184. 53310:211. DIONNE,0.J., KHAN T A Brookhoven Natonal Laboratory. Fnb-ruary 1990 534pp. 9004090237. DNL NUREG 52226See NUREG/CP 0105,V01 abstract 53312 016

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t

TNs report contains sumrwies of papers and discussions nos of inyttad papers concoming nuclear safety issues from the

presented at the Intematonal Workshop on New Developmentselectric utihties, the Electne Power Research institute (EPRI),

in Occupahonal Doe Control and ALARA implementaton at the nuclear hdustry, and frorn the govemments and industry in

Nuclear Power Plants and Sim4ar Facillbos held at BrookhavenEurope and Japan are also included. The summanes have teen

NaNoal Laboratory, Upton, New York, September 18 21,1909 compned in one report to provide a basis for meaningful discus-

The purpose of this workbhop was to bnng together scientists, s#on and informaton exchange dunng the course of the rneet-

engineers, regulators, and administrators who are involved with ing. and are grven in the oroer of thec presentation in each ses-cccupationa! dose control at nuclear facilit es to exchange Infor- sion.mabon on recent developments from their countnes 'ine elevencountnes represented included Canada, Finland, Frar,ce, Ger.

NUhEG/CR 0672 ADD 04: TECHNOLOGY, SAFETY AND COSTSOF DECOMMISS!ONING A REFERENCF E40lLING WATERmany, Itaty Japan, Luxembourg, Sweden, Switzertand, the

United Kingdom, and the United States of Amenca This work.REACTOR POWER STATION Companson Of Two Decommis-

shop was sponsored ntly by the U S. Nuclear Regulatory sioneng Cost Estimates DevelopW For The Same 'ommercialr

Nuclear Reactor Power Staton. KONZEx,GJa SMITH,R.1, Dat-Commiss on and the U.S. Department of Energy, in cooperaton tone Memonal Institute, Pactfic Northwest Laboratory. Decemberwith the Orgaruzation for Economic Cooperation and Develop- 1990. 73pp. 9012280246. 56257.259ment, Nuclear Energy Agency, This study presents the results of a compenson of a prwtous

NUREQ/^.P 0111: PROCEEDINGS Or THE SYMPOSIUM ON IN. decommissioning cost study by Pacifs Northwest LaboratorySERVICE TESTING OF PUMPS AND VALVES. Held At The, and a recem memissonog cut s% by M E@Hyatt Regency Hotet,Washingtun,0C, August 13, 1989, neenng. Inc, 6 the same commweial nusar pow reacWEG&G Idaho, Inc. (subs of EG&G, Inc.). October 1990.478pp. stabon The purpose of this comparatrve analysis on the same9011060112. EGO 2609. 55623:046. plant is to determire the reasons why subsequent esbmates for

The 1989 sympossum on interne Testing of Pumps and similar plants by othefs were significanuy hgher in cost and ex.Valves, jointy sponsored by the Board on Nuclear Codes and ternal occupatonal radaton exposure (ORE) tha n the PNLStandards of the Amencan Society of Mechanical Engineers suy. he pomary purpme of the onginal ste :y by PNLand by the Nuclear Regulatory Commission, provided a forum WWCRM was to prod intwmaton m me avadaNefor the discussion of current programs and methods for inserv. technology, the safety consideratons, and the probable costs6ce testing at nuc6 ear power plants. The sympossum also provid, and ORE for the decommissioning of a,large BWR power sta-ed an opportunity to discuss the need to improve inservice test, tion at the end of its operating hfe. Th e informaton was intend-ing in order to ensure the reliable periormance of pumps and ed for use as background data and bases in the modification ofvalves. The participation of industry representatives, regulators exisbng regulabons and in the development of new regutebonsand consultants resulted in the Jincussion of a broad spectrum pertaining to decommissioning activities it was also intendedof 6doas and perspectwes regarding the irnprovement of inserv. for use by utilities 6n planning for the decommissioting of theirIce teshng of pumps and valves at nuclear power plants, nuclear power statens, The TLG study was performed in 1989

NUREQ/CP 0112 V01: PROCEEDINGS OF THE THIRD INTER- for the same plant, Washington Pubhc Power Supply System's

NATIONAL ATOMIG ENERGY AGENCY SPECIALISTS' MEET- Unit 2 (WNP 2), that PNL used as its reference plant in its 1980ING ON SUBCRITICAL CRACK GROWTH. Opening Sesson decommissioning study. Areas of agreement and disagreementAnd Technical Sesson 1. Held At Moscow, USSR.May 14' are identifed, and reasons for the areas of disagreement are17,1990. CULLEN,W.H. Matenals Engineenng Associates, Inc. ' discussedArQonne Nat onal Laboratory. August 1990 312pp.

NUREG/CR 1667: RISK METHOOOLOGY FOR GEOLOGIC DIS-9009200013. ANL 90/22. 55214.324.This report is a compilaton of papers which were presented POSAL OF RADIOACTIVE WASTE. Scenaro Selecton Proce-

at the Thrd IAEA Specialists' Meety on Subentical Crack dure CRANWELL,R M.; GUZOWSKI,R.Vc, CAMPDELL,J E.; et

Growth, held in Moscow, USSR, on May 1417,1990. Volume 1 al, Sandia National Laboratorgis April 1990 114pp.

contains the welcoming remarks and attendance records, as 9005210151. SAND 001429. 53887.000well as the contnbuted papers for Sossen I, covenng Corrosion This report contains the desenphon of a procedure for select-

Fabgue. Volume 2 contains the contnbuted papers for Sessons ing scenaros that are potentany important to the esolaton of11. Ill, and IV, covenng Stress-Coirosion Cracbng. Test Methods. high level ramoactue wastes in deep geologic formatons, inModels and Mechanisms, and summanes of Nabonal Programs tNs report, the term scenano ts used to reproaent a set of natu-

in Argentina and the United Kingdom. Included as well are the rally occumng andtor human-induced conotons that representConclusions and Recommendatons (Session V) developed by reahstic future states of the repostory, geologic systems, and

tne organizing committee of the meeting and discussed and ap- ground water flow systems that might affect the release andtransport of radonuchdes from the repository to humant Theproved by the part c4 pants. scenano selection procedura discussed in this report is demon.

NUREG/CP-0112 V02: PROCEEDINGS OF THE THIRD INTER. svated by applymg u to the analysis of a hypothetical waste dis-NATIONAL ATOMIC ENERGY AGENCY SPECtAttSTS' MEET- posal ade contairung a bMded.sau formaton as me hostING ON SUBCRITICAL CRACK GROWTH. Technical Sessons medom fu me repository. A final set of 12 scenanos is select.II, til, And IV And Recommendatons And Conclusions Session ed b mis site.V. Held At Moscow, USSR.May 14 17,1990 CULLEN W.H Mate-nals Engineenng Associates, Inc * Argonne Nabonal Laborato- NUREG/CR 2000 V08N12: UCENSEE EVENT REPORT (LER)ry. August 1990. 2t9pp. 9009200015. ANb90/22. 55215 276 COMPILATION For Month Of December 1989 * Oak Ridge Na-

See NUREG/CP-0112,V01 abstract. bonal Laboratory. January 1990. 70pp. 9002120184 ORNL/

NUREG/CP 0113: TRANSACTIONS OF THE ElGHTEENTH NSIC-200. 52611:131.

WATER REACTOR SAFETY INFORMATION MEETING.This monthly report conta:ns Licensee Event Report (LERI

WEISS.A.J. Office of Nuclear Regulatory Research (Post operabonal informaton that was processed rnto the LER data

860720). October 1990,21Bpp. 9010230093 55471.220. file of the Nuclear Safety information Center (NSIC) during the

This report contains summanes of papers on reactor safety one month ponod identified on the cover of the document. The

research to be presonted at the 18th Water Reactor Safety tru LERs, from wNch this informahon is denved, are submitted to

formation Meeting at the Hohday Inn Crowne Plata in Rockville, the Nuclear Regulatory Comrrussion (NRC) by nuclear power

Maryland, October 22 24, 1990. The summanes bnefty descnba plant hcensees in accordance with federal regulations Proco-

the programs and results of nuclear safety research sponsr" %res for LER reporbng for tevmons to those events'occurnng

by the Office of Nuclear Regulatory Research, USNRC. Surr ar to 1984 are desenbod in NRC Regulatory Guide 1.16 and|

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|i

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, . . .


NUREG4161, " Instructions for Preparaten of Data Entry See NUREG/CH 2000,V00,Nt2 abstractSheets for Licensee Event Reports? For thoco events occurnngon and after January 1,1984, LERs are being submitted in ac- NUREG/CR 2000 V09N11: LICENSEE EVENT REPORT (LER)cordance with the revvod rule containod in Title 10 Part 50.73 COMPILATON For Month Of November 1990 * Oak Rdge Na-

. of the Code of Federal Regulatons (10 CFR 50.73 Licerisee tonal Laboratory. December 990, 73pp. 9101160011. ORNL/Event Report System) whKh was pubbshed 6n the Federal Reg. NSIG200. 56428 060.ister (Vol 48, No.144) on July 26,1983 NUREG 1022, V See NU9EG/CR.2000,V08,N12 abstract7ansee Event Report System . Descnpton c,f Systema andJuidelines for Reportng,' provdes supporting guidance arid in- NUREG/CR 2331 V09 N3: SAFETY RESEARCH PROGRAMSlarmaton on the revised LER rule. The LER aummanes in th:s SPONSORED BY OFFICE OF NUCLEAR REGULATORYreport are ananged alpnabebcally by facility name and then RESEARCH. Progress Report July-September 1989. WEISSAJ.cryonologically by event date for each facshty, Component. Brookhaven Natonal Laboratory. February 1990. 104pp.system, keyword, and component vendor indenes follow the 0003070194. BNL NUREG41454 52812.282.summanes. Vendors are those identified by the utihty when the This progress report desenbes cunent activities and techrscalLER fonn is ntiated, the keywords for the component, system, progress in the programs at Brookhaven National Laboratoryand general keyword indexes are ass #gned by the computer psorW h me De d R@W AWM Nmusing correlaton tables from the Sequence Coding and Search of Engineenng. Omson of Safety issue Resolut>on, and OmsonSgtem. of Systems Research of the U.S. Nuclear Regulatory Commas-

Sort Off ce of Nuclear Regulatory Research following the reor,NUREG/CR 2000 V09 N1: LICENSEE EVENT REPORT (LER) ganaabon in July 1988 The previous reports have covered tne

COMPtLATION,For Month Of January 1990. * Oak Ridge Na- pered October 1,1976 through June 30,1989.t F bruary 1990.112pp. 9004090292. ORNL/

NUREG/CR 2331 V09 N4: SAFETY RESEARCH PROGRAMSSee NUREG/CR 2000,V08,N12 abstract. SPONSORED BY OFFICE OF NUCLEAR REGULATORYRESEARCH October-December 1989. WEISS A.J. BrookhavenNUREG/CR.2000 V09 N2: LICENSEE EVENT REPORT (LER) Natonal Laboratory June 1990.140pp. 9007120223. DNL.COMPILATION For Month Of February 1990. * Oak Ridge No. NUREG 51454 54466:291,tional Laboratory. March 1990.120pp. 9004090225. ORNL/

NSIC.200. 53314:122 This progress report oescribes current a";tmtses and technscalSee NUREG/CR-2000,V08,N12 apstract. progress 6n the programs at Drookhaven Natsonal Laboratory

sponsored by the Dvisson of Regulatory Apphcatons. OmstonNUREG/CR-2000 V09 N3: LICENSEE EVENT REPORT (LER) of Engineenng. Dvision of Safety lasue Resolotson, and Dvisson

COMPILATION For Month Of March 1990. * Oak Rdge haton. of Systems Research of the U.S. Nuclear Regulatory Commis-al Laboratory. April 1990. 83pp. 9005210152. ORNL/NSIC 200. son, Office of Nuclear Regulatory Research following the reor-53886.325,

ganaaton in July 1988. The prevous reports love covered theSee NUREG/CR 2000,V08,N12 abstract penod October 1,1976 through September 30,1989.

NUREG/CR 2000 Va9 N4: LICENSEE EVENT REPORT (LER) NUREG/CR 2601 AD001: TECHNOLOGY, SAFETY AND COSTSCOMPILATION.For Month Of Aptl 1990. * Oak Rdge National

OF DECOMMISSIONING REFERENCE LIGHT WATER REAC-Laboratory. May 1990. 83pp. 9006080270. ORNL/NSIC 200.TORS FOLLOWING POSTULATED ACCIDENTS. Re-Evaluation540741072.

See NUREG/CR.2000,V08,N12 abstract Of The Cleanup Cost For The Doihng Water Reawr (BWR)Scenano 3 Accident From NUREG/CA.2601. tmzEK,G.J.;

NUREG/CR 2000 YO9 H5: LICENSEE EVENT REPORT (LER) SMITH,R.i Dattelle Memonal Insbtute, Pacific Nethwest Labo-COMPILATION For Montn Of May 1990. * Oak Adge Natsonal ratory. December 1990. 54pp. 0012280218. 56258.018.Laborabry. June 1990. 96pp. 9007120242. ORNL/NSIC 200. eshmaW cosu fu posbaccent cManup at the rob5M8 009 ence BWR (developed previously in N'JREG/CR 2601, " Tech-

See NUREG/CR 2000,V08,N12 abstract. nology, Mety, and Costs of Decommissoning Reference Ligm

NUREG/CR 2000 V09 N6: LICENSEE EVENT REPORT (LER)Water Reactors Following Postulated Accdents") are updated

COMPILATION For Month Of June 1990 * Oak Rdge Nabonal to January 1989 dohrs in tnis report A Smple fomula for es-calating post-accdent cleanup costs is also presented AccidentLaboratory. ;uly 1990. 89pp. 9008140508. ORNL/NSIC-200.cleanup following the most severe accident desenbed in54927;069.

See NUREG/CR 2000,V08.N12 abstract. NUREG/OR.2601 (i.e., the Scenaro 3 accident) is estimated tocost from $1.22 to $144 tullion, m 1980 dollars, for assumed

NU*,EG/CR 2000 V09 N7: LICENSEE EVENT REPORT (LER) escalaton rates of 4% or 8% in the years following 1989. TheCOMPILATION.For Month Of July 1991 * Oak Rdge Nabonal time to accomphsh cleanup remamed unchanged from the 8.3i

Laboratory. August 1994 101pp. 9009110143. ORNL/NSIC. years orgnally estimated. No reanalyss of current informabon.

200. 55194:181. on the technical aspects of tmh 2 cleanup has been performed.See NUREG/CR 2000,V08,N12 abstract. Only the cost of inflaton has been evaivated once the ongenal

NUREG/CR 2000 V09 N8: LICENSEE EVENT REPORT (LER)PNL analysts was completed.

COMPILATION.For Month Of August 1990. * Oak Ridge Nabon- NUREG/CR 2850 V09; POPULATION DOSE COMMITMENTS. al Laboratory. September 1990. 88pp. 9010090032. ORNL/t. N$1C-200. 55319:255. DUE TO RADIOACTIVE RELEASES FROM NUCLEAR POWER

PLANT SITES IN 1987. BAKER,0.A. BatteRe Memonal Inshtute,'

See NUREGICR 2000,V08,N12 abstract Pacific Northwest Laboratory. August 1990 187pp.

NUREG/CR 2000 V09.N9: LICENSEE EVENT REPORT (LER) 5W282.COMPILATION.For Month Of September 1990. * Oak Rdge Populabon radkabon dose commstments have been estimatedNahonal Laboratory. October 1990. 114pp. 9011150041 from reported radonuchde releases from commercial power re.ORNL/NSIC-200 55737.071, actors operating dunng 1987, Fifty year dose commitments from

See NUREG/CR-2000,V0%N12 abstract a one year exposure were calculated fro::1 both teou4d and at.mosphenc releases for four population groupa (infant, child,

- NUREG/CR 2000 V09N10: LICENSEE EVENT REPORT (LER) teen ager and adult) residing between 2 and 80 km from eachCOMPILATION:For Month Of October 1990, * Oak Rdge Na- of 70 sites. This report tabulates the results of these calcula-tional Laboratory. November 1900. 96pp. 9012100347. ORNL/NSIC 200. 55990:215. tons, showing the dose commitments for both kquid and air.

Dorne pathways for each age group and organ. Also included

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for each rit the sites is a histogram showing the tracton of the NUREQ/CR 3668: MINET CODE DOCUMENTATION VANTUYLE,G.J; NEPSEE,T.Ca GUPPY, J G Brook %aven Nabonal

total powston witNn 2 to 80 km around each site receivingvanous average dose commitments from the avtsorne pathways.

Laboratory Decernber 1989.321pp 9002120129. DNL NUREG-

The total dose commitments (from both hqud and airborne 51742. 52562.219.The MINET computer code, developed for the transient anaty-

pathways) for each site ranged from a hegh of 15 person-tem tosas of fivid fiow and heat transfer. 6s documented in tNs four-a low of 0.0016 person rem for the sites with plants operatingpart reference in Part 1. the MINET models, wNch are basedthroughout the year with an anthmete mean of 1.1 person-tem. on a mumentum integral network method, are described TheThe total population dose for all sites was estimated at 78 varous aspects of ubhrng the MINET code are escussed in

persorkrem for the 150 milhon people consdered at nsk. Part 2, The User's Manual. The tNrd part is a code desenpbon,NUREQ/CR 3145 V08: GEOPHYSICAL INVESTIGATIONS OF etaW the basic co@ Mwe and h vanws shwm

THE WESTERN OHIO INDtANA REGION Annual and Wm tat mau @ MET. In Part 4, example inputReporLOctober 1988 September 1981 YOUNG,C.J.; LAY,T.: a, as weh as mnt vaWaton aMes aM appleatom ofJACOBSON.J. McNgan, Uruv of, Ann Arbor, MI. February "''""***" #1990. 62pp. 9003070254 52802:257.

Earthquake Ntwity in the Western ONo-Ind,ana regon has NUREG/CR 3873: EFFECT OF WELDING CONDITIONS ONteen morvtored with a precison seismograph network consist. TRANSFORMATION AND PROPERTIES OF HEAT AFFECTEDing of nine statons located in west central ONo and four sta- ZONES ON LWR VESSEL STEELS. LUNDIN,C D.;tions located in in6ana. Three local earthquakes have been re' MOHAMMED.S. Tennessee, Univ. of, Knoxville, TN. * Oakcorded dunng tNs report penod, with magnitudes ranging from Rdge Nabonal Laboratory. November 1990. 148pp.

0.7 to 2.2. This may represent a return to a more normal local 9012100339. ORNLSUB737637/1. 55991:106lovel of seismicity after an anomalousty low level in the 2 years The contnuova coonng transformabon and isotnermal trans-following the occurrence of the m(b) = 4.5 earthquake, in SL formaion Dohaviors were determned for SA 508 and SA 533Marys, ONo on July 12,1986. If the quiescent penod reflected matenals for cordbons pertairwng to the standard heat t'est-a relear,e of most of the accumulated crustal strain by the St. ment and for the coarse-grained regon of the heat-effectedMarys event, then the increased level of seismicity may mark rone. The resulting diagrams help to delect welding conditionsthe beginr4ng of a new phase of strain a:cumulation. Four re- Sat produce the most favorable nucroconstituent Recommerygional events were also well recorded by the array statons dabons are provided regard.ng weld energy input and postwelddunng tnis year All of these events occurred in regens with heat treatment condbons to opbmue heat-affected 200e tough-we%stablished Nstones of seistmetty. Their magnitudes range ness. The reheat cracking tendency for both steels was evailual-

frun 3.1 to 4.4. ed by metallograpNc studios of simulated neat affected zone,

NURsG/CR 3444 V07: THE IMPACT OF LWR DECONTAMINA-Structures subjected to postweld heat treatmont cycles and se-multaneous restraint. Both SA 533 grade B class 1. and SA 508

TIONS ON SOllDIFICATION, WASTE DISPOSAL AND ASSO. class 2 stects cracked intergranularty, The stress rupture param-CIATED OCCUPATIONAL EXPOSURE. S00 P.; MILIAN.LW, eter showed thC SA 500 class 2 was more suscepubie toBrookhaven Nabonal Laboratory. July 1990. 74pp 9006070400. a class 1 Cold crackingreheat cracking than SA 533 gradeBNL NUREG 51699. 54844:188. tests (Battetie Test and University of Messee modifieo hydro-Stu$es were camed out to iruestigate if simulated decon-tarninabon ret. gent / resin waste combinations could give nse to gen susceptMty test) indscated that a higher preheat tempera.

gas generaton and thermal excursions during dewateringture is required for SA 508 class 2 to avoid cracking than is re-

,

events. The resufts of temperature measurements and visuai quered for SA-533 grade B class 1 Further, the hydrogen sus-

|ooservabons are grvert Some limited work was also camed out

ceptibihty tests snowed that the SA 500 is more suscepuble to

to determine ff gamma irradtaton of iorvexchange resens causes hydrogen embnttlement than the SA 533

structural changes and losses in ion-exchange caputy. In add- NUREQ/CR*3950 V06: FUEL PERFORMANCE ANNUALton, the Corrosion of vanous Container matenals in simutated REPORT FOR 1988. BAILEY,W.J. Battelle ,Jemorial insbtute,decontaminabon resin waste was studed. In partcular, the ef. Pacific Northwest Laboratory WU.S. Reactnr Systems Brancftfects of gamma irrad aten were quant feed. March 1990.175pp. 9005020352. PNL 5210. 53589.223.

| NUREG/CR 3469 YO5: OCCUPATIONAL UOSE REDUCTION AT This annual report, the e6eventh in a senos, provdes a bnef

NUCLEAR POWER PLANTS: ANNOTATED BIBLIOGRAPHY desenption of fuel performance dunng 1988 in commercial nu-

OF SELECTED READINGS IN RADIATION PROTECTION AND clear power piants Brm summanes of fuel design changes, fueli ALARA. KHAN,T.A.: TAN.H.; BAUM.J.W.: et al Brookhaven Na- surveillance programs, fuel operatng exponence and trends,l

tional Laborsay. September 1990. 95pp 9010090029. BNL- fuel problems, hegh burnup fuel expenance, and items of gener-I NUREG 51706,55319:160- al significance are provded. References to additenal, more de-i

| One of the functions of the ALARA Center is to collect and tailed informaten and related NRC evaluatons are included

iesseminate informabon on dose reducten at nuclear powerplants. TNs is the f:fth report in the senes of biblographies of NUREG/CR 4214 R01 Pt HEALTH EFFECTS MODELS FOR NU.Selected readings in radahon protecbon and ALARA that the CLEAR POWER PLANT ACCIDENT CONSEQUENCECenter pubhshes penn6cany. The abstracts in tNs biblography ANALYSIS. Low LET RadatortPart I:Introductiott Integrabon

were selected from proceecngs of technical meetings, jouma!s, And Summary. EVANS,J.S. Harvard School of Pubhc Health,

research reports, searches of informaton data bases and re, Boston, MA. * Sandia National Laboratones January 1990

pnnts of published arbcles provided to us by the authors. The 133pp 9002120313. SAND 85-7t85. 52597:294.

abstracts relate in one way or another to dose reducbon at nu- TNs report provides dose-response models intended to be

clear power plants, whether it is through good water chemistry, used in estimating the radclogical health effects of nucle #/

improvements in nuclear matenals, better control of corrosion, power plant accMents. Models of earty and conbnuing effects,robobcs, and remote toohng or good operabonal health physics cancers and thyfoed nodules, and genetic effects are provided.

The report contains 278 abstracts. Subject and author in6ces Two parameter Weibull hazard functions are recommended for

are proveed. The subject index covers all prevous volumes in estimaung the nsks of earty and continuing hearth effects Three

tNs senes. All informaton in the current volume is also evailable potenbally lethal earty effects-the bematopoiebc, pulmonaryfrom the ALARA Center's on-line service, whech is accessible by and gastrointestinal syndromes-are considered. In addibon,personal computer with the help of a modem. The preface of models are provided for assessing the nsks of several non-the report explains how the sendce may be accessed. The on- lethal earty and conbnuing eNecianclu6ng prodromal vomitinghne service will be updated as new informaton is recerved. and ciarrhea, hypothyroidtsm and rad aDon thyroidtis, skin

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burns, reproductive effects, and spontar tous abortons. Linear service condibons, and NDE capabilttias ard uncertaintes The- cnd knear, quadratic models are recommenied for estmating program scope is imvted to ISI of the pnmary systems includingcancer nsks Parameters are given for anat,nng the nsks of the piping, vesset, anc other inspected Components This is aseven types ut cancer en edutts- leukemia, boi % lung, breast, progress report covenng the programmatic work from Octotergastroentestinal, thyroad and "other" The categoi r "other" card 1987 through March 1988.cors, ts Intended to reflect the comNned nsks o multiple mye-bma, fymphoma, and cancers of the bladder, kdney, brain, NUREG/CR 4469 V09: NONDESTRUCTIVE DAMINATIONovary. uterus and cervix Models of cNidhood ci neers due to (NDE) RELIABILilY FOR INSERVICE INSPECTION OF LIGHT"in utero" exposure are also provided. For most cancers, both WATER REACTORS Somiannual Report,Aprit. September 1988incidence and mortality are addressed. The mi sols of cancer DOCTOR,S.R.; DEFFENBAUGH,1; GOOD.M Sa et al. Battenensk are denved largGy from information sum' .anred in DEIR Memonal Institute, Pacific Northwest Laboratory. Novembertil-with some adtustment to reflect rnore reuent studes. The 1989 115pp. 9002120296. PNL 5711. 52597.100.effect of the remed dosimetry in HirosNme and Nagasaki has Evaluation and improvement of NDE Rehatxhty for inserveenot been considered. Linear and lineartadratic models are inspecton of Ltght Water Reactors (NDE Rehabihty) Program atalso recommended for assessing genebc nsks. Five classes of the Pacific Northwest Laboratory was estabbshed by the Nucto-genetic disease-dormnant, mhnked, aneuploidy, unbalanced ar Regulatory Commssion to determine the rehabihty of cunenttransiocations and multifactonal dseases-are consdered In insonnce inspection (tSI) techniques and to develop recommon-additon, tne impact of radiat#on Wuced genetic damage on the dabons that mil ensure a suitably Ngh inspecton rehabikty. Theincidence of peri-implantation embryo bsses is oscussed. Theuncertainty in modehng radiologica; heatth nsks is addressed by

obectrres of tNs program include determining the rehabihty ofi

ISI performed on the pnmary systems of commercial hght waterproviding central, upper, and lower estimates of all model pa- reacters (LWRS), using probabihstic fracture mechanics anatysisrameters Data are provided wtach should enable ar,alysts to to determine the impact of NDE unrehabihty on system safety;consdor the timing and seventy of each type of heatth nsk. and evaluating reliabitty improvements that can be achievedNUREG/CR 4219 V06 N2: HEAVY SECTION STEEL TECHNOL- with improved and aovanced technology. A final obtectiva is to

OGY PROGRAM. Semiannual Progress Report For Apni-Sep formulate recommended revisions to ASME Code and Regula-tember 1989. PENNELL,W.E. Oak Ridge National Laboratory. tory requirements, based on matonal prope'tres, service condi.August 1990. 96pp. 9011090211. ORNL/TM-9593 E5660:156 tsons, and NDE uncertarntes The picgram scope is hm,ted to

The Heavy-Section Steel Techrology (HSST) Program studies ISI of the pomary systems including the paping, vessel, andconcern all areas of the technology of matenals fabncated into other mspecw componets TNs ts a progress report covenngtNck-section, pnrnary-coolant containment systems of hght- tre programmtsc work from April 1908 through Septemberwater cooled riuclear power reactors. The focus is on the be- Nhavior and structJral integrity of steel reactor pressure vessels(RPVs) containing crackhke flaws. Dunng tNs pered, ana'ytical NUREG/CR 4403 V10: NONDESTRUCTIVE EXAMINATIONefforts included examerung the influence of high crack. arrest (NDC) RELIABILITY FOR INSERVICE INSPECTION OF LIGHTtoughness on RPV integnty and an increased emphasis on eval- WATER REACTORS Semeannual Report,0ctooer 1968 Marchuating large international structural expenments. Two areas of 1989. DOCTOR,5 R.; DEFFENBAUGH.J.; GOOD M S ; et alNRC topical support were conhnued. (1) the evaluaton of Batteile Memonal institute, Pacific Northwest Laboratory. Sepmechanisms for enhanced low temperature. Iow-flux irradiaton tember 1990 96po. 9010230079 PNL 57t t. 55472181

d W Rek b bembattlement that may affect the integnty of RPV supports; and hh W(2) an overall assessment of low upper sheit (LUS) welds in service inspection of Lrght Water Reactors (nut Rehabbt )fRPVs with special empnasis on reevaluating ductile teanng en_ Program at the Pactfic Northwest I.aboratory was established bytena. The first four stub panel crack-arrest tests were per. the Nucioar Regulatory Commission to determine the retiabihtyformed Positest matonal characten ston was performed for of current inse e mspection (ISI) techniques and to developclad plate and wide-plate Senes 2 test matenals. Stabshcal recomandate that wdl ensure a suitably high inspection reh-analyses were performed on the data from the Fifth HSST trra- ablity. The ce sves of this program n lude determnng thediaton Senes on the study of K(Ic) sNfts. Anafysis of the irrade rehability of ISi wformed on the pnmary setems of commer.sted tracture-toughrmss testing was completed for the Seventh cial kg4 water roactors (LWRs); using probabee M:ve me-HSST trradtabon Series on cladding Detaileo planning was char %:s analysis to determine the impact of NDE uscWW onbegun for the next pressun2ed-thermal' shock expenment, system safety; and evaluabng rehabihty improvements that wFTSE-4, to examine the extent of duut se teanno and its interac- be acNeved with inproved and advanced technology _ A finalbon with cleavage fracture in an LUS weld metal objective is to formulate recommended revisions to ASME Code

and Regulatory requirements, based on matenal properties,NUREG/CR-4469 V08: NONDESTRUCTIVE EXAMtNATION(NDE) RELIABILITY FOR INSERVICE INSPECTION OF LIGHT Service condtions, and NDE uncertainties. The program scopoWATER REACTORS. Semiannual Report, October 1987 - March is hmited to IS) of the pnmary systems includng the pipiry1988. DOCTOR,S R.; DEFFENBAUGH,J.; GOOD M.S.; et al. vessel, and other corrponents inspected in accordance wiin

Battelle Memonal Institute, Pacific Northwest Laboratory. Octo- Section XI of the ASME Code. This rs a progress report cover.ing the programmatic work from October 1988 through Mathber 1989. 67pp. 9002120167. PNL 5711. 52603:122,t 989.

The Eva!uabon and improvement of NDE Rehabihty for Ir>service inspection of Light Water Reactors (NDE Relabr.y)

NUREG/CR.4525: CLOSEOUT OF lE BULWTIN 84-03 REFUEL.Program at the Pacific Northwest Laboratory was estal',aned by ING CAVITY WATER SEAL FOLEY,W J ; DEAN.R.S.;the Nuclear Regulatory Commsssion to determine the rehabdity HENNICK A. PARAMETER, Inc. June 1990 88pp 9007120236of current inservice inspection (ISI) techneques and to develop PARAMETER IE155 54468 336recommendations that will ensure a suitabfy Ngh inspection reis Documentabon is provided in tNs report to close LE Bulietmabhty. The objectNes of ths program include de18cmang thereliabehty of ISI performed on the pnma*y systems of commer.

64-03 on the subject of refuehng casity water seals The butistinwas assued on August 24, 1984, to att power factor fa% tiesCial hght water reactors (LWRs); using probabihsbc fratture me-except Fort St. Vrain. Because the excluded plant is gas cooloc

Chanics anatysis to determine the impact of NDE unreuabehty on and grapNte moderated. the suL ect ot the buttetin does notisystem safety; and evaluating reliabihty improvements th/it can apply to that plant. The event causing the safety concern wasbe acheved with impfoved and advanced technology A fina!objectlye rs to formulate recommended revisions to ASME Code failure of the pneumabc seats contaming water in ttw retuohng

cavih of Haddam Nock on August 2 t,1984 The Cavity hadand Regutatory requirements, based on matenal proporties, been tuded in preparahon for refuehng. but when the seals

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Main Citations and Abstrccia 19

failed. water level dec eased from ful1 level just below the oper- NURE0/CR-4550 V3 RIP 2: ANALYSIS OF CORE DAMAGE FRE.ating floor down to the level of the reactor vessel flange. On OUENCY: SURRY, UNIT 1,1NTERNAL EVENTS APPENDICES.

May 17,1988, another refuehng cavity seal leakage (about BEF.TUCIO,R C : JULIUS.J A El Sennces, Inc. * Sandia Nation-

three feet in water level) occurred at Surry 1, which was in the al1.aboratonos Apnl 1990. 702pp. 9006080169. SANC36 2084.

mad $6 of a refueling and maintenance outage. Evaluaton of 64 J79.127.

Utihty responses and NRC/ Region nspecten reports in accord. See NUREGICR 4550,V03,R01,P01 abstract

ance with a specific cntenon shows that the bulletin is closedNUREG'CR 4550 V3 RIP 3: ANALYSIS OF CORE DAMAGE FRE-

for 114 (97%) of the 118 affected facAtses it is concluded that OUENCY: SURRY POWER STATION. UNIT 1 EXTERNALthe concerns of the bulletin have been resolveo through design EVENTS. BOHN# % LAMBRIGHT,J.Aa DANIELS L.; et al.and procedure reviews and correctrve actons taken by licens. Sandsa Natonal Laboratonet December 1990. 393pp.ees. Follow-up items are proposed for use by NRC Regon il in 9101090373 SAND 86-2084. 56298.285.closing the butletin for the four (4) remairung facihties with open This report presents the anatysis of external events (earth-bullotin status. NRC Regon 11 veMes that the bulletm will not quakes, fires. floods. etc.) performed for the Sorry Power Sta-be closed for these four TVA facihties until construction is com- ton as pad of the USNRC-sponsored NUREG 11bo program.pleted. Background information is supphed in the introducton Both the internal and oCernal events analyses make full use ofand Appendix A. recent insights and developments in nsk assessment methods,

In addition, the extemal event analyses make use of newty do.NUREG/CR 4550 V01 R1: ANALYSIS OF CORE DAMAGE FRE- veloped simphfied methods As a first step, a screeneng anatysis

QUENCY: INTERNAL EVENTS METHODOLOGY. was pwformed which stowed that aH eximial events m mg-ERICSON.D M. ERC Envronmental & Energy Services. Inc, hgNo except for f res and seismic events Subsequent detailedWHEELER T.A.: SYPE,T.T.: et at Sanda National Laboratones. analysis of fires resutted in a total (mean) core damage frequen.January 199& 482pp. 9002120309. SAND 86 2084. 52576 007. cy of 1.13E 5 per year. The seismic anahsis resulted in a total

NUREG 1150 examines the nsk to the pub 4c from a se(ected (mean) core damage frequency of 1.16E-4 per year usinggroup of nuc4ar power plants. This report desenbes the rneth- hazard curves developed by Lawrence Livermore National Lab-odology that evohed as the intemal event core damage fre- oratory and 2E5 pw year using hazard ces helopd byquencies for four plants were generated in support of NUREG, the Electne Power Research institute. Uncertainty ana*yses1150, The ob!ectue is to perform an analysis that civsefy ap- were pedormM and dommant compownts and sources of umproximates a stale-of the art Level | Probabinstic Risk Assess C##N ** *ment (PRA) Therefore, in porry;"c, : e errular m %s ned inprevious PRAs. However, inis methodology, based upon preyb NVREG/CR-4550 V4 RIP 3: ANALYSIS OF CORE DAMAGE FRE-ous studes and us4ng ".inalysts ernanenced in these techniques, OVENCY: PEACH BOTTOM. UNIT 2 EXTERNAL EVENTS.allows the anatysis tu be foc6ed upor. P siected areas. With this LAMBRIGHT,J A; BOHN.M P.; DANIEL,S L; et al. Sanda Na-approach only the mod c.portant .ystems and failure modes tional Laboratones December 1990. 471pp. 9101090410.are emphastred and modeioc in #tani, and the data and human SAND 86 2084. 56313 086reliabdity analyses are simpfified An anahsis employing this Tu repor1 presents the anaiysrs of extornal events (earth-methodology (endusve of exicnal reviews) can be completed _1uakes, fires, floods, etc.) performed for the Peach Bottomin nine to tweNe monte,s uaing two or three futhtime experk Atomic Power Staten as part of the USNRC-sponsoredenced systems analysts and part time personnel in other areas, NUREG 1150 program. Both the tnternal and esternal eventssuch as data analysrs and human rehability analysis. This is s'9- analyses make tutt use of recent insghts and developments innaricantly faster and less expensive than previous ana'yses, but nsk assessment methods In additon, the extesnal event analy-even so, most of the insights that are obtained by the more ex* ses make use of nowh developed simpnhed methods As a f r$tpenswe stud es are still provided step, a screening anatysis was performed which showed that all

external events were noghgible except for hres and seismicNUREG/CR-4550 V3R1P1: ANALYSIS OF CORE DAMAGE events. Subsequent detaited anahsis of fires resutted in a total

FREQUENCY;SURRY, UNIT 1,1NTERNAL EVENTS. (mean) core damage frequency of 1,95E 5 por year. The seis.BERTUCIO.R.C.; JULIUS.J A. El Services, Inc. * Sandia Nation- mac analysis resutted in a total (mcan) core damage frequencyal Laboratones. Apni 1990. 484pp 9006080175. SAND 86-2034. of 7.66E 5 per year using halard curves developed by Law-54078.003. rence Livermore National Laboratory and 3.00E 6 per year using

This document contains the accident sequence analyses of hazard curves developed by the Electnc Power Research Insteinternally instiatbd events for the Surry Nuclear Staton, Unit 1. tute. Uncertainty analyses were performed, and dominant com.This ts one of the fue plant analyses conducted as part of the ponents and sources of uncertainty were identsed.NUREG-1150 effort by the Nuclear Regulatory Commission.NUREG-1150 documents the nsk of a selected group of nuclear NUREG/CR 4550 V5R1P1: ANALYSIS OF CORE DAMAGE FRE-power plants The work performed and desenbed here is an ex- QUENCY: SEQUOYAH.UNtT 1. INTERNAL EVENTS.

tensive teanalySs of that pubhshed in November 1986 as BERTUCIOAC.; BROWN.S R El Services, Inc, * Sand a Na-NUREG/CR4550, Volume 3 It addresses comments from nu- tional Laboratones Apol 1990. 422pp. 0005210262. SAND 86-

rnerous revwwers and srgnificant changes to the plant systems 2084. 53890'118and procedures made since the first report The uncerwnty This document contains the accident sequence analyses of

ana9 sis and presentation of results se also much improved. Intemalty initiated events for the Sequoyeh, Unst t nuclearThe context and dotad of this report are Grected toward PRA power pint. This is one of the fue plant analyses conducted aspractitoners who need to know how the work was performed part of the NUREG 1150 effort by the Nuclear Regulatory Com-

and the details for use in further studies. The mean core mission (NRC) NUREG 1150 documents the ask of a sofocteddamage frequency at Surry was calcutated to be 4.0E 5 per group of nuclear power pivts. The work performed and do-year, with a 95% upper bound of 1.3E 4 and 5% lower bound scnbod here is an extensNe reanalySs of that pubhshed in Fet>-

of 6.8E 6 per year. Station blackout type accidents (loss of all ruary 1987 as NUREG/CR-4550 Volume 5 it addresses com-AC power) were the largest contnbutors to the core damage fro- ments from numerous reviewers and significant changes to the

quency, accounting for approximately 68% of the total. The plant systems and procedures made since the first report. Thenort type of dominanl contnbutors were Loss of Coolant Acci- uncertainty analyvs and p.esentaton of results are also muchdents (LOCAs) These sequences account for 15% of core improved. The mean core damage frequency at Sequoyah was

damage frequency N nther type of sequence accounts for calculated to be 5 7E 5 per year, with a 95 percent upper bound

more than 10% of core da nage frequency. of 1.BE 4 and 5 percent lower bound of 1.2E 5 per year. Loss.

1

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1


of coolant type accdents were the largest contnbutors to core dstnteens and the ratonale support,ng the distnbutions fordamage frequency, accounting for approxirnate y 62 percent of the quesbons posed to the tr> Vessel Export Panetr

the total. The next most domsnant type of accdents were sta-ton blackout (loss of all AC powett which account for 26 per. NUREG/CR 4551 V2RIPh EVALUATION OF SEVERE ACC4,cent of core damage frequenew DENT RISKS (WitrtCATION OF MAJOR INPUT

PARAMETERS M4CCS liput SPRUNG.J L, Sandia NatonalNUREG/CR 4550 V5R1P2. ANALYSIS OF CORE DAMAGE FRE- Laboratones ROLLSilNa A Gram,Inc HELTON.J C; et at. Ar.

QUENCY: SEOVOY/.H. UNIT 1. INTERNAL EVENTS &PENDI- trona State Unsv , Terape. AZ. December 1990. 252pp.CES. BERTUCIO,R C.; BROWN.S R. El So vices. Inc * Sodia 9101090454 SAND 86-1309 56298 OOLNational Lcboratones. Apol t i )0. 686pp. 9005210142-SAND 66 2084. 63862:001. Estimaton of offsite accdont consequences is the customary

final step in a probabilmtic assessment of the nsks of severeThis document containt *he appendees tor the accdont se-nuclear reactor accdonts. Recently, the Nuclear Regulatoryquence analyses of enterne inibated events for the Sequoyah,Comrmsson reassessed the nsks of severe accidents at fiveUrvt t rrsclear power plent. ins is one of the five plant analy' U.S power reactors (NUREG-1150) Offsite accdent conse-ses conduct ( 3 as part of the NURiiG 1150 eh. . by the Nucle'

at Rogulatory Comrmscon (NRC). NUREG-1150 will docurment quences tor NUREG 1150 source terms were estimated usingthe MI .COR Accdont Consequence Code System (MACCS)the nsk of a selected groi uclear pov 1r plants. The workBefore these calculatons were periormed, most MACCS anputperformed and desenbed 9 eriensive reanahus of that

published ln February 198s (EG/CR a550, Volume 1 it parameters were reviewed, and for each parameter reviewed, abest. estimate value was recommended TNs report presentsaddresse? coniments from tw aus reviewors and Sagnahcant

changes to the plant systems wid procedures made since the the resuha of these reviews Specificany, recommended values

first report The uncertainty anaysis and presentation of results and the basis for their selection are presented for MACCS at.

are also much imoroved. The mean cca damage frequency at mosphenc and biospnenc transport, emergency response, food

Sequoyah was calculated to be the 5 7E 5 per year, with a 95 pathway, and economic input parameters Dose conversion fac,

percent upper bound of 1.8E-4 and 5 pe cent lower bound of tors anc hearth effect pa.rameters are not reviewed in this,,pyt

1.2E 5 per yea.. Loss-of coolant type accdents were the largestcontnbutors to core damage frequeecy, account ng for appro"-

NUREG/CR 4551 V3RtP1: EVALUATION OF SEVERE ACCl-mately 62 percent of the total The next most dominant type ofaccidents were station blackout (loss of all AC power). which DENT RISKS SURRY UNIT 1. Main Report DREEDING,R J.;

account for 26 percent of core damage frequency * HELTONJC; MURFIN.W.Ba et al. Sanda Natona! Laborato-nes October 1990. 511pp 9011260018. SAND 841309.

NUREG/CR-4550 V7 R01: ANALYSIS OF CORE DAMAGE FRE- M805 02LOVENCY; ZION, UNIT 1, INTERNAL EVENTS. SATTISON.M Ba in support of the Nelear Regulatory Comnvsson's (NRC's,HALL,K.W. EG&G Idaho, Inc. (subs. of EG&G, ine) May 1990. ataessment of the nsk from severe accidents at commercial nu-402pp. 9006290164. EGG 2554. 54325:223 cWar power plants in th LS reported in NUREG 1150, the

This docurrent contains the accident sequence anahses of Swere Accdont Risk Reduction PrcVam (SARRP) has com-intemally init ed events for the Zion Unit 1 Nxlear Power pMed a revised calculabon of the nsk to the general pubhc'Plant This is one of the five plant analyses conoucted as part from severe accidents at the Surry Power Staton, Unit 1. Thisof the NUREG 1150 effort for the Nuclear Regulatory Commis. pcn w piant, located in southeastem Virginia, is operated by thesion. The work performed and desenbod here is an extensive Virg nia Electnc Power Corp The emphasis in this risk analysisreanalysis of the work pubhshed in October 1986 as NUREG/ was not on determining a "so cahed" point estmate of nsk.CR-4550 Volume 7, it addresses comments from numerous r,. Ratrer, it was to determine the distnbutson of nsk. and to dis-viewers and provdes significantly more detailed modeling of covr the uncertainties that account for the breadth of this dis.most aspects of the Zion plant The mean core damage tre, tnbuton, Omsite nsk inihatsor' by events, both triternal to thequency at Zion was calculated to be 3.4E-4 per year, with a powr station and external to the power station were assessed,

_

95*w upper bound of 8 4E 4 per year and a 5% lower bound of1.1E 4 per year. Note that this range is based only on the stats. HUREG/CR-4551 V3 RIP 2: EVALUATION OF SEVERE ACCI-tical treatment of six specific t$ sues. Reactor coolant pump seal DENT RISKS SURRY UNil 1. Appendices, BREEDING.R.J.;icSS of coc4 ant accidents (LCCAs) were the largest contnbutors HELTDN.J C.; MURFIN.W D.; et al. Sand:a Nabonal Laborato-to the core damage frequency, account 4ng for approximatety nos. October 1990. 346pp- 9011260020. SAND 86130985% of the total. 55804 301.

See NUREG/CR 4551,V03 R01.P01 abstract.NUREG/CR 4551 V2R1Pt: EVALUAilON OF SEVERE ACCl-

DENT RISKS: OUANTIFICATION OF MAJOR INPUT NUREG/CR 4551 V4 RIP 1: EVALUATION vF SEVERE ACCIPARAMETERS Expert Opinion Elicitauon On in Vesse! Issues. DENT RISKS- PEACH BOTTOM. UNIT 2. Main ReportHARPER,F.T.; BREEDING.RJ; BROWN.T.Da et at Sandia Na- PAYNE.A Ca BREEDING.RJa JOW.H-N ; et al. Sandia Nationalbonal Laboratones. December 1990, 286pp 9101090429 Laboratones December 1990. 713pp 9101090481. SANO86-SAND 86-1309 56297:075. 1309 50001:036.

In support of the Nuclear Regulatory Commission's (NRC's) in support of the Nuclear Regulatory Commission's (NRC's)assessment of the nsk from aevere accdents at commerctal nu. assessment of the nsk from severn accdunts at commercial nu-clear power plants in the U S. reported in NUREG 1150, the clear power plants in the U S reported in NUREG 1150, theSevere Accdent Risk Reduction Program tSARRP) has com- Severe Accdent Risk Rxtuction Program (SAARP) has com-pleted a revised calculabon of the rrsk to the general pubhc pleted a revised calculaton of the nsk to the generat pubhcfrcm severe accidents at frve nuclear power plants Surry. Se- from severe accdents at the Peach Bottom Atomic Power Sta-Quoyah, Zion, Peach Bottom, and Grand Gulf. The emphasis in bon, Unit 2. This power plant, located in southeastern Pennsyl-this nsk anatysis was not on determining a "so- called" point vania. is operated by the PNiadelphia Electnc Company. TheI estmate of nsk. Rather, it was to determine the dstnbuton of emphasis in this nsk anaysis was not on c'etermining a "so-nsk, and to 6scover the uncortainties that account for the called" point estimate of nsk. Rather, it was to determine thebreadth of this distnbutiort Oti site nsk irvtaation by events, both distnbution of nsk. and to discover the uncertaintes that ac-intemal to the power staton and ertemal to the power station, count for the bree fth of this distnbubon Off site nsk intbated bywere assessed. Much of the importan input to the logic rnoools events both internal and external to the powar staton wuro as-was generated by expert panois. TNs document presents the sessed.

ee

i

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Main Citatbns Cnd Atstrccts 21

NUREQ/CR 4651 V4R1P2: EVALUATION 08 SEVERE ACCI- cask dunng a postuisted 6mpact with an uhyelding s#feceDENT RISKb. PEACH DDTTOM. UNIT 3 Appendices Three sets of buckhng anatys's formulas are included (1) CodePAYNE,ACa BRIEDiN3AJa JOW.H N; et ei. Sanda Natonal Case N 264 of the ASME Donor and Pressure vessel Code, (2)Laboratones. Decomter 1990. 436pp. 9101090470. SAND 66- Amersan Petroleum instituto Bullebn 2U an upg'ade of N 264

1309 56290 318 that incude* test results available ther 4264 was wntten in-

See NUREG/CR 4551.V04,R01,P01 abstract 1979, (3) fr, : ulas frequentty used by the piping and vetture

NUREQ/CR 4651 V5 RIP 1: EVALUATIOrs OF SEVERE ACCI.v*ssel industry and formutas recommended by the Siructural

DENT RISKS SEQUDYAH. UNIT 1. Main Report Stabihty Research Council To be compabble with the ASME

GREGDRY.J Ja HIGGINS SL et at San $a Natonal Laborato.Code, the first set to recommended for use in shipping cask

nes. MURMN W B Technadyne Engineenng Consultants. Inc. evaluation and tNs set is implemented 6n SCANS The second

December 1990. 307pp. 9101140293 SAND 66-1309 and trurd sets are recommended references for SCANS users.

66377:303in support of the U S Nuclear Regulatory Commisuon's as. NUREQ/CR 4564 V07: SCANS (SHIPPING CASK ANALYSIS

sessment of the risk from severe accdents at commercial nu. SYSTEMI A MICROCOMPUTER BASED AfdALYSIS SYSTEMclear power plants in the U S. reported in NUREC-1150, the FOR SHIPPING CASK DESIGN REVIEW Yolume 7. Theory

Sovt ' Accdent Risk Re1xton Program has completed a re- Manual Puncture Of SNpping Casks LO.T. Lawrence uvurnaevised calculaton of the nsk to the general pubhc ' rom uvere Natonal Latorstory. February 1990 65pp D04030060 00 0accdonts at the Seouoyah Power Staton, Unrt 1 This power 2067L 63226.100plant, locs'ed in southeastern Tennessee, is operated by the Under current regulatory requirements, a shipping caskTennessee Val!,y Aathorrty The emphas.s in this nsk anaif48 %hould be depgned for a senes of hypothebcal accdont condewas tot on deternvning a "so-catied" point est mate of nd tons These test condtons 6nclude a 40cch trne orop of theRather it was to deterrrune the d stnbuton of nsk, and to escov- cask onto a fanch diameter puncture pan in this study, existinger the urywtaintes that account for the treadth of tnis distribo- ureture test data was exammed Simple formutas bawd onton. Off site nska from inst 6atrng ever't internal to the powe' test data were proposed for puncture evaluaton of shippingstabon were assessed cons Dynamic and stabc nonlinear finite element anatyws

NUREO/CR-4551 VFR1P2: EVALUATION Or SEVERE ACCl- were performed to correlate analyses with the existing test data

DENT RISKS SEQUOYAH UNIT 1. AppenSces in this anatytical approach, three purxture failure predctonGREGORY,J.Ja HIGGINS.S.Ja et at Sandia Nabonal Lat orato- methcds were proposed and their t.ppigatobfy was evaluated.nes MURIIN.W tl Technadyne Engineering Consu'tants, Inc. The ar.nlytical approach provdes an attoma ,ve to testing DothDecemter 1990. 4Mpp 0101140299. SAND 861309. tamnated and achd well $Npcnng casks wow analysed in the66376 179 study of laminated casks, the effects of the inner shell on the

See NUREG/CR-45$1 V05.R01.P01 abstract- puncture of the outer shell wore examined, .n were the ettects

NUREQ/CR-45$1 V6N1Pt: EVALUATION OF SEVERE ACCI.of matenal strength of the puncture pin. Thu study of geometne

DENT RISKS. GRAND GULF, UNIT 1 Main Report scahng of casks indicated that the normalised encipeent punctur s

BROWN,T.Da DREEDING.R Ja JOW,H .N ; et al. Sarda Nabon. energy is 6nsenWtrve to vanstons in the scal # f actors This ' Aal Laboratones December 1990. 305pp. 9101140307. SANDB6- cluson ird:stes that the proposed anatytcal appere sr com-

1309. 56375:23( tHning firwte element anatyses and ladure predoion methods isin support of the Nuctor Regu'atory Commisson's (NRC's) consistent with the similarity pnnciples in Osts, enopt wtion

assessment of the risk from evere acedents at commercial nu* nocal yttrabon 6s excited donng the punt'ee process Furtherclear power plants in the U S reported en NUhEG 1150, the study < 8 this tocal vibraton is rmeded.Seyse Accettent Risk Reducton Prngram (SAR8P) has com.pleted a rewsed calculabon of the risk to the general pubhc NUREO/CR 4624 V06: RAD 60NUCUD! RELEASE CALCULA.trem severe accidents at the Grand Gulf Nucisar Stabon, Urut 1. TIONS FOR SELECTED $EVERE ACCIDENT

Ttus power plant, located in Port Gibson. Missimppi, rs operal- SCENARIOS Supplemental Calculaeons DENNING.R S.;

ed by tha System Energy Resources. Inc (SERit The emphasis LEONARD.M T.; CYOULSKIS,P.; et al Battehe Memonal Insb.en this risk analysis was not on determining a "so called" point tute, Columbus Laboratones August 1990,365pp.9009200004.estimate of nsk. Rather, it was to deterrrune the distnbution of RMI 2139. 56?t6.135.nsk, and to discover the urxertainbes that account fct the The results of source term calculatons are reported. Thesetwcadth of trus distnbuton, Onsite risk nt4ated by ever*s inter. calculations were performed in support of the NURLG.1150.

nal to the power pladt w&s assessed stuov. Analyses were pertormed for three plants: Peach Dottom,

NUREG/CR 4661 V6R1P2: EVALUATION OF SEVERE ACCi- a Mark I, toiliN water reactor, Surry, a subatmospheric contain-

DENT RISRS GRAND GULF, UNIT 1. Appereces. rnent, prestunzed water reactor; and Sequoyah, a subatmon-BROWN.T.Da DRtEDiNG,A Ja JOW,H. N.; et al. Sandia Nabon- phenc containt.sent, pressurued water reactor. Complete sourceat Laboratones. December 1990 533pp. 9101140337, SAND 86- term results are presented for the following sequences. stori1309. 56378.250 term stabon blanckout wtth faPure of the ADS system in the

See NUREG/CR-4551,V06,R01 P01 abstract. Peach Bottom plant stauon blackout with pump seal LOCA in

NUREG/CR 4564 V06: SCANS (SHIPPING CASK ANALYSISthe Surry plant, stat 60n blackout with a pump seal LOCA in the

SYSTEM)A MICROCOMPUTER DASED ANALYSIS SYSTEMSequoyah plant; and a very smail break with loss of ECC and

FOR SHIPPING CASK DESIGN REVIEW Volume 6 Theory spray rectreulaton in the Sequoyah plant. In additon, some par-tial ana yses were performed which ded tvt. require ruhr9ng all ofs

Manual Dukling Of Cercular Cyhndncal Shells LO T.; MOK,G CaCHINN.D.J. Lawrs. ice Lrvormore National Laboratory. February the modules of the Source Term Code Package. Thermal hy-1990. 76pp. 9004030139 UCID 20674. 53228.173 draulic calculabons were performed for the Pery and Sequoyah

A computer system called SCANS (Shipping Cask Analysis plants to evaluate the ettects of alternat ve emerDency operat.System) is t,eing developed for the staff of the U S. Nuclear ing procedures involving pomary and arcondary depressurtza-Regu!atory Comfrussion to perform confirmatory bcensing review ton. For the Surry plant, calculatons were W/med of rado.anaryses SCANS can handte problems associated witn impact, nuchdo transport through the pomary systwi during accident.in-heat transfer, therrnal stress, 6nternal or ertemal pressure loads, duced failure of ster.m generator tubes.and lead slump. A new capabihty implemented in SCANS isbuckling analysis of the steel shells of a spent l'jal shipping

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'12 Mdn Citations and Abstracts

NUREQ/CR 4639 V01 R1: NUCL E AR COMPUTE Rl2ED LIBRARY hardware rehaNbty anWysis an tuptort of a venety of no es.FOR ASSE SSING REACTOR RELIABILf?Y ,,essment activities The NUCLARR system is documented 6r's(NUCLARR) Summary Desenption GE R1 MAN.D t ; five volume senes of reports Vokime 6 " Data Manuar p oGILMORLW E.: GAL 1E AN.W J ; et al EG&G idaho. Inc (subs vues a hard-copy re6vesentaton o' all data and rea:ed inor.of EG&G, Inc ) May 1990 20p0 9006000202. EGG Pa58 mation avadable wnh the NUCLARR system mottware This doc-64074 042 ument is organized vi three sections Part 1 is the summary do.

The Nucicar Computerned Library for Assessing Reacts Re- senpton wNch presents an overview of the NUCLARR systemliatuhty (NUCLARR) is an automated 4 ata base management and data procesung procedu,es Part 2 contains all data ardsystem tot sturvg and processing hum in error probatukty and informatice relevant to the human error probatality (HEP) sde ofhard*are component f aAra rate data 'he NUCLADR system NUCL ARR Data and informaton for the hardware componentsoftware rendes on an IBM s f competit e) pernot al merocom- f ailure data (HCF D) ode are presented within Part 3putet. NUCLARR can be i a sased by the end user to fwnishdata nuitable for input in human and/or hardware rehntality anal. NUREQ/CR 4639 V6P2R3: NUCL E AR COMPUTER!lE D LLysis to support a ;nnety of nsk assessment activities The NU. BRAW FOR ASSESSIN3 HEACTOR REttABILITYCLARR syst6m is documented in a five vobme cones of re- (NUCLARR) Data Manual Pari 2 Human t:rror Protetality (HEP)

I ports Volume 1 of tNs senes is the Summary Desenpton, Data GILBERT,0 G ; HEECE.W J; GERTMAN Dl: et at EG&Gwhich prosents an overview of the data management system, Idaho. inc. (subs of EGAG, inc ) Docernber 1990 456ppincluding a desenpton of data co4ecton, data ovalificaton, data 9101100037 EGG.2458 $6437-073structure, and tasonowes Proyamming acttvities, procedures See NUREG/CR 4639,V0$P01,R03 atestractfor processing data, a user's gude. and hard copy data manual

NUREQ/C44639 V5P3R3: NUCL E AR COMPUTE R 2E D Lt.are presented in volumes 2 through S NUREG/CR 4639BRARY FOR ASSE SSING REACTOR RE LLABILITY

NUREQ/CH 4639 V4PIR2: NUCLEAR COMPUTE RIZED Ll- (NUCLARR) Data Manual Part 3 Hard*are Component FadureDRARY FOR ASSESSING REACTOR RELIAulLITY Data (HCFD) GIL BERT,8 G . RE JCL.W J ; GERTMAN=D l; et(NUCLMR) User's Gude Part 1: Ove vmw Of NUCLARR Data at EG&G Idaho, loc- (subs of EGAG. Inc ) December 1990Retnevat GILMORE.W Ea GENTILLON.C Da GERTMAN,0 L et 179pp 910118003 EGG P456 56448 320 jal EG8G Idano. Inc (subs of EG&G. Ir'c ) October 1990 See NUREG/C44639,v05,P01.R03 abstract 4

l4000 9010250026 EGG 2458 55496 050The Nuc6 ear Computented Library for Assessing Reactor Re. NUREQ/CR-4659 V03; SEISMIC FRAGittTY Or NUCLEAR

leatality (NUCLARR) is an automated data base inanagement POWLR PLANT COMPONENTS (PHASE 3) Switchgear, IACsystem for processing and stonag human error prr>batnMy and Panels (NSSS) And Reisys. BANDYOPADHYAY,hardware component f ailure data The NUCLARR system soft. HOFM AYER.C H ; KASSIAN K; et at Drookhaven Natonalware resides on an IBM (or compatible) personal microcomput. Laborstory Fetr;ary 1990 73pp 9004030128 DNL NUREG-er. NUCLARA can be used by the end user to furnish data $200T 53228.101.inputs for both human and hardware relaatdty anatysis in sup- As part of the Component Frag %y Program wNch was Wtist-port of a venety of nsk assessment activities The NUCLARR ed in FY 1985,15 tee addttonal equipment clas6es have beensystem is documented in a frve volume senes of reports evaluated This report contains the fragFty results and discusVolume 4. User's Gude is ;vesen19d in three parts Part l- lons on these equipment classes wNch are switchgear, lar'Ovarvier of NUCLARR Dua Retneval, provdes an introductory panets ard reisys Doth low and medium voltage switchgear as-overview to the system's capabilities and procedures for data sembnes have been considM ad a separate traplify estoretneval PM 2. Gude to Operations contains the instructons mate for each type is provded Test data on cabarets from theand basic procedures for using the NUCLARR softwee Part 3. nuclear instmmentaton/ neutron monitonng system, plant / proc-NUCLARR System Descripson orovdes 6n depth escusson of esa protecton system, sold state protectrve system and engsthe design charactenstics and special features of the NUCLAnq neered safeguards test system compnse the DNL data t ano forsoftware l&C panels (NSSS) Fraylity levels have beco deterfraned for

"NUREQ/CR-4639 V4P2R2: NUCLEAR COMPUTERIZED ll- terministic results are presented in terms of test responso spnc.

BRARY FOR ASSESSING REACTOR RELIABluTY q,a in anton the test data have teen evaluated for estimating(NUCLARR) User's Gude Part 2 Guide To Operations the respectwo probatahatic fragility levels which are expressedGILMORE.W Ea GENTILLC$LC D ; GERTMAN.D l; et al [G&G in terms of a median vslue. an uncertainty coefhcient, a ran-Idaho. Inc, (subs of EGAG. Inc ) October 1990 141pp comness coefhcant and an HCLPF value Due to a wid6 vana.

UAE /CR 46 9, 4 R02 abstract g ,, if, ,g ,, yNUREG/CR 4639 V4P3R2: NUCLEAR COMPUTEnl2ED G

NUREG/CR 4661: CLOSEOUT OF IE DULLETiN 8603 MOTOR.BRARY FOR ASSE SSING REACTOR RELIADillrYOPERATED VALVE COMMON MODE FAILURES DURING(NUCLARR) User's Gude Part 3 NUCLARR System DescopPLANT TRANSIENTS DUE TO IMF90PER SWITCH SET.ton, GILMORE,W Ea GENTILLON.C D ; GERTMAN.D l; et al.TINGS FOLEY,W Ja DEAN,R S ; STEINORECHER.H ; et al. PA-EG&G Idaho, Inc. (subs of EG&G. inc ) October 1990 23 pp

9010250020 EGG 2458 55406 224 RAMETER. Inc February 1990 10Hpp 9003120769. PARAME-TER IEiSB E2BB2 267-See NUREG/CR.4039,V04.P01,R02 abstract

Documentaton is provded in this report for the closcout of IENUT.EQ/CR 4639 V5P1R3: NUCLEAR COMPUTERIZED LI- Bulletin B5-03 The purpose of the bulletin was to receest le

BRARY FOR ASSESSING REACTOR RELIABILITY consees to develop and implement programs to ensure that the(NUCLARR) Data Manuat Par 1 1: Summary Descnpt:on switch settings on certain saf6ty4related. motor + operated valvesGILBJRT.00; REECE.W.Ja GLR TMAN.D l; et al. EGAG are selected 6et and maintained so as to ensure rehabie valveidaho, Inc (subs of EGAG. Inc )- December 1940 24pp operaton when valves are sub ccted to macmum d fterential91011B0027, EGG 2a58 56465 304 pressures expoeted donng normal operaton and the design

The Nuclear Computerued Litwary for Assessng Henctor Re- basis events The report uctuden dncomentaten and status ofliatulity (NUCLARR) is an automated data management system the revmw of Acton item e of the bulletin completed up to thefor procossing and stonng human error prubatety and hardware issuance of Generic Letter 8910 on June 28,1989 L6censeecomponent failure data. The NUCLARR system software re- actions for Achun item e were cornpleted satisfactonty for 102sdo,. on an IBM (or cornpatible) personal computer NUCLARA (66%) of the 119 faciblies for which actions were required Sat-Can furnish an end user with data inputs for toth human and Isfactory Complebon of the remaining 17 facilities is ensured by

i

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the genene lettee In the report conclusions, Fie inter retaton- g/s, and the ACAR maintained a pea 6 power level of 13 MWahip of the genenc letter and the bohetin in presented Dsch- dunng the tugh temperature ondaton phase of tt o test inducen0t

ground information is supphed in the introduction and Apperda atout 6.6 kW fiss6cn power and about 20 kW pen ondationA power in the assomtdy Waval(toervation showed earty clad re-

locah and pamal bMage bmaton at he gW spam hNUREG/CR 4667 V07: ENVIRONMENT ALLY ASSISTED CRACK- ton accompaned by pMon of a one awW ponnost

ING IN LIGHT W ATER Rf AC10RS Semisnnual Rogert.Apni-C' 0* * '#*"' '' ** CI*" 0**** # '" ''C''' 0'

'%ptemtier 19B8 SHACNW Ja KASSNI R TL, PARK.J Y.; et " * * " ' * * *** C "Oat Argonne Natonal latestory March 1990 63pp. maw hom N met two Ms of N Wo. The quanmy W9037120135 ANL 89/a0 $4470 200 hydrogen measured dunng the test was c(osistent with the old

This report summarises work periormed by Argonne Natonal served magnitude of cladding oxidaton Omdation driven heat-Latontyy on environmentaliy assisted cracking in Ight wata, eng rates of 25 K/s and peak terNwatures in eucess of 2525 Kreactors dunng the saa months tiom April to Septemter 1988 ute observed The anatyses,6nterpretaton, and apphcaton ofThe stress corroson cracking (SCC) of Types 316NG and 3D4 Vese mouM to sen W damage amMs we WMstainions stools (S$s) was investgated by means of slow-strairerate and tractu+e mechanets crack-growthrate tests v. hgh tem NUREG/CR 4671: THE Of 4 FUEL DAMAGE EXPERIMENT INpe store water. The eNects of load rato and water chemistry on ACRrt WITH A BWR CONTROL DLADE AND CHANNEL DOX-t5e cran growth t*have of Type 316NG and e.nsitised Type GAUNTT.R Oa GASSER.R D Sanda Natonal L aboratones3>l SS were detertruned in long-term fracture-mechanics tests OTT.LJ Ook Rdge Natonal Laboratory Novemter 1989The innuence of orgahic impunties on the SCC of sensitised 397pp 900307027b SAND 66-1443 b2006 2B3Type 304 SS was also investgated Fatgue tests were conduct- The DF 4 test was an egertments'investgaton into the melted on 1ype 316NG SS 6n air and simutued tiosling water reactor pog,esson behavior of boiling water reactor (DWR) core com-water at 288 doyees C to assess the degree of conservatism ponents under twgh temperature severe core damage corein the ASME Code $ccton ill f atque desgn curves An ongyng tions in trvs study 14 secaloy clad UO(2) fuel rods, and tepte-ir;vestgaton of the susceptit@ty of severai heats of ddterent sentations of the trcaloy fuel carvster and stainicas stcet/D(4)Cgrades of be alby forntic stee's to transgrarotar SCC in slow. control blade were assembled into a 0 $ m long test burde.strain-rate and tractee trechanics tests was continued The test burde was tipon heated 6n a flowing steam enytron-

NUREG/CR 4667 V08: ENVIRONMENT ALLY ASSISTED CRACK. ment, using tht Annular Core Research Reactor at Sards tab-

ING IN LIGHT WATER REACTORS Semennual oratones, simulating the environmental cordtons of an uncov.Report. October 1908 March 1989 KASSNER.T F : PAAK.J Ya cred DWH core expenencing tagh temperature damage as aRUTHER.W Ea et al. Argonne National Latoratory June 1990 result of residual fisson product decay heating The errernmem

$3pp 9007120144 ANLW/4 5446U67. tat results provide tr formahon on the thermal renfonte of theThts report summantes work performed by Argonne Nat.onal test turde oc4Nonents, the rapid emotherrme oxidation of the

Latoratory en environment #ty assisted cracking in hght water rircaloy fuel cladding and canister the production of hydrogenreactors danng the om maritna from Octoter 1988 to March from enetal steam omdation, and the failure tehavior of the pro-

1909 The effects of load tritio on stress corroton cracking grossively enettiry burde components Ttus informaton to pro-(SCC) of Types 316NG. 304. and CF 3M cast stainicas steels vided in the form of thermocouple data, steam ed hydrogon

(SS4) wore investigated by Inicture-mechanes crack growth. how rate data, test tund6e fission power data and visual (tser-

rate 4CGR) tests in hgh temproture water. The influence of or. valion of the damage progtwaiort in eMton to DWR barkDanic impunties on the SCC of lype 316NG SS was also 6nves- g'ound information, ttus document contains a desce ption of the

tgated in long term CGR tests Testa to determene the nascepts. expenmental hardware with details on how emportment was

tdry of a irt diameto Types st6NG and 304 S$ pipe weld- instrumented and diagnosed, a description > 2t progros-

ments to SCC in simulated DWR environments have been core sion, and a presentation of the on kne me < ats. Also inducted The influence of cartonate a, concentraticns between this report are the results of a thermal a + m sf the fueled01 and 3300 ppm on the SCC behavior of sensitized Typ9 304 test section of the orpenment demonstrsta + A worall consist-

SS in dooryganated water (less than 5 ppb) was determined in ency in the measurahte quantities frorn the to. A Moussion ofconstant extenson- rate tenske (CERT) tests. Fatque tests the results la provded.were conducted on Type 310NG SS in air and DWR environ-

NUREO/CR 4674 V09: PRECURSORS TO POTENTIAL SEVEREments to assess the oogree of conservatism in the ASME CodeCORE DAMAGE ACCIDLNTS 1988 A STATUS REPORT MainSecton til fatgue desgn curves CGR tests to determano sus. Report And ANendin A. MIN ARtCK.J Wa CLET CHER.J W ;

ceptblity tu SCC are teng conducted on A533-Gr D now alloy ME A A. Oak Rdge National Laboratory. Fetruary 1990femtsc swoiin simulated BWR environments 169pp 9003070234 ORNL/NOAC-232. 52B10 323

NUREO/CR 4660: DAMAGED FUEt EXPERIMENT DF 1 Resurts Thirty two c,porational events with condmonal probatdloes ofAnd Analyses GASSER R.D4 FRYER.C Pa GAUNTT,R Oa et al core damage of 1.0 m 10(-6) or higher occurnng at commercialSandia Natonal Laboratones January 1990 2fi9pp. Ight-water reactors donna 1988 are consdered to be procut-9003120772 SAND 86-1030. 62BB4 009 nors to pomntial severe core damage These are described

A senes c' in pde expenments addressing LWR severe fuel along with associated agnificance enhmates, categonzaton,damage phonemena hes been conducted in the Annular Core and subsequent analyses This study is a continuaton of earlierResearch Acuctor (ACRR) at Sandia Natonal Laboratones The work, which evatuated the 19691981 arn 19841987 events.ACRR Dcoris Formation and Relocation (DF) espenments a o The toport discusses (1) the general rationale for this study, (2)quesoseparate effects tests that provide a data base for the de' the telecton and documentation of events as precursors, (3)velopment and venhcation of modete for LWR severe core the estimation and use of conditional probabilities of subse-damage accidents The first expenment in this acnes, DF.1, was Quent severs core damage to rank precursor events, and (4) theperformed on March 15,1964 aad the results are presented in plant models used in the evaluston processthis report The DF 1 expenment examined the ettects of lowirvtial clad oxidation conditions on fuel damage and relocation NUREO/CR 4674 V10: PRECURSORS TO POTENTIAL SEVEREprocusses The DF 1 test assomtdy consisted of a nine-rod CORE DAMAGE ACCIDENT S 1980 A STATUS

square mminx bundle that employed PWR type fuel rods with a REPORT Appordnes D And C. MIN ARICK J Wa

0 5 m fissde length. The fuel rods were composed of 10% en- CLETCHER J W.; DLAKE,A A Oak Rdge National Laboratorynchod UO(2) pellets within a rircatoy 4 cladding Steam flowed February 1990 a73pp 9003070184- ORNLINOAC 232.through the test tondie at flow rates va ying between 0 5 and 3 52B13 073

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See NUREG/CR 4674.V09 abstract NVREG/CR 4704 V03: RELATIVE BIOLOGICAL EF FEC11V1-NESS (RBE) OF hSSION NEUTRONS AND GAMMA RAYS AT

NUREG/CR 4874 V111 PRECURSORS TO POTENTIAL SEVERE OCCUPATIONAL EAPOSURE LEVELS Studies On The GrossCORS DAMAGE ACCIDENTS 1989 A STATUS REPORT. Main And Microscopic Pathology Observed At Death Of Mice Ex-Report And Append.: A MINARfCK,J W.; CLETCHER,J W.; posed To 60 Eoval Once Weeuy Dows Of Fission...COPiNGER.D.A; et at Oak Ridge National Latoratory. August GRAHN.0; THOMSON.JE; CARNES.B A Ar0onne Natonal1990.I'/7pp 9009130048, ORNL/NC AC 232. 55192 068 Laboratory January 1990. 112pp 9004090170 ANL-86-33

Thirty operatonal events with conditonal probabilities of core 53314 010damagu of 10 s 10(-6) or higher occurnng at commercial hght- Dose-resNnte analyses of the pathologic consequences ofwater reactors dunng 1989 are considered to be precursors to exposure to 60 caual once weeMy doses of fission neutrons orNtontial severe core damage Tacse are descobed a ong with 60Co gamma ra,s were used to generate reistive twolopcal ef-ossociated sgosticance estimates, categontston, and subso- fect'veness t DE) values for the ma}or causts of death or forRquent an4%es. This study is a continuaton of earter work, tumor occurrences Cumulatrve probatul+es of death or occur-whech evaluatwf the 19691981 and 19t+4-1988 events The rence were generated for 15 categones of neoplastic di6 case in

; repor1 d scusses (1) the general ratonale for this study, (2) the the interval 800-999 days since first exposure for each dose,selecton and documentaton of events as precursors. (3) the set and raSation quality. Dopcoding upon the pathologic end-utimaton and use of conditonal probabihtees of subseauent pcunt, RBE values vaned from atout 10 to 50. Vanation in RDEsevere core damage to rank procwsor events, and (4) the plant values was not random or norisystematic RDE values wereenodels used in the anatysis process IO*e' for tumors 6nvo'ving the connective tissues (about 10 to

15) than for the epithehal tesue tumors (atout 20 to $0) Fe-NUREG/CR 4674 V12: PRECURSORS TO POTENTIAL SEVEle males o.d have segnificantry higner nsk co6,ficients tot manyCORE DAMAGE ACCIDENTS 1989 A STATUS endpants. The results so,rgest that the RBE value of 20 tor hfeRE PORT. Appendice B And C. W ARICK.J.W.; shortening from all causes of death is a weghted everage ofCLETCHER,J W; co/INGER.D A; et al. Oak Ridge National the RDE values representing the er@vrjual neoplastic diseasesLaboratory. August 1990, 5t0pp 9309130058. ORNL/NOAC. (approuimately 90% of the excess risk of mortakty induced by232 55192 245 re$aton at low doses) These results in conjunction with the re.

See NUREG/CR 4674,V11 abstract. suits of large-scale studies funded by the Department of Energyand using the same facihtes, support the conclusor, that the

NUREQ/CR 4H1 V01: MELCOR ACCIDENT CONSEQUENCE quality tactor (0) for feson neutrons should be ramed from theCODE SYSTEM (M ACCS) Volume 1: User's Guide P'esent value of 10 to a value of 20.CHANIN,01; SPRUNG.J L.; RITCHC.L T.; et at Sandia NatonalLatoratones F ebruary 1990. 507pp. 9005040033. SAND 86_ NUREG/CR 4731 V02: RES: DUAL LIFE ASSESSMENT OFg$et p$o3 g36, MAJOR LIGHT WATER REACTOR COMPONENTS OVER.

This report describes the MACCS computer code The pur. VIEW. SHAH.V.N ; MACDONALD.P.Ea AMAR,A S,; et at EG&Gpose of ttus code is to simulate the 6mpact of f ivere accident, a% M (subs of Q&Q lnc ) November 1989 467ppct nuclear power plants on the surrounding environmen. M02N9 N2W 52MB 021MACCS has been oeveloped for the U S Nuc6 ear Reg /ator; D' *PO'' P'esents an assessment of the aging (time de.Commisson to replace the Nevious CRAC2 code a id it encor. Wrent degradaton) of selected nient hgM watw macW com-porates many improvements in modeling flenibility in compenson pownts and structures The stressors. possible degradatento CRAC2 The pnncipal phenomena Considered 6n M ACCS are se and neanisms, potential failure nodes, and cunent eatmospheric transport, mitgattve actions based on dose protec- serytce inspection requirements are descussed for eleven mapr

waW ma c ments macW Want punps, pmss#tion. dose 40cumulaton by a number of pathways 6ncluding food *" ** " "*"" # "* "# **Ond water 6ngest.on, early and latent health effects, and eco-mam Want se"*ca sPn ng andnomic costs The MACCS code can tra used for a vanety of ap- ** D " ' Cplacations. These include (1) probabilistic nsk assessment (PRA)

awns W mam inWat W' waW mamof nuclear power plants and other nuclear facehties, (2) sensitryi-ty stu$es to gain a better understand.ng of the parameters im- (BWR) comainments, DWR feed *ater and main steam knes,

BWR controi rod dnve mechanisms and reactor internals, elec-portant to PRA, and (3) cost tenefit analysis This report 4"compos.3d of three volumes Volume 1, the User's Guide, de' incal cables and connectons, and emergency diesel genera-

tors Unresolved techrwcal tatues related to undwstanding andscribes the input data requirements of the MACCS code andmanaging the aging of these mapr Components are 6dentifiedprovides drectons for its use as illustrated by three sample

pecidems Volume 2, the Model Desenption, descnbes the uf> NUREQ/CR 473' V06: EVALUATION AND COMPILATION OFdedying models that are emplemented in the code. and Volume DOE WASTE PACKAGE TEST DATA. Biannual Report; August3. the Programmer's Ref0'ence Manual, desenhos the code's 1988. January 1989 INTERRANTE C G Office of Nuclear Ma-otructure and database management tenal Safety & Safeguards ESCALANTE,E.; FRAKER,A C. Na-

tonal Institute of Standards & Techno6ogy (formerty NatonalNUREQ/CR 4691 V02: MELCOR ACCIDENT CONSEQUENCE Bureau cf Standa November 1990. 115pp 9011270224

CODE SYSTEM (MACCS) Volume 2 Model Desenpton. 55856 001.JOW,H N; SPRUNG.JL; ROLLSTIN.JA; et at Sandia Natonal This rer9rt summarues evaluations by the Nabonal instituteLatoratories February 1990. 106pp 9003190289. SAND 86- of Standards and Technology (NIST) of Dep6rtment Energy1562. 5300$ 059 (DOE) actreties on waste packages designed for containment

See NUREG/CR 4691.V01 abstract. of radioactive high level nuclear waste (HLW) for the six monthpenod August 1988 through January 1900 included are reviews

NUREO/CA 4691 V03: MELCOR ACCIDENT CONSEQUENCE of related matenals research and plans, actrvities for the DOECODE SYSTEM (MACCS) Volume 3. Programmer s Referere* Matenais Characten7aton Center, entormation on the YuccaManual ROLt.STIN,J A.; CHANIN,01.; JOW,RN. Sanoa Nabon-

Mountain Protect, and other informaton regarding supporting re-al Laboratones February 1990, 341pp 9003190293. SAND 66- Search and special assistance NIST comments are given on1562 63042.250 the Yucca Mountain Consultaton Draft Site CharacteruationSee NUREG/CR 4691,V01 abstract. Plan (CDSCP) and on the Waste Compliance Plan for the West

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NUREG/CR 4744 V03 Nt LONG TERM EMDRITTLEMENT OF and the integration of thest data procestung and analyws re-CAST DUPt EX ST AINLE SS STEELS IN LWR querements in the reputat analysis stream for ECIN data TheseSYST E MS Semiannual Report.Octoter 1987 . March 1988 networks how acquire high quality 09stal data lot detailed anaty-CHOPRA.OM CHUNG,H M Argonne Natonal laboratory. Fet> sit of $wsmsc activity ard source proportes from these tworuary 1990. 5Bpp 9003070245 ANL 89/22. 52802198 areas, thus oNoctrvely doubbng the amount of SesmeC data

TNs progress report summartres work performed by Argonne bemg roccivW by the Ottawa data labNabonal Latorstory on long term omtrittlement of cast dup 6enstainless steels 6n LWR systems dunng the six months from Oc' NUREG/CR 4763 V04: CANADIAN SEISMICtober 1987 to March 198u A mechaniste understarding of the AGREEMENT. Annual Report 1988 1989. WET MIL LE R.R.J ;actvabon energy of aging is described on the basas of the re- LYONS.J A; SHANNOttW Ed et al. Canadian Commercialsuits of tructostructural charactenzatch of various heats of Corp. AprW 1990 61pp 9005210166 S3891:180.Grades CF 3. CF 8, and CF BM stainless steel that were used in this time perod eastem Canada exponenced its ta' gestin agng studies at different laterricM The kinetics of the earthquake in over 50 years whon a rnagrdtude (M) 6 0 eventspenodat decomposatson of fernte (ie., the pomary mechanism of took place at 18 48 EST on FrdaY Novemter 25 near 4812ayng omtrittlement) appear to be strorvy influenced by a syn- degrees W just south of Chicouterns Ovetec This eartrauake,ergistic etteet of G-phase nucleation and growth When the act,. whch has toon chnstened the Saguenay earttquake, has pro-voton energies (ranging from 18 to 50 kca!/mone) were plottedes a functon of the volume ftacton of G phase produced dunng vided a wealth of new data nortinent to earthr.luake engineenng

accelerated aging. a good correiston was obtatried regardless stud'es in eastern North A nertCs a%d is the tubject of fruiny

of vanatons en grade, buik chemical compositon. and fatrica. continuing studies The thography g4ves a summary of the scvton process. Spinodal-like decompoifaon of austenste in beats entific reports on earthr,uake or relatod studies that have beencontain6ng a relativety htgh level of N has also been invetugat- published or subrNttet for publicatior'. by GD staN in (Ns penoded Charpy impAC1 data for thermally aged Cast stainless steelwere anatytod to determine the kinetics and extent of embrtttle. NUREG/CR-4794: EVERIMENTAL RESULTS OF CORE-CON.ment. The ferrite morphology had a strong effect on the erteid CRETE INTERACTIONS USING MOLTEN STEEL WITH ZlR-of emtrittlement, whereas the matenal composition influervM CONIUM COPUS.E R ; ULOSE,R E.; BROCKMANN.J L; et al.the kinetc* of embnttlement Resutte obtained from the present Sandia National Laboratones Juty 1990 386pp. 9009070412study of mechanscal proporties, and data of other inveshgators SANDB6 2638. 54649 001.were anaYred to covelop the procedure and correlations fo' Four esponments were performed in order to evaluate the ad-predicting the kinetics and extent of embottlement, under reac- ditional effects of rircorwum metal oudaton on core debos inter.tor operating conditions, from the matenal parameters. actons with timestone concrete unang molten stainions stool as

NUREG/CR-4744 V03 N2: LONG1ERM EMBRITTLEMENT OF the core debrio simulant The OT D, OT E. SURC 3 and SURC.

CAST DUPLEX STAINLESS STEELS IN LWR 3A expenments eroded between 10 and 33 cm of limestoneSYSTEMS Semiannual Report, April-Septvmber 1988. concrete during mustained interactons whch lasted 35 to 120CHOPRA.O.K.: CHUNG,H M. Argonne Natonal Laboratory minutes Mett pool temperatures dunng the tests tanged fromAugust 1990. 50pp. 9009250047. ANL 90/5. 55244:021. 1900 K before rirconium addthon to 2100 K dunng the zirconb

This progress report summartres work pertonned by Argonne um steobconcrete phase of the testa large increases 6n pro-National Laboratory on longa rm omtrittlement of cast dupin' son rate, gas producten and acrosol release wore also mean-estainless steels in LWR systems donng the su months from ured shortly after Zr metal was added to the melt.April to September 19B8. Chanctenstcs of the pnmary mecha-nism of aging omtvittlement (i.e., spinodal decomposebon of ter. NUREG/CR 4818: PR=EDO. POWER REACTOR EMBRITTLE-nie) and 6ynergists effects of alloying and 6mpunty elements MENT DATA BASLVERSION 1. Program Descript onthat influence the kineuct of the pomary mechanism are dis- etALLMANN.F,W.; KAM,F B K.; T AYLOR D.J. Oak Ridge Na-cussed. Several secondary metallurgical processes of emtvittle' tonal Latoratory. June 1990.104pp. 9006290154. ORNL/TM-ment, strongty dependent on the C, N, Ni, Mo, and Si Content of 10328. 5 0 63 220vanous heats, are identified Infortnahon on kinetics and data on Data corcorni"O radiation emtrittlement of pressure vessel6mpact properties are anayred and correlated with mcrostruc- stels in cunnecial gower reactus have been collected from

l tural charactenstcs to provide a unified method of extrapolahng availab4 survemance repats. The purpose of this NRC spon-accelerated-aging data to reactor operating conditions. Fracturetoughness data are presented for several heats of cast stairy smed program is to provKle the technical banos for voluntary

| less steel aged at temperatures tetwten 120 and 450 degrees consensus standards, regulatory guiues, standard review plans,

I C for times up to 10,000 h. MecharA d wporty data are ans. and codes The data can also be used for the exploraton and

| ly7ed to develop the procedure and correistions for prs 1cting venfic#cn of embnttlement prediction models The data filesl the kinetcs and extent of emtsittlement of reactor components are given in dBASE lil Plus format and can be accessed with

from known matenal parameters. The method and examples of any personal computer using the DOS operating system. Menu-estimating the 6mpact strength and fracture toughness of cast dnven software is provided for easy access to the data 6nclud-

| components dunng reactor service are desenbed. The lower. 6ng curve fitting and plotting fac6tites This software has drastsbound values of impact strength and fracture toughness for cast calty reduced the time and effort for data A, cessing and eval'

stainless steels at LWR operating temperatures are defined. uaton compared to provous data bases The current compila-tion of the Power Reactor Embnttwment Data Base (PR.EDD,

NUREG/CR 4753 V03: CANADIAN SEISMICAGREEMENT. Annual Report 1987 1968 WETMILLER,R.J4 wwn 1) contains results from surveillance capsule reports of

LYONS,J A.; SHANNON.W E.: et al. Canadian Commercia! 78 reactors with 381 data points from 110 different arradiated

Corp. Apnl 1990. 4 tpp 9005210158 53687.048. base matenals (plates and forgings) and 161 data points from79 d.fierent welds Resutts froni heat-affected-fone matenalsDunng the period of this report the contract resources were

spent on operaton and maintenance of the Eastern Canada Te, are also listed Electne Power Research institute (EPR:), reactor

icmetred Network (ECTNL development of special purpose vendors, and utilities are in the process of providing back uplocal network systems, servcing and maintenance of the quality assurance checks of the PR EDO and will be supple-stro9 motion seismograph network in eastern Canada, oper. menting the data base with adAtonal data and documentation.aton and of the Ottawa data lab and esarthquake monrtonng and Penodic updates of data and bottaare will be released to au-reportmg. Of special note in this penod was the final completon thonzod users Future updatos will also include ratuits from ina-of the Sudbury (SLTN) and Charlevoix (CLTN) local networks diatons in matenals test reactors

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# Win Citat4fth ed Abstracts

i D G /O .Wra eTV 3,9ted FOR THE EXTERNAL EVENT son of the MAR and PIRR data tases ardcated no ofference in 1

$fM ~ ** W h hbhCY ANALYSES FOR NUREG 1150. detection capatukty was rneasured for long and abort cracks in'

4,' ' < i ' AMBRIGHT J A Sandia Natonal Laboratones addition to the pipe inspection round rotnn, a human fa; tors% a NO 145pp 9012200211. SANDBB-3102 study was conducted in coopnction with the MRR The most;

- *W % important result of the human factors study is that the Relat've; M6 r%. preents procedures which can be used to assess Operating Charactenstics (ROC) curves provide a bettet meth.. eriema, haraids at nuclear power plants. These methods were

tdology for des 0nbmg enspector performance than only POD orused to perform the external events nsk assessments for the,

single point crack /no crack dataSary and Peach Bottom nuc6 ear po*er piants as part of thei NRC sponsored NUREG 1160 prograin These methods apply NUREG/C44918 V04: CONTROL OF WATER INrlLTRATIONt; ire full range of hatards such as earthquakes. fires hoods.

INTO NEAR SURFACE LLW DISPOSAL UNITS Progressetc. wNch are collectivety known as external events ard are Report On Facid Espe iments Al A Humid Rogeonrbased on mahng full utiltration of the power plant systems logic Site.Deltsville, Maryland SCHULTER K Cahtornia, Univ. of'models developed in the internal events ana46cs. HElma'Ks of

Darkeley, CA RIDKY,R W. Maryland, Unw of, College Parkthe methods descrited metude the use of estensive computer.tided screenmg poor to the detailed analys#s of each externs. MD O'DONNELLE. Waste Management Branch DecemooIevent hazard to which the plant might concervably be erposed 1990' 28pp D101040285' 50271057'

These screening procedures denti y those external events The project obrectNe to to assess means for controlhng waterf

whch could contribute to the nok at the plant and segnifecantty infiltration through waste esposal unit covers an humid reponsreduce the numte of events for which subsequent dotaded ErMnmental work es twnng pWiormed in ta'De scale fysimetersanaysis is required Taken together, these techrugues provide a (70'm45'10') at Bettsvific. MD and results of the assessment arereistrdy straghtforward and, in some cases, simphfied set of appleable to esposal of LLW, uranium rrall tathr gs. hatardoustechniques for the analyts of the full range of esternal events waste, and Santtary tandhils Three concepts are urdor investeand prowdes for toth scrutability and reproducibility of the final gaton (1) tesestive layer bamer, (2) conductive layer bamur,

i results and tnoengmeenng wate* management. The reststive layer bar.* " " * ' ' # E" *** 'N #*"* '* f"NUREQ/CR-4882: OVAUFICATION PROCESS FOR ULTRASON- ""# " '##' '''' ' * ""#* Y D**" ""d d ' *4"" *' "IC TESTING IN NUCLEAR INSERVICE INSPECTION APPUCA-

TIONS. SPANNER,J C.; DOCTOR,S Ra T AYLOR T.T.: et al Bat- 9 sa% ban w a capa9 taat As pgas u M es m maM waw is emW Wtelle Memonal Institute Pacife Northwest LLtoratory, March Pw ow layw to ow Fw wasW TNs bane m nost eHicent1990.150pp 9004100344. PNL 6179 $3350 090.

The report documents one of the tasks conducted under a at low flow rates and is thus best placed telow a resistrve layerPache Northwest Laborato y (PNL) program entitled Evaluaton bemer. Such a Comtsnaton of the resistrve layer over the con-r

and improvement of NDE Rehatntity for Inservice inspecten of ductive layer bemer promises to be highly ettoctrve providedLight Water Reactors (NDE Rehaoihty Program). The obtectrve mee is to appreciable subsidence Boonginconng water inan-of thrs task was to develop recommended reoutrements and agement is a surface cover that is designed to accommodateprocesses for cuahtying the UT/ISI systems (personnet, equip, subsidance It consists of impermeable panels wNch enhancement, and procedJtes) for inservice mspection of r UClear power run off and limit infiltration Vegetaton is planted en narrowplant components. TNs report desenbes an overall Quahtication OP0hmgs l*t*een par'els to transpire water from t+1ow theprocess intended to acNeve statistically designed performance panets This system has successfully de*atered two tysimotorsvahdations, as weil as include the prercovisite training and other thus demonstrating that this procedure could be used for remo-ovahfication recommendations. The document stao contains dial action (" drying out") ei! sting water-loggad disposal sites atrecommendat6ons for the test specimens, environment, and low cost,other conditions under whsch the Quahfication processes shouldbe conducted. In general, the recommendatona described in NUREG/CR4001: EFFECTS OF MANUFACTURING VAR 1ADI FSthis document are more sinngent than the cunent indJatry rp ON PERFORMANCE OF HIGH. LEVEL WASTE LOW CARBONovirements however, there are exceptions The mapr areas STEEL CONTAINERS. FROST,R H Colorado School of Mines,wree specific enhancements are recammended include more Golden, CO. MUTH.LRa LIDf,A L Manufactanng Sciencessinogent entena for Level 111 quahtscatons, emphcit recommenda. Corp. Apnl 1990129pp 9005040070 $3647 242tons for reQuahficaton, greater emphasis on penodic annual) Analytical and expenmental research was portormed to deter.training, and recommendat ons for coordinating and a:1 minister. mine the effect of manuf actunng variables on the performanceing the quahficaton processes on a national (rather than local of cast steel overpacks The work examines the influence ofemployer) basis, casting and welding process vanables on the long term per.

NUREQ/CR.4908: ULTRASONIC INSPECTION RELIA 01UTY formance of 40* carten steel overpacks in the repository envoFOR INTERGRANULAR STRESS CORROSION CRACKS A ronment Contnfugal castmg was m6cated to be the mort eco-Round Rotwn Study Of The Effects Of Personnel, Procedures, nomical and technica!Iy favorable manufactun,y approach forEoulpment, And Crack Charactenstics HEASLER,P.G.; cast steel overpass A bottom would te welded into a hollowTAYLOR.T.Ta SPANNER.J Ca et al Battolic Memonal Institute, CYhud8' to make the container and final closure welding toPaafic Northwest Laboratory. July 1990.153pp 9008310179. Secure the hd would be done at the topository Effects of alloyPNL 6196. $$043.262 chemistry, sohdificaton processing. and sohd state phase trans-

A pipe inspecton round robin entitied " Mar >Round Robin" formations on f:nal microstructure of the cast and welded over-was condacted at Pache Northwest Latora'.ory from May 1985 pack has been examined in detail in this report. Codes andthrough October 1985 The research was sponsored by the U.S standards governing the manufacture of overpacks do not pres-Nuclear Regulatory Commist.on, Office of Nt: lear hoguistory ently exist. An extencion of the ASME Boiler and pressureResearch, under a program entitled "Evaluatiori and improve. vessel code supplemensd by government standards could tement of NDE Rehabihty for inservice inspecton of Ught Water adopted for the pur;ose Standard, well estabhshed methods ofReactors " The MineHound Robin (MRR) measured the IGSC non destructive ovatuston are adequate for the purpose ofcr&ck detection and sding capabihties of inservice inspection identifying hkely tranufactrnry defects Expenmental work fo-,

| (ISI) inspectors that had passed the requirements of IEB 83 02 cused on malenai and process combinatons to be used in man-and the EPHI suing training course The MRR data base was ufacture of overpaels Practical process hmits were experedcomprired with an earher Pipo inspection Round Robin (PIRR) and changos m microstructure due to repository thermal cone-that red measured effective detection pror to 1982. Compan- tons were investigt ted

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M:In Cit:tions and Abstreets 27

NUR(G/CR-6111: INTEGRATED REllABILITY AND Al5K ANAL. of uransum nugraton at a numter of d<sposal sites We haveYSdl SYSTEM (IRRAS) VERSION 20 USER'S GUIDE. used a chemical transport freodet to qualitattvety describe the of-RUSSELLK.D; SATTISON.M B EGAG Idaho, Inc. (subs of tects of geochmucal mechenemn on uranium transport TheiG&G, Inc ). RASMUSON.D.M Probatuhatic Risk Analyos resurt is a genershied conceptual model that can reproduce the 1

Branch June 1990. 464pp. 9007120205. EGG 2535 features observed at a numter of uranium mili talhngs disposat$4471103 artes

The integrated Rehatulity and Risk Analysis System (iRRAS)is a state of-the art, mectocomputer based probatutistic risk as. NUREG/CR 6141: NUCLEAR PLANT AGING RESEARCH THEsessment (PRA) model development and analysos tool to ad. 1E POtVER SYSTElf MEYER.L C; EDSON.J L EGAG idaho,dress bey nuclear plant safety istues IRRAS is an integrated inc. (subs. of CGAG, Inc ) May 1990.102pp 9306080179.so'tware tool that gives the user the atahty to Create ard ana- EGG 25a5. 64075 216tyre fautt trees and accedent scouences using a microcomputer Thas report presents the results of a study cf aging eHocts onThis prog am provdes furetons that range trom 9'aprucal fadt the Class 1E power system in nuclear power piants The 1Etree conerveton to cut set generation and avantificaton. Also power setem is the part of the plant audiwy poww systemprovded in the system as an entegrated tull-screen editor for ue that supphes power to the safety systems The purpose of thiswhen interfacing eth remote mainframe computer systems report is to evaluate the vHects of aging caused by (watonVerson 1.0 of tho #0 RAS program was released in February of within a nuclear facihty and the effectneness of maintenance,1987, Since that time, many user comments and enhancements testing, and monitoring on detectmg and mitwtang the effectshere been incorporated into the program provong a much of aging The U S. Nuclear Regulaton Commission's Nucleartwre powerful and user fnendly system. This verson has been Plant Aging Research gudelines work followed in performingdesignated IRRAS 20 and is the sutaect of this user's gude. the detailed study that eentibes 10 power system componentsVernon 2.0 of IRRAS provdes 34 of the same capatahtecs as susceptible to aging, svessors, enytronmental factors, and faibVernon 1.0 and adds a relatonal data base facil'ty for maneg- ute modes Testing. maintenarv e, codes and standards, anding the data. emproved functonality, and 6mproved algonthm per- regulatory issues are decussed Depa'taton mechants' 'a. fail-formance. ute modes and inspection, surveillance, and morwtonng rneth-

NUREG/CR 6117: STEAM GENERATOR TUDE INTEGRlTY cds are sumned for mapr class 1E components This reportPROGRAM / STEAM GENERATOR GROUP PROJECTfinal also presents the results of a revmw of the 1E power system

r Report KURT2.R.J4 CLARK,RAa operating exponences reporied in L6censee Event Reports, theProveet SummaiBRADLEY.E.R; et al Batiche Memonal Institute, Pacific North. Nuclear Power Emponence data base, the Nuclear Piant Reiswest Laboratory May 1990. 210pp. 9008070393. PNL4446 ability Data System, and plant maintenance records included in$4846 060 th's report are the alternating current system (4160 to 120 V).

The Steam Generator Tute integnty Program / Steam Gerera, the direct current system, and the vital 120 V ac instrument andtor Group Protect was a three phase program conducted for the control system.U S. Nuclear Reguletory Commisson (NRC) by Pacdse North ^

NUREG/CR 6211: ilNCERTAINilf S ASSOCIATED WifH PER-west Latorstory. The main goal of the program was to providtthe NRC wth validated informaton on the rehatdlity of nondo- mmNCE ASMSSMT OF HIGH LEVEL RADIOACTIVE

WASTE REPOSITORIES A Sunvnary Report DAVIS.p. A -structrve examination techniques to detect and stie flaws in -

steam gene stor tubing and to determine the remaining integoryof sonneedegraded tubing The program was performed in Gram. Inc. November 1990. 34pp 9012100331. SAND 68 2703-

three phases. The first phase involved turst and collapse tests W9t2Rand pngle frequency eddy current (EC) examinations of typical Th4s report culminates wor 6 performad by Sand 4a Nationalsteam generator tutung eth precinon mactuned flaws. The goat lateratones (W) b the U S Ncicar Regey Comimssonof Phase I was to develop empincal rnodels of romanng tube (NRC) on uncertainties associated with periormance assess-sntegaty as a function of flaw type and site, and to determine ment of HLW repositones Many different types of uncertaintythe capabibty of EC enspecton methods to detect and site tute can affect the performance of an HLW repository. In a perform-degradation in Phase ti, a smaller number of specimens wtth ance assessment, these uncertainties should be identified andthe same flew types were investigated, but tube specimens contadored, and to the went practicable, should be quantifiedwere degraded by chemical rneans rather than machining meth- and reduced Convenhonally, the different types of uncertaintyods This approach was used to better siraulate the arregular go, are dassified in three mator categones uncertainty in the futureometry of service induced degradation. In the final phase of the state of the dtsposal system, uncertainty in models needed toprogram, the retired from service Sorry 2A Steam Generator 8'mulate the behavior of the disp %al system, and uncertainty inwas used as a test bed to investigato the reliability of inservice data parameters, and coefficients needed for the ana9 sis ofEC inspecton equipment, personnel, and procedures, and as a the system All three major categones of uncertainty are covsource of service-degraded tubes for further validating the em, ered in trus report The reader should not rely on this report forpincal equahons of remaining tube integrity an indepth treatise of these types of uncertainty Oniy a short.

overview ts presented with numerous references to SNL reportsNUREG/CR 6169: MOBILt2ATION AND TRANSPORT Or URA- where different uncertainty topics are discussed 6n detail. as

NIUM AT URANtUM MILL TAILINGS DISPOSAL such, this report is not a stand alone report The report can beStTES Apphcaton Of A Chemical Transport Model used by (1) managors to famihante themselves with the issuesERIKSON,R La HOSTETLER.C Ja KEMNER.M L. Danel:e Me- regarding uncertainty 6n HLW repository performance, and (2)monal institute. Pacific Northwest Laboratory. January 1990 technical staff as a revio* of SNL's work for NRC in this area11500 9002120263 PNL 71b4 52596 210.

The geochemical processes of aquenus specificaton, precipo NUREG/CR 6211 V01: THE COGNITIVE ENVIRONMENT SIMO.tation, dissoluton, and adsorption influence the transport of ura- LATION AS A TOOL F OR MODELING HUMAN PERFORM-ruum at uranium rmli taihngs disposal sites Traditonal transport ANCE AND RELIA 0lLITYDecutrve Summary. WOODS D D.models involve the use of a stngle parameter, the retardaten Ohio State Univ., Columbus, OH. POPLE.H E. Pittsburgh, Univ.factor, to simulate the effects of these geochemical processes of, Pittr. burgh, PA. ROTH,LM Westinghouse Electoc CorpSingle parameter t',cdels are most appbcable to fie.d situatons June 1990. 3tpp. 9007120152. 54468163exhiating no changes in mayor element chemistry along the fiow The U S Nuclear Regulatory Commmson is spons0nng a pro-path Becaase of the changes in maior element chemistry that gram to d velop improvM methods to modo! cognitive t+hav6oroccur when acdC leachate Contacts a Deutrah2ing sod a single of nuclw jower plant (NPP) personnel. A tool called Cognitiveparameter transport model cannot accurately capture the optails Enytronment Simulation (CES) was developod for simulating

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28 M:In Cit:tions Cnd Abstrccis

I how reop6e form intenuons to act in NPP emergencies CES NUREQ/CR4263: PAHilTION A PROGRAM FOR DLFININGproodes an ana ytc tool for empionng plaumb6e human re- THE SOURCE TERM / CONSEQUENCE ANALYSIS INTE R.

FACE IN THE NVREG 1160 PRODADlLISilC RISK;sponses 6n tmergency situations in additon a methoelogycalied Cognieve hehatety Assessment Technique (CREATE)

ASSESSMENTS User's Gude IMAN,R L Sarda National Lat>3

was developed that desenbos how CF' can be used to provee oratones HE LTON.J C Antona State Unty., Tempu, A2.JOHNSON.J D. Science Applicatons internatonal Corp. (for-

6nput to human rebatety analyses (hRA) 6n probatubstic r sh as.,

sessment (PRA) studies This report desenbes the results of merty Science Appicatons,ine) May 1990.52pp 9006060t42.

three actMbes that were performed to evaluate CES/ CREATE: SAND 88-2940. 54076 318.This dacument has been ocogned for users of the PARib

(1) A lochncal review was conducted by a panel of experts in TlON computer program developed by the authors at San 4acognitive modebog. PRA and HR A; (2) CES was emercised on Nabonal Latoratories for defining the interface between thesteam generator tute rupture incoents for whch data on opeia. source term anatysis and the consequence anatysis The pur.los portormance entst, (3) A workshop with HRA practitoners pose of the PARTITION prog'am is to fo*m groups of sourcewas held to analyre a "workM example" of the CREATE meth- terms with similar properties One set of MACCS calculatons iscdology. The retu ts of all three evaluations indcate that CES/ pertormed for each of these groups The following or4natonsr

CREATE is a promising approach for modekog snienton forma- a's performed in PART1 TION (1) an early fatahty wtught and aton Volume 1 povides a summary of the results Volume 2 Ch'onc fatality weght are dehned for each source term, (2) tr.e~

provdes octans on the three evaluatons. enciveng the CES source terms are partitoned into groups of source terms withi

computer outputs for the tube rupture events similar radolog ca! potential on the bama of these weghts and a

NUREQ/CR 6213 V02: THE COGNITIVE ENVIRONMENT SIMU-single frequency weinhted source term 6s calcu!sted for each

LATION AS A TOOL FOR MODELING HUMAN PERFORM-source term group. i4 the source terms in each source term

ANCE AND RELIADILITY. Main Report WOODS.D D. Ohio State g'oup are drvided into autgroups on the bat's of evacuabonUniv., Columbus, OH. POPLE H E. Pittsburgh, Univ of. Patta- timing and a freovency-weighted source term is calculated for

'

each subgroup (4) vanous summary p6ots are produced to aidburgh, PA. ROTH,E M. Westirghouse Electric Corp June 1990. in checking the adequacy of the parttionng, and (5) an output09pp. 9007120162. 54468 091, file that serves as input to tha conseovence analysis is generat-

see NUREG/CR 5213,V01 abstract ed. The resoft of the partitoning process 66 a sutdvision of thesource terms on the bams of three dimensions early fatality to-

NUREQ/CR 6229 V02: TMb2 EPICOR41 RESIN / LINER INVESTpGATION LOW LEVEL WASTE DATA BASE DEVELOPMENT

tential, chronic latality potential, and evacus' on timing

PROGRAM FOR FISCAL YEAR 1989. Annual Report NUREQ/CR 6264; BIAS IN PEAK CLAD TEMPERATURE PRE.MCCONNELLJ W.; ROGERS.R D EG&G idaho Inc (subs. of' DICTIONS DOE TO UNCERTAINTIES IN MODELING OF ECCEG&G, Inc ). DAVIS.E C,; et at Oak Rdge Natona! Lateratory= BYPASS AND DISSOLVED NON CONDENSABLE GAS PHE.February 1990 52pp. 9003120764 EGG 2577. 5h82124. NOMENA. ROHATG1,U.S; NEYMOTIN.LYa JO.J.; et at Broc.k.

The EPICOR Il Rosin / Liner investgation Low level Waste haven Nabonal Lateratory September 1990. 17tpp.Data Base Development Program, forded by the U S. Nuclear 9010090047. BNL NUREG42168 $5322.253.Regulatory Commission (NRC), is studying the degradaton of' The U S. Nuclear Regulatory Commission (USNRC) tis con.fects in EPICOR41 organic on exchange remns caused by rad" tractors and consultants have developMI a methodology foraton; examnng the adequacy of test procedures recommend- ,,9,tbng Code Scaling. Apphcatahty and Uncertainty (CSAU).ed tn the Branch Techncal Pooton on Waste Forms to meet The CSAU method has been domonstrated by applying 11 to thethe reauirements of 10 CFR 61 using sch6fied EPICOR II resin; TRAC-PF1/ MOD 1, Vernon 14 3 code and its anahms of a

. obtaining performance informaton on soldfied EPICOR Il son large Dreak Loss of Coolant Accident (LDLOCA) for a Westing-enchange resins 6n a disposal enwonment, and determining the house four4oop plant in applying the methodology, the accocondton of EPICOR41 luers This report sumrien2es accom- dont couru m @vced into three $fferent phases hamefr Bbw.phshments of Fiscal Year 1989- down, Refdl and Reflood There are two d stinct peak clad tem-

peraturn A m 6n m mowdown maw and one in mNUREG/CR 6229 V03: EP6COR Il RESIN / LINER INVESTIGA- Reflood Phase The Rehood Phase PCT is affected by the phe-

TION LOW LEVEL WASTE DATABASE DEVELOPMENT PRO- um r a W ng Sy m S inGRAM FOR FISCAL YEAR 1900 Annual Report **""O*"* ** #"# " '** * ""**'

et atROGERS.R.0/'nc. JOHNSON DA; *9"*'* * * ** "9 " * * " ' "MCCONNELL.J Wa

l ) December 1990'65pp the Reflood Phase PCT from systematic errors (biases) assoc 6-EG&G Idaho, Inc- (subs of EG&G'0-9101160008. EGG 2019 56430:34 stod with the modelkng of the ECCS and dssolved nitrogen,

The EPICOR41 Rosinwner Investgatott Low-Level Waste and the apphcaton of this method The bias in the RehoodDatabase Development Program, funded by the U S. Nucica' Phase PCT due to the Jncertainty an the existing Code modelsRegulatory Commisson, is (a) studying the degradaton efiects for ECCS related phorbmena is 19 degrees K (,34 (%grees FLin EPICOR41 organic 6on exchange resins caused by radiation * The bias in the Pt.T due to the lack of modelling of dissolved(b) examnng the adequacy of test procedures recommended in N(2) in the code is estimated to be 9 9 dogees K (17.8 degreesthe Branch Technical Positon on waste Forms to meet the re- F) The code predeton for PCT ts conservative if the bias isQuirements of to CFR 61 using soldfied EpiCOnal remns. (c) negat,ve, and nonconservative if the bias is postive The biasobta.ning performance information on solched EPICOR41 non estimated here is based on full scale data from the Upperexchange resins in a daoosal enwonment, and (d) determong Plenum Test facihty and is unatiocted by the scale distorticosthe con 6 tion of EPICOR41 liners Results of the third samphnganalysis of ion exchange resins from prefdters PF 8 and PF.20 HUREG/CR 6266: COMPONENTS OF AN OVERALL PERFORM <are compared with baseline data from testa performed on unir. ANCE ASSESSMENT METHODOLOGY. DAVIS.P. A ;

rad 6ated resins and with results from the hrst and second san >PRICE,LL ; WAHi,K K.; et al Sande National Laboratones Fet>-

phngs to determine if degradation has occurred because of the ruary 1990.109pp 0003100287. SAND 88 3020. 53012 285Both the U S. Enwonmental Protection Agency (EPA) andhgh intomat ra$aton dose Resutts of compression tests on the U S Nuclear Regulatory Commisson (NRC) have promubseven-year old waste forms contanng EPlCOR* resins sole

fied with both Portland Type 141 cement and DOW vinyt ester- gated reguiations regarding the performance of geologic reposh

sty'one are presented and compared to earlier compresson tones for the disposal of t.igh level nuclear waste-Specificalty,lest data Nesults of the hfth year of data acquisition from the the EPA has promulgated three Quantit8tive. Postclosure re-

field testing are aiso presented and discussed. Quirements that apply to the entire darot.al system, while the

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|Main Citations and Abstracts 29

NRC's three quantitative, posiciosure reauvements apply onh was developed. The theory predicts that a occrease in strorsthto particulaf hubsystems of the reposttory. To a6sess complo of the lower crust (e 9. through a chan7 6n the fluid reg!me)anCe with all sin of these Quantitatfve requirements, th0 phe- leads to weakening and defortnation the stress Channel innomena . net can 4Hoct the pedormance of the repository, the the med+ crustal tona The weakenF , and stress coricer9at.ofiprocembes by whch these phenomena are produced, and tha may lead to major earthquakes E rthquake local mochanismspa'ameters asexisted with these processes will have to be in sN,heastern Tennessee are consistent with such a modeldentthod and Quantified in soition, the analyses periormed to Conclusions reached from this and other studies suggest thatasws compha'ge will have to t e conducted in accordance major earthquakes have haopened or could hapgen in south-with a portormance assessment methodology to ensure that all eastern Tennessee EarthquaAes an the Pedmorit are of a dit.regulatory cntena a'e addressed. A performance assessment forent type, being rnos*fy shallow, consstent with failure alongmethodoiogy proposed ty Sarda Natonal Latoratones is com- stunts and svedominantly associated with reservoir imgouroposed of sconscio deve6opment and screen.ng, conseavence ment This mechanism may leave an upper mag 4tude limit ofanalyst uncertainty anaiysis. and sonsttivity analys s This S 7. In Alabama. eucept near southeastern Tennenuws. the seis-methodoiogy can be used to assess comphance with the EPA's micity 16 largely enduced t y coal mine collapsesand NFCs requvements.

NUREG/CR 6262; PRAMIS PROBABILITY RISK ASSES $ MEN 1NUREG/CR 5258 V02: GEORGIA / ALABAMA REGIONAL SEIS- MODEL INTEGaATION SYSTEM Usor's Guide IMAN.R L;

MOGRAPHIC NETWORK Annual Report.Ju'y 19ti6 June 1987. JOHNSOkJ D; HELTON.J C. Sandia Natonal LaterstoresLON1L T. Geo gia institute of Technougv. At anta, GA April May 19A Mpp WM801M SAND 880093 W77.012.1990 71pp 9X$2OiB0 $3M1;242

This document has t+en desgned for users of the Probabilis-Data from continued operation of the seismographic network tic Rmk Assessment Model Integration System (pHAMtS) com-were und for topical studres A small swarm of cadhouakes oc- pute ptcgram developed by the a thors at Sandia Nationalcurred in the Lake Srnclaw, Georgia vicinity dunng the first qua'' Laboratones for easy assembly of the lodrvidual pads of theter of 198L The events ocevered in three main shocks of mag- NUREG 1150 plant analyses into overall nok resutM PRAMisnitude 2 and their attorshoch s The third event had an unusuauy aswmues the fo'iowing files associated with the NUREG 1160rapid decay in ahershock activity, suggesting complete release analyses in matna format to obtain not the Latin bype cubeof stress Attenuation and acattering were studied on the basis sa'npio, the results of the systems analysis, the results of theof theoretical evatuotons of the effects of spherical inclusanns in accidW progression analysis, tt4 tesutts of tLe source term /elastic or viscoelest6c media and on the basis of P wave codaResonance of the scatterer and viscosity of a solid matenal play parttorung anasysts, and the results of the consenwnce analy-

sit in addition, vanous intermeditte and cordtional quantitiesan important role in determining scattenng coefficients. Wave- are calculated when requested by user specified input, the trac-tels compnong the P, wave coda show systematic Increases

taonal contnbution to risk of individual plant damage states, acci-and decreases in spectral peaks that may be explained by shifts dent progression bans ahu source term gefyins are deterfraned,in the corner treauency cased ty absorptive attenuation and and a file contairung the onginal Latin hypurcube bample andscattenng in locating hypucenters, me method used at Ocorgia user-specified dependent vanabios is generated f ar utie as loputTech computes ongin time independent of locaton. Locaton to the SAS statstical package. Tfus report provxks a tutonaland depth are then computed with a fined ongin time. When 6

. that details how to use the PRAMIS prograrn. The PRAMis pro-ano P times are avadable, including off degonaf elements in the g,am is wntten 60 ANSI standard FORTRAN 77 to make thecovanance matna leads to locatons that are more precise than code as machin64rdependent (that is, portable) as pcssibiethuhe obtained with standard methods

NUREG/CR 6258 V03; GEORGIA / ALABAMA REGIONAL SEIS. NUREQ/CR 6273 V04: SCDAP/RELAP5/ MOD 2 CODEMOGRAPHIC NETWORK. Annual Report July 1987 June 1988 MANUAL. VOLUME 4 MATPRO A LIBRARY Or MA(ERIALSLONG T. Georg;a institute of Technology, Atlarita. GA Sep- PROPERTIES FOR LIGHT WATER-RE ACTOR ANDEN Ttomber 1990103pp 90102300% 55472 078. ANALYSIS DUCCAFURNI,A ; CARLbON,E R; CHAMBERS.R ;

A review of the histoncal se smicity of southeastem Tennes. et al EG&G idaho, Inc. (subs. of EG&G, Inc ) February 1990see suggests that the penod of 1970 through 1988 was anoma- Wpp 9003M269 EGG 2555 53002 040lously more active than before 1970. If this is true, then it repre. This repod describes tr a matenals properties conclations and&ents a unsque stress release event that would satisfy the computer subcodes (MATPRO) developed for use with vanousmodel for major intraplate earthquakes proposed by Long bght watw reactor pH) acceded anatysis computs prooms(1968) First motion data and SWP amphtude ration were used Formutation of the matenals propurtles are generally semermr-to deteirmine 36 eingle events and two composite focal mecha. ical a nature The matonais propwbos subcoctes contained innSm solutor,s for earthquakes in southeas,orn Tennessee. The this document are for uranium, uranium dioxide. rnamed uranium-dominant toJ11 mecharusm is sinke shp with reverse or normal plutoruum dioxide fuel, tircaloy cladding, tirconium darido,fault components Lineanting the relation betweeri measured stainless steel, stainles'n steel oxide. wiver Ircum-cadmiurnapparent coda O and assumed Constant coda Q for decrete alloy, boron certade, inconel 718 rirconium-uranium-orygonzones of crust suggests an anomalously low (Q = 50) regon melts. anc' fill gas m:sturesnortheast of staton CBT. Fracture density was mapped in anaron of induced seismoty near Civks Hill Reservoir It appears NUREQ/CR 6280 V01: AGE-RELATED DEGRADATION OF WES-that areas of higher joint spacing correspond to rones of In- TINGHOUSE 480. VOLT CIRCULI VtEAKERS Aging Assess-duced seismicity in tras and other reservoirs, earthquakes tend ment And Recommendations For improving Bresor Rehabihty,to occur in granite gness where 6ointing la sparte and the rock SUBUDHI,M ; SHIER W.; MACDOUGALL.E Drookhaven Naton.

at Laboratory July 1990 9 @ p. 9008070370 DNL NUREG.is strong Seismic activity is not often observou in foliated$pg7g g gschsts and aftered mat:c rockt .o which stress may be re-

leased througn cresp. An aging assessment of Westinghouse DS-senes low. voltageair circuit breakers was performed as part of the Nuclear Plant

NUREQ/CR 6258 V04: GEORGIA / ALABAMA REGIOr4AL SEIS- Aging Research (NPAR) prvgram. The obiectives of this studyMOGRAPHIC NETWORK Final Report August 1988 October are to charactense age reic.;ed degradaten within the breaker1990 LONGLT. Georg,a institute of Technology, Atlanta, GA assembly and to ident#y maintenance pract4ces to mitgate theirNovemter 1990 132pp. 9012280158 56195 316 effects Since this study has been promulgated by the f ailures

Data from the Georgia / Alabama network have contnbuted to of the reactor top breakers at the McGuire Nuclear Staten ina .>etter understanding of the sommacity in the Southeast Bared July 1987, resutts relating to the wolds in the breaker rxWe leveron these data a he* theory explaining intraplate earthquakes welds are also discussed The dvs an and opwation of DSG06

i

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arm DS 416 breakers wtwo reviewed Failure data from varcus tin (see page A-1) Background enformaton as supphed in the in-nab?inal data bases were anafried to 6denbty the predominant troducton and AppenAn A.failure modes, causes, and mechanstms. Additonal operabng

NUREG/CR+$296: CLOSLOUT OF IE COMPLIANCE DULLETINexponences from one nuclear staton and two industnal break. 66 03 POTENTIA', FAILURE OF MULTIPLE ECCS PUMPSer service componees were obtained to develop aging trends of

DUE TO SINGLE F AILURE OF AtR. OPERATED VALVE INvanous subcomponents The responses of the utdibes to the MINIMUM FLOW AECIRCULATION LINE. FOL EY,W J ;NRC Dunstn 68 01, wNch discusses the center pole leverwelds, were anatyred to assess the final resoluton of fanures of

DEAN.R S : HENNiCK A. PARAMETER, Inc October f Wo.31pp 9011050058. PARAMETER IE186. 55614152welds en the reactcw inps Documentaton is provded an tNs report for the etoscout of IE

NUREQ/CR 6280 V02: AGE.REL.ATED DEGRADATION OF WES- Comphance Dunebn 66 03 regarding the potential f ailure of mul-TINGHOUSE 480 VOLT CIRCUlf DREAKERS Mechanent Cy. tiple Emergency Core Cooling System (ECCS) pumps due to achng Of A DS 416 Dreaker. Test Results. SUDVDHl.Ma single failure of an airgetsted valve h a minimum flow reescu- ,

MACDOUGALL,E.; KOCHIS.S.; et al, Brookhaven Natonal Lab- laton hne Closeout is based on the implementaton and venfe- .

oratory. Novemter 1990.124pp, 9012280152 DNL NUREG- cabon of four actions reousted by the but!etin. Evt.lueton of utih.

52178 56f 95 f 92. iy responses and NRC/ Region inspecten reports in accordanceA D$-416 medum voltage air circuit tweaker manufactured by with specific crliere indicates that the bunctin to closed tot 116

Westinghouse was tvcharucalty cycled to identdy age-related (98%) of the 118 nuclear power faculbes b operation or underdegradat:ons TNs accelerated a;png test was conducted for constructon to wNeh it was itsued for acton Facihtet whichover 36,000 cycles donng 9 months. Three sorterate pole were shut down indefvutely or permanentty, or whch had con-shafts, one with a 60 degree weld, one with a 120 degree, and struction hatted indefinitely were rest inclu3ed in (Ns review A

one with a 100 degree were used to charactertre the cracking follow-up stem is proposed for the two (2) %t.hties with openin the pole lever welds. In additon, three @fferent operaung bulletin att.tus. It is concluded that the buDetin concern has~,

mecharisms and severd other parts we's replaced as the) teen remotved, pend ng closcout by the NRC of Zon 1.2. Back-became hoperable The testing yielded many useful resutta. ground infortnaton in provided in the introducton and AppendniThe burning of the closing coIs was found to be the effect of A.

tunding n the hnkages that are connected to tNs device.NUREO/CR 6297: CLOSEOUT Or IE DULLETIN 83-05 ASMEAmong the seven welds on the pole shaft, #1 and #3 mtve the

NUCLEAR CODE PUMPS AND SPARE PARTS MANUF AC-cribcal ones wNch cracked first to cause misahgnment ut theTURED BY THE HAYWARD TYLER PUMP COMPANY.pole levers, wNch in turn, had led to many prob'rms with the FOLEY,WL DE AN,R S.; HE NNICK,A PARAMETER, Inc

pperating mecharvsm including the burrung of coils, excessivewear in certain parts, and overstressed lekages Desed on August 1990. 33pp 9009160017. PARAMElER IE188

552f 4 200these findings, a maintenance program is suggested to alleviate Documentation is provided to this toport to cose IE Dulletinthe age related degradatons that occur due to mechanical cy. 63 05 regeding ASME nuclear code pumps and spare partschng of a breaker, manufactured by the Hayward Tyler Pump Company (HTPC)

NLREG/CR 5286: CLOSEOUT OF IE DULtETIN 7917 PIPE The bulletin was issued (1) to alert holde s of operahng heenses

CRACKS IN STAGNANT DORATED WATER SYSTEMS AT and construrbon permits of nuclear power plants that HIPCPWR PLANTS. FOLEY,W.J.; DEAN.R.S ; HENNICK,A. PARAM- failed to hapvment offect'vety their Quakty assurance (OA) pro-ETER, Inc. February 1990= 35pp ' '04090172 PARAMETER gram from 1977 to 1981 and (2) to requ*re affected utillhes toIE t F7. 533f 4 237, take acton to resou the potenbal for failure of the subject

Doc'.imentaten is prov6ded in tNo report for the closeout of IE pumps and their spare parts Evaluebon of utthty resterwes afdDuhebn 7917 and its reva6on on the safety related sub}cct of NRCinegon inspachon repor% shows that rebatety of the af.pipe cracks in stagnant borated water systert.e at operating focted pumps was ensured by means of procedures and per-plants with prsasunrod water reactors (PWRs). Cloteout is formance testing of the pumps as required t'y the tulletinbased on the implementabon and venfcation of actions required Dated on the evaluabon, 6n accordance with specific cnterta.

by the bulletin Evaluabon of utshY responses and NRC/ Reg,on the bulletin is closed for 11E (98%) of the 118 faclht es to wNch,

inspecton reports indicates that tne bulletin is closed fan all of it was issuAl for acton and wNch were not shut down 6tdet-the 41 operating PWRs to wNch it was issued for acton. It is rutety or permanentty at the time of issuance of ins report Aconcluded that the concerns of he buhetin have been remotved. followmp ttom is proposed for the two facshties with open bulle.

Background 6nformation is supphed in the introd_chon and Ao- tin status Based on favorable results, a concluson is presentedto indcate that the butletir) concerns f ee teen resolved Dack-pendu Aground intorn.ation is supphec' in the Introduction and Appendix

NUREO/CR 5289: CLOSEOUT OF IE DULLETIN 79-23 POTE% A.TIAL FAILURE OF EMERGENCY DIE 6EL GENERATOR FIELDEXCITER TRANSFORMER. FOLEY,W.J.; DEAN.R S.; NUREQ/CR 5298: CLOSEOUT OF IE DULLETIN B5401: STEAMHENNICK,A. PARAMETER, Inc. March 1990. 27pp. BINDING OF AUXILIARY FEEDWATER PUMPS FOLEY,W J:

9004090279. PARAMETER IE180. 53330 298. DEAN,R S.: HENNICK,A. PARAMETER, Inc. January 1Ir90Documentabon is provided in tNs report for the closeout of IE 37pp 9003070241. PARAMETER lE180 52003 268.

Dulletin 7423 regarding the potental future of emergency Documentation is provided 6n this report for the closcout of IE

diesel Generator beld exciter traraformers. Closecut m based BuHettn 85 01 regarding steam binding of austhary feedwaterupon the implementaten and venfcation of three actions re- pumps fnt certain pressurized water reactors (PWRs) in nuclearQuired by the bullebrt Evaluaten of utikty responses'and NRC/ power facihties indredual f aahty closcouts are based on the im-Region inspection reports tndicates that the buhetin is closed br p4ementabon and venficabon of the trVee schons required byall of the 119 nuclear power facHition with & operating hcense the Wetin Evaluaton of ubhty responses and NRC/ Region in-of a construcbon permit at the time the butiotin was issued, specton reports indicates that the bulletin is closed for 44September 12, 1979. Deviations f.om bulletin tesbng require- (92%) of the 48 facikties to wNch it was assuod for actiort Fobmonts, along with hcensee justihcations, are hated It is conclud- lowup items are proposed for the use of NRC regona! nnspec-ed that the problem cf concern was not genorc, since onry two tors in 90sunng satisfactory completion of required actons forplants, Nine Mile point 1 and Turkey Point, requued modifca- the four facihties with open bulletin status Conclusions are sum-tons to correct confMcbons wNch could cause hQh circulahng manied in accordance with Generic Leuer B843, wNch an-

*

currents The problem at Turkey Point is desenbod in the buile- nounced the NRC Sta'f's resoluton of Genonc Issue 93 on the

B

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i


autyect of tNa tubebri Dackground informabon is supplied in to a posst.ile loss of the Emergency Notifcabon System (ENS)the introduction and Appenen A upon loss of offsite power. Closecut is based on the emplemen.

NUREQ/CR4302: CLOSEOUT OF IE P JLLETIN 90-10 CON, tate and venfesten of am (6) rwed adone by iconsees of1 AMINATION OF NONRADIOACTIVE SYSTEM AND RESULT. wclear Wwer reacWs M operaMn or near to eving an &ING POTENTIAL FOR UNMONITORED, UNCONTROLLED RE. watmg a when me twin was M on M 4, NLEASE OF RADIOACTMTY TO ENVIRONMENT. FOLEY W.J; habatm of @ responm aM M%m Wen +DEAN.R S : HENNICK A FARAMETER, Inc. Fetruary 1990 p rts Mcates mat to buMin is closed b an of me 69 6

30pp.9003120758. PAR AMETER IE193. 52682 237. er power reactors to wNch it was issued for action and whichDocumentaton 6s provided 6n tNs report for the closoout of IE were tot shut m 6ndewe9 w pwmanenW at me hme d

Bulletsn 8010 regareng contamination of nonradoactrve sys. issuance of his tem Dad 0round Wmaton is suppbad mtems resutting in the potent al for unmorvtored, uncontrotted re- me htroducion and AppeMin A Nuclear fuel fame as wonlease of redoactrvity to the environment, Clomeout is based on as nuclear gewer facihtes were adentified 6n the enclosures tothe documentaton and vertficabon of four actons reQuesd by the tviletin. However, per an NRC memorandum, the closooutthe bulletn for holders of an operating teense for a nuclear of the bullebn for nuclear fuel facihties is tot witNn the scope ofpower facility at the time the buheten was issued (05 06-80L 1he IN8 ''PMbuhebn was issued for informabon to holders of a constructonpermtt for a nuclear power facihty. Evaluaton of utikty re- NUREQ/CR 6314 V03: LIFE ASSESSMENT PROCEDURES FORsponses and NRC/ Reg.on inspecton reports in accordance MAIOR LWR COMPONENTS Cast Stainless Steel Compo.with the C406e out Critenon indcates that the buhoten is closed nonts JASKE.C E.: SHAH.V.N. EG&G idaho. Inc. (subs offor 65 (98%) of the 66 nuclear power facihties to which it was EG&G. Inc ). Octobor 1990. 64pp. 9011000093. EGO 2562.ist.ved for actiort A foibw-up item is proposed for the facility 55616 297' ort presents a procedure for estimatin0 the currentTNs repwrth open status, for the use of NRC regional inspectors in erkaunng auccesstut completon of requwed actons When the bul- Condton and residual life of safety related cast stainless steellebn is clooed as anticipated for the f aciltty whch requees components in light water reactors (LWRs). The procedure ac.fotbw.up (see page C-1). the concerns of the bullebn will hava g pbeen tesotved completety. Background informaton is suppled tmttlement and 6ncludes the following a review of design andin the introduction and Appendx A fabncabon records innervice inspection records, and opersting

Nstory; a fracture mechanics evaluation to determine the re-NUREG/CR4306: CLOSCOUT OF IE BULLETIN 7910. AUD1DIL*

ITY PROBLEMS ENCOUNTERED ON EVACUATION OF PER.oured toughness estimates, and cnteria regateng conbnuedservice. tepair, or replacement of the component beeng (valual.SONNEL FROM HIGH NOISE AREAS, F OLEY.W.J4

DEAN.R Sa HENNICK.A. PARAMETER, hic Novemter 1990. ed. The report discusses the available Charpy V notch 4mpactenergy, tracture toughness, tensile strength, fatigue resistance,10pp 9012280214. PARAMETER IEt97. %250132.

Documentabon to provded in tNo report for the closcout of IE and fabgue-crack growth data, and prosents two rnethods forassessmg the degree of thermal embrittlement metanurgicalBubetin 79-18 regarding auditwhty problema encountered on

evacuaton of personnel from Ngh. noise areas. Closeout is evaluaton and anaWcal modeling of 6nwrvice degradabon.

band on the implementaton and venficabon of four (4) re- NUREG/CR4316: MELT PROGRESSION. OXIDATION. ANDquered actions. Evaluation of ublity respontos and NRC/ Region NATURAL CONVECTION IN A SEVERELY DAMAGED REAC-Inspechon reports an$ cates that the buHetin is closed for all of TOR CORE. DOSANJH.S S. Sandia Natonal Laboratones Feh-the 64 operating nuciear power facilities to wNch it was issued tuary 1990 93pp. 9003070229. SAND 88 3476. 53361:156for actiort Facikties wtuch were shut down indefinitely or perma- In the revised Severo Accident Research Program plan, thenently at the time t' issuance of tNs report are not included in U S. Nuclear Regulatory Commissica places a Dreat emphasistNe review. Backpod enformaton is presented 6n the intro- on code documentabort TNs present report, wNch describesduction and Appendix A. The conclusion is made that the tuno- work that was conducted over a penod of several years in thetan concerns have been resolved. MELPROG code development project, is 6ntended to support

NUREO/CR4307: CLOSEOUT OF IE DULLETIN B0 02: INAD. tNe goal Of interest here is the tato phase of core melt pro-EQUATE OUAllTY ASSURANCE FOR NUCLEAR SUPPLIED Dresseort A model that treats some of the important phys. calEQUIPMENT. FOLEY,W.Ja DEAN.R S.; HENNICK,A. PARAME. processes that can occur dunng tNs phase of the accsdent isTER, Inc. December 1989.15pp. 9002120237. PARAMETER desenbod herewt A number of straightforward esamples areIEt98 52611104. given to illustrate the utility of the model ard to identify the

Documentabon is provided in tNs report lor the closcout of IE dominant physical processesDulletin 80-02. The subiect is inadequate quahty assurance forruclear equipment supp6ed by the Marvin Engenoorng Compa' NUREG/CR4366: HTAS2: A THREE DIMENSIONAL TRANSIENTny. The equipmont of concern ta suppled either Grectty or SHIPPING CASK ANALYSIS TOOL WENDEL,M Wa GILES.G E.

through other supplers for use in General Electnc boiling water Oak Rdge Nabonal Laboratory. May 1990. 8tpp 9000290147.ORNL/CSD/TM 20t 54324.312.reactors (BWRs). Closeout is based on the 6mplementaton and

venficabon of three (3) requwed actsons EWehnn of ut tity re' 1No report describes the HTAS2 computer program wNchsponses and NRC/Rogon enspection reports 6ndicates ui.1 ** can be used to assess the thermal behavior of shipping casksbuttetin is closed for all of the 38 BWR facihties to wNch it was containing PWR. type fuel assomblies. HTAS2 has two parts: a6asued for acton. It is concluded that the tafety concems re. global cask anahsis and a single assomt9y analysis. The globalflect 4 in the IE Bulletin 80 02 were acequately resotved by the cash analysis is a three dimensional lumped parameter mode'actons taken by hcensees and venfed by NRC 6n6pectors for the entro sNppin0 cask and its contents. The user has the

Background informaton is presented in the introduchon and Ap- opton of simulating a prefwe steady state, a fro transient, apenda A postfre transient, or a final steady state in acceptable order.

Details witNn the fuel assomtmos are not resolved in tNs por-NUREG/CR4308: CLOSEOUT OF IE BULLETIN B015: POSSI. ton of the analysis The single assembty anatysis is two4 men.

BLE LOSS OF EMERGENCY NOTIFICATION SYSTEM (ENS) saonal and contains a detailed ra$ahon and conducton modelWITH LOSS OF OFFSITE POWER FOLEY,W.J: DEAN.R S4 wNch can be used to represent PWR square pitched fuel as-HENN1CK.A. PARAMETER. Inc. Decomter 1990. 38pp. sembhos A simple convection modelis available The boundary8101040257. PARAMETER IEt 99 56270 237. cordtons on the basket walls surroundng the assembly can be

Documentat.on is provded in tNo report for the closcout of IE dwectly specified or may come from a prevous global caskBulletin 8015 for nuclear power reactors TNs bulletin portained analyws Gocd companson was obtained with other computa.

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_


tional rewis for both pris of the anat w. Atthough good ~MI Act.on Plan Requiremente, and related orders the reviewy

agreement was found between the singte assemtay results and includes descontions of gone systems devvoped , y West ag-

expenmental data, the global cask ana'ysis has not yet teen house and Combust on E nginwnng. as won as piant specife re.

valdated against expenments this task is recommended as a views of each pressanspJ water reactor installaton Perform-ance charactenstics are awussed, snetuding feedback frompart of f.iture workplant personnel concern:ry instaliation. operational exponence.

NUREQ/CR 6368: REACTIVITY ACCIDENTS A Reassessment Of and operstor acceptance An waluaten of toding motor teactorThe Desgn-Basis Events. DIAMOND,D.Ja HSU.C.Ja systems e inWFITZPATRICK.R. Brookhaven Natonal Laboratory January1990.135pp 9002120269 DNL.NUREG 52198. 52596 325 NUREQ/CR 6376: OVAUTY ASSURANCE AND VERlFICATION

This report documents a study of hght water reactor event se- OF THE MACCS CODE. Verson 1.5 DOBBC.C. A ;

quences which have been investgated for their potential to MARWIL,E.S ; CARLSON,E R ; et at EG&G Idaho, Inc (subs. ofresult in reactivity accidents with severe consequences The t:G&G. Inc ) February 1990. 61pp. 9003120744 EGG-2566study is an outg*oeth of the concern whch arose after the acci- 52882 176dent at Cherrobyl and was rocommended by the report of the An independent quaW assu ance (OA) and venficanon ofr

U.S Nuc6 ear Regulatory Comisson (NRC) on the emphcatons of 33gggg g ,

that accident (NUREG 1251) The work was done for the NRC System (MACCS) was periormed The OA and venficaton in-to reconbrm or bong into Queston prevous judgements on reac- olved emartunaton of the code and assocated dacumentationtrvity events which must be analyzed for hconsing Event se- for consistent and correct implementaton of the mndets in anquences we's defined and then a probabikste assessment was error tree FORTRAN computer code The OA and venficatoncompleted to estimate the frequency of the reactivity event was not intended to deto*mine either the adequacy or appropo-and/or a deterministic calculaton was compicted to estimate a MN A n used in MACCS 1.5 The re-the consequences to the fuel. Using the results of this anaeysis views uncovered errors wheen were fixed by the SNL MACCSdone by others. and a set of screening critona developed wittun code development stati poor to the release of MACCS 1.5this study, judgements were made for each sequence as to its Some ddfeutties related to docu rontston imIirovement andr

importance, and recommendatons were inade as to whether code restructunng are also presented The OA and verificatonthe NRC ought to be consdenng the important sequences as process concluded that Waston 1.$ of the MACCS code, withinpart of the desgn basis or for further, more detaited, investga. the scope and hmitatons of the models implemented in theMn. code, ta essentialty error free and ready for wdespread ut,e

rdVREG/CR 6369: THE SEISMtC CATEGORY l STRUCTURESPROGRAM RESULTS FOR FY 1987, F ARRAR,C R.; NUREG/CR 5381: ECPNNU RISK OF CONTAMINATIONDENNETT.J G ; DUNWOODY,W E4 et al. Los Alamos Natonal CLEANUP COSTS rtESULTING FROM LARGE NONREACTORLaboratory. October 1990. B3pp 90t1000099. LA 11607 MS NUCLEAR MATEFJAL LICENSEE OPERATIONS PHILBIN.J S.

Sandia Natonal Laboratones SALOlOJ H ERC Environmental55616.212The accomphshments of the Seismic Category i Structures & Energy Serv 6ces. Inc. ROLLSTIN ) Gram, trw Ma'ch 1990

Program for FY 1987 are summanted. These accomplishments 185pp. 9004100430. S AND89-1302. 53344:114include the Quase-state load cycle testing of large shear wall Soveral gotent4al inc, dent scenanos invorving the acodontalmoments, an esiensive analysis of previous data to dotermine if release of radoactrve matonal at five reference, nonreactor nu-

equrvalent knear anaeytcal models can predict the response of clear matenal hcensees are anatytod in (Ns report The eco-damaged shear wall structures, and code committee actrv' ties nomec nsk ($/hcenseo/yr) of decontaminaton is evaluated fortri addition, previous testing and results that 'ed to the FY 1987 each reference beensee. Although most releases and cleanup

program pian are discussed and all previous data relating to costs are minor, some less frequent inodonts may result 6n verysheas wall 6tiffness are summan ed. Because separate reporte Ngh cleanup costs that dominate the economic risk of decon-have already summartted the expenmental and analytcal work tamination of a particular heensee The economic nsk for the 5in FY 1987, this repC't will bnefty Nghhght this work and the ap- plants ranged from a low of $14.000 per heenseo per year to apropnate reports will be referenced for a more detailed discus- Ngh of $104,000 per hconsee per year. This report is the

Second of two reports by Sandia National Latoratones on thesion. ecoromic nsk of nonteactor nuclear matenal heensee oporNUREG/CR 5373: A DEMONSTRATION EXPERIMENT OF stons This report provces techrucal basis for a proposed to

STEAM DRIVEN, HIGH. PRESSURE MELT EJECTION The nancal responsibikty ru6emaking for nonreactor nuclear matonalHIPS 10S Test ALLEN.M.D.; NICHOLS.R.Ta PILCH.M Sanda W nsees.Natonal Laboratories. July 1990. 92pp. 9008310209. SAND 89-1135,55043J 74 NUREG/CR 5385: INITIAL ASSESSMENT OF THE MECHA-

A steam blowdown test was perforrned at the Surtsey Direct NISMS AND SIGNIFICANCE OF LOMTi.MPERATURE EM-Heating Test Facihty to test the steam supply system and burst DRITTLEMENT OF CAST STAINLESS STEEt S IN LWR SYS-diaphragm arrangement that will be used in subsequent surtsey TEMS CHOPRA.O.K., SATHERA Argonne National Laborato-Direct Containment Heating (DCH) expenments Following suc' ry, August 1990. 252pp 9009040085. ANL 89/17. 55048 043cessful completion of the steam blowdown test, the HIPS-10S TNs report summan2es work periormod by Argonne National(Hgh-Pressure Melt Streaming) expenment was conducted to Laboratory on long-term embnttlement of cast duplex stainlessdemonstrate that the technology to periorm steam-dnven, hgh- steois in LWR systems Metallurgical charectentation and me-pressure mett ejecton (HPME) expenments had been success- chan6 cal property data trom Charppmpact, tensile, and J Rfulty oeveloped. In addition, the HIPS 10S expenment was used curve tests are presented for several exponmental and commor-to assess techniques and instrumentaten desgned to create cial heats, as well as for teactor aged CF-3, CF 8, and CF BMthe proper timing of events in HPME expenments. cast stainless stools. The effects of matunal vanables on the

NUREG/CR 5374: SUMMARY OF INADEOVATE CORE COOL- embottlement of cast stainless steels are evaluated ChemicalING INSTRUMENTATION FOR UNITED STATES NUCLEAR compositon and ternte morphology strong!y affect the catent

POWER PLANTS. ANDERSON.J 14 HAGEN E W.; and kinetics of embnttlement in generaf, the low carbon CF-3MORELOCK.T.C, Oak Ridge Natonal Laboratory. July 1990. stainless steels 9e the most resistant and the molybdonum-

197pp.9008070334. ORNL/TM 11200. 54850;027, containing Ngh-cart >on CF+M stainless steels are most suscop.TNs report summanzes a review of inadequate Core Cookng tible to embattlement The microstructural and mechanicaLprop-

Instrumentation installed in U S. nuclear power plants in re- erty data are anaty2ed to es ateh the mechanisms of embnttle-sponse to the requirements of NUREG-0737 Ctanfcaton of ment. ' w proceduto and cweistons for predicting the impact

|,

"

-* ' - - ' ' ' - ' ees--e-- - . - , . , , , . - . - . _ _ , , _ _ , _ _ _

. _ - - . - . -_ _ _ . ._=__ - - - _ . . . . - . _ - -

M:In Citat!ons cnd AbstrCcts 33

strength and fracture toughness of cast components during re. quacy of system codes, such as RELAP5 and TRAC, for pre.actor servce are deserted The lower bourd values of impact dechng abnormal plant transents The MIST program is reported |strength and fracture toughness for low temperature-aged cast in 11 voiumes The program is summartted in Volume 1; Voi,stainless steel are defimd- umes 2 through 8 desenbos g*oups of testa by test type- I

NUREG/CR 5386: BASIS FOR SNUBBER AGING RESEARCH. Volume 9 presents inter group compansons, Voiume 10 pro-iNUCLEAR PLANT AGING RESEARCH PROGRAM. vees compannons between the calculations of RELAP5/ MOD 2iBROWN.D P. Lake Engineenng, Inc. PALMER.G R. Wyie Lab. and MIST observabons, and Volume 11 presents the later

oratones WERRY,E V.; et at Battelle Memonal institute, Pacifc Phase 4 tests Ttus Volume 2 pwtains to MIST mapping testsNorthwest Laboratory. January 1990 119pp. 9002120341 PNL, performed to traverse the early post.SBLOCA events slowly.6911. 5260t908. This report describes a research plan to ad. The tests investgated the etteet of test-to. test variations indress the safet, concerns of aging in snubters used on pong boundary system controls, and only the pomary fluid massand egapmeni in commercial nuclear power piants. The work is vaned dunng a specifc test in this test group.to be performed under Phase 11 of the Snut'ber Aging Study ofthe Nuclear Plant Agng Research Program of the U S. Nucicar NUREG/CR f 395 V10: MULTILOOP INTEGRAL SYSTEM TEST 1

Regula'ory Commission with the Pacif c Northwest Laboratory (MIST) FINAL REPORT. RELAP5/ MOD 2 MIST Anatyws Com.(PNL) as the pnme contractor. Research conducted by PNL panaons KLINGENFUS.J.A.; PARtCE.M V. Babcock & Wilco

|under Phase i provded an erubal assessment of snubter operat. Co. December 1989. 300pp 9002120141 EPRl/NP 6480.ing exponence and was pnmanty based on a review of laconsee 52580 313.event reports. The work proposed to an extension of Phase i The Mutuloop integ+al System Test (MIST) is pa t of a muttsand includes research at nuclear power plants and in test lat> phase program started in 1983 to address small break loss.of.oratones included is technecal background on the design and coolant accidents (SBLOCAsl specific to Babcock and Wilcoxuse of snutters in commercial nuclear power appiscabons; the

designed plants MIST is sponsored by the U S Nuclear Regu-pnmary failure modes of both hydraube and mechanical snub- latory Commissaon, the Babcock & Wilcox Owners Group, thebers are discussed The anticipated safety, technscal, and reg *

Electre Power Research Institute. and Babcock and Wilcotlatory benefits of the work, along with concems of the NRC andThe unque features of the Babcock and Wilcox design, specifstne utilites, are also desented*rily the hol leg U bonds and steam generators, prevented the

NUREQ/CR 5393: A REVIEW OF TECHNIOVES FOR PROPA- use of ecsting integral system data or existing integral facihtiesGATING DATA AND PARAMETER UNCERTAINTIES IN HIGH. to address tne thermal.hydraul6c SOLOCA questions MIST andLEVEL RADIOACTIVE WASTE REPOSITORY PERFORMANCE two over suwbng fambes were trecifcany Wwgned andASSESSMENT MODELS. ZIMMERMAN.D A.; WAHLKK.; constructed for this program, ar'd an oosting facility-the OnceGUTJAHR.A.L.: et at Sande Nabonal Laboratones March Through Integral System (OTISFwas also used Data from1990.150pp. 9007120186. SAND 891432. 54470 01t M'ST and the other fac6%es wdl be used to benchmark the ade.

Technsoves for propagating data and parameter uncertainbes Quacy of system codes, such as RELAP5 and TRAC, for pre.in highlevel waste (HLW) repository performance assessment oschng abnormal plant transents. The MIST program la reportedmodels are docussed. Uncertainty anatyws technques asenbe in 11 volumes. The program is summansed in volume 1; Vol.Quant:tative rnessuros of rehabahty lo model prodctions. Both 10 umes 2 through 6 de9 ;r bes groups of tests by test type.CFR Part 60 and 40 CFR Part 191 require considerabon of un. Volume 9 presents inter group compansons, Volume 10 pro-certaintees including uncertaintes in data and parameters, in vides compansons between the calculabons of RELAPS/ MOD 2the performance assessment of an HLW repository system. and M!ST observavons, and Volume 11 presents the laterFour categones of uncertainty analysis methods are d* cussed. Phase 4 tests The compansons of RELAP5/MDD2 against theMonte Carlo simutebon, replacement models (response surface MIST data and conclusions reached are the subject of thistechnques). differenbal technques (dvoct, adjoint, and Green's volume.functon technique), and geostabsucal techrwques (stochasbcmodehng using Monte Cano simulabon and spectral anatysis). NUREG/CR 5395 V11: MULilLOOP INTEGRAL SYSTEM TESTAdvantages, disadvantages and applications of each technque (MIST) FINAL REPORT. MIST Phase IV Tests GEISSLER,G O.are presented Propagabon of uncertainbes through muttiple, Dabcock & Wilcos Co. August 1990 528pp. 9009210290. EPRl/hnked models is also discussed Appleabon of these technques NP 6480. 55237:,69to sensitivity anaryws is also presented. Sensittvity analyses can Tha Multiloop integral System Test (MIST) is part of a multi-be useful to uncertainty studies because the number of param- phase program started in 1983 to address small break loss of-eters included in tho uncertainty anatysis can be reduced by coolant accidents (SDLOCAs) specrfic to Babcock and Wilconehminating those parameters for which the uncertainty has a designed plants MIST to sponsored by the U.S Nuclear Regu-minimal effect on the performance vanab!e(s). latory Commission, the Dabco-k & Wilcox Owners Group. the

NUREG/CR 5395 V02: MULTILOOP LNTEGRAL SYSTEM TEST Electnc Power Research Insbtute, and Babcock and Wilcon.(MIST): FINAL REPOPT, Test Group 30, Mapping Tests The unque features of the Babcock and Wilcon design, specifi-GEISSLER,G O. Babcock & Wilcox Co December 1989. cally the hot leg U bends and steam generators, prevented the1,058pp. 9003070265. EPRl/NP-64BO. 52803.305. use of ensting integral system data or existing integral facshtees

The Mulbloop Integra! System Test (MIST) is part of a muito to address the thermal-hydrauhc SBLOCA queshons. MIST and' phase program started in 1983 to address small break loss of, two other supporbng facd bes were specif cally designed andt

coolant accidents (SDLOCAs) specific to Babcock and Wilcox constructed for ttva program, and an existing facdity-the Oncedesigned plant.. MIST 6s sponsored by the U S. Nuclear Regu. Through Integral System (OTIS)-was also used. Data fromlatory Commission, the Babcock & Wilcou Owners Group, tn, MIST and the other faciht es wdl be used to benchmark the ade.Electnc Power Research Instatte, and Babcock and Wilcox, quacy of system codes such as RELAP5 and TRAC, for pre-The unique features of the Babcock and Wilcox design, noecif- dict ng abnormat plant trans ents. The MIST program is reportedcally the hot leg U bends and steam generators, prevented the in 11 volumes The program is summarued in Volume 1, Voi-,

use of existing integral system data or existing integ41 facihtes umes 2 through 8 descrive groups of tests by test type; Volume,

| to address the thermal hydraube SBLOCA quest nns. MIST and 9 presents inter group compansons, Volur.se 10 provides com.s- two other supporting fac+ ties were specifcally demgned and pansons between the calculat.ons of RELAP5/ MOD 2 and MISTconstructed for this program, and an exishng facility-the Once observauons. and volume 11 presents the later Phase 4 testsTnrough Integral System (OTIS)-was also used. Data from This Volume 11 penains to MIST Phase IV tests periormed toMIST and the other facilibos will be used to benchmark the ade- invesbgate nsk dominant transients and non-LOCA events

. _ __ _ .___

- __ - - - - - - - .. _ -_ - -- .. . - - - . = - . -.

34 Main Citetbne Cnd AbstrCcts

NUREQ/CR4396 Vit AD: MULTILOOP INTEGRAL SYSTEM anatyws, deperding on the importance of the analyvs, the ac.

TEST (MIST) FINAL REPORT MIST Phase IV Tests ceptatniity of the conceptun' model behind the anatysis and theGEISSLER G O Batcock & Wilco Co August 1990 273pp soluton techruque used, and the potential for 6ncreasing conh-9009210229 EPRl/NP-6480. t,5233 202 donce an the bystem desenption Should the NRC decide to de-

The MJteop Integral System Test (MIST) la part of a mufb- veksp its own models/ codes An appropnate level of review canphar * Ngiam started 6n 1983 to address small-treak loss of- be determined by applying these four critona in a spocifscwa it accdents (SBLOCAs) specifc to Babcock ard Wilect manner.oesced plants MIST is sponsored by the U.S Nuclear Regulatory Comrnisson, the Babcock & Wilcon Owners Group, the NUREQ/CR 6399: SURVEY OF STATE AND TRIBAL EMERGEN-Electre Power Research Institute, and Babcock and Wilcos. CY RESPONSE CAPABILITIES FOR RADIOLOGICAL TRANS.The unique features of the Batcock and W6lcon design, specif6- PORTATION INCIDENTS VILARDOJ.J.; MITTER.E L;

cally the hot leg U-bends and steam generators, prevented the PALMER.J A; et at ind ana Univ., Bloorrwngton, IN May 1990.

use of existng integral system data or existing integral facilites 230pp 9006290123 54322'294to address the thermal bydrauls SBLOCA Questons MIST and This publicaton is the final retort of a protect to survey the

r

two other supportng facilites were specthcally designed and fifty states, the Distrct of Columbia. Puerto Aco, and snlectedconstructed for this program, and an ernsting facabty-the Once indan tnbat Junsectonw to ascertain their emergency prepared-Through integral System (OTIS)-was also used Data from ness pienning and capabilities for respnrxhng to transpo tabon

MIST and the other f acilities will be used to tonchmark the ade- incdonts invoMng ra$oactrve matenals. The survey was con-quacy of system codes, such as RELAPS snd TRAC, for pre- ducted to provde the Nuclear Regulatory Commiss60n anddicting abnormal plant transients The MIST program is reported other federal agencies with informaton concerning the currentin 11 volumes. The program is summanted in Volume 1; Vob level of emergency response preparedness of the states andumes 2 through 8 desenbe groups of teste by test type, Volume selected trites and an assessment of the changes that have9 presents inter-group compansons, Volume 10 provides com- occurred since 1980 (when a sinWar survey was performed

moons between the calculatons of RELAP5/ MOD 2 and MIST [NUREG/CR 1620]) There have been no maior changes in theweervatons, and Volume 11 presents the later Phase 4 tests. states' emergency response planning strategies and hold tac-Thrs Volume 11 addendum pertains to MIST natural circulation ties The changea noted included an increased evadatahty oftests- dEhcated emergency response vehicles, wider availatdty of

specialized ra$aton detect on instruments, and higher propor-NUREG/CR 6397;VALUE4MPACT ANALYSIS OF REGULATORY tions of pohce and fire personnel w4th training in the handling of

OPTIONS FOR RESOLUTION OF GENERIC (SSUE C 8 MSlV suspected rad ation threats Most indian tnbes have no capabil.LEAKAGE AND LCS FAILURE, JAMtSON.J Da VO.T.V,; Ity to evaluate Isuspected radation threats and have no fortnalTABAT ADAl.A S Battelle Memonal Institute, Dacife Northwest relations with emergency. response personnel in ediacent states.Laboratory. May 1990. 63pp. 9007120218. PNL-6931, For the naton as a whole. the incidence of suspected ra$ation54467.273 threats deckned substantially from 1980 to 1D68

This report oesenbes the analysis conducted to estabhah thebasis for answering two remaining regulatory Questons facing NUREG/CR 6404 V01: AUXILIARY FEEDWATEP SYSTEMthe NRC staff regarding the resoluton of Genonc tssue C-8, AGING STUDY. CASADA.D A Oak Ridge Natonal lateratory'specificalty- 1) What act60n shouid the NRC take concerning March 1990183Pp' 9004090260 ORNL 0M6 $3314 311'plants that currently have a leakage controf aiyStem (LCS)? 2; This report documents the resuits of a study of the AuxiliaryWhat acton should the NRC take concerning plants that do not Feed *ater (AFW) System that has been conducted for the U Shave an LCS7 Using tndtvidual MSIV teak test data, the pe,. Nuclear Regulatory Commission's Nuclear Plant Aging Re-formance of a systern of eight such valves in a standard DWR search Progam The study reviews histoncal f ailure data avail-configuraton was modeled. The pertoimance model was used able from the Nuclear Piant Reitabihty Data System. Licenseealong with estimates of core damage acGdent frequency and Event Report Sequence Coding and Search System, and Nucle-calcuisted dose consequences to determine the public nsk as- ar Power Exponence data bases The failure histones of AFWsociated with each of the attomatives The occupatonal expo, System compomnts are considemd from the perspecbves ofsure ernphcatons of each asternative were calculated using esti- how the failures were detected and the agnificance of the fail-mates of labor hours in radat on zones that would be 6ncurred ure. Results of a detailed review of operating and morutonngor avoided. The costs to industry of implementing each afterna- practces at a plant owned by a cooperating utlity are present-tsve were estimated using standard cost formulae and NRC staff ed %neral system conhguratons and pertinent data are pro.estimates The costs to the NRC were esbmated based on the vided for Weshnghouse and Babcock and Wilcox unitseffort incurred or avo6ded for reviews or other staff actons en-gendered by the selecton of a partcular afternat~ve. The costs NUREG/CR4405: ANALYSIS OF SHELL RUPTURE FAILUREr

and naks thus calculated suggest that no regulatory acton can DUE TO HYPOTHETICAL ELEVATED TEMPERATURE PRES.be justif ed on the basis of risk reducbon or cost savings' SUR12ATION OF THE SEQUOYAH UNIT 1 STEEL CONTAIN-

NUREG/CR4398: TECHNICAL BASIS FOR REVIEW OF HIGH- MENT BUILDING Mii.LER.J.D. Sandia Natonal LaboratonesLEVEL WASTE REPOSITORY MODELING. PRICE,LL; February 1990.100pp. 9003070222 SANDB9-1650 52B11:132WAHl,K.Ka GALLEGOS,0.Pa et at Sanaa National Laborato- San 6a National Laboratones, as part of the Containment in-nos. March 1990. 43pp. 9004100413 SAND 891557. tegnt) Programs under the sponsorship of the Nuclear Reguta-

S?344.042. tory Commission (NRC), has developed analytca! techniquesBoth tSe U.S. Environmental Protecton Agency (EPA) and for predicting the performance of light water reactor steel con-

the U.S Naclear Regulatory Commission (NRC) have promul- tainment build ngs subject to loads beyond the des gn basisgated regulatons regardng the performance of geologic reposs- The anatytcal techniques are based on exponence with large-tones for the disposal of high-level nuclear waste.'One of the scale steel containment model tests that provided important in-

responsjbitibes of the U.S. Department of Energy (DOE) is to sights and expenmental validation of the analytical mdhods Asdemonstrate comphance with the appropnate regulations. The a means of demonstrahng these analytcal techniques, the NRCDOE will most likely use extensive numencal modehng to show asked Sand a to conduct a structural evaluaton of an actualcomphance with the vanous Quanttative requirements Theses steel containment build ng The obloctive of the anatysis was to

(' analyses wdl then be evaluated by the NRC There are 6tterent deternune the actual pressure capacity and the modo, location,levels of evaluaton: peer review, Conservative estimates, use of and sl7e of failure, where a functional defenstion of failure ts

fexisting models/ Codes, and development of models/ Codes by rJSed The purpose of this report is to do :Urtient the Calculationstne NRC. The intensay of the review wdt vary from analysis to performed to determine the pressure hmits for the shelt. rupture

i

!

|.. . - - . -. - - -- --- ._--_ - . . _ . - . - . _.

__ ._ _ _ _ __ _ _ _ _ _ .. _ __ ___ _ _. __


mode of failure. General failure of the containment shell is pre- NUREG/CR44t9. AGING ASSISSMC NT OF WSTRUMt NT AIRd*cted by apphcaton of a fadure enteron to the remutts from SYSTEMS IN NUCLEAR POMR PLANTS VIL L AR AN M ;firute element structural analyses. The failure entenon relates FULLWOOD.R.; SubuDHI,M Drookhaven Naimal Lahnratorythe calcuisted values of strain in the containment plates, due to January 1990 139pp po0J070250 DNL NURE.G 522126ntomal-pressun2ation load:ng, to the 6,ttimate strain limit et tre 52503 129steel. Included in the failure entwon are adustments for factors NRC Genene issua 43, " Contamination of instrument Anenherent en finite eiement analysis, such as level of detail and Lines", has been unresolved since 1980. The potenbal sonous-element age of finite element model and vanatons in matenal ress of trus 6ssue was reinforced in a 1987 study by the Omceproperty data Separate finite element models were used to for Anatysis and Evaluation of Operatonal Data Aging of com.evaluate the overall free-field behaver of the structure and the ponents wittwo compressed air srstems, karhng to do<ya&dlocalized behavior at a stecific penetraton locaton, Three see. functon of the system, is the sutyoct of ttus stucty Ttus worknaros of state internal pressurttaton, based on gases tvilding was performed under the ausruces of the NRC's Offece of Nu.up slowiy within the containment shell dunng a severe accident, clear Regulatory Research as part of the Nuc6 car Plant Agingwere evaluated, The scenanos included pressure loading with Research (NPAR) Program The obm/tive of this stmfy was totemperatures uniformly increasing 6n the finite element model in idenhty all the aging frodes and ther caut.es, which stov6d becorrespondence to the proportes of pressurtred saturated rivtegated to achieve a rehatdo 00 oration of all safete elated 66.r

steam, pressure loading with non-uniformly increasing tempera- equipment Also encluded ts an intenm review of typecal mainto

tures, and pressure loa $ng without a co* responding tempera, nance act#vities for air systems in the nuclear power irdustryture increase, which was done for compahton wtth earlier pub- The Phase 2 effort of trus study wil! make recommendate,is for

lashed analysea it is concluded that thermal effecta do not dMiotung an cHectw mantenance program industry wde tochange the overall response of the structure or the general couNw tre eHects of agng The anatysis of operating erpmsshell f ailure trode, compared to the response due to pressun28 ence data revealed that aging degradation occurs en the Com.

ton at amtxont temperature. The reducton 6n the predicted in- pmssed air s$em and tecones a todor as Um systen apsmal Mar of syWn and contaminaton M Pe er domsternal pressure capacsty of the containment building at tempera-

ture corresponds to the reducton in the ultimate strength of the hate We @ms of syWn fem bsbng main %ance proA516 Grade 60 steel due to the temperature increase grams wm Pe inksW lad undamay, and quaMy assurance

is not ngorous tecause the system es classified as non salety

NURE0/CR 5409: NEUTRON EXPOSURE PARAMFTERS FOR NUREG/CR 5421: LAPUR USER'S OUIDE- OT ADUY.P.J ;THE METALLURGICAL TEST SPECIMENS IN THE SIKTH MARCH LEUBA.J Oak Rdge Natonal Latoratory JanuaryHEAVY SECTION STEEL IRRADlATION SERIES. M!LLER,L F4 1990 77pp 900307023t ORNL TM/11285 52001;001.BALDWIN.CA; STALLMANN,F.WJ et at Oak Rdge National LAPUR, a computer program in FORTRAN.IV, is a mathemat-Laboratory. May 1990. 49pp. 9005210206. ORNL/TM 1126L scal desenpfen of the core ci 3 boeling water reactor Its two53991:314 hnked modules, LAPURX Md .pfVRW, respectrvely solve tre

The goal of the Heavy-Sechon Steel tria$aton (HSSI) Pro- steady state governini Muah mr the coolant aqd fuel andgram Stxin irradiation Sones is to determire the effect of irradia- the dynamsc equatons fur Wotant, fuel, and neutron feld intion on the shape and shift of the crack.anest toughness versus the frequency domain. GenM31 !@smentation desenptions aretemperature curve Two capsules which contained crack arrest fonowed by a detadod escripacn of input and output param-and Charpy V. notch test specimens have been irradiated at the eters of LAPURy and i OURW. Sample laputs are includedOak Rdge Research Reector located at the Oak Ridge National and statulity bemhmarkn are rotedLaboratory. These capsules have been disassembled, internalcostmeters have been anayred, and esposure parameters aro NUREG/CR 5424: ELIC111NG AND ANALYllNG EXPERTpresented for each irra$ation test specimen This report de. JUDGEMENT.A Practical Gude. MEYER.M A.; DOOKER.J Macnbes the Computational methodology for the least-squa'es los Alamos Natonal Lacoratory January 1990 424pp.adjustment of the donimetry data with neutronees calculations, 9002120292. LA 11667 MS 52574 303and presents exposure parameters at each test specimen loca. In this book we descobe how to chcit and ana9e experttion for the fluence rate greater than 10 MeV, fluence rate judgment. Expert judgment is defined here to include both thegreater than 0.1 MeV, and displacements per atom. The specahe experts' answers to technical Questions and their mental proc-actrvity of each dosameter at the end of irra$ation is hated in the esses m rea% an answn H rders specthcally to data thatAppendix, am OMained in a debberate, structured manner that makes use

of the tody of research on human cognition and communKa.NUREQ/CR-5411: ELICITATION & USE OF EXPERT JUDGMENT tse Our aim is to provde a guide for lay persons in eiport

IN PERFORMANCE ASSESSMENT FOR HIGH LEVEL RADIO. Judgnw These persons may be from phytocal and engineenngACTIVE WASTE REPOSITORIES BONANO,EJ Sandia Naton- sciences, mathematics and statistics. business, or the mihtary.at Laboratories. HORA,S C. Hawaii, Univ. of, Hilo, HL We provde background on the uses of expert Judgment and onKEENEY,R L: et al. Southern Californiac Unrv of Los Angeles, the processes by which humans solve problems, including thoseCA May 1990 94pp. 9006080176 SAND 891821. 54075122 that lead to bias Dotaded Dustance is oierod on how to ehcitr

' #"This report presents the concept of formahting the clicitaten s W tg a M m"9aW N Wa bpos e 6tand use of expert judgment in the performance assessment ofa up b eM chm N Maton Anaham mhigh-level raioactive waste (HLW) repositones in deep geol >gic ** # * #"**'"9"" " * "formations. The repod begins with a discusson of (1) chara;ter-

# '* ""latics (advantages or disa tvantages) of formah2 ng expert judg. ," "f, , g,g g entsment, (2) examp'es of previous uses of export judgment in re-dioactive waste programs (3) cntena that can assist in dociding NUREQ/CR 5435: ENVIRONMENTAL EFFECTS ON CORRO-when to formaltze expert judgment. and (4) the relationship of SiON IN THE TUFF REPOSITORY. BE AVER S.J. A.;formal une of expert judgment to data collection and modekng THOMPSON,N O Cortest Columbus. Inc. February 1990.52ppThe current state of the art with respect to the chcitaton, use, 9003100208 53012133=and communiceton of formal erpa rt judgment is presented The Cortest Columbus is investigating the long term perfoemancereport concludes with a discusson on potential apphcations of of container matenals used for htgh level waste packages asformal expert Judgment in performance assessment of HLW repart of the informaton needed by the Nuclear Regulatory Com-positones. misson to assess the Department of Energy's appbeation to

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construct a pe060u6c repos! tory for hegtvlevel radeoactrve waste defning and descritwng errors in comples systems in addition, aThe scope of work cor$ists of employing short term techreques, review of ensbng hources of human telability data and ap-auch as electrocherrucal and slow strain rate mecharucal test proaches to human performance data base develcpment is pre-technaques, to saamine a wde range of possible fadure mps. sented Attwnabve task taxonomen, wtuch are protrusing for es-Long term tests are ber , 'd to vertry and further esamine tabhshmg the comparatukty on nuclear and nordnuclear tasks.apectfc failure modes Lenbf' d as importali by the short terrn are also denbfed Desed on such taxonomic achemes, variousstudies. This report summarties the results of a lderature survey data base prototypes for generahzing human error rates acrobsperformed under Task 1 of the proyam The survey focuses on settings are proposed.

; the ofluence of environmental vanables on the corroton te-havior of can&dato container inatorals for the Tufi repositoT NUREGICR4439: HUMAN FACTORS ISSUES ASSOCIATEDEnvvonmentat vanatnes consdered incided radabort thermal WITH ADVANCED INSTRUMENTATION AND CONTROLSOnd nuerobial eNects TECHNOLOGIES IN NUCLEAR PLANTS CARTE R.RJ :

NUREQ/CR 6436 V01: THE DEVELOPMENT AND EVALUATION UHRIG R E. Oak Rdge Natonal Laboratory. June 1990,202ppOF PROGRAMMATIC PERrORMANCE INDICATORS ASSOCl- 9007120224 ORNL/TM 11319. 64467.071.ATED WITH MAINTENANCE AT NOCLEAR POWER A aurvey of advanced instrumentaton and controis (l&C)PLANTS Main Report WREATHALLJ.; FRAGOLA.J4 technologes and associated humart factors tatues in the U S.APPIGNANIf,; et al Science Apphcatons internabonal Corp and Canadian nuclear industnes was comed out The purpue(formerty Science Apphcatons, Inc ). May 1990. 133pp- of the survey was to provde teckground for the development of

'st ment and evaluabon of I&C systems as well as human engineenng gudelines for avale

programmabc performance irdcators of maintenance These in-dcators were selected ty (1) creating a formal framework of shng Fwse typnis W amy W 9c5g congoronts v

the U.S nuclear industry surveyed to be qu te nterested in ad.plant processes; (2) 6dentifying features of plant behavior cordcedered important to safety (3) evaluating eusting indcators vanced l&G but m cautous n inWnenung such systems dCgamet these features, and f4) perfornwng statistical analyses nuclear facilmes and power plants The trend in the factl*esfor the selected indicators. The repoi1 recornmends a% tonal surveyed se to apenment cautiously when there to an intuittve

teshng advantage or short-term payoff. The rnost advanced l&C sys-*"" " '" " " " " ' ^ "" * * " *

NUREQ/CR 6436 V02: THE DEVELOPMENT AND EVALUATION newest plant has dgetal systems in aimost 100% o'f its controlOF PROGRAMMATIC PERFORMANCE INDICATORS ASSOCl- 'Y N ** ""d # # O' "' E'" E0##" 8f8I"* PATED WITH MAINTENANCE AT NUCLEAR POWERPLANTS.Appendcos. WREATHALL 1; FRAGOLA,J.; Wesa vist NWy 90troducir>g d9tal systems increasesAPPIGNANI.Pa et at Science Appications intomatonal Corp, safeV is supported by the Canaden expe'isno4 A numtw of

(formerty Science Apphcotons, Inc.) May 1990. 2250p. Safete related human fecWe mses *m dor vert from the re-9006080152. SAIC-90/1130 54076 014. suits of this survey They lnclude is an advanced 14C guidehne

See NUREG/CR 5436,V01 abstract eqwalent to NUREG 07oo needed? What chan0es wf ttore'" " # "" "

NUREQ/CR 6437: ORGANIZATION AND SAFETY IN NUCLEAR '" " " "*POWER PLANTS, MARCUSA; NICHOLS,Ma BROMILEY,P.; et

ing anng ogy ma a aW e anced01 Minnesota, Univ. of, Minneapolis, MN May 1990. 214pp,* *# ""# "CC*b"* * "CC *

9006080166. 64077:098Perspectives from 6rdustry, academe, and the NRC are NUREQ/CR 5447: DEPRESSURIZATION AS AN ACCIDENT

brought together to develop a logical framework that knks orga. MANAGEMENT STRATEGY TO MtNiMt2E THE CONSE.rwraton factors and safety in nuclear power plant performance' OVENCES OF DIRECT CONTAINMENT HEATINGThe framework focuses on Intermediate outcomes whch can be HANSON,0 Ja GOLDEN.D W.; CHAMSERS.R; et al EG&Gprodcted by organtratonal factors, and whch are subsequentty g gg gknked to safety. The mtermediate outcomes are effcioney, conu

9011000143. EGG 2574. $5b60.252'phance, Quahty, and innovation. The organizabon factors can beclass. fed in terms of environment, context, organtrational gov, Probabelste Risk Assessments tPRA4) have identified severeemance, organizatonal design, and emergent process. In*al accdonts for nuclear power plants that have tte potential toempincal ana yses were conducted on a hmated set of hypoth. cause fadure of the containment through duect Containmentv

eses dortved from the framework. One set of hypotheses corp heating (DCH). Prevention of DCH or rnitigaton of its effectscorned the relatonships between effcency, measured by crtt,. may be possible uWng accident management strateges that in-cal hours and outage rate, and safety, measured by 5 NRC 6nde. tentonally depossunto the reaftor coolant system (RCS). Theca'. ors Resutta of the analysis suggest that crttcal hours and effectiveness of intentonal depressurtraton dunty a stationoutage rates and safety, as measured in this study, are not re- blackout TMLD' sequence was evaluatod consJdenng the phe-lated to each other, Hypotheses were tested conceming the of- nomenological behavior, hardware periormance. and operation-facts on safety and eficency of utility financial resources and al performance Pheromenological behavior ens calculatedthe tagged racogniton and correchon of problems that a:com- using the SCDAP/RELAPS severe accident anarysis code Twoparues the reporting of fr'ssor volahons and hconsee event re- strategies to mitgate DCH by depressurizabon of the RCS wereports Resuits auggest that te financial resources and orgarv- considered. One strategy, cahed early depressunration, as-rational problem soNing/6earnitg have agnificant effects on the sumed that the reactor head vent and pretisunior power operat-outcome vanables when time is property taken into account ed rehef vanes (PORVs) were latched open at steam generator

NUREQ/CR 6436: BASIC OONSIDERATIONS IN PREDICTING dryout The second strategy, called lato depressurizaton, as-ERROR PROBADILITIES IN HUMAN TASK PERFORMANCE. sumed that the head vent and PORVs were latched open at aFLEISHMAN,E,Aa DUFFARDILCa ALLEN J Aa et at George core enn temperature of atout 922 K (12005F) Depressunta.f.tason Univ., Fairtat VA. Apnl 1990. 49pp. 9005040081. CBCS tion of the RCS to a low value that may rmtegate DCH was pro-

dicted poor to reactor pressure vessel breach for both earty andRPP #901. 53622'022 .

late depressurization. The strategy of lato depressuntaton isit ts weH estabhsted that human error plays a major role inthe rnattunctoning of complex systems. This report takes a pretened over earty depressurizaton because there are greaterbroad look at the study of human error and addresses the con- opportun$es to recover plant functions prior to core damageceptual, methodo40gcal, and measurement lasues involved in and becausa failure uncertainties are lessened

I-_ _ _ . _ _ _ _ . _ _ _, , . _ _ _ _ __ . . . . _ . _ _ _. .,

Maln Citations and Abskncts 37

NUREG/CR toes: AQWG i.VALUAflON OF CLMS It BATTI R. of the Charpy uppor.sheit regime in a rising toughra+n regonIES SEISMIC TESTING EDSON.J L LG&O 41ano, Inc (subs and with an 6ncreasing driving force Results obtained froms,EG&G, ) Auga WA 233pp 90063iO22t EGG 296 these tests have pr'duced crack arrest tougtviess values well55042iM ateve tre lenit recognized by the current ASML gudelines (??O

This report presents Os resetin of a seismic testing prtvam we e /Wa with arrests occomog at 44 to 102 degrees C atoveon natureihr aged c4ss 1E battenus ot.tained from a nuclear the matenal DW(NOT) (60 degrees C) The teneture data suppiant The tephng progam ss a Phase il artety resulting from a port (t) the une of fracture rnochanics concepts to analyreW te i ayng evaluahon of clahs 1E bettenes in safety systems cleavage fun arrest events. (2) the treatment of c6eavage run-of nuc6 ear power pwnis, performed previously as a part of the anest and ductde tracture modes as separate events, and (3)U S Nuclear F egietory Commn,ssun's Nuclear Plant Aging Re- the fact that cleavage arrest occurs atove the ASME linvt-sess ch Program wM 'opcried in NUREG/CR 4457. The pomaryr

purpose of the 737mm was to $* valuate the se$rnic ruggedness NUREQ/CR4461: CRACK-ARREST DEHAVIOR IN SEN WIDEof naturally aged txtenes to octermine if apod battenes could PLATES OF LOW UPPER-SHEtr DASE MEiAL T ESTEDhave adeauste ensevicai cepacity, as determinod by teste rec- UNDER NONISOTHERMAL CONDITIONS WP.2 SERIESommended by #EEF StaMarJs. and yet have inadoQuate seis- NAUS,0 Ja AEENE%WAL AER; BAS $ 0 Ra et al Oak Ad;)emic ruggedness to prpyde needed eketncal power dwing and Natona! Latostory August 1990 P99pp 9009170076 ORNL-after a safe shutt.wn earthquake (SSE) event A seconda'y 6564 55201 163-purpose of the pog'am was to evaluate telected advanced s#- Siu wide plate crack-arrest tests (WP 2 Senes) s's discumdveillance met % to determine if ttey were hket/ to be more in tNs report Each test utiirted either a 1 s i n 01.m or a 1 m 1sensitive to tie agog dog'adation that reduces seismc rugged- a 015 m thick singleMge notch spec 6 men (alw - 0 2), fatri-nets The program used twelve batteres naturally aged to cated from a lorupper shelf base metonal, that was sut9ectedatout 14 years of age in a nuclear facility a d tested them at to a linear thermal gra$ent along the plane of crack propage-four %9 tent seismic 6evels representavve of the leves of pos- ton The tests were conducted at the National institute ofsitde earthquakes specified for nuc6 ear plants in the United Standards and Technology and were dersgned to provide frac-Stat a Seismic testing of the battenes dd not cause any loss two toughness measwoments at tornperatures approaching orof eisctncal capacfty atove the onset of the ChaTy upper sheit reyme, in a nong

NUMarCR4449; DETERMINATION OF THE NEUTRON AND twghness mgon, and with an inacasing d tving force. ResultsGAWA FLUX DISTRIBUTION IN THE PRESSURE VESSEL obtained from these tests have prcduced crack arrest tough-AND CAVITY OF A BOILILNG WATER REACTOR ASGARI M ; ness values well atove the limit recognaed by the currentWittlAMS.M L.; KAM.F B K Oak Ridge Natonal Latorstyy AbW gudeir+s v220 MPa Vm) with a"ws o<ccumno at up toJune 1990 115pp. 9006290142. ORNL/TM 11350 S4325 030 102 degrees C above the matenal DW|NDT)(60 degrees C)

The Grand Gutt Bouing Water Reactor (BWR/6). Owned and De fracture data support (1) use of fracture mechanics con-operated by Mississippi Power & L6ght Company has been ana. tepts to analy7e cleavage run-arrest events, (2) treatment ofty7ed to deterrreo the neutron and gamma energy spectrum cleavsgo and dxtile fracture modes as separate evuots, andand flus lovels in regions from the reactor vessel throughout the (?) fact that cleavage arrest occurs above the ASME hmitconcreta shCo es|1 Several two dimensional and one dimen.

NUREG/CR 54b3 V05: BACKGROUND INFORMATION FOR THEsional transport ca;culations were performed for the Grand GulfDEVELOPMENT OF A LOW LEVEL WASTE PERFORMANCEreactor configuenton The results from these calculations were

synthestad to obtatn the three dimens6onal neutron flun spectra ASS SSMENT METHODOLOGY Computer Code impiomenta,and dosimeto actmtics The resuits trum the transport salcula.tions indicate the flux above 1 MeV peaks near the anal md. M ATliNGLY,P. A : et al Sandia National Laboratones Augus"t

- -

10m 105pp 90083101B4 SAND 89 250W 55044 055plane and anmuthal ang6e between 40 degrees and 48 de.grees, Orpending on the radial locatons. The peak flus above i This mpod documNs Uw Implomotaton ar d assessment of

MeV incdont on the vessel and at mdcavity is about 182 x comMer codes tw a bwevel waste podsmance assessmN10(9) and 1.07 x 10(8) n a cm02) a ab1), respectrvely. The methodology. Computer codes and analytical solutions are Im-vessel fluence accumulated dJong Cycle 2 and shof 32 ettec- P'' " M*d 'O' 9'wnd water flow and transport analyses,tive full power para is about 4 41 a 10(16) and 1.84 x 10(1B) n tource term anaiyses, surf ace water transport analyses, air-a cm( 2) a s( 1), respectively. The peak flux atove 1 MeV at the transpod analyses Whain analyses, and dosistry ana%front of the concrete shtold wall,15 24 cm (6 en ) into the con, ses The capatulity has been retained to perform teither simplecrete wall, and 30 48 cm (1 ft) into the concrete wall is atout or rnore complicated analyses of the nource term and grourd-7 91 m 10(7), 7.24 x 10|6), and 6 44 x 10t5) n : cm( 2) a $( il, water transport aspects of the performance assessment. Therespectrvely. The results obtained from the gamma calculatons simple approaches consist of analytical and simple numencalanow that the peak gamma heating at the 0,T tocaton of the analyses that are appropnote for relatively simple conceptua,reactor pressure vessel has a value of 2 54 x 10(-3) W/g of models. For fully moltedimens6onal or transient problems. more

stainiesa stee; (SS 304) The peak gamma absorbed dose rate complicated numencal solutons are recommended Dt tads are

at the mdcavity is about 7.31 x 10(3) rad /h at full power ope,. given of the recommended anatytecal methods, together withat m sensityty analyses that demonstrate important aspects of the

solutons The implementaton processos for the more comph.NUREG/CR 5450: HiGH TEMPERATURE CRACK ARREST cated computer codes and those problems that arose donng

TESTS U$ LNG 152 MM THICK SEN WIDE PLATES OF LOW- implementaten are discussed Finally, a companson is givenUPPER-SHELF BASE MATEntALTESTS WP 2.2 AND WP 2.6- betwoon the simple and complicated ground water transportNAUS.DJ: KEENEY WALKER, BASS,8 R.; et al Oak Rdge anaiyses for a simple conceptual model.Natioral Laboratory. February 1990 143pp 0003070238.ORNL/TM 11352. 52802 055 NUREG/CR 5450; A CAUSE DEFENSE APPROACH TO THE UN-

Two 152 mm th ck wde plate crack ar'est tests (WP-2 senes) DERSTANDING AND ANALYSTS OF COMMON CAUSE FAIL-are discussed in this report. Each test used a 1 x 1 x 015 m URES PAULA,Ha CAMPBELL Da et at JDF Associates, Inc.tNck sangle-edge-notch specimen (a/w = 0 <), f abocated from PARRY,G NUS Coro March 1990 137pp, 9005020340a low upper shelf base matena;, that was sutaected to a linear SAND 89 2368 muo vae.thermat gradient along the piane of crack propagc . ion The This report prese% the results of research to aevelop a newtests were conducted at the Natonat institute of Standards and methodology for common cause fadure analysis and preventionTechnology and were designed to povce fracture-toughness Common cause failures are dehned as thow caused by singlemeasurements at temperatures approacNng or above the or set events that can make redundant components unavailabte, thus

_


compromising the relebihty of redundant trains of equipment mu ous tips on successf4fy applythg the theory to vanous typesr

Probatulistic nsA assessments (PRAs) and nuclear power plant of shielding problems The ternainder of the document to devot.(NPP) operatons have demonstrated that CCF events are ohen bd to input ard output desenptons of the OADS code with sev-masor contributors to the potential nsk posed at such plants. eral tilustrative sample problemsOver the years. Qualitstrve and ovantitative analysis methodshave t+en deve6oped to improve CCF anatysis However, these NUREQ/CR 6472: A Rt$kbASED REVIEW OF INSTRUMENImetnodNog*s have not espleitty accounted for the impact of AIR SYSTEMS A' NUCLE AR POWLrt etANts DEMOEE,0 ;plant specahe defenses, such as den gn features and operstonal LOFGREN,Ea ROTHLEDE R.D ; et al. Scaence Apphcatonsand maintenance pohcies, in reducing tne kkehhood of failures intomatonal Cet (formerty Science Applications. Inc ) Januaryat NPPs The research docutnented in this report desentes a 19901Mpp 900307T61 DNL-NUREG42220 52602 324cauto defense methodology for CCF anasys:s and prevention to The tiroad otvective of this anatysis was to provde nsk basedhelp correct this debciency The report discusses the develop- infortnaton to help locus regulatory actons related to tr'strv-ment of (1) procedures for 60entifying the potential for CCF ment Att (IA) systems at operating nucinar powre plants Weevents at 6ndivdual NPPs and (2) cause defense matoces for first created an ertensNe data base of summanrod and charac-analyvng CCF events New concepts and more precise defirw tented lA related events that gave a aunhtatrve todicaton of thetons are tr%roduced to enhance CCF termirology and enterpre. natura and seventy of tr+se events Adibonalty, this data basetaton of histoncal event data was t k d to calculate the frequencies of certain events, which

""""**"*""""*'#"*"*"" """ * **""'" # # *NUREQ/CR 5461: AGING OF CABLES. CONNECTIONS, AND mweg s As a NR Accent Sewnee WswELECTRICAL PENETRATION ASSEMBLIES USED IN NUCLE. '" # ' ^ ^ " "C " " ' " "'*L '^ #'" " " *"" * "AR POWER PLANTS JACODUSAt J Sand 4a National Latera- n e Wm and NNaN nnk sgn4am wents Senth

July 199J B t pp- 9006080195 SAND 89 2369tones, g sty calculatons were periormed when powbic Genoncalty, tAg7

' ' " '' '" "" ""I "% " 'This report esamines effects of aging on cables, connectchs' " 9" *" " " ' " " " " "'and containment electncal penetration assamthis (EPAs) # "" "Agog as dehned as the cumulative eMeets that occur to a com- n ,

ponent with the passage of time. ff unchecked, these eNectscan lead to a loss of function and a potential impairment of NUREQ/CR 6473: INCLUSION OF UNST ABLE DUCTILE TEAR-plant safety. This study includes a review of component usage IN3 AND EXTRAPOLATED CRACK AtWEST TOUGHNESSin nuclear power plants; a revsew of some commonly used com- DATA IN PWR VESSEL INTEGRITY ASSESSMt:NT.ponents and their matenals v construction, a review of the DICKSON,T La CHEVER TON R D.; SHUM.D K Oak Rege Nastressors that the components might t* esposed to in both tona! Latoratory May 1990 35pp 9007120177. ORNL/TM.normal and accident environments, a compdaton and evalue. 11450 54a70iMtion of industry failure data; e decusson of component f ailure Over the past several years, the Heavy Section Steel Tech-modes and causes, and a tnet desenption of current ndustry nology Program &t Oak Rdge National latoratory has per-testing and maintenance practices ty,,=d a tenes of largriva* fracture mecMnics expenments

NUREQ/CR-6463: EFFECTS OF MINERALOGY ON SDRPTION These uponments have demonstrated that prototypical nucicar

OF STRONTIUM AND CESIUM ONTO CALICO HILLS TURF. reactor vessel steels can cahitat crack anest toughnns valuesMEYER,R E.; ARNOLD,W Da CASE.F t ; et al. Oak Ridge Na- Consde'at9y ebove 220 Mpa * Vm arthough enest can be followedtona! Laboratory, Apnl 1990. 42pp 9005040072. ORNL 6589 imn*Mately by ur stable ducide teanng This report evaluates$3622 071. the 6nfluence of the Crack aneU toughness above 220 mpg * /m

Sorption and desorption measurements were maos of stronti- on the intepnty assesaments of nsiclear reactor pressure ven-um and cesium onto chnoptdolite and Cahco Hdia Tuff The seis for p'essunrod thermal shock (PTS) loading conditions,object was to see whether there was a correlaton between taking into account the potential for unntab6e ductise teanng fol-sorpton of strontium and cesium onto Ca!,co Hdis Tuft and the lowmg arrest The 6nhuonce of the high c-tack-arrest toughnesssorption of st ontium and centum onto chnoptiiohte based on the cata and unsta51e ductdt, teanng on pressunted mator reactorcontent of clnoptdohte in the Cahco Hdis Tatt if sorption onto v1ssel integoty assessrmnt is PTS transient dependent 11 ap-Cakco Hdis Tutt is solety due to the presence of chnoptdohte, pears that the potentae' beneht from cracbanest events cone,then the ratios of the sorpton ration on tuff to those on chnopte spornhng to toughnms vaW utove 710 MPa * Vm for ow uppv-lohte at simnar conditons should be the weight traction of the shelf ekt RUSWI matsnal ami atuve 370 MPa e Vm for %suchnoptdokte on the tuff. Since the tuff contained atout 50% vessels not contening LUSW matenal wdl usualty be negatedchnoptdohte, the ratios would t+ espected to be atout 0.5 if by unstable ductile teanngSorption was due so6ety to chnoptdokte The cuponmental evk

NUREQ/CR 5474: /,SSESSMENT OF CANDIDATE ACCIDENTdonce showed that the ratos were generally near 0 5 for tothMANAGEMENT STRATEGIES LUCKAS,W ; V ANDE NKIE-costum and strontium Sorption and that son +venange processen

were operatrve for both the chnoptdohte and the tuff. However, DOOM, LEHNER,J.R B ookhaven Neronal Laboratory Marchthe ratos difiered to a small extent for the different conditons, 15 C 46pp 9004100337. DNL-NUREG $2221,53343 029

%- and there were indications that other sorption processes were A sut of selected (anddate accdont management strategios.

involved. whose purpose is to prevent or rmtigaie in vessel core darr, age,were developed from vanous NRC and inoustry reports These

NUREQ/CR 5468: OADS. A MULTIDIMENSIONAL POINT strateges have been groupod in this repnrt by the chatiengesKERNEL ANALYSIS MODULE, BROADHEAD,B L Oak Rdge they are intended to m9et. and assessed to provde informatonNatonal Laboratory. May 1990. 66pp 900(>080320 OHNL/ which may be useful to individual bcensees for considerationCSD/TM 270. 54075 054 m % g m m m g pu % %% % g

CADS ts a mutt > dimensional point komei computer code that sessment fxused ori desentung and explaining the strategy,utihres the simplihed free form input of the SCALE system as consdoring its relatonship to esisting requirements and prac-weH as compatibdity with ORIGEN S produced sources. SCALE tices as wen as dente ing possible associated adverse eHectsrcross secton htvanes, and standard composition da'.a settOADS consists of a preprocessor that takes the free-twn inpat NUREQ/CR 5475: MODEL Ff AS@uTY STUDY OF RADIOAC-and prepares input for the widely ava. table OAD-CGGP code, TIVE FATHWAYS FROM ATMOSPHERE TO SURFACEwhich is then automaticalty executed by a dnver module This WATER SM|TH.R E, SUMMER,R M : FERREIRA,V.A Agncul-report descr bet the point kernel theory briefiy, followed by nu- tuie. Dept of. Marc.h 1990 43pp D005020324 'A*.80 328.

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A teasitulity 6t4y of the ein % i to buttace mator ra&o- critK al flew properties accurately and relintify m the [weste<* ofrixlde patheers mas (Wtormt small Catchments uorQ a Dagnals (autml by thebe other pro (etty vanations, we rnutt havephyucally tened byto tgosyster . sAdel, Oput Detalt + crwgh informaton to distingut$h the fle* E gnals from the en -s

6ntenwty (fresyont) prectfWtebon rounds from Arts d trane os oriet Therefore. we devebped at strumentation toe

Georg a were veed as in(41 to d'tve the rNdel Tetts of h ael mea 6ure toth the emplito:le and the phane of the eddy-current6ensit'vity to @s'ruuton coefhcients, Ad, for C6137, Co 134, 6 9nal at Several diftenent frequences, as wolt as c.omputerard Sr 90 6llustrated d efment vegetation too eroacrwunoff cupment to process t e data quickly and rehatity TNs heeft topathways an res;ons.c to apeuttatat rnanagement pract<es R"' octoct 6 mall ftset in Pie pesence porturt4ng property vanation6nJts rehected the tact innt 60* Ad values alo* a re:tionucide g g ,g,ed the deselopment of more 6cnartive ard moreto Mtrate nto the toil profile and isolate et from autinequent comphcattd probet, awh as pancaba a<d rehectsun probenturch ard eco$on Of the ra$onsides and phyncat settings

Thou amaher Ms can octtNt much smaller fians avi are lessstuS40 only the Sr 90 with lon Ad values ts suffoently motWeten 6fte e to Wtdacts outsde the tutie, such as tut.e supforts.vand 60'O lived to tw rernoved from the system via percolation

tselow the root tone Conve'te% bg4y adsortitd ra$onuchdes rnagnetrie, or ccpper Oy being pressed against the tube wall,MWf M To up N v@Wn Wwe's lubtect to removal try ad6;rptor. to bediment particles and

6VtH Quent runo f Companton of dttforent effective half-ltvel of Yr

l 131 :lemonstrated the importance of the timing of an proson- 4%, new and rnore compkattd Late stardards wtve con-runch 6torm event dJrinQ or immD18tery s'ter a f allout event strWied to inck de the range of property vanationtE. eat onal ts"ung of a faliout event ard crop management attoaNo, t the fate of th's shortwed ra$onocide Removal tiy sol # NUREO/CR4479. CURRENT APPLICATIONS OF VIBRATIONton to 6ada:e was * runott w_s negt9|tWe for all nuclic'en stud MONf10 RING AND NEUIRON NOISE ANAL YSl$ Detectionted Model timtat*on results for up to 10 hattIrves are corroto. And Ann'ysis Of Structural Depadation Of Reactor vesselinter-rated tty resafts t'om long-term fiold stu&es These re4utts 6how nals From Operational Aging On Ai ANO.D , ARrit R R C Debthe feasitety cre nodekog pathways in small catchments using FMac National Laboratory F etwuary 1940 43pp 9004090i90.Opus ORNL/TM.113p 53314 270

This report. wh4ch was prepared urdor the Nuclear Pla dNURLO/CR4476: POSTTEST AN/ LYSIS OF A i 6 SCALE RE.

INFORCED CONCRETE REACTOR CONTAINMENT DUILD- Aging Research program sp nmored tiy the United States h u-

IN3 WEATHERBY,J R Sanaa National lateratones Fetruary cmar Regulatory Commissen, d+cuswa the appbcation of vF

199199001004030052 SANDB9 NO3 63226 001. I' ration monnonng and neutron nome analysis for monitor.ngin an expe'iment condated at San $a National Laboratories, bgM *ater reactor (LWR) vessel intemats The report tiegins tiy

a i 6-scale roodel of a reinforced concrete tght water reacto, desentung the eficcts of loss of structural Intt9' tty on internalscontainment busiding mt.s pressurized with nitrogen gas to more vibration and how nonstdo parameters can te und to detectthan three times its design pressure The pressurtraton pro. and t'ack the progrest of degradation TNs is followed try a oe-duced one large tear and neveral smalier tears in the steet liner acnoton and compensen of nbreton rnonitornD and reutronplate that functoned as the pomay pneumatic 6ent for the no*e anatymis, two methods for rnontionng the mechantcal re-structure T5+s report deser.bes posttest finite element analyses tegory of reactor vstsolinternal components The mapr rio: tonof the 16 acale model test and compares pretest predictions of of the rogort describes the statut of reactor vessel internalsthe structura| response to the expenmentat results. Strains and cordtion morutoring program 6 6n the United States. Federal Re-d4 placements calculated in aosymmetoc finite element anal - putoc of Germany, ard F rance, three countnes hanng tubstan-ySes of the 16 bcale enodel are compared 10 6 trains and dis- taal commitments to nuclear power, The last section prebentsplacements measured in the expenment Detailed analyses of guidehnes for V S ut.ht ca wisNng to estabbah rea: tor intwnalsthe inner plate are also descnbed in the report The results from cordton monitonng programsthese analytes ind4cate that the pomary mechanisms that trutial-ed the tear can be captured m a two dimensional finite element NUREQ/CR4460 DAT A SUMMARY Rf PORT FOR FIS$10N

Furthermore, the anat wes show that studs which were PRODUCT RELEASE TEST VI 3 OSBORNE.M Famodel t

used to anchor the liner to the concrete wall, played an impor. LORENZ,R A.; COLLINS J L; et at Oak Rdge National Latora4

tant role an ervteating the hrwir tear tory June 1993 70pp 9006290135 ORNL /T M-11399

NUREQ/CR4477: AN EVALUATION OF THE RELIABILITY AND 54325 4 1.USEFULNESS OF EXTERNAL INITIATOR PRA METHODOLO- Test VI 3, the tNid in a senes of high temperature fissonGlES DVDNfT7,R J ; LAMBERT,H E future Resources Assoce product release tests in the vertical test apparatus, was con-ates. Inc January ID90111pp. 9002120340 52577.129 ducted in fewing steam The test specimen was a 15 2.cm long

TNs report, prepared to assist policy 4evel docitron-makers, secton of a fuel rod from the BR3 reactor an Belgiurs wNchevaluates the extent to wNch each category of externaMrutie. had ticen irradiated to a burnup of 42 Nd/kg Using an toduc-tors PRA mettodolcv.y produces reliable and useful results and ton furnace. It was heated order simulated L WR accdont con-insights at its current state of the-art level TNs report andress- ditons to two test temperatures. 20 min at 2000 K and then 20es this need in the fol6owing five categones of enternal trutiators min ht 2700 K The cladding was comp 4ctoly ondaed dunng the(t) ea'thquakes. (2) .nternal fires. (3) ertomal floods. (4) 00 test, and very little mettmg or fuel-(tadSng interaction had oc-treme winds; and 15) tramportation accdonts Each rnitiator is curred Dawd on fission product tnventones measured in theesamined separately. The thrust is to dentify and debenbe the fuel or calculated tri ORIGEN2, analyses of test componentspnetapal aspects of the cunent state of-tt+ art PRA methodolo- EWod total re' eases from the fuel of 100% for Kr 05, L% forgy, wMt aspects are less robust and therefore provide less inh'

RM 99% for Sb 125. and 99% for toth Ca 134 and Cs 137atWe insights, and whySmall release fractons for many other fiswon products were de-

NUREG/CR4478; IMPROVED EDDOCURRENT INSPECTION tected in additon, very 6 mail arrounts of fuel matonal uranomFOR STEAM GENERATOR TUDING Progress Report f or Jan- and pluton 6um were relear.6d The total mass reiensod fromvary 1%5 To Docember 1987. DOOD,C V.; DEEDS.W E., the furnace to the cotioction system was 317 g. 78% of *NchMCCLUNG.R W. Oak Rdge Natonal Laboratory Januaq 1990 was collected on the filters The results from thai, test more36pp 9002120284 ORNL/IM 11389 52597 255 compared with previous tosts in this sones and with a common.

A maior hmrtaton of ed3y cunant inspect,oq of steam genera- ly usod model for fisson product remaptot tubing is that small f a* nignats can be masked by the ef-fects of benign vanab60s, sv& as t<Jbe supports To dentify the

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40 Main Citations and Abstrach

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i NURIQ/CR4482; LADORATORY ANAliSIS OF FLUID FLOW Protucton of uranium mill wWers from occupational capo-

AND t.0 LUTE TRANSPORT THROUGH A VARiADLY SATU- sure to uranium through routine tucassay p ograms ary* the as-i; RATED FRACTURE EMBEDDID IN POROUS TUFF. sessment of accountal worker esposures are a&ctsod Com.

CHU ANG Yc HALDEMAN WA; RASMUSSEN.T.C ; et al An20- pansons of chemical properties and the tuological tchavor ofna Univ of, Tuc60n, AZ f ebrun'y 19D0 332pp 9003070258 refine uranium ora (yellowcake) are made to identify important52ti0t003 proporties that influence utaruurt. distribution among orgaris

3

i La!O'atory tophrHQues Ive devidopM1 that allow concurfent These studies will fa;ilitate calculatons of organ doses aher edI meas #ement of unsatWeted rnatnt hyd'auliC ConductMty and posures and associated health nsk estimates and will identifyI frattu's tra'1h%WVity of fra0tJred rock blocks Two Apache important bioassay procedJres to improve evaluations of hornan

Lehp IJff bocks with naturalif actJtes wefe removed from near egosures Samples of airt@ne uramum from operating miheSaponor, Anzona. 8% ped into rectangstar pnsros and instru- and depositon models were used to predict appreciable doposo

! mented in t% latcratory PoroJs cetamic plates provided solu- tion in the uppe' respiratory tract of workers, if respiratory prCrton to blo;L taps at fepJlated D'cksJres infitrston tests were lecton were rot used Latoratory ana ybes of comf%rcial yel-l e

4

pefiormed on toth test blocks Steady flow testing of the satu- nowcake, and inhalaton studies in rats, showed that inhalaton

]' rated ft'st biock p'ovded estimates Df matria hydraulic Corduc- of yellowcake aerosols might be Consdored to tie inhalaton of' ttvity and fractare trantmissMry. Faheen Centirneters of sucton vanatde m:rtures of amrronium diuranato and U(3)Og8) Studes

|Appl *d to ISO second bloCh top showed that tract #e flow was of yeliowcake Clearance l'om rats after wound Contaminationrf,yymal and inn tna bytaJ ic CorKl.netivtfy was an order of mag- showed that uran!um behavior in vwo could not be Quantrtativelyi

1

futude les$ tha$ the fir $t block saturated matria Conductivity related to Chemical compositon A tuokinetic model of yehow.Coated wire on-seiet!ve civetecces monitored saucous chlord- cake inhaled by Deag!e dogs was develaped Companson withed treakthroufi concetrations Minute sampies of tracer anl+ avadable data from human exposures sho*pd that organ bur-tch were coheeled wth l'ter paper, The technioves worked ws!I dens in an exposed worker can be estimated from unnary two-for stu:fyvig t'anwo't 14f aWO' at near saturated flow con $ tons assay results and in vivo counting. If the chemical composton,and altio appen' to tie promising for unsaturated conitons or solubic fraction, of the inhaled yetio* cake is knownD'eakthrough curves in he fracture and matn( and a concen-

NUREQ/CR4490 V01: REGULATORY INSTRUMENT REVIEW.tration map of chionde ( ^(entratons witNn the tracture, sag.MANAGEMENT OF AGING OF LWR MAJOR SAFETY RELAT.post p'efe'enba! fQw path.s in the fra:ture and substantial diffu. ED COMPONENTS WEHRYI V. Battelie Memonal institute,aion into the rnatnx Averaga travel veloety, dispersion coeffePac k Normwest Laboratory. Octoter 1990- 140pp

cient and longitudinal depe's'vity to the t'actee are obtained9011150043 PNL4190 63737:18$

NUnt0/CR4464: PH SENSORS BASED ON IRIDIUM OXIDE. This report compnses Part i of a review of U.S nuclear plantT ARLOEM J.; LREIDER.K Ga SCM ANClK.S ; et at Natonal in. regulatory instruments to determine the amount and knj of instatute of Standards & Technobgv (formerty National Bureau of formaton they contain on managing the owng of safety rotandStahan March 1D90. 21pp. MC4100360 $3344 092. comp 0nents in U S nuclear power plants The revww was con.

Results are presented on the pH. potential response of dc docted tot the U S Nuclear Regulatory Commesson (N;4C) bymagnetron reactrvely sputtered ridium onde filins The films en, the Pacific Northwest Laboratory under the NRC Nxicar Planth1M a nearly Nornslian response to pH. no hysto'es$ effects. Aging Research (NPAR) Prog'am Eght selected regulatory in-and minimal renoon6e to bnic interio'ences Sonsttsvity to cor. Struments, e g , NRC Regulatory Guides and the Code of Fedor,tain redon spec +s is observed, however. In aMtion, methods at hogu'atons, were reviewed for safety related informaton ona's discussed for prepanng rnodelindium onde sensor sur1 aces fwe selected components reactor pressure vessels, steam gen-

for ultraNgh vacuum sprice anai/ teal studies Stoichiometnc erators, pomary piping, pressort2ers, and emergency diusel gen-IrO(?) like surf aces are shown to tie re:atecty iner1 to gas phase orators The focus of the revew was on 26 NPAR definedcrator However, hydrory14tK,n of IrO(2)like so"sces can be in. safety-related aging essues. including examination, inspect on,duced by tf water plasma treatment and maintenance and repair, onessivo/ha'sh testing. and irra-

d.ation embnttement. The mapr conclusion of the reviow is thatNUREQ/CR44% STATIC LOAD CYCLE TESTING OF A LOW- safety related regulatory instruments do provide implic t gue-

ASPECT. RATIO FOLA. INCH WALL, TAG TYP(! STRUCTURE ante for aging management. but incluia Lttie explicit gudanceTAG 44 (t0.0.56) F ARR AR.C R.; DENNETT,J G ; A maior recommendaton is that the instruments t>e remed orDUNWOODY,W Ea et al Los Alamos National L.borato*y. N> augmented to supst!y address the management of agingvember 19n 16Bpp. 9011200032. LA11739-MS. 55797.348.

This report is the second in a senes of test reports that do. NUREQ/CR4491: SHIPPINGPORT STATION AGING EVALUA.tans the quasostatic cyche testing of low heght to-length aspect TION ALLEN.R P.; JOHNSON.A 0. Battelie Memonal institute.

latio reinforced concrete structures The test structures were Pacifc NcCFTwost Laboratory, January 1990 143pp

des gned accD' ding to the recommendationa of a technicai 9302120344. PNL 7191 52577 240review p'oup for the U.S Nuclear Regulatory Comm.asm spon. The Shippingport Atomic Pownr Staton, the first U S. targo.

i

sored Lemmsc Category i Structures Program The structure scale, contral-staten tweleat plant, now in the final stages of'

tested and repo*ted here had 4 inch-tNck shear and end wails, decornmmsioning. has been a mator source of naturally agedand the clastic octo mation was cominated by shear. The beo. equipment for the Nuclear Plant Aging Acharch (NPAR) andD'ound of the progf am and previous results are given for com. Other V.3. Nuclear Regulatory Comrrussion (NRC) programspleteness Details of the geometry, matenal prcperty tests, con. The evaluaton of natura|ty aged components is an integral partstruction history, ultrasonic testing, and modal teshng to find the of the NPAR pegram strategy Decauso naturally aged compo-

undamaged dye.amc charactenstica of the structures are given nonts and matenata expenonce the actua! service related enter.

Nont. the static test O'Dcedura and resuna in terms of stiftness nel stressors, corrosion and wear, test.ng procedures and main-and load deformation behavior are given. Finally. results are tenance practices. their evaNston is valuable in ventying degra-'

shown relative to other known resutts, and conclusiotto att psa. dation models, validatirq aging protectons based on the ex.'

tented trapoistori of accelerated test data, and detecting unespectedagmg mechanisms (surprmes) that Could SQnificantly impact

NUREQ/CR4489: BIOLOGICAL CHARACTE812ATION OF AADL component or system safety performance As part of the SNp-ATION EXPOSURE AND DOSE ESTIMATES FOA INHALED pingport katen aging esaluato, work. more than 200 items.URANIUM MILLIN 3 EFFI,UENTS EIDf 0N.A F inhalation Too ranging in we from smallinstruments and matenals sampics tocology Research institute. Juhe 194 82pp. 9007120243 LML one of the main ecolant pumps have t+cn removed and

124 $44661D6 sNpped to dewgnated NRC coritractors Although detaned eva'.

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uations of the components and matenal ' rom the Shippingport do not f all teiow assumed levels To assess tNs t chavor, com.Staten are lust teginning, the prehnunary tesults from the stud- pensons of AT's defined t y elashc plastic fracture toughnus andses conducted to date are indcatrve of the value of the aging C(v) tests have teen rude using data from RPV t ase and wraldinformation that ultimately may be obtained. metals in which irf aiations were inade urder test reactor core

NUREQ/CR4492: INVESTIGATIONS OF IRRADLATION- **^*ANNEAL RFIRRADIATION (TAR) PROPERilES TRENDS OF NUREQ/CR4506: PRELIMtNARY STRUCTURAL EVALUATIONRPV WELDS Phase 2 Final Report HAWTHORNE.J R ;

OF TROJAN RCL SUBJECT TO POSTULATEO RPV SUPPORTHISER.A L Matenals Engmenng Associates, Inc January FAILURE. LU.S C. Lawtonce Ltvermore Natonal Latioratory1990. 302pp. 9002t20277. MEA 20B8. 52574 001.Janua"y 1990. 35pp. 9002120234 UCtD 21831. 52611.224Notch duct hty, fracture toughness and tensile property ' rends

This report descHbes a prohnunary structural evaluation madeof two high copper content, submerged a'c welds with 2B8, ** to determine whether the teactor coolant loop (RCL) peng ofdgrees C errasaton (1),399 degrees C postirra$aton annea.6ng(tA) and 288 degrees C rearradaton (IAR) were investigated the Trojan nuclear power plant is capable of transfemng thePnmary ot9ectrves includod the determinston of weld metal loads normally camed by the reactor pressure vossol (HPV)

supports to other component supports in the RCL system if thereembnttlemen? rate with fluence following an ahneal and the RPV We stould tait, say hom ra$abon damap For theinftvence of fest cycle flusnce level (hg5 or low) on reembrittle-ment suscept&bty The wcis were commercialty made using a evalaation, we use the computer model of the RCL system of

single lot of fdier wve and hvo welding fluxes (Linde 80 and Unit 1 of the Zeon ruclear power plant because it is tea $lyLinde 0091). A 4'etivety-rp?.d reembnttlement of totn weld avaitable, tre ACL systems of 'bese two plants closoty resem.

. b6e each other. As a bounding case 6n 3e evaluation we postu-types was observed eth in val retrradiaton; however, the reem* late that all tour RPV supports have tarted 1wo load comtuna-bnttlement rese i|ecrestw nwkedty after a reirra$ation fluenceof about 0.3 x 1059) "i/cm(2), E greater than 1 MeV, in turn, tons are evaluated (1) the comtunation of dead weght, operat.

the tenefit o' lA ;,.vceres toward reducing total properties ing p, essure, and the safe. shutdown earthqaake, and (2) the

change with Nence war retairwd. The reembntilement trend comtenation of dead weight. Operating presaure, and a loss of-coolant accdont Both load comtunat ons are classihed sh Levelwas independent of first cycle Fuence level for the range irtves-D Service Limits " accordance with the ASME Boller and Pres-tgated. Rosadaai emtrittlemer. after 399 degrees C 108 tour

anneahng, indexed by 414 t& nperature, appears independent sure Vessel Code Stabc and dynaft c knear elastic annyses

of the pre-ahneal Corditon (I or lAR); however, wde vanatxPty are conducted to comph with rules specified by Subsechon NBin corQuncton with Appendes F, Dmsson 1, Sechon 111 of theamong we'ds in percent recovery la indicated. Trends 6n LAR be.

havior from Charpy V specimen tests were found to be ten ASME Code Results of trus prehrninary evaluatson indscate that

forced tg tensi6e specimen and tracture toughness (0,$T CT ASME Code Appendix F requirements are sabshed by each of

specimen) test findings the load comtanations conadered in the analysis, leading to theconcluson that the Trolan RCL piping is capable of transfornng

NUREG/CR4493: INFLUENCE OF FLUENCE HATE ON RADI- the RPV support loads to the steam generator and reactor cool.ATION INDUCED MECHANICAL PROPERTY CHANGES IN FsE. ant pump supportsACTOR PRESSURE VESSEL STEELS Final Report On Explora-tory Expenments. HAWTHORNE.J Rd HISERAL Matenats En- NUREG/CR5507: RESULTS FROM THE NUCLEAR PLANTgineenng Associates, Inc. March 1990. 347pp. 9004100351. AGING RLSEARCH PROGRAM THEIR USE IN INSPECTIONMIA 2376. 53344 299. ACTIVITIES. GUNTHER,W.; TAYLOR.J. Brookhaven Naticnal

Tin report descritos a set of expenments under'.aken using a Laborstory. Jeptember 1990. Bopp. 9010240401. BNL NUREG-2 MW test reactor, the UBR, to quakty the segnificance of 52222. 55495.329fluence rate to the artent of embnttlement produced in reacto, The US NRC's Nuclear Plant Aging Research (NPAR) Pro-pressure vessel steels at tnear service tornperature The test gram has determined the susceptstahty to aging of compnnentsmatenals inch;ded two reference plates (A 302 B, A 533 0 and systems and the potential for aging to impact plant safetysteef) and two submerged arc weld deposits (Linde 80, Linde and availabikty. The NPAR Program also dentified methods for0091 welding fluxes). Charpy V (C(v)), tenson and 0 5T CT detectng and mitigating aging in components. This report de-compact specimens were employed for retch ductihty, strength scribes the NPAR results wtuch can enhance NRC inspechonand fracture toughness (J-R curve) determinatons, respect vely. actmbes. Fwcommendatons are provided for communicatingTarget flueace rates vcore 8 x 10(10),6 x 10(t1) and 9 x 10(12) pertinent informaton to NRC 6nspectors There recommenda-n/cm(2)-6( 1). Specimtvi fluences ranged from 0.5 to 3 8 x tons are based on a detailed assessment of the NRC's lospec-10(19) n/cm(2) E greater than 1 MeV. The data desenbe a ton Program, and foodback from resdent and regional inspec-fluence-rate ettect which may extend to power reactor surveil, tors as desenbod within included are NPAR report summanoslance as wcil as test reactor facihtses row in use. The depend. aM aging inspecten gudes for components and systems whichence of embrtitlement sensitmty on fluence rate appears to have been evolusted at DNLdiffer for plate and weld deposit matenals. Relattvely goodagreetnent 6n fluence-rate effects definiton was observed NUREG/CR 5510: EVALUATIONS OF CORE MELT FREQUENCYamong the three test methoos. EFFECTS DUE TO COMPONENT AGING AND MAINTE-

NANCE. VESELY,W.E.; KURTH,R E.: SCALZO S M. ScienceNUREG/CR 5494: CORREuTION OF IRRADIATION INDUCED Apphcatens intomational Corp (formerly Science Apphcations,

TRANSITION TEMPERATURE INCREASES FROM C(V) AND inc l. June 1990. 236pp 9007120191. SAIC 89/ t 744K(JC)/K(IC; DATA Final Report HISER,A. Matenals Engineenno 54486 001.Associates, Inc. March 1990. 224pp 9005020331. MEA 2377. A methodology is developod to incorporate eging effects into53590:175. Probabihstic Risk Anatyses (PRAs). The methodology separates

Reactor pressure vessel (RPV) surveillance capsules contain the PRA analyses from the aging analyses, allowing availableCharpy V (Ctv)) specimens, but many do not contain fracture PRAs to be efficiently used in evaluating nsk e'fects of agingtoughness specimens, accordingly, tne radiat%:nduced Wft. The methodology was apphed to two NUREG 1150 PRAs usingOncrease) in the betttle-to ductile transmon region (AT) is bMed aging rate data that was developed for actrve components. Van-upon the AT determined kom notch ductihty (CivH tests. Since out survedlance and maintenance programs were evaluated tothe ASME Kpe) anrt K(tr) reference tracture tovahness curves determine their et'ects in controlk a agmg Doth point evalua-are shihed by the u from Civl assurance that this AT does not tons and uncertainty evaluatons meo camed out The resultsunderestenste AT associated with the actual irradiated frsature of the apphcatons showed the se notyty of aging effects ontoughness is required to provide confdence that safety margins core melt fm.ency to the efficie ecs of the maintenance and

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survedlance program in managing aging effects The detailed estary for personnel involved in the rnanagement of an accicontobutors to the aging effects showed reWaty te, e compo. dent to diagnose that an accdent is in progress, select ard 6m-nents contntoting. imptpng that pnonttrod aging mar sgement piement strategies to prevent or rnitigate the occdont, ard moreprograms would be most effective in controthng nsk. Itor the effectiveness of these strateges This report descnbos

the methodology and presents an apphcaton of this methodolo.NUREG/CR 66tt: IRRADIATION EF FECTS ON STRENGw C gy to a pressunted water reactor (pWR) wrth a large dry con-

TOUGHNESS OF THREE WIRE SERIES ARC STAINLEC tainment A nskamportant severe acedent soauente ftw a PWRSTEEL WELD OVERLAY CLADDING. HAGGAGf M; is used to enamene the capabihty of the existing measu ementsCORWIN,W.R; NANST ADA & Oak Rdge Natonal Latoratory. 2 supW N nessay aton %e mew incW anFebruary 1990 150pp. 9003190328. ORNL/TM-11439 assessment of the effects of the sequence on the meassement$3gp3

"'"d*N "9 I"' #"CI' 0' ""#0'"*"I #0"#*''The potential for stainless steel cladding to improe the trac. The 6nformat on needs and capabikties 6dentifm1 using this ap-

ture behavior of an operating nuclear reactor pressure vessel. proach are also intended to form Me basis tot more compre.partcularty dunng certain overcoohng transients, may depend MnsW m on news assessM MM W the

. greatty on the properties of the arra$ated clad $ng Therefore, a a yws and development of specific strategies for use in accon'three-wira staintess Steel claMng rrad.ated at temperatures dont management preventon and mitsgationand to fluences relevant to powee eactor opereton was exarr-ined. Postartad:stion tensile testing routts stow that, frore 't$ HV^ 1/CR 6613 V02: ACCIDENT MANAGEMENT INFORMA-to 2BB degrees C, the yield strength neressed by B to 4 Tlori NEEDS Volume 2 - Appendices HANSON.D.J.;ductility increased insignificant!y, with aWost no change in ult" WARD.LW.; NELSON.W R; of al EG&G Idaho. Inc (sutis ofmate tensile strength. All claddeng et vbited ductile to bnttle EG&G, Inc ) Apnl 1990 304pp 9905040140 EGG 2%2transiten behaviot dunng Charpy impact esting. because of the 53622 246dominance of detta femte fadures at low ?emperatures On the See NUREG/CR4513,V01 abstractupper sheif, energy was reduced 15 and W%. and lateral en-panson 43 and 41%, owing to tra$aton exposure of 2 and 5 x NUREG/CR 66H: MODELING AND PERFORMANCE OF THE10(19) neutrons /CM(2) (greater than I MeV). respectNeiy in MHTGR REACTOR CAVITY COOUNG SYSTEM CONKUN.J Caddton, radiaton damage resutted in 13 and 28 degr es C Oak Rdge National Lateratory Apnl 1990 30pp 9005210212eshrPts of the Cha'py impact sunsiton temperature for the low ORNL/TM 11451,53863.327.and high fluences, respect'vety, irra$aton exposure of ';2 5- The Reactor Cavity Cooling System (RCCSI of the Modatarmm thck compact specimens (0 5TCS), to a fluence of 2 41 x Hp inmperature Gas Cooled Reactnr (MHTGR) tropowd by10(19) neutrons /cm(2) (greater than i MeV), resulted in de- the U S Department of Energy in desgned to remove the nucie-creases in the initiaton fracture toughness, J(Ic), and the tear * af afterheat passively in the event that neither the heat trans-ng modulus port system not the shutdown cooling orculator subsystem is

NUREG/CR 6512 DRF FC: RESIDUAL RADIOACTIVE CONT AMI.availab6e A computw dynamic simulaton for the physical and

NATION FROM DECOMMISSIONING Technical Basis For matherhatica, modehog of an RCCS is desenbod here Two con-clusont can be made from computatens performmf under theTranslating Contaminaten Levels To Antbal Dose Draft Report assumpton of a unttc<m reactor vessel temperature first, theFor Comment KENNEDY,W E,: PELCOUiN.RA Dettelle Mortoheat transferred across the annutus from the reacte venet a dnel Institute, Pacific Northwest Latoratory. January 1990. then to amtaent conditons is very dependent on the surface317pp 9003070227. PNL 7212. 52811132. emsswities of the reactor vessel and the RCCS panels These

This document desenbos the genene modehng of the total ef.factrve dose eovivalent (TEDE) to an indevdua' in a population omssrvities should be penodicany checkod to ensure the sa4fy

functon of the RCCS Secord, the heat transfer from tho roac-from a urut concentraton of resdual radoactNe contamination tot vesselis reduced by a manimum of 10% by the presence ofRadnactive contaminaton insioe buildings and 6041 contamina.tion are consdered Unit concentration TEDE factors by rado- steam at 1 atm in the reactor cavity annulus for an assumed

constant reactor vessuf temperature of 500 K Thus, the pres-nucide, exposure pathway, and exposure scenano are calculat. em of a mo6Jm that participates to the transmisson of rad-ed. Teterence radalon exposure scenares are used to dortveurut concentration TEDE factors for about 200 indivdual radon. ant energy across the annuius can be expected to resoft in an

increase in the reactor vessel temperature for the MHTGR Fur-ucides and parent daughter mariures For buildngs, these unit ther investgaton of participating ranton rneda. incluengconcentration factors hst the annual TEDC for vo6ume and su,,face contamination situations For sod, annual TEDE factors are small particles, in the reactor cavity annulus is warranted

presented for unit concentratons of radonuchdes in soil dunng NUREG/CR 5515: LIGHT WATER REACTOR PRESSURE ISOLA-rescential use of contaminated land and the TEDE per unit TION VALVE PERF ORMANCE TESTING NE ELY,H H -totalinventory for potential use of dnnking water from a ground- JEANMOUGIN N M ; CORUGEDO,J.J Energy Technology Enp*5water source. Because of the genenu treatment of potentially noenng Center. July 1990 111pp 9000070338 ETEC 68-01complex ground water systems, the annual TEDE factors for 1,4B60 014dnnbng mater for a grven inventory may only indicate when ad- The Light Water Reactor Valve Performance Testog Program6 tonal site data or modehng sophisticaton are warranted De- was initiated by the NRC to evaluate leakage as an in6 cation ofsenptions are provded of the models, exposure pathways, ex.posure scenanos, parameter values, and assumptions used An val e coneton, provde input to Secton XI of the ASME Code [evaluate motor signature testing to measure valve operabilityanalysis of the potential annual TEDE resulting from reference ovatuate acoustic emismon monitonna for conston and degra-matures of resdual radonuchdes na provided to demonstrate dation and in seroce inspecton techniques Six typical checkapphcaton of the TEDE factors and gate vaives were purchased for testing at typical plant con-

NUREG/CR 5513 V01: ACCIDENT MANAGEMENT INFORMA. d:tions (550 F at 2250 psig) for an assumed number of cyclesTION NEEDS Volume 1 Methodology Development And Apph- for a a0 year plant hfetime. Testa revealod that there were var.cation To A Pressunzod Water Reactor (PWR) With A large, sances between the test results and the present statement ofDry Containment HANSON D J; WARD,L.W.; NELSON.W.Ra et the Code; howeveh the testing was not conclusNe The lifecycloal. EG&G Idaho, Inc. (subs c? EG&G, Inc ) Apol1990 69pp. tests showed that high toch acoustic emiss on can be ut;lited to9005070008 EGG-2592. 53656.277. trend smal1 }eaks, that specific motor signature measutoment on

in support of the U.S Nuclear Regulatory Commisuon (NRC) gate vatves can trend and indicate potential failurn, and that in.Accdont Management Research Program, a methodology has seNice inspecton techniques for chock valves was shown to bebeen devtiloped for dentdying the plant information needs nec- both feasibio ard an excellent preventive maintenance indca-

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tor. Lifecycle testing performance here dsd not cause tarpe ods are to provce capatetees for estabhshing degradationvalve leakage typical of some plant operaton Other testng es trends poor to failure and developeng gudance for ettectiverequired to fuity understand the empiecahon of Noe rebutta and maintenance The top cs of tNs Phase I assessment report arethe reoswed program to tupy implement them tallure modes and causes resulting from agng. manufacturer-,

NUREQ/CR 5516: CAUSES OF FAILING THE DRAFT ANSI mcunnended mamtmave and swance gwactices and

STANDARD N13 30 RADIODIOASSAY PERFORMANCE CRI. meas (ratde paranwters Wueng functonal m$catws) tw useTERtON FOR MINIMUM DETECTABLE AMOUNT. h assessing operational rea$ ness, estateshing degradationMACLELLANJA Battelle Memonal lostquie. Pacafc Northwest keda, and reMcMg tropient failure The resorts presented areLaboratory. Fetsvary 1990. 43pp. 9003070190 PNL 7217. taned on information dertved from operatsng eigenence52813 026. Was, mandschauppled Worwon, and hput kom plant

The test methods used for PNL beoassay partnrmance tests operators. For each failure mode, failure causes are tested bywere evaluated by companng the MDA based on pedormance teompawnt, and paranwters potentelty useful for detechngtests results with the MDA caiculated tiy PNL using the boag. degradam Mt Wd kad to few are NMsay latoratory's own quakty control (OC) data Two m vitro lab.

NUREQ/CR S$21: USE OF PERFORMANCE ASSESSMENT INoratones and two in vrvo laboratones were stwieert and a corre-lation between the periomance test MDA estimates and OC ASSESSING COMPLIANCE WITH THE CONT AINMENT RE.data was demonstrrted. However. It was often necessary to e,. QUIREMENTS IN 40 CFR PART 19t. BONANO.EJ Sandia Na-amene the OC data to identity 6mportant charactenstics of the tonal Labcretores WAHi K K Gram. Inc September 1990tdank estnbuton that affect the MDA calculation. $4nce the Mpp 9010230042. SAND 90 0127. 5547316tMDA equation must be based on the spectfc anatysis and cal. This report summantes the role of periormance assessmentculational methods of the procedure evaluated. Even when the h assesseg comgaance with the containment requeements incorrect MDA equation as appled, the MDA calculated will hav, 40 CFR Part 191, the Envronmental Protect.on Agency's Stand-a relattvery large confdence interval when only a few repicates ard for the esposal of spent nuclear fuel, hgh-level and transu-are used to estimate the standard deviatort For tNs reason, a 'ane radioactive wastes. In 1986. Hunter et al. prepared a aimereistrvety precise estimate of the MDA is generalty only ava61 tar report (NUREG/CR 4510. SANDBS 0121) whch provided anable when Poisson statistics may be apphed it was concluded Ove'vew of the approa0h to essess compkance with this stand-that performance testing alone cannot provide all the informa. ard The present report builds on its predecessor 60 that it hcor-ton necessary to make an accurate estimate of the macsur,. parates advances en periormance assessment subsequent toment process MDA. Review of the laboratory's OC data and the Hunter et at's report The snain purpose of this report to toentse measurement prrxedure will te necessary. Specific rec- se've as e mechanism for transtemng to tre Nuclear Regalatoryommendatons for charque to draft ANSI N13 30 " Performance Commentuun (NRC) and its contractors the performance essess.Cntena for Ra$obioassay" are givert ment methodologies (PAMs) develored by Sandia National Lab-

maw W W WW raMw wn2 msms WNUREQ/CR 6517: IMDACTS BRC. VERSION 2.0 Program User's stana wdh a scupon of reconn M 40 URManual. O'NEALO L: LEE.C E. Sands Natonal Laboratones' * * "# # " ** "" #April 1990. 244pp 9005040021. SANDB9 3060. S3649.3080 0This manual descrites the procedures for implementing IM-

PACTS DRC Versson 2.0 the IMPACTS BRC computer code aucumt and ns use M mgdatwy canphance. The reportends wh a escuum of swer of notam4 tmatantwas desgned for use by the N clear Regulatory Commisson

and industry to evaluate pet hons to classify specife waste uWain%s. and N cmMon of N cunplemntary c+nMaa esWe We M sumed numaW Wal +streams as tetow regulatory concem (DRC) The ecde provides as u to accessMe menet tw one m mye semana capatety for calcutating raadtton doses to a manmalindivid- DamNetam pmam W f N Amskaton of @nval, crthcal group, and the General populaton as a result of

transportaton, treatment. @sposal, and post-disposal activtties ance assessment methodologies for h>g4 level westo esposal

involving low level radoactive waste. Impacts are calculated for at two trpothetical attes Consistent with the technology trann-

multiple nuchdes and pathways depending on the treatment /Ga- for @cM. nuum Mmes am Me WwgW Wsposal optons spec hed try the code user. The treatment /6spos- rep rt to pubtscatena related to the SNL PAMs As such, this isal options include ons:te inceneration, ofistte inceneraton at mu- not a stand alone report and the reader is encouraged to core

b"" N " '''''*"C"'nicspat and ha2ardous waste taeshties. and ofinite dtsposal atmunscipal and hazardous waste landhlis. Included withm the dis-

NUREQ/CR 6623: DEVELOPMENT OF AN INFILTRATION EVAL-posal optons is the abmty to calculate impacts from the sortingUATION METHODOLOGY FOR LOW LEVEL WASTE SHAL-and/or recychng of mow containers and metal and glass ma+LOW LAND BURIAL SITES SMYTH.J Da DRESLER.Ecnals, Defauft envec.nmental and facility parameters are devv6' GEE.O.W4 et al Battene Memonal Institute, Pacche Northwestoped from refererice treatment / disposal sites, but the user has MoratW May W M7pp WW 9 PNb7356the opton to replace default parameters with site specific pa- $g g',

remeters. To facshtate use of the cme. data 6nput files are cre.ated and/or ested using a data pr7 processor vth pull-down An intittaton evaluation methodology (IEM) has been omrei-

g , g gmenus and contact sensitive help screens. Le code is wnttenin FORTRAN and runs on 640K IBM PC and compatible com ualmg fqcam mhitraton and drainage at low-twel wasteputers. siwa. hw ILM te designed to simulate significant factors and

hydrologic condtons that determine or 6nttuence moisture inhl-NUREQ/CR 6619 V01: AGING OF CONTROL AND SERVICE AIR tration, redistributon, and drainage in engineered cover and bar-

COMPRESSORS AND DRYERS USED IN NUCLEAR POWER ner systems. Tht IEM recognues the sources of uncertainty inPLANTS. MOYERSJC Oak Rdge Natonal Laboratory. July estimating moisture movement through engincored covers and1990.129pp 9008070332. ORNL 6607. 54850.2?4. Quantifies their influences on inhttraton and drainage estimates.

This report was produced under the Detecton of Defecta and The IEM is davoloped on the basis of regulatory requuements jDegradaten Monitonng of Nuclear Plant Safety Equipment ele- grven to 10 CFR 61. Engneered cover design and data svail-ment of the Nuclear Plant Ag<ng Research Program. This ele- ability will be largoiy site specihc. Because of the site-specahcment includes the identihcaton of pracical and cost-effective nature of the design and data avadatety, the IEM ts a flooblemethods for detecting. monitoring and assessing the seventy of framework that accepts vanous numencal models, closed formtime-dependent degradaton (aging) of control and service air ar,atytica! models, and uncertainty approaches Two apphcatonscompressors and dryers in nuclear power plants. These moth- of the IEM (a closed-form analytical medel and a senes of inte-

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grated numersal models) are dernonstrated for a hypothetical NUREQ/CR 6628. AN ASSESSMENT OF DWR MARK 11 CON.weste arte T AINMENT CHALLENGES.F AILURE MODLS. AND POTL N-

TIAL IMPROVEMENTS IN PLRf0RMANCE. AL L L Y,D t. ;NUREQ/CR 6624 V01: TML2 VESSEL INVE STIG ATION JONES.K R.; DALLMAN.R J.; et al LG&G laaho. Inc (subs of

PROJECT (VIP) MET ALLURGICAL PROGRAM Progress EG&G, inc ) July 1990 317pp 9009040046 LGG J593Repcst, January-Septemtet 1989. DIERCAS.O R. Argonne NF 55049 270tonal Latoratory March 19(O 43pp 9008090018 ANL 90/2 TNs report assesses chahenges to UWR Mart li containment$4672 048 6ntegrry that could potenttany ante from severe accidents Also

TNs report summanzes the work portormed by Argonne No- assataed are some potentir' improvements that coud preventtional Laboratory on the TMi-2 Vessel invest gation Protect (YlP) core damage or containment fadure, or could rwtigate the con.Metallurgical Prcyram during the nine months from the trutiabon Oequences of such failure by reducing the reieat.c of fissionof the program in January 1989 through September 1969 products to the environment These challenges ard improveDuring the reporting penod, arcNye matonal for the program enents are ana9ed via a limited quantitatrve nok/ benefit analy-was obtained from the lower head of the cancelled M dtand ..u- sit of a genonc DWR/4 reactor with a Mark || %ontainmentclear reactor in Md:and, ML in the form of four plates. Chemical Point estimate frequencies of the dominant core damage so-ana!yses and hardness measurements were performed on sam- Quences are obtained and simple containment prent tsces arepies from the four plates, the asceceived microstructure was constructed to evaluate the response of the containment tocharacten20d, and a tentative determinaton of rolhng direction these severe accident wQuences The resulting containment re-was made initial results from heat treatment expenments on lease modes are then txnned into source term release catego-the archive material sndicate that those regions of the TMi 2 ries, wNch provide inputs io the Loriscouerxe ana ysis Thematenal where the maumum temperature exceeded 727 de- output of the consequence analysis is used to construct an

grees C should be readdy identifebne on the basis of micros. ove'all tese casa risk profde potential improvements and sen-tructural ot4erystions A senes of round.rotun mechanical tests sitmtses are evaluated by moddying the event tree spht frnc-

and microstructural studies on the ataccorved arcNve matenal cons, thus generating a reviwd nsk profde Several irntortantwas developed, and specimens and specimen blarAs for tensde sensstrvity cases are examined in order to evaluate the impactand stress rupture tests were distnbuted to the participating of phenomenobgical uncertainties on the final resultsOECD laborflones Two toal specimens cut from a pate of A36 NUREQ/CR 6630; ANALYSIS OF H D ROBINSON PWR VESSELplairwcamon structural steel by pCl Energy Systems using metal

FLUENCE FOR CYCLE 10 UTILIZING PAR 11AL LENGTHdentegration macNning (MDM) were eaamined metal 6ograpg SHIELD ASSEMDLIES CHILDS,R L Oak Rdge Nationa! Labo-c,9' retory W LLIAMS.M L.; ASGARI.M Loumana State Univ.. Baton

NUREG/CR 6624 V02: TML2 VISSEL INVESTIGATION Rouge, LA. September 1990 95pp 9010230106 ORNL / T M-

PROJECT (VIP) MET ALLURGICAL PROGRAM. Progress 11476 55470 177.Report, October 1989 June 1990. DIERCKS.D R. Argonne Na. Neutron transport calculations have ticon performed to deter.

tional Laboratory. Novemter 1990. 79pp 9011290026 ANL-90/ mine the pressure vosul fivence and cacty dosimeter re.34 55880.106 sponses for cycle 10 of the H Et Robinson pressunted water to

Dunng the perod from October 1989 through June 1990, a actor. TNs cycle was the fast to utdi2e " partial length shiold an-semblies" witNn the core tc reduce the fluence rate at the critsseries of heat treattnent expe iments on arcNye matenal fromcal weid locaton in the vessel This work to part of the ongomgthe lower heed of the Mdiand nuclear reactor was completed, survedlance of fM Rotunton plant to ensure that the propsclod

the resutting microstructures were examined, and hardnesschannel, ates are reliable The flui calculations utslate a "two-D'";* r

values were determined. Round-rotun microstructural character- smsis approximaton and recently proceswd 6 tonnatons Lad mechanical touts on the archrve maternal were also soas wetens based on a new evaluation for the inciastic datacompleted by the participating Organisation for Economic Coop _ above 3 MeV. The methodology used to calculate tNs NgNycration and Development (OECD) partner taboratones Good asymmoincal confguration la discussed 6n detail, and a compar.agreement was generah obtained in these evaluatons and e ca aW W maw wWsq Wa istests Decontamination of sampics from the TMI 2 lower head is presented Decrepancies are oburved in the computud andunderway at ANL and detailed microstructural and scannng " " ' '" EU'electron microscope examinations of Specimen E-6 were car- "" " * * * * * "#riod out Metallographic emaminaton revealed that the surface

'

cracks present extended the0#9h the stainless steef cladda00- fast flux and dpa witNn the pressure vessel are given Thebut continued for only about 3mm into the undertying forntic effect of a least squares consolidaten of the measured and calsteel base metal. Extermive secondary cracking of the Cladding' Culated results is stJdied.not connected to the surface, wcs observed The evaluation in-dicated that the base metal 6n the vicinity of the crack attamd NUREC/CR 6632: A PERFORMANCE ASSESSMENT ME1 HOD-a maulmum temperature of about 1000 to 1100 degrees C OLOGY FOR LOW LEVEL WASTE FACILITIES KOZAK,M.Wadunng the acceent The molton fuel apparently did not pene- CHU,M S Y.; MATTINGLY,P.A Sandia Natonal Laboratonestrate into the eracks and interact with the base metal July 1990. 65pp 9006080187. SAND 90-0375. 54871243

A performance assessment methodo60gy has been dove 6cpodNUREG/CR 6627: AISK SENSITMTY TO HUMAN ERROR IN to, use by the U.S Nuclear Regutatory Commission in evaluat-

THE LASALLE pRA WONG.S.; HIGGINS,J; O'HARA.Ja et al. Ing license appkcations for low level waste disposal facilmesBroo haven National Latoratory March 1990 153pp TNs report provides a summary of background reports on the9004030071. BNL-NUREG 52228. 53226.169- development of the methodology and an overview of the

A sensmvity evaluaton was conducted to assess the impact models and codes selected for the methodology The overywwof human errors on the internal event nsk parameters in the La' includes d cussons of the pNtosophy and structure of theSalle plant The results provce the vanation in the nsk param- methodolo., and a sequential procedure for applying the metn-eters, namely, core melt frequency and acedent sequence fre- odology. Discussions are provded of models and associatedquencies, due to hypothetical changes in human error probabil- assumptions that are appropnate for each phase of the rnethod-ites A:so provided are insights denved from the results, wNch ology, the goats of each phase, data required to implement thehgNight important areas for concentraton of nok limitation et- models,66grvficant sources of uncertainty associated with eachforts associated with human performance phase, and the computer codes used to imrdomont the appro-

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! Miln Citations and Abstracte 46 '

Ipnate rnodels. In adston, a sample demonstraton of the meth- NUMEG/CR 6646: VICTORIA: A MECHANISTIC MODEL OF RA-

! odology is presented for a simple conceptual model. DIONUCLIDE BEHAVIOR IN THE REACTOR Ch0LANTi SYSTEM UNDER SEVERE . ACCIDENT CONDITIONS; NUREG/CR4633: STATIC LOAD CYCLE TESTING OF A VERY HEAMES.T.J.: WLLLIAMS,DA: BlXLER,N E.: et at Serda Na-! LOW ASPECT RATIO SIX INCH WALL TAG TYPE STRUC- tonal Laboratones. Cetober 1990. 215pp. 9011150046.

TURE TRG 6 6 (0.27, 0.60). FARRAR.C R.; BENNETT,J G. Los SAND 90 0756. 66737.325.Alamos Natonal Lateratory, BAKERW E.: et al New Mexico, TNs document provides a desenphon of a model of the rado.Unhr of. Albuoveraue, NM. November 1990.64pp.9012100346. nuctede behavior in the reactor coolant system (RCS) of a hghtLA 11796 MS. 65990.311. water reactor dunna a severe accident TNs document servesTNs test report is the tNrd for a tones of tests Camed out by as 15e user's manual for the computer code called VICTORIA,the Los Alamos Natonal Laboratory under the sponsortNp of based upon the model. The VICTORIA code predacts fission

j the Ursted States Nuclear Regulatory Commisson's Dtvisson of product release from the fuel, chemical reachone between he-Engineenng TNs research program has a Techrucal Review non products and structural materials, vapor and t.orosol be-a

Group that recommended test geomotnes and stres for the hav6or, and fissaor, product decay hostng. TNs document pro-tests. The quasi state load cycle testing of a totally shear- Vides a detailed descnptson of each part of the implornentabondominated structure (ben &ng deforf.ishon negligible) made of 6- of the model into VICTORLA, the numerical algorit'ime used,Inch tNck reenforced concrete walls is reported herein. The and the correlatoas and thermochemcel data t scest,ary for de.background of the program and the retutte that led to tNs term'rdng a solutcrt A desertpton of the coo, structure, inputsenes of expenments is first reviewed for conurwty, Next, the and output, and a sample problem are prov6ded The VICTORIAgeometry of the test structure, the desagn parameters, and the code was developed upon a CRAY XMP at Sandia Natonalconstructon of the structure, inclueng the matenal property Laboratones in the US A. and a CRAY 2 and vnnous SUN'tests, are reported. Both mndal anatysse and mortal test ng were workstations at the Wintrtth Technology Centre 6n England.done to vertty the undamaged dyname properbes of the struc-ture. Finally, the results of the quasi state cycle teshng are re. NUREQ/CR 6647: APPLICATION OF SURFACE COMPLEXA.ported in detail Resutts are compared with otter invesugatons TION MODELS FOR RADIONUCLIDE ADSORPTION.Senarttvityand with the Amoncan concrete institute (ACL) 349-85 code AnaFysis Of Model input Parameters. HAYES K.F ; REDDEN.O.;predictons. ELA.W.: et al. Battel 6e Merhonal institute, Pactfc Northwest Lab-

orstory. April 1990. 88pp. 9005210220. PNL.7239. fi3904.280.NUMEQ/CR 6640: PERFORMANCE TESTING OF EXTREMITY TNs report $$ cusses activity in two areas: 1) an evaluation of

i DOSIMETERS, STUDY 2. - - HARTY,R.: REECE W.D.; methodologes currently used for the phyncal a-d cherrucal|

HOOKER,C.D. Battelle Memonal institute, Pacife Northwest charactortfalon of metal oxide and hydroxide adsortients and 2)Laboratory. April 1990. 89pp. 9005040084. PNL 7278, the senafttvity of the vanous surface Complexabon models' ad-,

| 63648.319.. sorbent 6nput parameters for describing adsorpbort The report

The second of two performance tests of extremity dosimeters desertes the relative merits of three surface complexabonwas conducted userig a draft of a proposed standard for extrem- rnodels (SCM), procedures to estimate values of the model pa.Ity dosameter performance tesung The draft standard was writ- tame' ors from t,raton data and what is required of experimen.ten by the Health Physes Society Standards Committee tal titrabon data sets, The t#tirnate goal as to determme how and(HPSSC) Workin0 Group on the Performance Tesung of Extrem- whether SCMs can successfully describe adsorption of contami-sty Dosameters. The 6twtial performance test study (reportaf M nants from deposed nuclear wastes 6n natural soils and sedoNUREO/CR 4959) indcated that approximately 80% of the tung ment. Th a study's results help clarity the appicabihty of SCMs,the processors met the perfor. nance criterion spectfed in the partcularly wtth respect to their sensattvity to input parameters

I draft standard. Because of these results, an inveshgaton con- A rnethod is presented try wh6ch unique, best fit values forducted to determene the sources of error during the first per- these parameters mGy be obtained An appen&x is providedformance test indcated that errors occurred as a result of poor that reviews methods for determirung surface area, site density,procedures, equipment malfunctions, and because processors partcle size estnbuton and pore strucf Jre,were not prepared for the tests. A second periormance test re-suited in a passang rate of approximately 70% for nng dos;. NUREQ/CA 6648: REVIEW OF GEOCHEMICAL PROCESSESmeters and 81% for wnst dosimeters. Although this is an overall AND CODES FOR ASSESSMENT OF RADIONUCLIDE MiGRA.improvernent, the reouits in$cated that most processors were TION POTENTIAL AT COMMERCIAL LLW SITES. SERNE,T.J.;unable to meet the perfortnance crttenon Consistently for all ir. ARTHUR R.C,; KRUPKA.K.M. Battelle Memonai institute Pactic

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ra$aton categorass. Vanahons in the results were also ob. Northwest Laboratory. April 1990.136pp, 9005210229. PNL.| served within specsfc categores as a result of the irradiaton 7285. 63888:074c

source. Recommendations for changes to the draft standard in. Informaton on geochemical processes that control contams-cluoe eviding the beta parbcle and mixture categones, e%minat. nant soluton concentrabons -and nygraton at existing LLW

.- Ing the neutron category, and changing the tolerance l+ vel for waste sites is summartred. The review 6dentihen the current! the performance enterion. status and future 6nformalen needs required for the develop-

|ment of effective performance assessment rnodels for use in

NUREQ/CM-6642: MODELS FOR ESTIMATION OF SERVICE site hcense appicahons Except for some reports on LLW dis-LIFE OF CONCRETE BARRIERS IN LOW LEVEL RADIOAC. posal sites at Sheffield, fL. and West Valley, NY, few referencesTiVE WASTE OtSPOSAL WALTON.J C.; PLANSKY,LE.; were identified tht.1 contained adequate geochemical data nec.SMITH.R W. EG&G Idaho, Inc. (subs. of EG&G, inc4 Septem- estary to model geochemcal processes that affect migraton.ber 1990. 52pp. 9010090060. EGG 2597, 65319:043. Tntum aopears to be the most trobile redonuchde migrating

Concrete barriers will be used as 6numate parts of systems for from bunal',renches at commercial LLW sites. The review 6 den-isolaton of low level radioactive wastes subsequent to 6sposal. tified mcrebial-degradahon induced anoxia, subsequent iron

- This work reviews mathematcal rnodvla for othmahng degrada- onde precipitehon dunng oxidahon, alkahnity co1 trolled pHtion rste of concrete in typcal servce environments The changes, and organse complexaton reactons as key controls of fmodels considered cover sulfate atteck, romforcement corro- redonuchde migrabon. The quantity of expenmental and feldson, calcium hydroxide teaching, cartenaton, freeze / thaw, and data against whsch to test geochemeal codes is very hmited. Allcracking. Ad$ tonally, riuid flow, mass transport, and geocirm6- expenmental work on redonuchde adsorpton at commercialcal propertes of concrete are bnefly reviewed. Example calcula- LLW sites robes upon the K(d(60)) concept Studes of the of-tions included it!ustrate the types of predctons expected of the facts of organcs on radionuclide mobihty suggest that a Co.models. EDTA chetate formed in the onginal waste may persist indefr

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46 Main C!tations and Abstracts

ritely and lead to enhanced m6graton Other organic endeonu. Safeguards requestod that the U S Nuclear Hewlatory Com.cide compleias are less stable and do not signifeantty on- msson investigste the consequences of emtvirtioment of Apvh;nce motality urder conditone anticipated at commercial LLW supports TNs resort summarues the current literatu's relatedartes to these studies. evaluetes their contributon towd resolving

NUREQ/CR : 42: AN OVERVIEW OF THE LOW UPPER SHELFGenenc Safety lasue 16 concerning matenal embottlement. and

TOUGHNM SAF ETY MARGIN ISSUE. MERKLE.J G Oakrecommends any further acton consdered appropnate. This

Rdge Natonal Lateratory August 1990 6?pp 9009040031 review also contains a short discuss on of the uses of structural

ORNL/TM 11314. 65052 he mechanics and fracture mecharucs to anatyre embnttsoment

The low upper shelf toughness issue has a long Notory, te-gmning with the choice of matenals for the submerged arc weld. NUREG/CR 666h RELAP5 THERMAL HYDRAULIC ANAL ySIS

jng process, but also potentially invotving the use of A302 0 Or THE SNUPPS PRE SSURilED W AT E R REACTORplate. Cntens for vessels contatrung low uppor shelf matenale KULLDERG C M EG&G Idaho. Inc (subs of IG&O, Inc ) Mayhave usuah been onpressed in terms of the Ctwpy upper shett 1990,89pp 9006000313. EGG-2599 54074 283Impact energy. Afthough these critena have had several dator- ThermaLhydraube anatyses of frve hytothetical accdont sco-snt bates, the range of hmiting values for well tNcAnesses aD- nanos were performed with the RELAP5 computer etde for theproacNog rune anches has remained between 40 and 50 tilbs Westinghouse Standareted Nuclear Unit Power hant SystemValues for vessels with thinner walls and/or onty circumferential p,essurtred water reactor. This work was sponsored by the U $bw upper shell welds could be less A decision on critene to be Nuclear Regulatory Commission and is being done in conjunc-incorporated into the ASME Code is approacNng Cho6ces to tie teon with future anatysis work at the U S Nuc! car Regulatorymade concem the method for estimatng the decrease in upper Commisson Techncal Trairung Center in Chattarooga, TNshenf impact energy, flaw geometry for cacumierontial welds. These accdont scenanos were chosen to assess and bench-statistical significance of toughness values, the choece between mad N Nrmal hydraulic capaWies of me hchreal TrainingJ(D) and J(M), reference pressure, safety factors, and the inclu- Conner Standardised Nuclear Unit Power Plant System tamutatorson of 6nstatAlity pressure calculations by means of R curve er,

to nodel abnormal transient cond' tonstrapolation, TNs report presents a comprehensive overview ofthe including Nstory and rocommendations for expedttng NUREQ/CR 5560: AGING Or NUCLEAR PLANT RESIST ANCE

TEMPC.RATURE DET ECTOhS- HASHEMi AN.H M ;

NUREQ/CR 6553: COMPUTER PROGRAMS FOR EDDY CUR' DEVERLY D Da MITCHELLD Wa et al. Analysis & MeasurementRENT DEFECT STUD:ES pATE.J R.; DODO.C.V. Oak Rdge Services Corp. June 1990 247pp 900712024B $4469127.Natonal Laboratcry. June 1990. 256pp, 9007120211, ORNL/ An expenmental research profect was completed to kjenttfy

TM 11505. 54472.307'rograms to aid m the des 6gn of eddy cut-the effects of formal agmg on performance of nuclear salety.Several computer p related HTDs The limit for initial accurseY of those RTDs wasrznt tests and probes have been wntton Tf,* programs, written estabbshed and the range of their response time was rioter.

in Fortran, deal In varcus ways with the response to defects on. runed Representattve nuclear grado Rf Ds were tested for cali-htited by four types of probes the pancake probe, the refw,;. bration drift at simulated reactor cordsons and for stwlf hfeton probe, the circumferential boresde probe, and the circum, dnft TNs 6nchoed a numre of naturally aged RfDs receivedf@renbal encirchng probe Programs are incluoed wNch calcu.Icto he empedance or voltage change in a coil due to a defect, from nuclear power plants The results of (Ns work have shown

wtuch calculate and piot the defect sensittvity factor of a coil, that perrxkc calibra'*on and response time testing performedend wtuch invert calculated or empenmental readmgs to obtain once every fuel cycle is a reasonable approach for manage-the stre of a defect The theory upon which the programs are ment of aging of nuclear grade RTDsbased is the Durrows point tietect theory, and thus the calcuta,t:ons of the programs will be more accurate for small defects. NUREQ/CH.666& EVALUATION OF HEALTH E FFTCTS IN SE.

OVOYAH FUELS CORPORATION WORKERS FROM ACCI.NUREQ/CR 6554: RECOMMENDATIONS FOR THE SHALLOV. DENTAL EXPOSURE TO URANIUM HE XAF L UORIDE

CRACK FRACTURE TOUGHNESS TESTING TASK WITHIN FISHER.D R ; SWINT,M.J., KATHREN,R L Dattelle Memonal lrITHE HSST PROGRAM THEISS.TJ Oak Rdge National Lato- stitute. Pacific Northwest L aboratory. May 1990 60ppretory September 1990 65pp. 9010090068. ORNL/TM 11509 9000290116 PNL 7328 64323 311.$5318 346 Uranium unnalyses and medical laboratwy results were stud-Recommendalons for the Heavy-Section Steel Technology led to determine whettW there were any health effects fromProgram's investigaton into the Intluence of crack depth on thefructure toughness of a steel under conditons prototypic of urancm intake among a group of 31 workers e4ched to urant

those in a reactor pressure vessel are included 6n ttus report um henafluorde (UF6) and hydrotysis products foHowng the ac-

The pnmary goal of the shahow crack protect is to investigate tidental rupture of a 14 ton DNpping cyhndtw in earty 1966 atthe influence of crack depth on %cture toughness under con & the Sequoyah Fuels Corporaton uranium conversion facihty intions prototypic of a reactor vessel A hm'ed data base of frac- Gore, Oklahoma Physiological indicators studied to detectture-toughness values Ctl be assembled using a beam specF kdney tissue damage included tants for urinary protein, castsmen wtth a depth of 100 mm (4 In) using prototypic reactor and ceus, blood, specific gravity, and i ttne pH, blood urea nitro-vessel matenal. Resutts of the investigatson are expected to irn. gen, and blood Creatmine We cono sdod after reviewing twoprove the urderstanding of shallow flaw behavior in pressure years of folicwasp medical data that none of the 31 workersvessels, thereby provdtog more realistic information for apphca- sustained any observable health effects from exposure to urarv.ton to the pressurtrod- thermakshock 6ssues um. The unnary encreton data were used to develop an im-

NUREQ/CR 5556: REVIEW OF CURRENT LITERATURE RELAT, proved systemec recychng model for inhaled soluble uranium

ED TO GENERIC SAFETY ISSUE 15 LIPtNSKl R.EaWe estimated mitial intakes. clearance rates. kidney burdons,

GARNER,R.W. EG&G Idaho, Inc. (subs of EG&G, Inc ) July and resulting radiation doses to lungs. kKincys, ard tone sur.faces. Radiaton done limits and hmits on intake, as recom-1990. 28pp 9008080197 EGG 2598. 54B81:320

Recent evaluabons of survedlance samples in the High Flux monded by the ICRP, were not encoedod. However, the NRCisotope Reactor at the Oak Rdge Natonal Laboratory 6ed to denved hmit of 9 6 mg was exceeded by e>ght of the 31 work-

the concluson that the rmonttiernent rates of several reactor era Maximum hdney concentratons in egosed workers rangodpressure vesSol(RPV) tteel$ may be greater than ongeally are from 0.Or> to 2.5 pg U1g kidnu tessue We found no tonicologicat4Cipaled. In June 1987, the Advisory Committee on Reactor effects on the kdneys of workers at these concenlrations

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f'


NUREQ/CA 6667: PWR DRY CONT AINMENT ISSUL CHARAC- 6rxtiested that imp 6ementaton of both types of upgrades wouldTi Hil ATION Y ANG,J W Droakhaven Naticnal Latoratory- improve human geriormance and lower n$t tivt that onty theAupst 1990 204pp. 9XW40020 DNL NUREG-62234 panel desgn rmprovements would te cost teneficial

3t LSevere acedent issues have tieen charactertred for pressur- WHEQ/CR4671 DORON FLUSHING DURING A DWR ANTICl-

trod water reactors with tarpe dry containments A descrrhin of PATE D TRANSIE NT WITHOUT SCRAM MIRKOVIC.Dc-

g*PWR dry containment performance oder severe accdont s,& -

DNL NUREG 52237. 64408.246ditons is provded Amews and diwussions of earty contain. 42pp 9007120100ment failure due to direct containme it beating (DCHL In-vess61 Ih's report oxuments a study of an accdont sequence in asteam explosons hydropn tiurns and steam spAes, late con. toiling weier reactor (DWR) in vtuch there is a targe teactrvitytainment failure due to gradual overpressunreton ahd tesemat inserton due to the flustvng of torated water from the core-mett~through, and containment tiypass (intertpong systems Ttus has the potential to occur danng an anticipated transientLOCA) events are incluoed An assessmant of potential im. without scram (ATWS) atter the insection of berat$d water fromprovements such as RCS deposswtzaton, reacts cavity te_ Pe standtiy leoud control system The toron shuts down theflooding, hydrogen control, containment venting and accident [ower, tnt if thefe le a rapd depressunraton of the vessel (e 0,management st9tegy is presented The ti view and discusson due to the loadvertent actuation of the automatic depressurtra-a's largely t:ased on oosting in9mation otit?>ned from the tu tion system) large amounts of low pressu e. relattvety cold. un-clear Industry and the NRC's semre accrdent research pro. tiorated walk, enters the vesset causing a rap 6d diluton andgrams Additional analyses related to operator settons were per. coohng Ttwo stay was comed out to determine if the reectMtyformed and are presented in the appendees ad3 ton caused tiy this flustung could lead to a power excurson

NUREQ/CR 6668 Wt: INDUSTRY DASED PE,RFORMANCE IN- sufficient to cause catastroptuc fuel damage Calculations wereg,,nM out using the REW6/MDD2 computer code under def.DICATORS FOR NUCLEAR POWER PLANTS Phase 1 Report

June 1909 February 1990 CONNELLYI M ; VAN HEMELS B ,,,ont assumptons regarding tim 6ng and availatiility of low pres.auto pumps and with daterent reactivity cocthe$ents Tre resultsCommunications Technology Apphcatons, Inc. HAAS,p M Con' Sowed that the fuM enthalpy nse was insuthcient to cause cat 4cord Associates, Inc. My 1990 99pp P006090024 CfA

900216 025 54B72 004 astrophic fuel damage although less severe fuel damage m6ghtThis report preter.ts the results of the first phase of a two- still be possibi6 due to the overheehng of the fuel cladsog

phase study, periormed with the goal of developing indirect NUREQ/CR 6674: DEtCRMINATION OF THE CHEMICAL FORM(lea $ng) indicators of r.uclear power plant safety, using other n- OF TRITIUM IN SELF LW;NOoS stuns DOWERMAN.0 8;dustnes as a r cdel. It was hypotheaued that other industnes C2AJkOWSKI C.J Orookhaven Natonal .atioratory. May 1990-with similar putilic safety concerns could serve as analogs to 430p 90060803t4 DNL.NUREG 5223B 64076 000the nuclear power industry Many process industnes have many Building exit egns containing tntsum self luminous ightmore years of operating expenance, and many more plants than sources were dismantied, and the Ight towces were tested tothe nuclear power industry, and thus should have ac-cumulated determine the chomecal form of intium 60 th#s study The obtec-much useful safety data in Phase 1, the investgators screened live was to quanttty the amounts of intiated water (T(2)O ora vanety of potential industry analogs and chose a chemical / 10Hj present in the Ight sources The light sources consist ofpetrochemical manuf actanng industry as the pnmary analog for sealed glass tutes coated internally with a phosphor (rinc sul.further study. Informaton was gathered on safety prcgrams and fde) and fihed with tntium gas (T(2)) Light source tutes fromindicators in the chemical industry, as well as in the nucleaf four emit agns weie testod Two were new agna, one was supower trdustry Frameworks were selected for the development yea's old, and one was thirtoon yews od in one of the newof endicators which could be trhnsferred from the chemical to agna, the total totiJm inventory included two percent intiatedthe nuclear power envvonment. and canddate sets of direct water Two sgos had hgher amounts of inteated water 46%and Indirect arfety indicators were deveioreJ Estimates were for the other now sign, and 14 6% for the sa year old ogn inmade of the availabikty and quality of data to the themical in- the oldest syn, an accurate Inventory of the intrum content wasdustry, and plans were developed for turther investgating and not available, but intiated water accounted for 12 2% of thetesting these cand'date Mcators against safety data in both total tntium conectod tot countingthe Chemacal and nuclear power industnes in Phase 2.

NUREG/CR 6676: QUANTIT ATIVE ANALYSIS OF POTENTIALNUREQ/CR 6672: AN EVALUATION OF THE EF F ECTS OF PERFORMANCE IMPROVEMENTS FOR THE DRY PWR CON-LOCAL CONTROL STATION DESIGN CONFIGURATIONS ON T AINMENT. HELLY.O L; PAFF ORD.D J ; SCHROEDE R.J A ; etHUMAN PERFORMANCE AND NUCLEAR POWER PLANT al EG&G Idaho. Inc (aut s of EGAG. Inc ) August 1990.RISK O HARA,1; RUGER.C ; HIGGINS,J ; et al Brookhaven 163pp. 9009200008 EGG 2602. 05232 035Nationel Laboratory Sepiernber tWO 71pp 900925009 DNL*NUREG 52236. 65243 31f TNs report calculates the nsk benefit associatoc' with poten-

tial pertarmance improvemeras for the larDe d'y p'essuruedA human factors anahsis was performed to assess how iden. water reactor WW Mtainmnnt The anaiysis is based on the12fied upgrades to local control staton, (LCSs) in nuclear powe'June 1989 Gratt NUREO t 150 ter.ults for the Zon commercialplants attect both human performance and plant nsk Upgrades nudcar 94ctor Simplhed contamment event trees and thein the desgn of individual control panels and overall improve larDn acc lent progress.on event trees from draft NUREG 1150ment of functsunal centralization were consdered The analyws are used :o evaluate the e focts of potential imprcrvements onr

methodology was accomphshed in four stages First a hat of the respor se of t% Zion containment to dominant severe acc6-LCS human engineenng desgn deficiencies was developedusing data cohected from a vanety of sources 6nciuding visits to dent sequences Source terms are generated parametncally

using the 7'SOR ccde and offsite consoquencos are calculatednuclear power plants From these data, a set of potent:al up' with the MELCOR Accdont Consequence Gode Systemgrades were defined to cci act the defcencies Second, the et-(MACCS) These results give point estimates of the nsk reduc-tects of the upyades on man error probant'bes (HEPs) were ton associated with each containrnent improvement dentifwid

determined using a computer based rnethodology for schcitng by Brookhaven National Latoratory in their dratt issues Charac.expert Judgement. TNrd, the HEPs were propagated through a tergabon Reportplant probabbstic nsk assesse 'PRAL and new core meltfrequenmos were establu , Jechminary, scoping value- NUREQ/CR 6676: SURVEY Or tiORIC ACtD CORROSION OFimpact assessment was Wrr a to evaluate the regulatory CARBOf4 STEEL COMPONENTS IN NUCLEAR PLANTSnood for further reve* of possit>le acton to improve toe human C2AJKOWSKLC J Drookhavon Natonal Laborf .ory June 1990f act9rs engineenng asf>ects of local control statens The results 45pp 9007120198 pNL NuREG 52239 54468 203

:

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A review of heensee resporses to Genene Lettne No. BB 06 h0 REG /CR4564: RESULTS OF CRACK.AhREST TESTS ONwas pertormed t'y the U S Nuclear Regulatory Commisson TWO IRRADIATED HIGH COPPER WELDS. ISKAND( R.S K.;

(USNRC) This review encompassed 60 satisfactory responses CORWIN.W R ; NANST AD.R A Oak Ridge National Laboratory

trom the affected bcen ees A senes of ten (10) $nt Brookha. Decemt.cr 1990 197pp 9101040295. ORNL/TM 11576von Natonal Laboratory (BNL) and USNRC audits were per. 66271.085

formed on a selecton of utilites All of the licensees auusted The obtectrve of ins study was to determine the effect ofhad proyam implementations wtuch met the intent of the Go- neutron tra-tiaton on the SNft and shape of the lower tound

nerc Letter. A review of the avaitable l!terature and the vtant curve to crack-a' rest data Two suteerged arc welds with

audits has led to the concluson that the waverements of the Copper contents c4 0 23 and 0 31 wt % were commercalty fab-

Genene Letter have etwnbally t+en mot for the to plants a# rested in 220 nym (Nck plate Crack anest speamens fabocat-eted and it is renommended that res4 cot inspectors venty that ed from those wees wore trrasated at a hominal temperature

a documented and implemented prograre is in eNect at their of 268 deyeen C to an average flucoco of 19 a 10(19) neu-trons/cm(2) (greater than 1 MeV) Evaluaton of the resultsown plants shows that the neutron treadalon-thduced crack arrest tough-

NUREG/CR 5579; VALUE/ IMPACT ASSESSMENT OF JET IM- ness it"nperature sNft to atout the same as the Cha py V4 etch

PtNGEMENT LOADS AND PIPE.TO-PIPE IMPACT impact temperature sNft at the 41,J energy tevet The shape ofDAMAGE.Revmed Methods And Cntena. BROWN.J B ; the lower bound curves (for the range of test temperaturesBAMPTON.M C e.; ALZHEIMERJ M. Battelle Memonal Insttute, covered) did not seem to have been altered by irra:tiaten com.

Pacific Northwest Laboratory June 1990 72pp. 9007120168 pared to those of the ASME Atla) curve

PNb7339. 64470 267. NUREG/CR 5586: MITIGATION Or DIRECT CONT AINME NTTo account for effects that might result from a lotrof-coolant HEATING AND HYDROGEN COMBUSTION EVLNTS IN ICCeccedent (LOCA), nuclear power plant designers have teen to. CONDENSER PLANTS Ana'yses With The CONT AIN Code Andoured to anaWe the eifects of double-ended guillotne breaks Nt' REG 1160 PRA Methodology WILLI AMS.D C.:(DEGP) in hgh+nergy piping The U S. Nuencar Regulatory GF iGORY,J J. Sandia National Laboratones October 1990Commission (NAC), through its Standard Review Plan (SRP). re- pp M2ME SAWMR W Wautres that plant designers follow certain press sed methods Using Sequ yah as a tepresentatrve plant. cak.ulahons haveand entena in the estimahon of dynamic effects associated with been performed with a developmental version of the CON f AINthe postulated rupture of peng The work reported in this cmnWW co@ to asun N MNeness of varcus possibleNUREG ts entended to provde the basis for NRC devisons on immemna to o cWesw contain=nu in mtigatingadopting revisons to para of the SRP 3 6 2 entitled "Desermi- swm a ant smaros invoMng met contamnt Wngnaton of Rupture Locatons and Dynamic Effects Associated (DCH) and/or hydrogen combuston Mitigaton strateges con-with the Postulated Rupture of Piping" The revisions conse, a inc bedup poww tm Wms anCm aw rNurnered in tNs work evaluateo updated presenptons for criculaung '"" ' '' #*"" #@ #"")ct impingement forces on ent cal systems and the requirement "" "E # # # 'D C#8""' #'I*"' ''##to consider pre whip damage to a new populahon of pipes In "* *" #" * "" P"***"'#"""""***accordance with the procedures documented in NUREG/CR- * ** *3$86 entitled "A Handbook for Value-impact Assessment", this ered Only tnerting the containment or pnmaiv system depres.report found indicaton that substantial costs and occupatonal son 2ston combined with backup power suppio for the ignitorradiaton esposure would result from the proposed action with' systems resulted in large decreases in the peak nrossures cal-out substantially reducing the riska to put,lic health and safefy culated to resuet from DCH events Potential hydrogen detona.

# "" " " " ***** # # "9 #"P P *" D bNUREG/CR 6563; PREDICTION OF CHECK VALVL PERFORM. toth the 6gnitor systems and the air return fans would signifr .l

ANCE AND DEGRADATION IN NUCLEAR POWER PLANT #"" #"* ** #" "9" " #"DWEAR AND IMPACT TEST S F6nalSYSTEMS . "* "" * * "'*O

Report. September 1988 Apol 1990. KALSI M S4 HORST C L"' methodoiogy indicated that primary system depressuraabonWAhlG.J K.: et al Kalai Engineenng. Inc. August 1990 118pp comtuned with backup power for toth ignitors and fans could9009070007. KEl 1656. 55070 010. reduce the contnbubon to the mean nok potential of the class of

Check valve failures 6n nuclear power plants have led to events considered by atout a factor of threesafety concerns as well as extensive damage and loss of plantavailability in recent years Swing check valve internals may en- NUREQ/CR 6686 V01: CARES (COMPUTER ANALYSIS FORponence premature degradation tf the dsc is not firmly held RAPID EVALUATION OF STRUCTURES) VERSION 1.0 Seismicopen against its stop and significant flow disturbances are Module. Theoretical Manual. XU,JJ PHILIPPACOPOULO.present upstream witNn 10 pipe diameters The ob echve of the MILLER.C.Aa et al Brookhaven Nabonal Laboratory July 1990

t

current Phase 11 research was to develop and expenmentally 80pp 9008070356 DNL NUREG 52241. 54844 3t6.verity a quantitatrve methodology for predictng swing check Dunng FY's 1968 and 1989, Brookhaven Natonal Laboratoryvalve performance and the degradaten of internals caused by (DNL) developed tne CARES system (Computer Anaiysis forhnge pin wear or disc stud impact Phase I research had fo- Rapid Evaluation of Structures, for the U S Nuclear Regulatorycussed on nnvestigating the stabihty of the swing check valve Commission (NRC) CARES is a PC software system wNch hasdisc at offerent how velocibes for a *de vanety of upstream been deogned to perform structural response computaSonsflow esturbances located witNn 10 pipe d ameters of the check similar to those encountered in licensing teviews of nuclearvalve Vane performance predictons based on methodology poww plant structures The documentabon of the Seismicdeveloped as a result of Phase 1 and il research correlate weli Module of CARES conosts of three volumes. TNs report repre-

with actual valve operating history at plants The conservairve sents Votume 1 of the three volume documentabor. of the Seis=guidelines provided by tNs methodology, tempered and refined mic Module of CARES it concentrates on the theoretical basisby actual performance history and integrated with prevenuve of the system and presents modeling assumptons and tirtuta-maintenance act vit es. have the potent at for ogNficantly 6m. tons as well as notuton schemes and algonthms of CARES

prcnnng the overall reliability of check valves in nuclear power The User's Manual is published as Volume 2 wNie sulationsand resuta from a set of sample problems are puo%hed asplantsVolume 3 of the CARES cocumentaten

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NUREG/CR 5588 402: CARES (COMPUTER ANALYSIS FOR drogen burn, and corwecong matenal with the proper composhRAPID EVALUATION OF STRUCTURES) VERSION 1.0.Seisme ton 6nstead of a mixture gas through flow juncbons HECTRModule User's Manual. XU,J.: PHILIPPACOPOULO; predictons compare reasonably well with the measured peakMILLER.C.A.; et ni. Orookhaven Natonal Laboratory. July 1990 pressure ratos for 12 NTS promised hydrogen experiments it is110pp. 90080703518NL NUREG 52241. 54848.105. concluded that the capatMity of the new correlatons for flame

Dunng FY's 1988 and 1p09, Brookhaven Natonal Laborebry speed and combuston completonoss is sufficient for the NTS(BNL) developed the CARES system (Computer Analysis Lr expenments Dased on the analyses of the NTS and VGES ex-Rapid Evaluation of Structures; fcr the U.S. Nuclear Regulatory panments, using a single room as e node is recom.nended forCommissson (NRC) CARES is a PC software system which has the nodalaston in the HECTR combuston calculation.been designed to perform structural response computa!Onssimilar to those encountered in hcensing reviews of nac6 ear NUREG/CR 5591 V01 Nt: HEAVY SECTION STEEL IRRADIA-power plant structures. The documentation of the Seismic TION PROGRAM Semiannual Progress Report For OctoberModule of CARES consists of three volumes This report is 1989. March 1990 CORWIN.W.R. Oak Ridge Natonal Labora-Volume 2 of the three votume documentahon of the Seisme tory August 1990. 44pp 9008310217. ORNL/TM-11568Module of CARES and represents the User's Manual. Volume 1 55043:011.concentrates on the theoretcal bass of tne system and pre. The pomary goal of the Heavy Sect 6on Steel Irtadiaton Pro-sents modehng assumptons and hmitatsons as well as soluton gram is to povtde e thorough, quantitatNe assesamont of theschemes and algonthms of CARFS. Solutons and results from effects of neutron rimuiaton on the matenal behaver (particu-a set of sample problems are pubbshed as volume 3 of the tarty the fracture toughtiosa properties) of typical pressure-CARES documentabon. vesset steels as they relate to hght water reactor pressure.

NUREG/CR-5588 V03: CARES (COMPUTER ANALYSIS FORvessel integrity. The program includen direct continuaton of irra-

PAPID EVALUATION OF STr.JCTURES) VERSION 1,0 Seisme diabon studios prevt'usty conducted by the Heavy. SectonSteel Technology Program augmonted by enhanced examina.Module. Sample Problems, XV,Ja PHILIPPACOPOULO;

MILLER.C.Aa et al Drookhaven Natonal Lacoratory. July 1990. tons of the accompanytng micrestructural changes. Effects of146pp.9006070359 DNL NUREG,52241. 54848.215- specimen stze, matenal chemistry; product form and merostruc-

Dunng FY's 1938 and 1989, Brookhaven Nabonal Laboratory ture; tradiaton fluence, flux, temperature, and spectrum; and

(BNL) developed the CARES sgtem (Computer Analysis for posbrradiaton snnealing are exsmined on a wide range of frac-

Rapid Evaluaten of Structures) for the U.S. Nuclear Regulatory ture proporties. Detailed statishcal analyses of the fracture data

Commaston (NRC), CARES is a PC nottware system which has on K(Ic) shift of high copper welds were peeformod. Analysis of

been des #gned to perform structural resportse cynoutatens the first phase of tradiated crack arrest testlng on high copper

similar to those encountered in Ir;9nsing reviews af nuclear wolds was completed Final analysis and pubicabon of the re-power plant skuctures The documentaton of the Soinac suits of the second phase of the tradiabon studies on stain 6ess

Module of CARES onaists of three volumes This report repre- steel wold-overlay cladding were completed Cuterminattons

seats Volume 3 of the three volume documentabon of the Seis- were made of the vanabons in chemistry and untreadiatedRT(NDT) of low upper shelf weld metal from the Midland reac-me Module of CARES. It presents three sample problems typi'

calty encounWed in the Soil Structure in(cmetion analyses. The tor. Final analyses were performed on the Charpy impact 3ndtensaio data from the Second and Third Irradiation sones on lowtheorebcal bases, modehng assumptons and hmitabons as wolt upper shelf welds, and the report on the series was drafted. Aas soluton schemes ano algonthms of the Setsme Module of

CARES are given in Volume 1. The User's Manual is published dewled survey of existing data on merostructural models and

as Volume 2. data bases of irradiation damage was performed, and initial do-velopment of a reachon rate-based mndet was completod,

NUREG/CR 5589: ASSESSMENT OF ICE CONDENSER CON-TAINMENT PERFORMANCE ISSUES NOURDAKHSH,H,P. NUREG/CR 6594: RADIATION DEGRADATION IN EPICOR ItBrookhaven Nat onal Laboratory. July 1990. 57pp. 9000070396, ION EXCHANGE REStNS. MCCONNELL,J W; JOHNSON,0 A.; *

DNL NUREG-52242. 64844:259, SANDERS.R D. EG&G Idaho, Inc. (subs. of EG&G, Inc ) Sep-Vulnerabibbes cif an ice-condensor containment to challonges tomber 1990. 46pp. 9010230109. EGG-2603, 55470.125.

that couM anse from severe accidents have boon assessed. The Low Lovel Waste Data Daso Development.EPICOR llThe phenomenological tasues associated with containment Resin /Linor Investgaton Program funded by the U.S. Nuclearchallenges have been evaluated. A number of containment tm, Regulatory Commisson is investgabng chemical and physicalprovements which have the potenbal to mitigato severe acci. condibons for organs son exchange resins contained in severaldont challenges have been evaluated. This report is intended to EP6COR il prefttters. Those preNters were used dunng cleanupprovide a comprehenswo statement of the relevant issues that of contaminated water from the Three Mile Island Nuclearcan be used in the NRC staff's evaluaton process and by the Power Station ahnr the March 1979 accident The work wasutilities dunng their indmdual plant eramanations (IPEs) performed by EG&G idaho, Inc. at the Idaho Engineonng Labo.

ratory. This is the final report of this task and summanzes re-NUREG/CR 5590: ASSESSMENT OF THE COMMTION sutts and analyses or three samphngs of ion exchange resin;MODEL IN THE HECTR CODE. PONG,LT. Science splica- from profilters PF 8 and 20. Results are compared with beso-

bons intomat>onal Corp. (formerly Science Apphcatons, Inc.). * hne data from tests performod on urwrradiated resins supphedSandia Nabonal Laboratones. November 1990. 59pp. by Epcor, Inc. to determine the extent of degradat on due to90112600M SAND 90-70BO. 55806:179- the high intomal radiaton dose received by the oganic resansHECTR (Hydrogen Event Containment Transient Response) Results also are compared with those of other researchers.is a lumped parameter containmont analysis code developed tomodel the containment atmosphere dunng a nuclear reactor ac- NUREG/CR 5596: UNSATURATED FRACTURED ROCK CHAR.cident involving the release, transport, and combuston of hydro- ACTER12ATION METHODS AND DATA SETS AT THEgen. A new set of flame speed and combusbon completeness APACHE LEAP TUFF SITE, RASMUSSEN.T.C4 EVANS,0.Dacorrelatons has been included in HECTR. The combustion SHEETS,P.J.; et al. Arr2ona, Urvv. of, Tucson, AZ August 1990.model in HECTR was assessed against a simplo two-compart- 146pn. 9009 t 10122. 05123.350mont problem, as well as the NTS (Nevada Test Site) and P%iormance assessment of high lovel nuclear waste contain-VGES (Vanable Geometry Exponmunta! System) expenments ment feasibihty requires representabve values of paramotors asThe example using the two-compaament problem demonstratos input, including parameter moments, distnbutiona! charactens.that the combustion modof in the modified HECTR code is ca- tics, and covanance structures between parameters. To meetpoble of locabng the flame position in a compartment with a hy. this need, charactortzation methods and data sets for interstitial,

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hydraulic, pneumatic and thermal parameters for a sl6ghtly five of the seven plant damage state groups (PDSGs) identifiedwelded fractured tuff at the Apache Leap Tuff Site situated in by the NUREG4150 anaiyses, whch includes both short andcentral Antona are reported in this document. The data sets in- long term station blackout scouences (SBOs), transients, loss-ciude the influence of matric suction on rneasured parameters of. coolant accidents (LOCAs), and anticipated tra..et witfoutSpatial vanabihty is investigated by samphng along nine bore- scram (ATWS) Steam generator tube rupture (SGTR) andholes at regular distances Laboratory parameter est. mates for event VPOSGs were not analyzed because of ' heir ec-tainmentIOC core segments are proveed, as well as field estimates cen- bypass nature. After bei.,,, benchmarked with t' SET s intered on the intervals where the core segments were conected- terms of containrment failure mode and nsk, as WET 4 wereMeasurement uncertainty is estimated by repetitively testing used to evaluate a number of potential containment modifica-controf samp6es. tions ' he modificatons were examined for their potential to

NUREG/CR 559h IN VESSEL ZlRCALOY OXIDATION / HYDRO- nvtig. or prevent containment failure from hydrogen burns or

GEN-GENERATION BEHAVIOR DURING SEVERE ACCI- direcs empingement on the containment by the core (both fauDENTS. CRONENBERG.A.W Engineenng Science & Anatysis tors dentified as sign 6feant contnbutors to nsk in the NUREG-

September 1990 57pp. 9010230038. 65473;10L 1150 Seoucyah anatysis). However, because of the relativelyin vessel zircaloy ox6daten and hydrogen generaton data low baselire nsk postulated for Seouoyah p % 12 person. rems

from various U.S. Nuclear Regulatory Commission severe fuel por reactor year), none of the potential modificatons appear todamage test programs are presented and compared, where the be cost efiectiveeffects of riraloy melting, bundie reconfiguration, and bundlequenching by reflooding are essessed for common findings. The NUREG/CR 5603: PRESSURE-DEPENDENT FRAGluTIES FORexpenments evaluated include fuel bundles incorporating fresh PIPING COMDONENTS Pilot Study On Davis Besso Nuclearand previously tread.ated fuel rods, as well as control rods. Find- power Station. WESLEY,DA; KIPP,T.R.; NAAAKl.D Ka et alings indicate that the eFtent of bundle oxidatOn is largely con- ABB impell Corp. (formerty Impell Corp ). October 1990 113pp.trolled by steam supply conditons and that Ngh rates of hydro- 9011090189 EGG.200t $5661:016gen generaton continued a'ter melt formaton and relocation ~ The capacities of four, low pressure 1,uid systems to with-Ukewise, no retardation of hydrogen generation was noted for stand pressures and lemperatures above the design levels wereexpenments wNch incorporated control rods Metaflographic estabhshed for the Davis.Desse Nuclear Power Stat on. The re-findings indicate extenstve oxidation of once molten zircoloy WN N @M d dmpbeanng test debne. Such test results indicate no apparent lims- from |nterf acing System Loss of Coolant Accidents (ISLOCA) astations to rircaloy oxcation for fuel bundles subjected to part of the probabihstic nsk assessment of the Davis Besse nu.severe-accdont coolant boiloti conditons clear power staton undertaken by EGa0 idaho, Inc. Included in

NUREG/CR 5599: DY8MiC TESTING OF A CIRCULAR FOUN' this evaluation are the tanks, beat exchangers, fdters, pumps,DATION AND ANALYSES OF SOIL / STRUCTURE INTERAC- vatves, and flanged connections for each system. The probabil-TION. SRINIVASAN,M G.; KOT.C.A.; HSIEH.B J. A' Donne Na' ities of failure, as a function of internal pressure. are evaluatedtional Labors y October 1990.190pp. 9011050063. ANL-90/ as well hs the vanabikties associated with them. Leak rates or

"""***** " " """ "9 '"T o r e basemat of a one quarter este modet of a nu- The pressure capacities for the pipes and vessels are evaluated

clear power plant containment building was mobrected to steedy. usmg stam anaWs W N vanous fadum Ms andstate forced vibration testing The measured response was used ''ed The capacities are dependent on several f actors, includingto estimate the impedance functons for all ngd-body degrees the matenal propertios, modeling assumptions, and the postulat.of freedom and natural frequencies and dampag for the funda, ed fadure entona. The failure modos for gasketed-flange con.mental modes Bknd predictions of the soil / structure interaction nections, valves, and pumps do not lend themselves to evalua-(SSI) dunng the vibraton tests were made independently by l'on by conventonal structural mechanics techniques and eval-other invesbgators. The tests, extraction of SSI parametus On- uabon must rely pnmanty on the results from ongoeng gasket re-ciuding impedance functions from measured responees), results search test programs and available vendor information and test

.

of tne bknd predictions, and vafcus compansons of test deter,data.mned parameters with their ana6ytical counterparts are de-

scnbed. Analytical impedance fuactions based on a model of aNUHEG/CR 6605: LAPUR DENCHMARK AGAINST IN PHASEnged plate on an elastic half space were found to have a sirmlar AND OUT-OF PHASE STABillTY TESTS MARCHLEUBA,J

trend and/or values as the test determined functions in the tre.quency range containing the ngid-body rr )$ but not outside Oak Adge National Laboratory October 1990 34pp.

that range. The discrepancies between anaiysis and expenment 9011050068 ORNL/TM.1162L $56ta.164are traced to possue errors 6n test measurements and geo- This paper documents a benchmark of the LAPUR codephysical data, as well as to the assumptions of rigid-body versus expenmental stability data collected dunng startup test.

motco and soil homogeneity- ing at the Oskarshamn-3 reactor. The data consists of decayratios and natural frequencies of oscillation measured under

HUREG/CR 5602: SIMPLIFIED CONTAINMENT EVENT TRdE seal eeactor operating conditions Satisfactory agreementANALYSIS FOR THE SEOUOYAH ICE CONDEN5ER CON. was found between the measured decay ratios and the onesTAINMENT, GALYEAN,W.J.; SCHROEDER J.A.; PAFFORD,D JEGa0 idaho, Inc. (subs of EG3'3, Inc ) December 1990. calculated by LAPUR for both the in phase and out of phase

instabihty modes. The largest error in the calculated decay ratio130pp. 91011028L EGG-2606. 583R001, was 0.11, and it conosponded to test point 3 that is a veryAn evaluauon of a Pressurtred Woer Reactor (PWR) ice con-

denser containment was performed. In this evaluation, simphfied stable condition and, tnus, hard to determine the decay ratocontainment event trees (SCETs) were developed that utilued from the expenmental measurements The fact that LAPUR pre-

the vast storehouse of information generated by the NRC's dicts that in test 7,6, and 9 the out of. phase mode should have

draft NURE41150 effort Specifically, the computer programs been unstable (decay rato 103) when indied a limit cycle wasand data files produced by the NUREG 1150 analysis of Se- observed imphes that the theoretical apprr ach used in LAPURquoyah were used to electronically generate SCETs, as op- to estimate the stability of the out of-pNse mode is not onlyposed to tne NUREG 1150 accdent progression event trees physicatty sound but alc noie to produce numencally correct(APETs) TNs simphfication was performed to allow graphic de- resuitspecten of the SCETs in typical event tree format, which facih-tates their understanding and use. SCETs were developed for

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Main Cit:ti:ns cnd Abstr: cts 51

NUREG/CR 5607; FLOW AND TRANSPORT AT THE LAS NUREG/CR 5616- AUXILLARY FEEDWATER SYSTEM RISK-CRUCES TRENCH SITE Expenments 1 And 2. WlERENGA,P.J.; BASED INSPECTION GUIDE FOR THE DIABLO CANYONHUDSON.D.B Anzona, Unty. ut, Tucson, A7. HILLS R G ; et a!. UNIT 1 NUCdAR POWER PLANT. GORE,0 F.; VO,TV.;New Mexco State Unrv., Las Cruces, NM August 1990.426pp. HARRISON.D G. Dettehe Memorial Institute, Pacific Northwest9009040036. 5505):200. Laboratory. August 1990. 32pp. 9010230060. PNv7351,

Two water flow and solute transport experiments were per- 55472.318.formed as part of a comprehensive fie6d trench study near Las in a study sponsored by the U.S. Nuclear Regulatory Com-Cruces New Mexico. TMse expenmerst. vere designed to pro- miss#on (NRC), Pacife Northwest Laboratory has developed andyde data to kst determsnitts and stochasJc models of vadose apphed a metrodology for dertving plant specific nsk. based trFrone flow and transport. In Expenment 1, a 4 m by 9 m area spection guidance for the auxlhary feedwat*r IAFW) system atwas smgated for 10 days with wa'et contaming tritium. Thereat. pressurt2ed water reactors that have not L. sgone probatAhsticter, water was apphed without tntium for an addiSonal 76 days nsk assessment (PRAT This methodology uses existing PRA re.Simple one dimensional uniform and layered soit determniste suits and plant operating exponence Informatiort Existing PRA-models for infdtrabon adequatefy predected the overaH move- based inspection guidance informabon recently developed forment of the wetting front dunng inhttrabon, but poorty predicted the NRC for varcus plants was used to identary geners compo.postu values for water content due to spot al vanability. Use of nent failure modes. This Informaton was then cornbined wtththe layered soil model, rather than the uniform soil model, did plant specifc and industry wda component informaton andnot consistently improve predction accuracy for this paricular fallure data to identify failure modes and failure mechanisms forfield apphcaton. In Expenment 2, a 1.22 m by 12 m area was the AFW system at the selecN plants Diablo Canyoret wasirngated for 11.5 days with water contarning tnbum and bromde. selected as the first plant for study. The product of th's effort isThereafter, wete was apphed withuut tracers for an additional a pnoritized hsting of AFW failures which havt occurred at the64 days Water and bromede moved fairly unfformly donng infil- plant and at other PWRs Ths hsting is Intended for use bytrabon, whereas brnh concentrations of tabum developed on NRC inspectors in the preparation of inspecbon plans address.one side of the irogated area. Dunng redistributon, trrtium ing AFW risk tmportant components at the Diablo Canyore1moved httle. whereas bromsde displayed signifcont movement plantboth downward and to one side A two-d:monstonal determinss-be model for water flow showed quahtadve, but not quanttative, NUREG/CR 5617: AUXIUARY FE5DWATER SYSTEM RISK-agreement with observatons. A two r.hmensional determinisbc BASED INSPECTION GUIDE FOR THE J M F ARLEY NUCLE.model for solute transport poorty Described intem and bromide AR POWER PLANT. VO,T.V.; PUGH.R.; GORE.B.F.; et at Bat.movement dunng redistnbutort telle Menonal Insutute, Pacife Northwest Latxxatory. October

1990. 34pp. 9011090201. PNL 7349. 55661:129.NUREG/CR4113: PALEOLIOUEFACTION FEATURES ALONG In a study sponsored by the U.S. Nuclear Regulatory Com.

THE ATLANTIC SEABOARD. AMICK.D.; GELINAS,R.; mission (NRC). Pacific Northwest Laboratory has developed andMAURATH.G ; et at Ebasco Services. Inc. (subs. of Enserch apphed a methodology for deriving piant-specife nak based irrCorp.). October 1990.167pp. 9011200055. 56791:078. specten gusdance for the auxiliary feedwater (AFW) system at

This study to a phased irwssbgation u Mermanc in a systerm pressortzed water reactors that have not undergone probabahsteate fashion, whether or not seismically inw.ed paleoliquefac- nsk assessment (PRA) This rnethodology uses existing PRA re.bon features such as tose obsented in the Charleston, S C., suits and plant operabng exponence informahon. Exisbng PRA-area are present elsewhere in young sediments of the Atlante based inspechon Quidance recently developed for the NRC forCoastal Plain. The disemery of similar hquefaction features ir' naous plants was used to identty genenc component failureother areas could 6ndicate that large, potentally damaging, modes. This information was then Combined with plant specificearthquakes have not oeen f.stncted to the Charleston area in &nd industry-wde component informabon and failure data tothe recent geologic past Conversety, if no evidence of similar idenbfy failure modes and fadute mechanisms for the AFWhquefaction features is found, the uniqueness of the Charleston system at the selected plants J.M. Farley was selected as thearea in the context of eastern United States seismcity would second plant for ettdy The product of this ettort is a pnontredtend to tw;> confirrned. Phase 1 of this study centered on docu, heting of AFW failures whch have occurred at the plant and atmenting the age 6 anff charactensucs of controt kquefaction other PWRs. This hsting is intended for use by NRC inspectorssites and features located in the Charleston area, and ident fy. in the preparabon of inspection plans addressing AFW t'sk-am-ing the enteria by wNch simi'ar sites and features, which may portant components at the J M Farley plantbe located elsewhere, could be idenbfied Phase 2 invesbga-bons built on the results of these control studies and centered NUREG/CR 5622: ANALYSIS OF REACTOR TRIPS ORIGINAT-on the search for seismcally induced palcohquefact on features ING IN DALANCE OF PLANT SYSTEMS- STET SON,F.T.;outside the epicentral area of the 1886 Charleston earthquake. GALLAGHER.O.W.; LE,P.T.; et al_ Science Apphcabons interne-

bonal Corp. (former1y Science Apphcabons, Inc.) SeptemberNUREG/CR4615: LOW LEVEL RADIOACTIVE WASTE OlSPOS. 1990. 215pp 9010090026. SAIC-89/1148. 55323.064.

AL FACILITY CLOSUEPart 1: Long-Term Environmental Core This report documents the results of an analysis of balance-ditons Affecting Low 4evel Waste Disposal Site ofplant (DOP) related reactor inps at commercial U.S nuclearPerformance.Part it- Performar e Monttonng To Support Regu. power plants ovor a 5 year penod, from January 1,1984,lator) Decisions. WHITE G.J.; FERNS,T.W.; OTIS,M.D.; et at through December 31,1988 The study was performed for theEG&G Idaho, Inc. Nbs. of EG&G. Inc.). November 1990. Plant Systems Branch. Off>ce of Nuclear Reactor Regulaton,140pp 9011260040. EGG 2604. 55707.20& U.S. Nuclear Regulatory Commissior- The objectives of the

Part I of this report desenbes and evaluates potential impacts study were: 1) to improve the level of understandirv, of DOP.associated with changes in environmental condibons on a low, related challenges to safety systems by iderW71 J catego-level radcactiv. waste disposal site over a long penod of time rmng such events; 2) to prepare a cr.iputenzed data vase ofPart 11 of this report contains gutdance on the design and impio. DOP related reactor tnp events and .se the data oase to identemontabon of a performance monitonng program for low level ra. fy trends and patterns in the ponation of these events,3) todioachve waste disposal facihties invesbgate the risk imphcations of BOP events tnat challenge

safetv systems, and 4) to provde recommendatons on how toaddre.sr. BOP related concems in a regulatory context.

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58 Main Citations and AbstrOcts

NUREQ/CR 5627: ALTERNATE MODAL COMBINATION METH.common quantity for stating prenatal dose hmits and is appropn.

00S IN RESPONSE SPECTRUM ANALYSIS, BEZLER.P.; ate for the unique ettects of prenetal exposure Our knowtodge

CURRER!,J.R.; WANG,YA et at Brookhaven Nabonal Labora- is currently Insuffoont to warrant tie ur.e of radiation protectrontorw. October 1090. 216pp. 9011090235 BNL NUREG.52257. Imts for prenatal radonucid ex@$ures that are based on life.

bme detnments55t 32 060Tas technical report ne prepared to docume at the resuf's of

NUREQ/CR 5635: CELLULAR AND MOLECULAR RESEARCHan investigation of alternate methods to combine betweenTO REDUCE UNCERTAINTIES fN ESHMATES OF HEALTH,

modal response components when using the respo:Sc spec- EFFECTS FROM LOW LEVEL HADIATION A Feasibibty Study,trum mothod of analysis. These rnthods are mathematicapy ELKIND,M Ma BEDFORD.J.; et at Colorado State Urvv., Fortbased to property account for the combination between nged Colisns, CO GOTCHY R L Science Appbcatens internatonaland fienible modal responses as well as closely spaced modesThe methods are those advanced by Gupta, Hadpan and Lind- Corp. (formerly Science Applications, Inc ) October 1990-

ley Yow to address nged response modes and the Double Som 309pp 9011150052. 55738180-

Combinabon (DSC) method and the Complete Quadre$c Comta- A stur,ty was undertaken by e cytogenebeist. a cell tuologist, a

naton (COC) method to account for closely spaced modes. A heatth phywctst, a mammahan twologist, anr1 a molecular taolo-

dvect companson betwecn these methods as well as de $4SS gist to examine the feasitabty of reducrig the uncertainbos in

procedure is made by using them to predict the respanse of sixthe othmahon of risk due to protracted low doses of ionizing re-

piping systems. The results provided by each method are com- diabon. In addressing the question of feasitahty, a review was

pared to the corresponding time history estimates of results asmade of current cellular, molecular, and mammalian radiaton

well as to each other. The degree of conservsdsm associated data of the way in wNch altered oncogene properties could be

with each method is characlertzedinvolved in the loss of growth control that culminates in tumon-genesis; and of tne sigrutcant progress that had been made in

HUREQ/CR 5629: MICROEARTHOUAKES IN KANSAS AND NE- the oneogonic charactenratons of several human and animalBRASKA 19771989 F nal Report STEEPL ES.D.W.; m plasms On N bass of tNs mysis, the study group con-BENNETT.6 Ca P ARK.C.; et al. Kansas. Unrv. of, Lawrence, KS. cluded that, at the present time, it is feasible to mount a pro-October 1990. 39pp. 9011060t t $. 556*.6170. gram of radiaton resourch directed at the mechanism (s) of radr

The Kansas Geological Survey operated a microcarthquake ation4nduced cancer with special reference to nsk of neoplazanetworn from August 1977 to August 1989 with stabons located due to protracted, now doses of sparsely onizing radiaton. Toin eastern Kansas and Nebraska Locatable microcarthquakes implement a program of research, a review was made by thewith duration magnitudes less than 3.2 occur at the rate of study group of the methods, technigves, and irwtruments thatroughty 20 per year in the two-state area, with most of the mag. would be needed. This review was followed by an inibal surveynitudes ranging from 1.4 to 2.5. The microcarthquake pattern of major laboratones and institutons where scientific personnelobserved dunng the 12 years of recording is consistent with the and facilities sufficient to participate in a pgnificant part of thepattern of hestencal earthouakes reported since 1867 Much of program am krown to be available A research agenda of thethe actmty occurs along the Precambnan Nemaha Ridge, wNch pnncipal and broad objectivos of the program is also discussedhas been the site of several eartryauakes v MM intenerty Vliover the past 125 years Some seismicity is observed riong the NUREQ/CR 5637: GENERIC RISK INSIGHTS FOR WESTING-northwest ftank of the Midconunent Geophysical Anomaly in HOUSE AND COMBUSTION ENGINEERING PRESSURIZEDKansas, but 4ttle is obseNed in the Nebraska or lowa portions WATER REACTORS TRAVIS R ; T AYLOR.J ; FRESCO,A.; etof this Precambnan feature The Central Kansas Uphft. a buned at Drookhaven Nabonal Laboratory. November 1990. 00pp.

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anbcnne smlar in age to the Nemaha Ree, has been the site 9012100341. BNL NUREG 52200 55991:016of several icit earthquakes since 1982. Ar50ther trend of earth- A methodology has been developed to extract genenc nsk-quakes extends northeastward across central Nebraska and is based Wormaton from probabikste nsk assessments (PRAs) ofnot associated with any prominent geologic structure. All the Wesbnghouse and Combuston Engineenng (CE) pressun2edseismicity in central and eastern Kansas can be roughly corre. water reactors (PWRS) and apply the insights gained to Wes-lated to known geologic structures. tinghouse and CE plants that have not been subjected to a

NUREQ/CR 6631: CONTRIBUTION OF MATERNAL RADIONU- PRA. The available PRAs (five Westmghouse plants and one

CLIDE BURDENS TO PRENATAL RADLATION DOSESintenm CE plant) were examined to identi y the most probable, ie ,t

Recommendatons.For Comment. SIKOV,M.R4 TRAUB R.J.; dominant acc6 dent sequences ut each plant. The goal was toMEZNARICH.H.K. Battelte Memonal institute, Pacific Northwest includo all sewnces which represented at least 80% of coreLaboratory. - October 1990. 109pp. 9011160230. PNL 7445- damage frequency. If the same plant specific dominant accident

55754 283. sequence appeared within this boundary in at least so plantThss report descnbes approaches to calculating and express' PRAs, the sequence was consdered to be a represen stve so-

ing rad (ation doses to the embryo / fetus from internal radon quence Eleven sequences met this dehnition. From these so-chdes. Informaton was obtained for setected. occepatonalty quences, the most important component f ailures and humansignificant radoetements to provvje a spectrum of metabolic errors that contnbuteo to each sequence have been piontizedand dosametnc charactensbcs. Fractional placental tran:fer and Guidance is provided to pnonb2e the representative sequencesratos of concentration in the embryo / fetus to that in the women and modify selected basic events inat have been shown to bewere calculated for these matenals, and were integrated with sensitive to the plant specific desgn or operabng vanations of

data from biokinetic transfer rnodels to estimate radcactmtY the contnbubng PRAs This nak based gudance can be usedlevels in the embryo / fetus as a function of stage of pregnancy for utihty and NRC actmties including operator training, mainto-and time after entry The MIRD methodologies were extended nance, design review, and Inspectons-

,to formalize and desenbe details for calculating radiabon ab-

! sorbed doses to the embryo / fetus. Calculabons were performed NUREQ/CR 5638: TECHNICAL CONSIDERATIONS FOR EVALU-

for representative situations; int <oduction of I gCi into a ATING SUBSTANTIALLY COMPLETE CONTAINMENT OF'

woman's blood at successn,o months of pregnancy was as. HIGH-LEVEL WASTE WITHIN THE WASTE PACKAGE.sumed to accommodate the stage dependence of geometnc re. MANAKT ALA,H.K. Center for Nuclear Waste Regulatory Anaty-

Labonships and bological behavors. Summary tables of results, ses. INTERRANTE.C G Division of High4evel Waste Manage-

Correlabons, and dosimetnc relations, and of tentabye general- ment (Post 8704 t3). December 1990. 116pp 9101100445.

(20d Categonzatons are provided in the report. These approach- 56321. t 4 7.This report deals with technical information that 18 consideredes yield radiaton absorbed doses, and multiphcaton by quahty essenbal for demonsbating the abihty of the high-level radioac.factor (0) converts them to cose equivalent, This is the most

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Maln Citations and Abr., acts 53

t've waste package to provide "substantially complete contain. HUREQ/CR4649 V01: COMMIX 1C: A THREE DIMENSIONALment" of its contents (vitnfred waste form or spent hght. water TRANSIENT S:NGLE PHASE COMPUTER PROGRAM FORreactor fuef) for a penod of 300 to 1000 years in a geological THERMAL HYDRAUUC ANALYSIS OF SINGLE COMPONENTrepository environment. The discussion is centered around tech- AND MULTICOMPONENT ENGINEERING SYSTEMS Equatonsnical consderations of the repository environment, matenals And Numencs. DOMANUS,H M.; CHA,Y,S.; CHIEN T.H ; et al.and fabncation processes for the waste package components. Argonne Nationa! Laboratory. November 1990. 158pp.various degradaton inodes of the maturials of const,ucton of 901228012$. ANL 90/33 56198.316the waste packages, and inspechon and morvtonng of the The COMM101C computer progrsm, e ertanded version ofwaste package dunng the preclosure and retnevabdity pered, previous single phase COMMIX codes, is designed to analy7ewhich could begin up to 50 years after init ation of waste om. steady state / transient, single-phase three dimensional fluidplacement. The emphasis in this report is on metalkc matenals flow with heat transfer in reactor components and multicompon-However, bnef references have been made to other matenals ent systems The concepts of volume porosity, direchonal sur.such as ceramics, graphite, bonded co amic tretal systems, and face porosity, distnbuted resistance, and distributed heat sourceother types of composites The content of this report was pre. or sink is used to model a flow domain with stabonary struc-sented to an external peer review panel of nine members at a tures The new porous rnedium formulation permits a simialationworkshop held at the Center for Nuclear Weste Regulatory O' 8'ther a single component or a multicomponent engineenngAnalyses (CNWRA), Southwest Research Institute. San Antonio, system The conservaton equatons of mass, momentum, andTexas. Apnl 2-4, 1990. The recommend tons of the poor energy based on the new porous medium formulation arereview panel have been eorporated into this report There are SM as a Mavak proWm in space and an diahtwo companon reports, t 4 second report in the senes prov des value Wem in bm MN 1 of Wa repon entitled "Eque-the state.of the a't techruques for uncertainty evaluatons The tions and Numerics," desenbos in detail the basic equations,methods provided in that report can be used to quantity vanous mulalons, soMon prochs. howMaW 6%pwNtypes of uncertainbes. The third companion report, on the basis smawn s&m, Wsy qsm me auday phm-of the informaton provided in the first two reports, develops pa, e en s a ar em,

s f4 wrecommendabons for the resoluton of the issue of " substantial sampi ]oblems, etc. charts, avadable optons, input instructons,ty complete containment" of Ngh level radioactive waste withinthe waste package, as addressed in 10 CF R Part 60

NUREO/CRO t9 V02: COMMIX 1C: A THREE DIMENSIONALTRANStENT SINGLE PHASE COMPUTER PROGRAM FORNUREG/r;R 5640: OVERVIEW AND COMPARISON OF U.STHERMAL HYDRAULIC ANALYSIS OF SINGLE COMPONENTCOMMERCIAL NUCLEAR POWER PLANTS Nuclear PowerAND MULTICOMPONENT ENGINEERING SYST EMS User'sPlant System Sourcebook. LOBNER P.; DONAHOE,C.;

CAVALLIN.C. Science Applications internatonal Corp. (formerlyGuide And Manual. DOMANUS.H M.; CHA,Y.S ; CHiEN.T H ; etel Argonne Natona! Laboratory. November 1990 199ppScience Apphcations, inc ). September I HO. 601pp 9012280137. ANL 90/33. 56222.047.9010090058< SAIC 89/1541,55320-212-

See NUREG/CR-5649.V01 abstract.This report is the introductory volume to the Nuclear PowerPlant Sourcebook Senes and is intended as a source of current NUREG/CR 6653: RECRITICALITY IN A BWR FOLLOWING Asummary and comparshve informaton on U.S commercial hght CORE DAMAGE EVENT, SCOTT,W.Da HARRISON.D Gawater reactors (LWL). The summary and comparative informa. LIBBY,RA; et al. Battelle Memonal institute, Pacific Northwestton is organized into the fohowing four parts: (a) general U.S Laboratory. November 1990 167pp. 9012280221 PNL 7476LWRs, (b) pressun2ed water reactors (PWRs), (c) bothng water 56227.349.reactors (BWRS), and (d) bibbograprwes of general PWR and This report desenbos the results of a study conducted by Pa-OWR references, plant specife references, system specific ref. C8fic Northwest Laboratory to assist the U.S. Nuclear Regulatoryerences, and component specific references This report is sup. Commsmn m Walwbng the potenbal for recnticakty in bolhngptemented by a set of Source *coks that prudes more detailed water reactors (BWRs) dunng certain low probability severe ac.informaton on specifc U.S. LWR piants cedents Based on a conservatrve boundin0 analysis, this report

concludes that there is a potential for recnticahty in DWRs ifNUREG/CR 5644: CONSEQUENCE EVALUATION OF RADt. core reftovd occurs after control blade melting has begun but

ATtON EMBRITTLEMENT OF TROJAN REACTOR PRESSURE pnor to signifcant fuel rod melting However, a recnticahty eventVESSEL SUPPORTS LU.S C.; SOMMER,S C.; JOHNSON,G L.; will most hkoty not generate a pressure pulse significant enoughet al. Lawrence Livormore Nabonal Laboratory. October 1990. to fail me vessel. Instead, a quasosteady power level would119pp.9011160222. UCRL ID 104845. 55806 244. result and the containment pressure and temperature would in,

e report desenbos a consequence evaluation to address crease until the containment failure pressure is reached. unlesssafer) <oncerns raised by the radiaton embattlement of the reactons am taken to wmnate N went. Two strategies areactor pressure vessel (RPV) supports for the Trojan nuclear identified that would aid in rega"ung control of the reactor andpower planL The study compnses a structural evaluaton and an Wmnak N reucaW mnt We comainant fake pms-effects evaluabon and assumes that all four reactor vessei sup- sures are reached. The first strategy involves initatng borationports have completefy lost the load carrying capabihty. The at & We N W of com Mood H N potenbal forstructural evaluabon indicates that the Trotan reactor coolant control blade melting exists. The second strategy involves initsloop (RCL) piping is capable of transfornng loads to the steam abng residual heat removal suppressen pool cooling to remove

at 9 aW W N mcnkahh mnt and Nsgenerator (SG) supports and the reactor coolant pump (RCP)supports A subsequent analysis further demonstrates that the ama amSG supports and the RCP supports have suffeient design mar-

NUREG/CR 5659: CCNTROL ROOM HABITABILITY SYSTEMgins to accommodate additonal loads transferred to them REVIEW MODELS G LPIN,H Science Applications Internabonalthrough the RCL piping The effects eva!uaton, employing a Corp. (formerly Sconce Apphcatons, Inc ). December 1990systems analysis approach, investigates initiaung events and 143pp. 91010402Fd SAIC-90/1054. 56270.274.the reliability of the engineered ofegua d systems as the RPV This report prr vvJes a method of calculating control room op,is suotect to movements caused by the RPV support failure erator doses from postutated reactor accidents and toxic chemrThe study concludes that a hypothebcal failure of the Trojan ca! spells as part of the resoluton of TMI Action Plan ill.D.3 4.RPV supports due to radiaton embnttlernent wiil not result in The computer codes contained in this leport use source con-Consequences of sfgnificant safety Concems Centrations calculated by either TACTS, FPFP, or EXTRAN and

_. _


transport them via user defined flow rates to the control room break LOCA scenano with a 3 inch equ6 valent diameter break in

envelope. The codes compute doses to six organs from up to the hot nog of a commercial PWR operating at full power. The150 radionuclides (or i toxic chemical) for time steps as short experiment was performed on July 14,1983,in the LOFT faelitty

at the Idaho Nabonal Engineenng Laboratory under the auspic.as one second. Supporting codes wntten in Chpper assist ines of the Organizabon for Economic Coopershon and Develop-data entry and manipulation, and graphically display the resuttsment (OECO). TNs analysis presents an evaluabon of the codeof the FORTRAN calculat ons,capability b reproducing the complex phenomena which deter-

NUREQ/lA 001t TRAC-PF1/ MOO 1 POST TEST CALCULA. mined the LP SB 2 transient evolut on. The analysis compnsesTiONS OF THE OECD LOFT EXPERIMENT LP SB 1, the resutts obtained from two different runs The first run is de-ALLEN,E.J. United " ngdom Atomic Ene*gy Authonty. April acribed in detail analyring the main vanables over two bme1990.128pp. 9007120212. AEEW R 2254. 54466.163. spam. shod and longer ternt Smral conclusons are eawn

Analysis of the small, hot leg break, OECO LOFT Expenment and Nn a second Nn tesung some of Nse consens isLP SB 1, using the "best eshmate" computer code TRAC PF1/ ""MOO 1 la presented Desenpbons of the LOFT fac4hty and theLP SB 1 expenment are gNen and development of the TRAC * NUREQ/lA 0021: RELAP5/ MOO 2 CALCULATIONS OF OECOPF1/ MOO 1 input model is detailed. The ca.culabons pedormed LOFT TEST LP SB 2. HALL,P.C. Central Electncity Generabng

in acheeving the steady state conditions, from which the expert. Board. Apnl 1990, 43pp. 9005040095, GD/PE-N/606.ment was initiated, and the specification of experimental bound- 53622.176.aty conditions are outhned- To help in assessing the capabilities of RELAPS/ MOO 2 for

PWR Fault Anatysis, the code is being used by CEGB to simu-NUREG/LA 0012: RELAPS/ MOO 2 CALCULATIONS OF OECD. late several small LOCA and pressurund transient expenments

LOFT TEST LP SB-01. HALL P.C.: BROWN,G. Central Electnci. in the LOFT experimental reactor. The present report describesty Generabng Board. January 1990. 40pp. 9002120283. GD/PE- an analysis of small LOCA test LP-SB 02, which simulated aN/544. 52597:215. 1% hot leg break LOCA in a PWR, with delayed inpping of the

To assist CEGB in assessing the capabihbes and status of pnmary coolant pumps This test was camed out under theRELAP5/ MOO 2, the code has bean used to simulate SBLOCA OECD LOFT Program.test LP-SO41 camed out in the LOFT exportmental reactorunder the OECO LOFT programe, This test simulated a 1.0% NUREQ/lA 0022: TRAC-PF t / MOO 1 POST TEST CALCULA.hot leg break in a PWR, with earty tnpping of the primary cool. TIONS OF THE OECD LOFT EXPERIMENT LP.SB-3.ant circulating pumps. This report compares the results of the ALLEN,E.J.; NEILL,A P. United Kengdom Atomic Energy Author.RELAP5/ MOO 2 analysis with expenmental measurements ity. April 1990.100pp 9006290072. AEEW.R 2275. 54319 001,

NUREQ/lA 0013: RELAP5/ MOO 2 CALCULATIONS OF OECD-Analysis of the small, cold leg break, OECO LOFT Expenment

LOFT TEST LP SB-03. HARWOOD,C.; BROWN.G. Central Elec.LP SB 3 using the best estimate computer code TRAC PF1/

tncity Generating Board January 1990. 48pp. 9002120316. GD/MOO 1 la presented Desenptions of the LOFT facility and theLP-SB 3 expenment are given and development of the TRAC-

PE N/535. 526f t083. PF1/ MOD 16nput model is detailed The calculations pnriormedThis report compares the results of the RELAPS/ MOO 2 anal,

ysis with expenmental measurements. A simulabon of test LP-6n aaeving the steady state conditions, from which the experi-ment was inibated, and the specification of expenmental bound.

SB-03 was previously carned out at GDCD using the RELAP5/MOOl code. RELAP5/ MOD 2 was developed from RELAP5/ ary condvens are outhnod.

OOj NUREG/lA 0023 V01: ASSESSMENT OF TRAC #F1/ MOO 1"

co ti tive ea nah Com n of ELA / VERSION 14.3 USING SEPARATE EFFECTS CRITICAL FLOWand MOO 1 calcutabons show that RELAP5/ MOO 2 perfoms AND BLOWOOWN EXPERIMENTSVolume 1. Text And Tables.better than RELAPS/ MODI in a number of key areas, notabty SPINDt.ER.B.; PELLISSIER,M. France, Govt. of. January 1990.mass errors are much reduced, there is improvod numencal sta, 141pp.9006110015. SETH/LEML88-138. 5408(238.bihty, and improved separator modelling and modelhng of accu. Independent assessment of the TRAC code was conductedmulator $ ton' at the Centre d' Etudes Nucleaires de Grenoble of the Commis-

NUREG/lA 0018: RELAP5/ MOO 2 ASSESSMENT,OECD LOFT sanate a FEnergie Atomaque (France) in the frame of the ICAP.SMALL BREAK EXPER! MENT LP SB-03. GUNTAY,S. Paul This report presents the results of the assessment of TRAC-Scherrer Institute Apnl 1990.100pp. 9006080163. 54084136 PF1/ MODI version 14.3 using cribcal flow steady state ests

An analysss of the expenmental resu'ts and post-test calcula- (MOBY DICK, SUPER-MOBY DICK), and blowdown teststions using RELAP6/ MOO 2 carned out for . ECD-LOFT small (CANNON, SUPER CANNON. VERTICAL CANON, MARVIKEN,

break experiment LP SB 3 a.<e presented Expenment LP SB 3 OMEGA TUBE, OMEGA BUNDLE).

was conducted on March 5.1984 in the Loss-of Fluid Test NUREG/lA4023 VD2: ASSESSMENT OF TRAC PF1/ MOD 1(LOFT) facihty located at the Idaho Natonal Engineenng Labo. VERSION 14.3 USING SEPARATE EFFECTS CRITICAL FLOWratory (INEL). The expenment simulated a small cold leg break, AND BLOWDOWN EXPERIMENTS Volume 2: Figures,with concurrent loss of high pressure injechon syste% and coot. SPINDiER,0.; PELLISSIER,M. France, Govt. of= January 1990.down and recovery by feed and bleed of the steam generator 238pp 9006110013. SETH/LEML88138. 5408'! 264.secondary side and accumulator injection respectively. This See NUREG/iA 0023,Vs1 abstractreport documents a short post test anatyens of the expenmentemphasmng the results of additonal analysis performed during NUREG/lA-0030: ASSESSMENT OF RELAPS/ MOO 2 CODEthe course of this task RELAP5/ MOO 2 Nut model and resulta USING LOSS OF OFFSITE POWER TRANSIENT DATA OFof the post test calculaton are documented. Included in the KNU #1 PLANT. CHUNG.B-0.; KIM.H4 Korea Advancedreport is the results of a sensitivity analysis which show the pre- Ene.gy Research Institute LEE,Y-J Seoul Natonal Univ., Seoul.dicted thermal hydrauhc response to a different input model. Repubhc of Koroa. Apnl 1990.100pp. 9005040134 53620:286.

NUREQ/lA-0019: TRAC PF1/ MODI POST TEST CALCULA-This report presents a code assessment study, based on a

TiONS OF THE OECO LOFT EXPERIMENT LP SB 24real plant transient that occurred on June 9.1981, at the KNU

PELAYO.F. United Kingdom Atomic Energy Authonty. December # 1 (Korea Nuclear Unit Number 1) KNU # 1 is a two-loop Wes-

i 1990.165pp 9012280144. AEEW A 2202 56196 315. tinghouse PWR piant of 587 Mwe The loss of offsite powerAn anatysis of the OECD LOFT LP SB 2 expenment making transient occurred at the 77.5% reactor power with 0.5%/hr

use of TRAC-PFt/ MODI is desenbed in the report LP SB-2 ex- power ramp. The real plant data were collected from available

penment studies the effect of a delayed pump tnp in a small on-hne plant records and computer diagnostcs The transient

Main Citations and Abstracts SS

was simulated by RELAPS/ MOO 2/36.05 and the results wereNUREQ/lA 0033: ASSESSMENT OF RELAP5/ MOO 2 CYCLEcompared with the plant data to assess the code weaknesses

36.04 AGAINST LOFT SMALL BREAK EXPERIMENT L3 6.and strengths. Some nodal:2aton studies were performed to ER!KSSON.J. Sweden, Govt of. Juh 1990, 103pp.contnbute to developing a guidehne for PWR nodalizaton for 9008140510. STUDSVIKNP87128. 54926.326.the transient anatyWs. The LOFT smau break eWmt L3 6 has be anaN2ed as

part of Sweden's contnbution to the intomatonal ThermaMiy,NUREG/lA 0031: ICAP ASSESSMENT OF RELAPS/ MOO 2 draulec Code Assessment and Appicahons Program (tCAP).

CYCLE 36 05 AGAINST LOFT SMALL BREAK EXPERIMENT Three calculatons, of which two were sensitivity studies, wereL3 7. LEE.E4.; CHUNG.B.O.; K)M,H4. Korea Advanced Enwgy camed out The following quantibes were vaned. (1) the contentResearch Institute. Apnl 1990,171pp. 9005040112. 53621028. C' **"'ndary sioe nued and the feed water vaNo closure, and

The LOFT small break (1 in dia) experiment L3 7 has beer) (2) the two-phase characteristics of the main pumps. All threeanalyzed using the reactor thermal hydrauhe analysis code predctons aged esmaW weH wnh rnost of N maswedRELAP5/ MOD 2, Cycle 36 05. The base calculaton (Case A) data. he senswh caWatens resuned mh in marginal b

nts. he preW and mased data am cunparedwas completed and compared with the experimental data p eThree types of sensittvtty studies (Cases B, C and D) were car. ",i and h Menen am @anM w hals mned out to investgate the effects of (1) tweak dracharge coeffs '

cient Cd, (2) pump two-phase difference muftspher, and (3) high NUREG/lA-0034: ASSESSMENT STUDY OF RELAPS/ MOD 2pressure insectic.i system (HPIS) capacity on major thermal and CYCLE 36<04 BASED ON PRESSUR|2ER SAFETY ANDhydraube (T/H) parameters. A nodalizaton study (Case E) was RELIEF VALVE TESTS. STUBBE.E.J.: VANHOENACKER,L

. conducted to assess the phenomena with a simphfed nodelca, TRACTEBEL Jufy 1990. 86pp, 9008080178. 54871:157,gn' This report presents a code assessment study based on full

size rehef and asusted safety valve (called SEBIM) tests per.NUREG/lA+0032: ASSESSMENT OF RELAP5/ MOO 2 CYCLE formd on N CUMULUS vaNo test ng operated by Electrote

36 04 USING LOFT LARGE BREAK EXPERIMENT L2 5, de France (EOF) The increased awareness that the pressun2erBANG,Y.S.; LEE,S Y.: KIM,H4. Korea Advanced Energy Re- safety and relief vatves are not rehabic under water blovdownsearch institute. Apnl 1990.183pp. 9005040105. 53621:199. ceNons, has led to N desgn, teshng and bstaunton of so

The LOFT L2 5 LOLOCA expenment was simulated using the caw assisted saky vaNM of whch N SM M vaNMRELAP5/ MOO 2 Cycte 36 04 code to assess its capabahty to * * " " * * * * *** * # I" * "* 7"**D *predet the phenomena in LDLOCA. One base case calculation placing the saloty and 'ellof vanes on pressun'2ers in some Eu-

and three cases of different nodah2ahons were camed out The ropean PWB's. Before instanahon at the plant, the Belgianeffect of different nodalaation was studied in the area of the safety authonties requested a thorough full scale testing ofdowncomer and core, For a sensitrvity study, another calcula- these vanes on a test ng (CUMULUS) equipped with suffoontbon was executed using an updated verson of RELAPS/ MOO 2 diagnosbcs to measure the charactenstics of the vaNo. The

Cycle 36 04. A split downcomer with one crossflow Juncton and Be6gtan architect engineering firm TRACTEBEL was called uponto specify, order and test these vanes for installaison at the

two core channels were found to be effective in descnbing the DOEL 1 and POEL 2 power plants These tests do not provideECC bypass and hot channel behavior. And the updated version suffcont data of high quahty to justify an assessment study ofwas found to be effective in overcoming the code defcency ln the code RELAP 5 MOO 2 CYCLE 36 in the ICAP framewMthe Interfacial fncton and reflood quenching which is the subject of this report.

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S;cand:ry Report Number index

This index lists, in alphabetical order, the performing organization hsued report codes for theNRC contractor and international agreement reports in this compilation. Each code is cross-referenced to the NUREG number for the report and to the 10 digit NRC Document Control-System accession number,

SECONDARY REPORT NUM8ER REPORT NUMDER SECONDARY REPORT NUM8ER - REPORT NUMBER- AEEW-R 2254 NOREG/W 0011 EG42602 NUREG/CR4575AEEW.R 2275 NUREG/lA 0022 EGG 2603 NUREG/CR 5594AEEW R-2202 - NUREG/A-00t9 . EGG-2604 NUREG/C45615ANL 86-33 NUREQ/CN704 YO3 EGG 2006 NUREG/CR 5602ANL49/17 NUREG/CR4365 EGO 2007 NUREG/CR 5603ANL49/22 NUREG/CR-4744 VG) N1 EGG-2600 NURE G/CP Ot t 1ANL 69/40 NUREG/CR 4667 V07 EGG 4619 NUREG/CR 6229 V03ANL 90/2 NUREG/CR4524 Vol EPRl/NP4480 NUREG/CR 5395 VIOANL 90/22 NUREG/Ch0112 V01 EPR1/NP4480 NUREG/CR4395 V02ANL 13/22 NUREG/CP4112 V02 E PRt/NP4480 NUREQ/C4 5395 V11 AD#W b90/26 NUREG/CR4599 EPRl/NP4480 NUREG/CR 5395 V11ANb90/73 NUREG/CR4649 V01 ETEC 8641 NUREG/CR4515ANb90/33 NUREG/CR4649 V02 GD/PE N/535 NUREG/' A4013ANLM/34 NUREG/CR4524 V02 GD/PE N/54J NUREG/lA 0312ANb90/4 NUREG/CR-4867 V06 - GO/PE N/606 NUREG/lA4021ANL 90/5 NUREG/CR-4744 V03 N2 IEB 79-17 NUREG/CR 4286BAW 2067 NUREG/CR4395 V11 lEB-79-18 NUREG/CR4306BAW 2078 NUREG/CR4395 V10 10B-79 23 NUREG/CR4269BAW 2060 NUREG/CR4395 V02 IE B-80 02 NUREG/CR 5307BAW.2099 NUREG/CR 5395 V11 AD 1EB40-15 NUREG/CR 5338BMs-2139 NUREG/CR 4624 V06 IEE,-63 05 NUREG/CR4297BNL NUREG41454 NUREG/CR-2331 V09 N1 ' IEB45-001 NUREG/CR 5296BNL NUREG41454 NUREQ/CR-2331 V09 N4 IEB-85 003 NUREL/CR 4661BNbNUREG-51699 NUREG/CR4444 V07 lE B-86-003 NUREG/CR 5295BNbNUREG41706 NUREG/CR 3469 VOS lEB 88 005 4UREG 1402BNbNUREG41742 . NUREG/CR 3668 KEi1656 NJREG/CR 4583BNbNUREG42007 NUREG/CR-4659 V03 LA 11607 MS NUREG/CR 5360BNbNUAd452168 NUREG/CR4254 (A 11067 MS NUREG/CR4424BNbNUREG42178 NUREG/Crl4260 V01 LA 11730-MS NUREG/CR 5487BNbNUREG $2178 NUREG/CR4280 V02 LA 11796-MS NUREG/CR4533BNbNUREG 52196 NUREG/CR4366 (M 0124 NUREG/CR 5489RNbNUREG42212 NUREG/CR4419 MEA 2068 NUREG/CR4492BNbNUREG42220 NUREG/CR4472 MEAE70 NUREG/CR 5493BNbNUREG-52221 NUREG/CR4474 MEA 2377 NUREG/CR 6494BNbNUREG42222 NUREG/CR4507 MTR 90W00013 NUREG/CP 0108BNbNUREG42226 NUREG/CP 0110 ORNb6566 NUREG/CR 5404 V01BNbNUREG42226 NOREG/CR4527 ORNI.4564 NUREG/CR4451BNbNUREG-52234 NUREG/CR4567 ORNi4589 NUREG/CR4463BNL NUREG42236 NUREG/CR4572 ORNb6607 NUREG/CR-5519 V01BNL NUREG 52237 - NUREG/CR-5573 ORNbTM/11285 NUREG/CR4421BNbNUREG42238 NUREG/CR-5574 OR4UCSO/TM-267 NUREG/CR 5366: BNLAUREG42239 NUREG/CR4576 ORNUCSD/TM-270 NUREG/CR4468BNbNUREG42241 NUREG/CR 5588 V02 ORNUNOAC 232 NUREG/CN674 V10BNbNUREG 52241 - NUREG/CR4586 V01 OrtNVNOAC 232 NUREG/CR-4874 V09BNbNUREG-52241 NUREG/CR 5588 V03 ORNUNOAC-232 NUREG/CH-4674 V11BNbNUREG-52242 NUREG/CR4569 ORNUNOAC432 NUREG/CR 4674 V12BNkNUREG-52257 HU9EG/CR4627 ORNUNSC400 NUREG/CR-2000 V08N12BNbNUREG 52260 = NUMEG/CR4637 ORNUNSC200 NUREG/CR 2000 V09 H2CBCS RPP #90-1 NUREG/CR-6438 ORNUNSC200 NUREG/CR 2000 V09 NiCTA 900215325 NUREGICR4566 V01 ORNUNSC200 NUREG/CR-2000 V09 N3EGG 2458 NUREG/CR 4639 V01 R1. ORNUNSC200 NUREG/CR 2000 V09 N4EGG 2456 NUREG!CR 4639 V4P3R2 ORNUNSC200 NUREG/CR 2000 V09 N5EGO-2456 NUREG/CR 4639 V4P2R2 ORNUNSC200 NUREG/tA2000 V00 N6EGO-2458 NUREG/CR-4639 V4P1R2 . ORNUNSC200 NUREWCR4000 V09 N7EG42458 NUREG/CR-4639 V5P383 ORNUNSC200 NUREG/CR4NO V00 N8EGO-2458 NUREG/CR-4639 V5P1R3 - ORNUNSC200 NUREG/CR-2000 V09 N9EGG 2458 NURE9/CR-4639 V5P2R3 ORNUNSC200 NUREG/CR-2000 V09N t0EGG 2469 - NUREGICR-4731 V02 ORNUNSC200 NUREG/CR 2000 V0GN11EGO 2535 NUREG/CR4111 ORNUTM 10328 NUREG/CR-4816EGG 2545 NUREG/CR 5181 ORNUTM-11200 NUREG/CR4J74EG42554 NURIG/CR-4550 V7 RO) ORNUTM.11267 NUREG/CR4409EGG 2555 NUREG/CA-5273 V04 ORNUTM 11314 NUREG/CR 5552EG42562 NUREG/CR4314 YO3 ORNUTM 11319 NUREG/CR 5439'

EGO 2566 - NUREG/CR4376 ORNUTM 11350 - NUREG/CR4449EGG 2574 NUREG/CR4447 ORNUTM 11352 NUREG/CR4450> EGG 2576 . NUREG/CR 5448 ORNUTM 11389 NUREG/CR 5478EGG 2577 - NUREG/CR4229 V02 ORNUTM 11398 NUREG/CR-5479"

EGO-2592 NUREGICR4513 V02 ORNUTM 11399 NUREG/CR 5400EGG 2592 . NUREG/CR4513 V01 ORNUTM 11439 NUREG/CR45 t 1EG42593 NUREG/CR-5526 ORNUTM.11450 NUREG/CR4473EGG 2597 NURFG!CR4542 ORNUTM-11431 NUREGICA 5514EGG 2598 NUREGICR4556 ORNUTM 11476 NUREGICA 5530EG42599 - NUREG/CR 5557 ORNUTM 11505 NUREG/CR-5553 '

57

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50 Secondary Heport Number indOx

SECONDARY REPORT NUMSER REPORT NUM8ER SECONDARY REPORT HUMidR REPORT NUMBER

ORNL/TM-11509 N'JREG/CH $554 SANDe61309 NUREG/CR4551 V2 RIP 1

ORNU IM-11568 NUkfWCRadet V01 NI SANC96,009 NURE Glen 4551 V2 RIP 7

ORNL/YM 11575 NUREG/CR 5584 SANDe&1 EYJ NUREGICR 4%) V4RlP2SANDee-1309 NURE G/CR4551 V4R1P1

ORNL/TM 11621 NUREG'UR 5605 SANDf41309 NUREG!CR 4551 V381P1ORNL/TM 9593 NURE G /CR4219 V06 N2 SANh8A1%9 NURL G/CR-4551 V3 RIP 2ORNLSUB'87637/1 NURL G/CR-3873 SANDo&1309 NURE 'i/CH-4551 VSRIP1PARAMETER IE 155 NURtG/CR4525 DNDo& 1309 NUREG/CR4551 V5R1P2PARAMETE R 16158 NURE G/CR4661 SAND 8tx1309 NUREG/CR 4551 V641P1PAR AMET ER IE 177 NUREG/CR 5286 SANDe&1XS NURE G/CR4s5 t V64tP2PARAMETER lE180 NUREG/CR 52S9 SANDe&1443 NUREQC c4671PARAMETE R I0186 NUREG!CH 5295 MW6-1562 NUREG/CR4691 V02PARAMETER IE168 NUREG/C4 5297 S AND861562 NURE G/CR 4691 V03PARAMETER lE 189 NURE GICR-5298 SANDb61562 NUREG'CR4691 VO)PARAMETER IE 193 NUREG/CR 5302 SAND 862084 NUREGICR4550 V01 R1

PARAMETE R IE 197 NUREG /CR4306 SAND 862084 NUREG/CA 4%0 V4R1P3

PARAME7ER IE 198 NUREG/CR 5307 SAND 862084 NUREG/CR 4550 V341P2

PARAMETE R IE199 NURE G/CR'5308 SANDB6-2084 NURE G/CR-4550 V341P1NUREG/CR-2850 V09 SANDe6-2084 NUR$ G'CH-4%0 V3R tP3Pf0 4221

PNb5210 N JREG /CR 3950 V06 SAND 66 2064NURiGiCR 4%0 V5 rip 2

PNb5711 NUREG/CR4469 Vue SAND 842084 NURE GICR4MO V5R t P t

PNL-5711 NURE G/CR4469 V09 SAND 662tG8 NUREG/GR,4 Tw4

E PNL 5711NUREG/CR4469 V10 SAND 88 2703 NUREG/CR 5211

PNL 6119 NURE G /CA-4882 SAND 68 2940 NUREG/CR 5253

PNb6196 NUREG/CR-4908 SAND 66-3020 NUREO/CR 5256

PNL. 6446 NUREG/CR 5117 SAND 88-3093 NUREG/CR 5262

PNL4911 NUREG/CR 5386 SANt*8-3102 NUREG/CR 4640

PNb6931 NUREG!CR 5337 SAND 88 3476 NUREG/CR 5316

PNL.7154 NUREG/CR 5169 SAND 69-1135 NUREG/CR 5373

PNL.7190 NURf G/CR 5400 V01 SAND 691302 NUREGICR4381

PNL 7191 NURt G/CR 549t SAND 691432 NUREG/CR 5393

NUREG/CR4512 DAF FC SANDUS-1 % 7 NUREG'OR 5398PNL.7212PNb7217 NUREG/CR 5516 SANDS 9-1650 NUREG/CR 5405

PNL-7239 NUREG/C4 5547 SAND 891821 NUREG/CR 5411

PNb7276 NUREG/CR 5540 SAND 89-2368 NURLG/CA M60

PNL 7285 NUREG/CR 5548 SANDBS 2369 NUREG/CR 5461

PNb 73.'8 NURE GICR4566 SAND 89 2509 NUREGiCR 5453 VOS

PNL 7339 NUREG/CA5579 SAND 89 2603 NUREG/CR 5476

PNb7349 NUREG/CR 5617 SAND 89-3060 NURt G /CR-5517

PNb7351 NUREG/CR-5616 SAND 904127 NUREG/CR-5521

PNb7356 NUREG/CR 5523 SAND 90-0375 NUREG/CR 5532

PNb7445 NUREG/CR-5631 SAND 904375 NUREG/0H $453 VOS

PNb7476 NUREG/CR-5653 SAND 90-0756 NUREG/CR 5545

SAIC.89/ t t 48 NUREG /CR-5622 SAND 941102 NURE/s/CR 5586

SAC 89 /1641 NUREG/CR 5640 SAND 90-7080 NUREG/CR 5590

SAce9/1744 NUREG/CR 5510 SFTH/LEML88-138 NUREG/lA 0023 V02

SAC 90/1054 NUREGICR 5659 SETH/LE MiB8138 NUREG/6A4023 V01

SA C 90/1130 NUREG/CR 5436 V02 STUDSvikNPB7128 NUREG/lA4033

SA C 90/1130 NUREG/CR 5436 VOI UCfD 20674 NUREG/CR4554 V07

SAND 80-1429 NUREG/C%1667 UCID 206 /4 NURE G/CR-4554 V06

SAND 85-7185 NUREGICR4214 001 Pl UCID21831 NORFG/CR 5506

SAND 86-1030 NUREG/CR4668 UCRuiD 104845 NUREGICA 5644

Personal Author Index

This index lists the personal authors of NRC staff, contractor, and international agreementreports in alphabetical order Each name is followed by the NUREG number and the title ofthe report (s) prepared by the author, if further information is needed, refer to the main cita-tion by the NUREG number. i

|

ADAMSJ. ANGLINJ.M.NUREGrCR-4753 W3. CA NADIAN SEISMC AGREEMEN7. Annual NUREG/CR4753 V03. CANADIAN SEISMC AGREEMENT AnnualReport 1967 1968. Neport 1967 1988INTIEG/CR4753 V04 CANADIAN SEISMC AGREEMENTAnnual NURE'UCR471L3 V04. CANADIAN SEISMC AGREEMENT AnrwalReport 198814B9 Report 1968 1989

ALE X ANDER,DJ. APOSTOLAKis,G.NUREG/CR M51: CRACK-ARREST BEHAVOR IN SEN WIDC PLATES NUREG 1420. SPECIAL COMMITTEE REVIEW OF THE NUCLEAR 'IEG-OF LOW UPPER SHELF BASE METAL TESTED UNDER NONISOTH- ULATORY COMMISSON'S SEVERE ACCOENT RISKS REPORTiRMAL CONDITONS: WP 2 SERIES. (NUREG-1150)

ALLEN,EJ. APPtGNANI,P.NUREG/lA4011: TRAC-PFI/ MOO 1 POST. TEST CALCULATONS OF NUREG/CR 5436 V01: THF DEVELOPMENT AND EVALVATON OF |THE OECD LOFT EXPERIMENT LP.SB 1.NUREG/lA4022 TRAC-PFI/ MOD 1 POST TEST CALCULATIONS OF PROGRAMMATIC PERFORMANCE INDCATORS ASSOCIATED WITH j

THE OECD LOFT EXPERIMENT LP-SB-3. MAINTENANCE AT NUCLEAR POWER PLANTS Men Report I

NUREG/CR-5436 V02 THE DEVELOPMENT AND EVALUATON OFALLEN,J.A. PROGRAMMATC PERFORMANCE INDCATORS ASSOCIATED WITH

NUREG/CR-5436. BASIC CONSIDERATONS IN PREDICTING ERROR JAINTENANCE AT NUCLE.AR POWER PLANTS Appendees

PROBABILITIES IN HUMAN TASK PERFORMANCE. ARNOLD W.D.

NUREG/CR 5463 EFFE"TS OF MINERALOGY ON SORPTON OFREG /dR-5373 A DEMONSTRATON EXPERtMENT Or STEAM-

DRIVEN, HIGH-PRESSUPE MELT EJECTION The HIPS-10S Test AR THUR.R.C.

ALLEN.R.P. NUREG/CR 5548 REVIEW OF GEOCHEMICAL PROCESSES ANDNURFG/CR-5491: SHIPPINOPORT STATON AGING EVALUATON CODE 3 FOR ASSESSMENT OF RADONUCLIOE MIGRATION PO-

TENTIAL AT COMMERCIAL LLW SITESALLENSPACHf.

NUREG-1214 ROS: HISTORICAL DATA SUMMARY OF THE SYSTEMAT- gggggg y/CR-5449 DETERMINATON OF THE NEUTRON AND GAMMANUREGINU EG 12 06 H T L AA UM OF THE SYSTEMAT.

C ASSESSMENT OF LCENSEE PERFORMANCE A Olt LNG E REACTORNUREG/CR4530- ANALYSIS OF H B. ROplNSON PWR VESSEL

ALUSON,0.P.FLUENCE FOR CYCLE 10 UTILI2ING PARTIAL LENGTH SHIELD AS.

NUREG-1409 BACKFITTING GUIDELINES SEMBUES

ALZHEIMER,J.M. AULUCK,R.

NUREG/CR-5579 VALUE/ IMPACT ASSESSMENT OF JET IMPlNGE. NUREG-1232 V04 SAFETY EVALUATION REPORT ON TENNESSEEMENT LOADS AND PIPE. TOP!PE IMPACT DAMAGE. Revised Metg VALLEY AUTHORITY: WATTS BAR NUCLEAR PERFORMANCEods And Cntena. PLAN.

A*f AR,A.S. 8AILELWJ.NUREG/CR-473! V02: RESIDUAL LIFE ASSESSMENT OF MAJOR NUREG/CR-3950 V06 FUEL PERFORMANCE ANNUAL REPORT FOR

LIGHT WATER REACTOR COMPONENTS OVERVIEW, 1968.

AMICK D, BAKER,0.A.NUREG/CR.5813. PALEOLIQUEFACTION FEATURES ALONG THE AT, NUREG/CR-2850 V00 POPULATION DOSE COMMITMENTS DUE TOLANTC SEABOARD.

RADIOACTIVE RELEASES FROM NUCLEAR POWER PLANT SITESIN 1967.AMOS,C.N.

NUREG/CR4551 V2 RIP 1: EVALUATION OF SEVERE ACCIDENT BAKER,W1RISKS: QUANTIFICATION OF MAJOR INPUT PARAMETERS Empert NUREGICA-5369 THE SEISMIC CATEGORY I STRUCTURES PRO-Opmion Ehertation On in Vessel issues. GRAM RESULTS FOR FY 1987.

NUREG/CR 4551 V6A t Pl: EVALUATON OF SEVERE ACCOENT NUREG/CR 5487. STATC LOAD CYCLE TESTING OF A LOW ASPECT.RISKS GRANO GULF. UNIT 1.Mac Report RATIO FOUR-INCH WALL,TRG TYPE STRUCTURE TRG-5-4NUREG/CR4551 V6R1P2 EVALUATON OF SEVERE ACCOENT (10.056).

RISKS. GRAND GULF. UNIT 1. Appendcas.NUREG/CR 5533. STATIC LOAD CYCLE TESTING OF A VERY LOW-

ANDERSONJ.L. ASPECT RATO SIX INCH WALL TRG-TYPE STRUCTURE TRG-6-6(0 27. 0.50)

HUREG/CR-5374 $UMMARY OF INADEQUATE CORE COOLING IN-STRUMENTATON FOR UNrTED STATES NUCLEAR POWER B AK R,M.H.PLANTS.

NUREG/CR-4731 V02. RESOUAL LIFE ASSESSMENT OF MAJO7LIGHT W ATER REACTOR COMPONENTS . OVERVIEW

NUREG/CR-4753 V03. CANADIAN SEISMC AGREEMENT Annual BALOW!%C.A.Report 1987 1988.

NUREG/CR 5409. NEtJfRON EXPOSURE PARAMETERS FOR THENUREG/CR 4753 V04 CANADIAN SEISMIC AGREEMENT. Annual METALLURGICAL TEST SPECIMENS IN THE SIXTH HEAVY SEC.Report 1988-1983TION STEEL IRRADIAT)ON SERIES.

59

- - __ - - - _.-.. - - - _.- ..- -- - - - - - _. -

60- Personal Author index.

SEZLE R.P.

SAMPTD7LM.C.C. ' . . -NUREG/C45579 VALUE/ IMPACT ASSES $ MENT OF JET IMPINGE.NUREG/CR 5627: ALTERNATE MODAL COMBINATION METHODS IN

MENT LOADS AND PIPE.TO PtPE IMPACT DAMAGERevised Metn. RESPONSE SPECTRUM ANALYSIS

. 0:.s And Cnteria. SILLINGTON,L

SANDYOPADHYAY NUREGICR 5613. PALEOUQUEF ACTON FEATURES ALONG THE AT.NUREG/CR 4659 V03 SEISMIC FRAGILITY OF NUCLEAR POWER LANTIC SEABOARD

PLANT COMPONENTS (PHASE ll).Switchgoer, I&C Panees (NSSS)WRKHOFERI.H.And Relays '

NUREG 1420; SPECIAL COMMITTEE REVIEW OF THE NUCLEAR REG-I ^ "

NU G/tA 0032- ASSESSMf NT OF RELAP5/ MOD 2 CYCLE 36.04 RE 5'- USING LOFT LARGE BREAK EXPERIMENT L2 5

MELER,E -gggg,gg NUREG/CR4545: VICTORLA A MECHANISTIC MODEL OF RADONU.,

NUREG/CR-5450- HIG4 TEMPERATURE CRACK ARREST TESTS CLOE BEHAVOR IN Th' REACTOR COOLANT SYSTEM UNDERUSING 152 MM-THICK SEN WCE Pt.ATES OF LOW. UPPER-SHELF SEVERE ACCIDENT CONDITIONS-BASE MATERtAL: TESTS WP 2 2 ANC WP 2 6

.

NUREG/CRM51: CRACK ARREST DEHAVIOR IN SEN WOE Pt.ATES ' SLAKE.A.A' OF LOW. UPPER-SHELF BASE METAL TESTED UNDER NONISOTH- NUREG/CR4674 V09 PRECURSORS TO POTENTIAL SEVERE COREERMAL CONDITONS:WP 2 SERIES. DAMIGE ACCIDENTS 1988 A STATUS REPORT. Main Report And Ap-

pendix ABAUMAW, NUREG/CR 4674 V10 PRECURSORS TO POTENTIAL SEVERE CORENUREG/CP.0110: PROCEEDINGS OF THE INTERNATONAL WORK. DAMAGE ACCOENTS:1968 , STATUS REPORT Appentimes B And

SHOP ON NEW DEVELOPMENTS IN OCCUl" TONAL DOSE CON.. TROL AND ALARA IMPLEMENTATION AT NUCLEAR FOWER

C.

PLANTS AND SIMILAR FACILITIESNUREG/CR 3469 V05: OCCUPATIONAL DOSE REDUCTION AT NU-

BLANFORDAH.NUREG/CR 5596 UNSATURATED F AACTURED ROCK CHARACTER.

Ct. EAR POWER PLANTS. ANNOTATEC BIBLOGRAPHY OF SELECT. 12ATON METHODS ANO DATA SETS AT THE APACHE LEAP TUFFED READINGS IN RADlATION PROTECTION AND ALARA SITE.

DEAUDOIN.B.F.NUREG/C44731 V02: RESOUAL UFE ASSESSMENT OF MAJOR

BLOSE,R.L

UGHT W A TER REACTOR COMPONENTS . OVERVIEW. NUREG/C44704 EXPERIMENTAL RESULTS OF CORE (X)NCRETEINTERACTIONS USING MOLTEN STEEL WITH ZlRCONIUM

DEAVE RS,J.A.NUREG/C45435. ENVIRONMENTAL EFFECTS ON CORROGION IN pOHN,g.p,

THE TUFF REPOSITORY, NUREQ/CR-4550 V'intP3. ANALYSIS OF CORE DAMAGE FREQUEN-CY: SURRY POWER STATION UNIT 1 EXTERNAL EVENTS

NUREG/CR-4550 V4 RIP 3. ANALYSIS OF CORE DAMAGE FRCOVEN-DEDFORDA

NUREG/CR 5635. CELLULAR AND MOLECUt.AR RESEARCHREDUCE UNCERTAINTIES IN ESTIMATES OF HEALTH EFFE'{,NUREG/CR-4540 PROCEDURES FOR THE EXTERNAL EVENT CORE

.

CY: PEACH BOTTOM. UNIT 2 EXTERNAL EVENTSa

FROM LOW. LEVEL RADtATON A Fennuty Study DAMAGE FREQUENCY ANALYSES MR NUREG-11%

DEERS.0,H- NO,EANUREG/C44639 V4P1R2: NUCLEAR COMPUTERIZED UBRARY FOR NUREG/CR4211: UNCERTAINTIES ASSOCIATEO WfTH PERFORM.

ASSESSING REACTOR REUABluTY (NUCLARR) User's Guide Part 1: ANCE ASSESSMENT OF HIGH-LEVEL RADIOACTIVE WASTEOvemew Of NUCLARR Data Retneval REPOSITORIES A Summary Report

NUREGIC44639 V4P2R2- NUCLEAR COMPUTERIZED LIBRARY FOR NUREG/C45256: COMPONENTS OF AN OVERALL l'ERFORMANCEASSESSING REACTOR REuABILffY (NUCLARR). User's Guide Part 2 ASSESSMENT METHOOOLOGY.Otede To Operatwa NUREG/C45411 EUCITATION & USE OF EXPERY JUDGMENI |N

NUREG/CR-4639 V4P3R2 NUCLEAR COMPUTERIZED LfBRARY FOR PERFORMANCE ASSESSMENT FOR HIGH-LEVEt, RADCACTIVEASSESSING REACTOR REUABILITY (NUCLARALUser's Guide Part 3: WASTE REPOSITORIES.NUCLARR Setem Descrption. NUREG/C45521: USE OF PERFORMANCE ASSESSMENT IN AS-

SESSING COMPUANCE WITH THE CONTAINMENT REQUIRE-BENJAWN.SA

NvREGIC45635: CELLULAR AND MOLECULAR RESEARCH TO MENTS IN 40 CFR PART 191.

REDUCE UNCERTAINTIES IN ESTIMATES OF HEALTH EFFECTS 800KERAM. -FROM LOW. LEVEL RADIATION A Feasuty Study.NUREGIC46424. EUCITING AND ANALYZING EXPERT 4

JUDGEMENT.A Practical GuideSE NNETT,5.C.NUREGIOR 5629. MiCROEARTHOUAKES IN KANSAS AND NEBRAS- 90WE N.W.M.KA 19T71969 Final Report

NUREG/C45117. STEAM GENERATOR TUBE INTEGRITY PROGRAM /#

NURE /C 53A9 THE SEISMIC CATEGORY l STRUCTURES PRO-GRAM RESULTS FOR FY f 987.

NUREG/C45487: STATIC LOAD CYCLE TESTING OF A LOW. ASPECT. DOWERMAN.B.S.RATO FOURINCH WALL.TRG. TYPE -STRUCTURE YRG-5 4 NUREG/C45574: DETERMINATON OF THE CHEMICAL FORM OF

TRITIUM IN SELF. LUMINOUS SIGNS/CkS533: STATIC LOAD CYCLE TESTING OF A VERY TOW-N

ASPECT-RATO SIX INCH WALL- TAG TYPE STRUCTURE TRG 64 BRADLEY,EANUREGICR-5117. STEAM GENERATOR TUBE INTEGRITY PROGRAM / '(0 27. 0,50L

STEAM GENERATOR GROUP PROJECT. Final Project SummarySERTUCICAC. N'P 't

NUREG/CR 4550 V3RIPt: ANALYSIS OF CORE' DAMAGEFREQUENCY.SURRY, UNIT 1,1NTERNAL EVENTS BREEDING *RA

. NUREG/C44550 V3 RIP 2: ANALYSIS OF CORE DAMAGE FREQUEN- NUREG/CR4551 - V2 RIP 1: EVALUATON OF SEVERE ACCIDENTCY SURRY. UNIT 1 INTERNAL EVENTS APPENDICEg RISKS: QUANTIFICATION OF MAJOR INPUT PARAMETERS Export

NUREG/C44550 V5AIP1: ANALYSIS OF CORF dam.\GE FREQUEN. Opirwon Elettaton On in. Vessel lasues.-

HUREG/CR4550 V581P2: ANALYSIS OF CORE DAMAGE FREQUESNUREG/CR 4551 V3 RIP 1: EVALUATION OF SEVERE ACCIDENTCY: SEQUOYAH. UNIT 1. INTERNAL EVENTS

RISKS: SURRY UNfT 1.Mam ReportCY; SEQUOYAH, UNIT t,1NTERNAL EVENTS APPENDICES. NUREG/C44551 V3 RIP 2: EVALUATION OF SEVERE ACCIDENT

RISKS SURRY UNIT 1. Appernce-

NUREG/C45560- AGING OF NUCLEAR PLANT RESISTANCE TEM-NUREG/C44551 V4 RIP 1: E' " oATION OF SEVERE ACCIDENTBEVERLY,D.D. .

RISKS: PEACH DOTTOM.UPT r. Main ReportPERATURE DETECTORS.

- - - - - - - _ - _ _ _ _ - __ -. - - - . .- - . , -, , ,- . - . -

_._ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ . _ _. ,

_

_ Personal Author index 61

NUREG/CR4551 V481P2. EVALUATION OF SEVERE ACCOENT - DUESCHER.S.J.RISKS: PEACH DOTTOM. UNIT 2. Apperdces -

NUREG/CR 4731 V02 RESOUAL LIFE ASSESSMENT OF MAJOR -.NUREG/CR-4551 V5R1P1: EVALUATION OF SEVERE ACCOENT LIGHT WATER REACTOR COMPONENTS . OVERVIEW.*

RISKS SEOVOYAKUNIT l Main Report.- NUREG/CR4551 V5R tP2: EVALUATON OF SEVERE ACCIDENT- SUFFARDI.LC. .

. . .

- RISKS' SEQUOYAH.UNff 11 AMes. NUREG/CR4551 V6AIP1: EVALUATON OF SEVERE ACCOENT NUREG/CR 543A BASIC CONSIDERATONS IN PREDOTING ERROR.

PROBABlUTIES IN HUMAN TASK PERFORMANCf.RISKS GRAND GULF, UNIT 1 Men ReportNUREG/CR4551 V6R182: EVALUATION OF SEVERE ACCOENT

RISKS: GRAND GULF VNIT 1. Appereces DURULE,0.s

NUREG/CR.5436 Yot; THE DEVELOPMENT AND EVALUATION OFMESLER,E. PROGRAMMATIC PERFORMANCE INDtCATORS ASSOCIATED WITH

NURFG/CR-5523. DEVELOPMENT OF AN INFILTRATION EVALUA. MAINTENANCE AT NUCLEAR POWER PLANTS Men ReportTON METHOOOLCGY FOR LOW 4EVEL WASTE SHALLOW LAND NUREG/CR 5436 V02: THE DEVELOPMENT AND EVALUATON OFBURIAL SfTES~ PROGRAMMATIC PERFORMANCE INOICATORS ASSOCIATED WITH

MAINTENANCE' AT NLOLEAR POWER PLANTS Apperdee6DRIOGS.RC.

NUREG/CR 539t SURVEY OF ST ATE AND TRIBAL EMERGENCY RE. CAMP.A.LSPONSE CAPABlVTIES FOR RADOLOGICA1 TRANSPORTATION NUREG/CR-4550 V01 R1: ANALYSIS OF CORE DAMAGE FREQUEN-INCIDECS. CY: INTERNAL EVENTS METHODOLOGY.

DROADHEAD,4.L- CAMP 9 ELL,0,NUREGICR 5468. GADS. A MULTIDIMENSIONAL POINT AERNEL NUREG/CR 5460 A CAUSE DEFENSE APPROACH TO THE UNDER.ANALYSIS MODULE.

STANDING AND ANALYSIS OF COMMON CAUSE FAILURES.BROCKMANN).E. CAMPSELL,J.E.

NUREG/CR4794- EXPER:ML NfAL RESULTS OF CORE. CONCRETENUREG/CR1667: AISK METHOOOLOGY FOR GEOLOGO DISPOSALINTERACTIONS USING mot. TEN STEEL WITH ZlRCONtVM.

OF RADIOACTIVE WASTE. Scenano Selectkin ProcedureMOMILEY,P. '

NUREG/CR.5437; ORGANIZATON AND SAFETY IN NUCLEAR POWER CANNONAPLANTS. NUREG/CR.5613. PALEOLIQUEF ACTION FEATURES ALONG THE AT.

LANTO SEABOARD.MOOEM

NUREG-0713 V09 OCCUPATONAL RADIATION EXPOSURE AT COM- CARL 80NI*R.MERCIAL NUCLEAR POWER REACTORS AND OTHER FACluTIES NUREG/CR 5273 V04' SCOAP/RELAPS/ MOO 2 CODE

' 1987.1wentieth Annuel Report MANUAL. VOLUME 4 MATPRO . A UDRARY OF MATERIALS PROP.ERTIES FOR LIGHT. WATER. REACTOR ACCIDENT ANALYSIS.

DROSSEAU.DA NUREG/CR 5376 QUALITY ASSURANCE AND VERIFICATON OF THENUREG/CR4550 V4R1P3: ANALYSIS OF CORE DAMAGE FREQUEN. MACCS CODE. Versson 11

CY: PEACH BOTTOM. UNIT 2 EXTERNAL EVENTS.- NUREG/CR-5398; TECHNICAL BASIS FOR REYlEW OF HIG4 LEVEL CARNES.BA

WASTE REPOSITORY MODEUNO. NUREG/CR4704 V03 RELATIVE DOLOGICAL EFFECTIVENESS (R8E)BROWN.Ci OF FISSION NEUTRONS AND GAMMA RAYS AT OCCUPATIONAL

NU6EG 1404. UCENSEE USE OF TACTICAL EXERCISE RESULTSEXPOSURE LEVELS Studies On The Gross And Microscopic Pelhoto-gy 00eerved At Death Of Ma:e Esposed To 60 Equal Once-WeeMyDonos Of Fission.

NUREG/CRS386. BASIS FOR SNUBBER AGING RESEARCH NUCLE. CARTER,R.J.AR PLANT AGING RESEARCH PROGRAM.

NUREG/CR5439 HUMAN FACTORS ISSUES ASSOCIATED WITH AD-MOWN,0 VANCED INSTRUMENTATION AND CONTROLS TECHNOLOGIES IN

NUREG/LA4012: RELAPS/ MOO 2 CALCULATIONS OF OECD LOFTNUCLEAR PLANTS.

N / RELAPS/ MOD 2 CALCULATIONS OF OECD. LOFT CASADkUAEG 5404 V01: AUXILIARY FEEDWATER SYSTEM AGING

STUOY.MOWN.J.5.

NUREG/CR5579: VALUE/lMPACT ASSESSMENT OF JET IMPtNGE. CASE.F.LMENT LOADS AND PIPE.TOPIPE (MPACT DAMAGE. Revised Meth. NUREG/CR5463: EFFECTS OF MINERALOGY ON SORPTION OFcds And Critene. STRONTitfM AND CESIUM ONTO CAUCO HILLS TUFF.

MOWN,5 R.. - CAV ALLIN,C.

NUREG/CR4550 V5 HIP 1: ANALYSl$ OF CORE DAMAGE FREQUEN- NUREG/CR5640 OVERVIEW AND COMFARISON OF U S. COMMER-- CY: SEQUOYAH. UNIT IJNTERNAL EVENTS-NUREG/CR4550 V5 RIP 2; ANALYSIS OF CORE DAMAGE FREQUEN- CIAL NUCLEAR POWER PLANTS.Huc6 ear Power Plant System Sour.

cebook.CY: SEQUOYAH. UNIT 1.lNTERNAL EVENTS APPENDICES.

DROWN T.D.CHA,Y.S.

NUREGICR 5649 V01: COMMIX tC: A THREE DIMENSIONAL TRAN-. NUREG/CR4551 V2R tP1: EVALUATON OF SEVERE ACCOENTRISKS: QUANTIFICATON OF MAJOR tNPUT PARAMETERS Expert SIENT SINGLE. PHASE COMPUTER PROGRAM FOR THERMAL HY.Opevon Elicitaten On in Vessed issues DRAUUC ANALYSIS OF SINGLE. COMPONENT AND MULTICOM-

NUREG/CR4551 V6 RIP 1: EVALUATON OF SEVERE ACCOENT PONENT ENGINEERING SYSTEMS Equahone And Numencs -NUREGICR5849 V02. COMMILIC: A THREE DIMENSIONAL TRAN-

AbATNU G 5 Y OF SEVERE ACCOENT SIENT SINGLE PHASE COMPJTER PROGRAM FOR THERMAL HY.~ RISKS: GRAND JULF, UNIT 1. Apperecee' ORAUUC ANALYSIS OF SINGLE. COMPONENT AND MULTICOM.

PONENT ENGINEERING SYSTEMAUser's GuMe And HanualBUCCAFURNI,A.NUREG/CR5273 V04 ~ SCOAP/RELAP5/ MOO 2 CODE CHAMBERS.R.

MANUALVOLUME 4 MATPRO . A UORARY OF MATERIALS PROP. NUREG/C45273 V04 SCOAP/RELAPS/ MOO 2 CODEERTIES FOR UGHT.WATERREACTOR ACCIDENT ANALYS4S, MANUAL VOLUME 4 MATPRO + A UDRARY OF MATERIALS PROP.SUONITZAJ. ERTIES FOR LIGHT WATERREACTOR ACCOENT ANALYSIS.

NUREG/CH 5447. DEPRESSUR12ATION AS AN ACCIDENT MANAGE.04UREG/C4d477: AN EVALUATION OF THE REUABILITY AND USE. MENT STRATEGY TO M: nim 12E THE CONSEQUENCES OF DIRECTFULNESS OF EXTERNAL. INITIATOR PRA METHOOOLOGIES. CONTAINMENT HEATING

,

. . _ _ - --r ,.- +<*-m e 'V9-"Om WW ~ ~ * * * *~

-. - - -- -- . _ . - - - - - --- - -- .- - - . .

62 Personal Author Index

CHUNG).CHANIN.D.L

NUP8iG/CR4691 V01: MELCOR ACCIDENT CONSEQUENCE CODE NUREG/CR 5637 GENERC RISK INSIGHTS FOR WESTINGHOUSE

SkTEM (MACCS) Volume 1 Users Guide AND COMBUSTON ENGINEERING PRESSURIZED WATER REAC-NUREG/CR4691 V02: MELCOR ACCOENT CONSEQUENCE CODE TORS

SYSTEM (MACCS) Volume ? Model DescrqteonNUREG/CR 4691 V03- met.COR ACCIDEm CONSEOVENCE CODE CLARK.R.A.

SYSTEM (MACCS) Volume 3 Programmer's Reference Manual- NURECC8' . . .r' STE AM GENERATOR TUBE INTEGRrTY PROGRAM /STED GENERATOR GROUP PROJECT. Final Protect Sumnwy

CHAO.K..&.NUREu/CP 0109 PROCEEDINGS OF THt: SEMINAR ON LEAK +

N'PO't

BEFORE.OREAK Further Deve4opments in Regulatory Poloes And CLETCHERJ.W.b"PP D "'# NUREG/CR-4674 V09 PRECURSORS TO POTENTIAL SEVERE CORE

DAM AGE ACCIDENTS 1988 A ST ATUS REPORT Main Report And AD-CHEVECON,R.D. perdu A-

NUREG/CR 5473: INCLUSON OF UNSTABLE DUCTILE TEARING AND NOREG/CR4674 V10 PRECURSOR $ TO POTENTIAL SEVERE COREEXTRAPOLATED CRACOARREST TOUGHNESS DATA IN PWR DAMAGE ACCOENTS 1988 A STATUS REPORT.Apperdmes B AndVESSEL INTEGRITY ASSESSMENT. C

NUREG/CR-467 6 Vit PRECURSORS TO POTENTIAL SEVERE CORECHIEN.T.M-NUREGICR 5649 V01- CCWM%1C. A THREE DiMENSONAL TRAN. DAMAGE WlDENTS 1989 A STATUS REPORT Maan Report And Ap-

STENT SINGLE. PHASE COVPUTER PROGRAM FOR 1HERMAL HY- penda A-

DRAUUC ANALYSIS OF SINGLE COMPONENT AND MULTICOM- NUREG'CR4674 V12: PRECURSORS TO POTENTIAL SEVERE CORE

OdL TRAN-Nb /CR 64 2 CO Mix I H ED NSIENT SINGLE PHASE COMPUTER PROGRAM FOR THERMAL HY.

'

DRAUUC ANALYSIS Or S:NGLE COMPONENT AND MULTICOM- COLEY.J.

PONENT ENGINEERING SYSTEMS Users Guide And Manual- NUREG 1425 WELDING AND NONDESTRUCTIVE EXAMINATIONISSUES AT SEADROOK NUCLEAR ST ATON An independent Rem

CHILDS,R.L Team ReportNUREGICR 5530 ANALYSIS OF HB ROBINSON PWR VESSEL

FLUENCE FOR CYCLE 10 UTILIZlNG PARTIAL LENGTH SHIELD AS- COLLINS).LSEMBUES' NUREG/CR 5480: DATA SUMMARY REPORT FOR FISSON PRODUCT

RELEASE TEST V13CHINN.D.J.

NUREG/CR4554 V06. SCANS (SHIPPING CASK ANALYSIS SYSTEM) A CONKUN'J O'MICROCOMPUTER BASED ANALYSIS SYSTEM FOR SHIPPING NUREG/CR-5514. MODELING AND PERFORMANCE OF THE MHTGRCASK DESIGN REVIEW. Volume 6 Theory Manual Bucung Of Cacu. REACTOR CAV1TY COOUNG SYSTEM.tar Cyhndncal Sheus.

CONLE Y,D.A.CHMIELEWSKI,&,

NUREG/CR 6273 V04. SCDAP/RELAP5/ MOO 2 CODE NUREGICR4731 V02- RESIDUAL LIFE ASSESSMENT OF MAJOR

MANUALVOLUME 4 MATPRO . A USRARY OF MATERIALS PROP. UGHT W ATER REACTOR COMPONENTS OVERVIEW.

ERTIES FOR UGHT WATER-REACTOR ACCIDENT ANALYSIS. CONNELLY,E.M.NUREG/CR-5568 V01: INDUSTRY BASED PERFORMANCE INDICA.

CHOPRA.O.K 4744 V03 NS- LONG TERM EMBRITTLEMENT OF CASTTORS FOR NUCLEAR POWER PLANTS Phase 1 Report June 1989NUREG/CR

DUPLEX STAINLESS r. iEELS IN LWR SYSTEMS Semannua! February 1990.Report. October 1987. Marcn 1988

NUREG/CR4744 V03 N2 LONG TERM EMBRITTLEMENT OF CAST CONRAN.J.H.DUPLEX STAINLESS STEELS IN LWR SYSTEMS $enwannual NUREG 1400. BACAFITTING GUIDEUNES.ReportApnkSeptember 1988

NUREG/CR-5385. INITIAL ASSESSMENT OF THE MECHANIS64S AND COPINGER,0.A.

SIGNIFICANCE OF LOW TEMPERATURE EMBRITTLEMENT OF NUREG/CR-4874 V11: FRECURSORS TO POTENTIAL SEVERE CORECAST ST AINLESS STEELS IN LWR SYSTEMS. DAMAGE ACCIDENTS 1989 A ST ATUS REPORT Main Report And Ap-

D'* A-CHOWN.N M NUREG/CR-4674 V12- PRECURSORS TO POTENTIAL SEVERE CORE

NUREGlCR 5545 VICTORIA: A MECHANISTIC MODEL OF RADIONU. DAMAGE ACCIDENTS 1989 A STATUS REPORT.Appereces D AndCUDE BEHAVOR IN THE REACTOR COOLANT SYSTEM UNDER OSEVERE ACCIDENT CONDITONS

COPUS,E.R.CHU,M.S.V,

NUREG/CR-5453 V05 BACKGROUND INFORMATON FOR THE DE.NUREG/CR 4794 EXPERIMENTAL RESULTS OF CORE CONCRETE

VELOPMENT OF A LOW LEVEL WASTE PERFORMANCE ASSESS.INTERACTIONS USING MOLTEN STEEL WITH ZlRCONIUM

MENT METHODOLOGY. Computer Code implementatpon And Assess-CORUGEDOJ.J.

NUREG/CR 5532: A PERFORMANCE ASSESSMENT METHODOLOGYNUREG/CR-5515- UGHT WATER REACTOR PRESWRE ISOLATIONment

FOR LOW-LEVEL W ASTE FACILfilES VALVE PERFORMANCE TESTING

CHUANO.Y. CORWIN.W.R.

NUREG/CR 5432 LABORATORY ANALYSIS OF FLUlO FLOW ANO NUREG/CR-5511: IRRADIATION EFFECTS ON STRENGTH ANDSOLUTE TRANSPORT THROUGH A VARIAOLY SATURATED FRAC. TOUGHNESS OF THREE-WIRE SERIES ARC STAINLESS STEEtTURE EMBEDOED IN POROUS TUFF. WELD OVERLAY CLADDING

NUREG/CR-5584. RESULTS OF CRACK ARREST TESTS ON TWO IR-CHONG.B D RADIATED HIGH COPPER WELDS,

NUREGnd-0030: ASSESSMENT OF RELAP5/ MOO 2 CODE USING NUHEG/CH 5591 V01 N1: HEAVY.SECTION STEEL IRRADtATIONLOSS OF OFFSITE POWER TRANSIENT DATA OF KNU #1 PLANT PROGRAM Serrmannua: Progress Report For October 1989 March

NUREG/lA 0031. ICAP ASSESSMENT OF RELAP5/ MOO 2. CYCLE 1990.36.05 AGAINST LOFT SMALL DREAK EXPERIMENT L3 7

COSTANTINO,C.CHUNO.H.M.

NUREG/CR 4744 V03 N1: LONG TERM EMBRrTTI.EMENT OF CASTNUREG/CR-5588 V01: CARES (COMPUTER ANALYSIS FOR RAPID

DUPLEX STAINLESS STFELS IN LWR SYSTEMS Semiannual EVALUATON CF STRUCTURES) VERSION 10 Seisme

Module ihooretu:al Manual.Report. October 1987. March 1968NUREG/CR4744 V03 N2: LONG TERM EMBRITTLEMENT OF CAST NUREG/CR-5588 V02. CARES (COMPUTER ANALYSIS FOR RAPID

DUPLEA STAINLESS STEELS IN LWR SYSTEMS Semannual EVALUATON OF STRUCTURES) VER$10N 1.0SesmeModule Utst's Manual.Report.Apr& September 1988

|

|

)

i

i

Personal Author Index 63 I!

' NUREO/C45568 V03 CARES (COMPUTER ANALYSIS FOR RAPID DAYlS,E.C.EVALUATON OF STRUCTURES) VERSON 10.SeistNc NUREO/CR 5229 V02 TMI 2 [PICOR41 RESIN /UNEfi INASilGATiONModule Sample Problems.

LOW LEVEL WASTE DATA BASE DEVELOPMENT PROGRAM FORFISCAL YEAR 1909 Annual Report

NUREO.1363 V02 ATOMIC SAFETY AND LICENSING BOARD PANEL DAyts,P A.ANNUAL REPORT FISCAL YKAR 1989-

NUREO/CR 5211: UNCERTAINTIES ASSOCIATED WITH PERFORFCRAMOND,WA. ANCE - ASSESSMENT - OF HCH-LEVEL RADIOACTIVE WASTE

NUREO/CR 4550 V01 R1: ANALYSIS OF CORE DAMAGF FREQUEN- REPOSITORIES A Summary Report= . CY; INTERNAL FVENTS METHOOOLOGY. NUREO/CR 525& COMPONENTS OF AN OVERALL PERFORMANCE

ASSESSMENT METHODOLOGY,

- CRA"WELL.R.M' . NUREO/C45353. A REVIEW OF TECHNIQUES FOR PROPAGATINGNUREO/C41e67; RISK METHODOLOGY FOR GEOLOGIC OISPOSAL DATA AND PARAMETER UNCERTAINTIES IN HIGH4EVEL RADtO-

OF RADIOACTIVE WASTE, Scenano Selection Proce&se ACTIVE WASTE REPOSITORf PERFORMANCE - ASSESSMENTMODELS,

4

CRONENGERO.A.W.-

~ HUREO/CR 5597, IN-VESSEL ZiRCALOY<OxtDATION/ HYDROGEN. DEAN.R.86 -

GENERATION BEHAVOR DURING SEVERE ACCOENTS. NUREO/C44525 CLOSEOUT OF IE DOLLETIN 6443 REFUEUNOCAVITY WATER SEAL

CROUCH,D, NUREO/CR 4661: CLOSEOUT OF IE BULLETIN 85 03 MOTOR. OPE 4- NUREO/CR $527; Al$K SENSITIVITY TO HUMAN ERROR IN THE LA. ATED VALVE COMMON MODE FAILURES DURING PLANT TRArt

,

(SALLE PRA SIENTS DUE TO IMPROPER SWITCH SETTINGS. r

NUREO/CR 5572. AN EVALUATION OF THE EFFECTS OF LOCAL NUREO/CR M'Be CLOSEOUT OF IE BULLETIN 79-17. PIPE CRACKS IN= CONTROL STATION DESIGN CONFIGURATONS ON HUMAN PE4 STAONANT DORATED w ATER SYSTEMS AT PWR PLANTS-

FORMANCE AND NUCLEAR POWER PLANT RISK. NUREO/CR 5209 CLOSCOUT OF IE BULLETIN - 79 23 POTENTIALFAILURE OF EMERGENCY DIESEL OENERATOR FIELD EXC IERCROWLEY,W.TRANSFORMERNUREO-1425; WELDING AND NONDESTRUCTIVE EXAMANATION

NUREO/C45295. CLOSEOUT OF IE COMPUANCE DULLETIN 80-03ISSUES AT SEABROOK NUCLEAR STATON An Independent RNewPOTENTIAL FAILURE OF MULTIPLE ECCS PUMPS DUE TO SINGLETeam ReportFAILURE OF AIROPERATED VALVE IN MINIMUM FLOW RECIRCU-

CULLEN,W.H. LATON UNE. '

- NUREO/CP.0112 V01. PROC'EEDINGS OF THE THIRD INTERNATION-NUREO/CR 5297, CLOSEOUT OF IE BULLETIN 83-05 ASME NUCLEAR

AL ATOMO ENEROY AGENCY SPECIAUSTS' MEETING ON SUB- CODE PUMPS AND SPARE PARTS MANUFACTURED BY THE HAYEW ARD TYLER PVMP COMPANY.CRITICAL CRACK OROWTH Opening Session Ard Tectncal Session

NUREO/CR 6296 CLOSEOUT OF IE BULLETIN 85 00 STEAM BIND.LHeld At Moscow USSR. 14-1 Wo.NUREO/CP 0112 vot PR EDI S OF THE THIRD INTERNATON- ;No or AuxiuAny rgtowAign pyyps

AL ATOMtC ENEROY AGENCY SPECIAUSTS' MEETING ON SUB. NUREO/C45302 CLOSEOUT OF lE DULLETIN 80-10- CONTAMINA-CRITICAL CRACK OROWTH,Tectncal Sessions 11, Ill, And IV Ard TON OF NONRADtOACTIVE SYSTEM AND RESULTING POTENTIAL

FOR UNMONITORED, UNCONTROLLED RELEASE OF RAD 40ACTIV.A w .. - s tons -And Conclusions Sessaan V Held AlITY TO ENVIRONMENT.Moscow, USSR,May 14 17,1990-

NUREO/CR 5306- CLOSEOUT OF IE BULLETIN 7918 AUDI0luTY - !CURRER W PROOLEMS ENCOUNTERED ON EVACUATON OF PERSONNEL

NURE CR 562 ERN AL COMBINATION METHODS IN " ' ^'

NU E C 5 S OF lE dVLLETtN 8002: INADEQUATEOVAUTY ASSURANCE FOR NUCLEAR SUPPLIED EOUiPMENT,

CURTIS,LA- NUREO/C45308. CLOSEOUT OF IE BULLETIN 9015. POSSIBLENUREO/CR-4624 V06: RADIONUCLIDE RELEASE CALCULATIONS LOSS OF EMERGENCY NotifiCATON SYSTEM (ENS) Wl'tH LOSS

FOR SELECTED SEVERE AGCIDENT SCENAROS Supplemental Cal. OF OFFSITE POWER.' " ' * "

DEAN,W,~ CYDULSKis,P. NUREG-1021 R06. OPERATOR LICENSING EXAMINER ST ANDAROS

NUREO/CR4624 V06: RADONUCUDE RELEASE CALCULATONSFOR SELECTED SEVERE ACCIDENT SCENAROS.Suppeemental Cal. DEEDS,W.E,culabona - NUREO/C45478 IMPROVED EDDY. CURRENT INSPECTION FOR

STEAM OENERATOR TUBING Progress Report For January 1965 ToCZAJKOWSK1,C.J. Decemtwa 1987,NUREO/CR-6574- DETERMINATON OF THE CHEMICAL FORM OF -= TRITIUM IN SELF. LUMINOUS SiONS DEFFENSAUGH,J.NUREO/C45576; SURVEY OF BOReC ACID CORROSION OF CARBON

STEEL COMPONENTS IN NUCLEAR PLANTS. NUREO/CR 4469 V06 NONDESTRUCTIVE EXAMINATION (NDE) REU-ABluTy FOR: INSERVICE INSPECTION OF UGHT WATER

DALLMAW REACTORS Sernannual Report,0ctober 1987 March 1988

NUREO/CR5528. AN ASSESSMENT OF BWR MARK ll CONTAINMENT NUREO/CR4469 V09. NONDESTRUCTIVE EXAMINATION (NDE) REU,ADIUTY FOR INSERVICE INSPECTION OF UGHT WATERCHALLENGES, FAILURE MODES, ANO POTENTIAL IMPROVEMENTS

IN PERFORMANCE' REACTORS Semiannual ReportApnl. September 198't

NUREO/C44460 V10 NONDESTRUCTIVE EXAMINAtlON (NDE) REU-- DAMIANO,5. ADIUTY FOR INSERVICE INSPECTION OF UGHT WATER

.NUREO/C45479' CURRENT APPLICATIONS OF VfDRATION MONI- REACTORS Sermannual Report, October 1988. March 1989TORINO AND NEUTRON NOISE ANALYSIS Detection And Analyssa Of NUREO/CR4908 ULTRASONIC INSPECTION RELIABILITY FOR IN-

' Structural Degradaton Of Reactor Vessel Intertale From Operahonal TERORANULAR ' STRESS CORROSidN CRACKS A Round Robin .A 'n0- Study Of The Effects Of Personnel, Processes. Equipment. And CrackQ

Charactenstics.DANIEL,S.L

NUREO/C44550 v3 RIP 3; ANALYSIS OF CORE DAMAGE FREQUEN. DE HAAN,M.S.

CY: SURRY POWER STATION UNIT 1 EXTERNAL EVENTS . NUREO/C45615. LOW. LEVEL RADIOACTIVE WASTE DISPOSAL FA-NUREO/CR 4550 V4R1P3. ANALYSIS OF CORE DAMAGE FREQUEN. CluTY CLOSURE Part L Long-Term Enwonmental Coretions ANoct-. CY. PEACH BOTTOM. UNIT 2 EXTERNAL EVENTS. ino Low. Level Weste Dmposal Site Performance Part !!. Performance

Morwtonrig To Support Regulatory Decmona.

NUREG-1395 DRFT: INDUSTRY PERCEPTONS OF THE IMPACT OF DE MOSS,0.THE U.S. NUCLEAR REOULATORY COMMISSON ON NUCLEAR NUREO!CR 5472 A RISK. BASED REVIEW OF INSTRUMENT AIR SYS-POWER PLANT ACTIVITIES. Draft Report . TEMS AT NUCLEAR POWER PLANTS.

.- _. ._ . - . . - - - - ._ -. .


DENNINGAS. DOLAN.B W.

NUREG/CR4624 V06 RADONUCUDE RELEASE CALCULATIONS NUREG/CR4674 V11: PRECURSORS TO POTENTIAL SEVERE COREFOR SELECTED SEVERE ACCOENT SCEHARIOS Sapp 4emental Cab DAMAGE ACCIDENTS 1989 A STATUS REPORT.Mam Report And Ap-

culations. ponen ANURIG/CR4653 RECRrTCAUTY IN A BWR FOLLOWING A CORE NUREG/CR4674 V12. PRECURSORS TO POTENTIAL SEVERE CORE

DAMAGE EVENT 4 DAMAGE ACCIDENTS-1989 A STATUS REPORT.Appeneces B And

DEWITAPUREG/CR 5450- HIGH-TEMPE RATURE CRACK-ARREST TESTS DOMANUSAM

USING 152.MM. THICK SEN WOE PLATES OF LOW. UPPER SHELF NURE3/CR 564 V01: COMMIX.10: A THREEOMENSONAL TRAN.SIENT SINGLE. PHASE COMPUTER PROGRAM FOR THERMAL HY.

N RE /C 54 1 CR A R T IN SEN WLDE PLATES DRAUUC ANALYSIS OF SINGLE. COMPONENT AND MULTCOM-Or LOW. UPPER. SHELF BASE METAL TESTED UNDER NONISOTH, PONENT ENGINEERING SYSTEMS Equations And Nurnerics,ERMAL CONDITONS WP 2 SER;ES' NUREG/CR4649 V02: COMMIX tC* A THREE.OtMENSIONAL TRAN-

SIENT SINGLE PHASE COMPUTER PROGRAM FOR THEF. MAL-HY-DE7,M.WUREG-1333 MAINTENANCE APPROACHES AND PRACTICES IN SE. DRAUUC ANALYSIS OF SINGLEtOMPONENT AND MULTICOM-

LECTED FOREIGN NUCLEAR POWER PROGRAMS AND OTHER PONENT ENGINEERING SYSTEMS user's Gukte And Manual

U S. INDUSTRIES. REVIEW AND LE SSONS LEARNED. DONAHOE,C.

DlAMOND,D.J. NOREG/CR 5640 OVERVLEW AND COVDARISON OF U S. COMMER-NUREG/CR $368 RfACTMTY ACCOENTS A Reassessment Of The CIAL NUCLEAR POWER PLANTS Nuclear Power Ptant System Sour.

#

NUWEbC 73YORON FLUSHING 00 RING A BWR ANTIC 4 PATEDTRANSIENT WITHOUT SCRAM. DOSANJHAS.

NUREG/CR4316 MELT PROGRESSON. OXIDATION. AND NATURALCONVECTON IN A SEVERELY DAMAGED REACTOR CORE.

/dR4473. INCLUSON OF UNSTABLE DUCTILE TEARING ANDEXTRAPOLATED CRACK-ARREST TOUGHNESS DATA IN PWR DRAHOS F.RVESSEL INTEGA:TY ASSESSMENT. NUREG/CR4731 V01 RESOUAL UFE ASSESSMENT OF MAJOR

UGHT WATER REACTOR COMPONENTS OVERVIEW.DIERCKS,0 R.HUREG/C04867 V08 ENVIRONMENTALLY ASSISTED CRACKING IN 7.UGHT WATER REACTORS. Sermannua! ReportOctoter 1968 March

NUREG/CR-5524 V01: TML2 VESSEL INVESTIGATON PROJECT (VIP)CY; INTERNAL EVENTS METHOOOLOGY,

METALLURGICAL PROGRAM Progress Report, January SeptemberDRYSD ALE.J A.

1989.NUREGrCR 5524 V02: TMb2 VESSEL INVESTIGATION PROJECT (VIP) NUREG/CR 4753 V03- CANADIAN SEISMIC AGREEMENT. Annual

METALLURGICAL PROGRAM. Progress ReportOctober 1989 . Juno Report 1967 1968NURE G/CR-4753 V04 CANADIAN SEISMIC AGREEMENT Annua!1990.

DIONNE,B.J.NUREG/CP-0110: PROCEEDINGS OF THE INTERNATIONAL WORK. DUNWOODY,W.E.

SHOP ON NEW DEVELOPMENTS IN OCCUPATIONAL DOSE CON- NUREG/CR 5309 THE SEISMIC CATEGORY I STRUCTURES PRO-TROL AND ALARA IMPLEMENTATION AT NUCLEAR POWER GRAM RESULTS FOR FY 1987.PLANTS AND SIMILAR FACluTIES NUREG/CR4467; ST ATIC LOAD CYCLE TESTING OF A LOW ASPECT.

NUREG/CR 3469 V05: OCCUPATONAL DOSE REDUCTION AT NU. RATIO FOURINCH WALL,TRG-TYPE STRUCTURE TRG54CLEAR POWER PLANTS ANNOTATED DiBLIOGRAPHY OF SELECT- gi o,o,$e)ED READINGS IN RADIATON PROTECTON AND ALARA NUREG/CR4533 STATIC LOAD CYCLE TESTING OF A VERY LOW-

ASPECT.RATO SlX-INCH WALL TRG-TYPE STRUCTURE TRG46DOBBE.C.A. (0 27, a50)

NUREG/CR4376 OVAUTY ASSURANCE AND VERiflCATION OF THEMACCS CODE. Version 1.5. E BE RT,M.W.

NUREG/CR-5447. DEPRESSUR12ATION AS AN ACCOENT MANAGE- NUREG/CR 5622 ANALYSIS OF REACTOR TRIPS ORIGINATING INMENT STRATEGY TO MINIM 12E THE CONSEOVENCES OF DIRECT BALANCE OF PLANT SYSTEMS-CONTAINMENT HEATING

EDSON.J.LDOCTOR,P.G.NUREG/CR 5117; STEAM GENERATOR TUBE LNTEGRITY PROGRAM / NUREG/CR4181: NUCLEAR PLANT AGING RESEARCH THE 1E

STEAM GENERATOR GROUP PROJECT Feel Project Summary POWER SYSTEMNUREG/CR 5448 AQlNG EVALUATON OF CLASS 1E BATTERIESReport

SEISMIC TESTINGDOCTOR.S.R.

NUREG/CR4450 V06 NONDESTRUCTIVE EXAMINATON (NDE) REll- EIDSON,A.F.

ADIUTY FOR INSERVICE INSPECT!ON OF UGHT WATER NUREG/CR5489 BIOLOGICAL CHARACTER 12ATION OF RADIATON^ ^

Nt EGIC 4 9 V09 N E UC E A'M I NDE) REU. NG UENABlUTY FOR INSERVICE INSPECTON OF UGHT WATERRE ACTORS Sermannual Report Apr4 September 1988 g(A,w

NUREG/CR4469 V10: NONDESfRUCT1vE EXAMINATON (NDE) REll- NUREG/CR 5547: APPUCATION OF SURFACE COMPLEXATION@Ed M NNUDE ADNM W' Ae O

ACTOR rma .1 . M rth 1989 Mocel lnput Parameters.

NUREG/CR4882; QUAUF ION PROCESS FOR ULT RASONICTESTING IN NUCLEAR INSERVICE INSPECTION APPUCATIONS ELKIND,M.M.

NUREG/CR4008: ULTRASONIC INSPECTION REUABlUTY FOR IN- NUREG/CR 5635 CELLULAR AND MOLECULAR RESEARCH TOTERGRANULAR STHESS CORROSON CRACKS A Round Rotan REDUCE UNCERTAINTIES IN ESTIMATES OF HEALTH EFFECTSStudy Of The Effects Of Personnel. Procedures. Equipment, And Cracs FROM LOW 4EVEL RADIATION A Feasdality Study.Charactenstics

EMRIT.R.DOOD,C.V.NUREGo033 SIE A PRORIT12ATION OF GENERIC SAFETY ISSUES.NUREG/CR5478 IMPROVED EDOYCURRENT INSPECTION FOR

STEAM GENERATOR TUDING. Progress Report For January 1985 ToE RICSON.D.M.

Decerrter 1987.NUREGICR-5553 COMPUTER PROGRAMS FOR EDOY CURRENT NUREG/CR450 V01 R1 ANALYSIS OF CORE DAMAGE FREQUEN-

CY. fMTERNAL EVENTS METHOOOLOGtDEFECT STUDIES.

|

| . Personal Author index 65

ERIKSON,RLNUREG/C45209 CLOSEOUT OF BE BULLETIN 79 23 POTENTIAL

NUREG/CR$169. MOBlu2ATION AND TRANSPORT OF URANIUM AT FAILURE OF EMERGENCY DIESEL GENERATOR FIELD EXCITERURAN 1UM MILL TAluNGS DISPOSAL SITES A # cation Of A Ohemi- TRANSFORMERfcal Transport Modet NUREG/CR-5295 CLOSEOUT OF lE COMPUANCE BULLETIN 8643.

POTENTIAL FAILURE OF MULTIPLE ECCS PUMPS DUE TO SINGLE

4033. ASSESSMENT OF RELAPS/ MOD 2 CYCLE 36 04 tf " "AGAINST LOFT SMALL BREAK EXPER! MENT L3-6

NUREG/CR 5297: CLOSEOUT OF lE BULLETIN 83 05 ASME NUCLEARESCAMNTE,E. CODE PUMPS AND SPARE PARTS MWUFACTURED DY THE HAY.

NUREG/CR4735 V06 EVALUATION AND COMF1LATION OF DOE WARD TYLER PUMP COMPAUf.WASTE PACKAGE TEST DATA. Biannual Report August 1988 Janu- NUREG/C45298. CLOSEOUT OF IE BULLETIN 85 01: STEAM BIND'"U 08 ING OF AUXILIARY FEEDWATER PUMPS.

NUREG/C45302- CLOSEOUT OF IE BULLE~ TIN 8010 CONT AMWA-E V ANS,0.D. TION OF HONRADIOACTIVE SYSTEM AND RESULTING POTENTIAL

NUREG/CR 5482. LABORATORY ANALYSIS OF FLUID FLOW AND FOR UNMON!TORED, UNCONTROLLED HELEASE OF RADIOACTibSOLUTE TRANSPORT THROUGH A VARIABLY SATURATED FRAC, ITY TO ENVIRONMENT.TURE EMBEDDED IN POROUS TUFF. NUREG/CR-5306: CLOSEOUT OF lE BULLETIN 7918 AUDIDIUTYNUREG/CR4590, UNSATURATED FRACTURED ROCK CHARACTE4 PROBLEMS ENCOUNTERED ON EVACUATION OF PERSONNEL12ATION METHODS AND DATA SETS AT THE APACHE LEAP TUFF FROM HIG4 NOISE AREASSITE NUREG/CR 5307; CLOSEOUT OF lE BULLETIN 80-02: If4 ADEQUATE >

EVANSAS- OUAUTY ASSURANCE FOR NUCLEAR SUPPUED EOUIPMENT.NUREGIC45308. CLOSEOUT OF IE BULLETIN 8015. POSSiBLENUREG/CR4214 ROI PL HEALTH EFFECTS MODELS FOR NUCLEAR

LOSS OF EMERGENCY NOTIFICATION SYSTEM (ENS) WITH LOSSPOWER PLANT ACCIDEYT CONSEOVENCE ANALYSIS.Lew LET OF OFFSITE POWERRadation.Part I:6ntroduction,Integrshon And Summary

FARRAR,CA FRAGOLA.J.

NUREG/C4536R THE SEISMIC CATEGORY l STRUCTURES PRO- NUREG/C45436 V01: THE DEVELOPMENT AND EVALUATION OFPROGRAMMATIC PERFORMANCE INDICATORS ASSOCIATED W.iH

NUREG/ ST C D CYCLE TESTING OF A LOW ASPECT. MAINTENANCE AT NUCLEAR POWER PLANTSAlan RepetRATIO FOUH-INCH WALL,TRG TYPE STRUCTURE TAG-5-4 NUREG/CR 5436 V02: THE DEVELOPMENT AND EVALUATION OF

PROGRAMMATIC PERFORMANCE INDICATORS ASSCOIATED WITHNR /C 5533: STATIC LOAD CYCLE TESTING OF A VERY LOW, MAINTENANCE AT MCLEAR POWER PLANTS Apperuces

A CT TIO SIX-INCH WALL TRG-TYPE SIRUCTURE TRG46'

FRAKEi A.C.NUREG/CR4731 V06. EVALUATION AND COMPILAh0N OF OOEFERNS,T.W. WASTE PACKAGE TEST DAT A. Own.si Report August 1988 Janu-

NUREG/C45615 LOW-LEVEL RADIOACTIVE WASTE DISPOSAL FA. ary 1969CluTY CLOSURE.Part L Long-Term Envronmental Cordtons Af'ect-ing Low Level Weste Disposal Site Performance Pad 11; Performance FRESCO A.Morstonn0 o Support Asgulatory Docsaions. NUREG/CR 5637. GENERIC RISK INSIGHTS FOR WESTINGHOUSET

AND COMOUSTION ENGINEERING PRESSURIZED WATER REAC-FERREIRA,V.A.TORS-

NUREG/C45475: MODEL FEASIBlVTY STUOY OF RADIOACTIVEPATHWAYS FROM ATMOSPHERE TO SURFACE WATER. FROST,R,H.

NUREG/CR 5001: EFFECTS OF MANUF ACTURING VARIABLLS ONNU G/C45117: STEAM GENERATOR TUBE INTEGRITY PROGRAM / "

ESWAM GENERATOR GROUP PROJECT Final Protect Summary '

ReportFRYE R,C.P.

FESENMAIER,J. NUREG/CR 4668 DAMAGED FUEL FXPERJMENT DF 1 Results AndNUREG/CR 5399. SURVEY OF STATE AND THIBAL EMERGENCY RE- Analyses

SPONSE CAPABlUTIES FOR RADrOLOGICAL TRANSPORTATIONINCOENTS. FULLWOOO.R.

NUREG/C454t9 AGING ASSESSMENT Or INSTRUMENT A!R SYS-FIELES,R.J. TEMS IN NUCLFAR POWE' PtANTS

NUREG/CR 5450- HIGH-TEMPERATURE CRACK ARREST TESTSUSING 152-MM-THICK SEN W1DE PLATES OF LOW UPOER SHELF GALLAGHER,0,W.BASE MATERIAL TESTS WP-2 2 AND WP 2 6 NUREG!C45622; ANALYSIS OF REACTOR TRIPS OR!GINATING IN

NUREG/C45451: CRACK. ARREST BEHAVIOR IN SEN W10E PLATES 6ALANCE OF PLANT SYSTEMSOF LOW UPPERSHELF BASE METAL TESTED UNDER NONISOTH-ERMAL CONDtilONS- WP-2 SERIES GALLEGOS D.P.

NUREC/CH-5256. COMPONENTS OF AN OVERALL PERFORMANCEFISHER.DA ASSESSMENT METHODOLOGY.NUREG/C455f6: EVALUATION OF HEALTH EFFECTS IN SEQUOYAH NUREG/CR 5398 TECHNICAL BASIS FOR REVIEW OF HIGH LEVEL

FUELS CORPORATION WORKERS FROM ACCIDENTAL EXPOSURE WASTE REPOSFORY MODEUNGTO URANtUM HEXAFLUOPIDE.

GALYEAN,W LFITZPATRICK R-

NUREG/C45368: REACTMTY ACCIDZNTSA Reassessment Of Tlw NUREG/CR4639 V01 RI: NUCLEAR COMPUTERIZED UORARY FORDessge>Baws Events = ASSESSING REACTOR REUADIUTY (NUCLARR) Summary Descnp-

gn,

FLEMHMAN EA. NUREG/C44639 V4P1R2. NUCLEAR COMPUTER! ZED LIBRARY FORNUREG/Ck5438: BASIC CONS)DERATIONS IN PREDICTING ERROR ASSESSING REACTOR REUABluTY (NUCLARR). Users Gukte Part 1.

PROBABluTIES IN HUMAN TASK PERFORMANCE' NU E CR 639 UC A MPUTERi2ED UBRARY FORFOLEY,W.J. ASSESSINO RF ACTOR RELIADIUTY (NUCLARR). User's Guide Part 2

NUREG/CR4525 CLOSEOUT OF IE BULLETIN 84 03 REFUEUNG Guide To Operstons.CAVITY WATER SEAL. NUREG/CR-4439 V4P3R2: NUCLEAR COMPUTERIZED UBRARY FOR

NUREG/C44661: CLOSEOUT OF IE BMETIN 85 03 MOTOR OPER. ASSES $1NG REACTOR REUABluTY (NUCLARR). Users Gusde Part 3ATED VALVE COMMON MODE FAILURES DURING PLANT TRAN. NUCLARR System Descnpt on.SIENTS DUE TO IMPROPER SWTTCH SETTINGS. NUREG/CR4S39 V5PIR3. NUCLEAR COMPUTERIZED UORARY FORNUREG/C45286. CLOSEOUT OF lE But,LETIN 7917.P!PE CRACKS IN

ASSESSING REACTOR REUABlUTY (NUCLARR) Data ManuatPart 1:STAGNANT BORATED WATER SYSTEMS A' PWR PLANTS Summary Desenptort

1

-_ .. - _ _ _ - _ _ _ _ _ _ _ - - _ _ - - - - _ _ - _ _ _ - _ - _ _ _ - - - - - - - - - - - - - -

. _ - _ _ _ _ _ _ _ _ - . - - - _ - - _ - - - - - - _

66 Personal Author index

NUREG/CR4639 V5P3R3. NUCLEAR COMPUTERi2ED LIBRARY FOR NUREG/Cn4639 V5P3R3 NUCLEAR COMPUTERl2ED UORARY FOR

A0SFS3NG RE ACTOR REUABluTY (NVCLARR) Data Manual.Part 3 ASSESSING REACTOR REUADIUTY (NUCLARR)Dete MamalPad 3.

Ha*we Com.mnent Fa+se Deta (HCFD) Haroware Cenconent Fadure Data (HCFD)NUREG!CR-5602 SMPUFtED CONT AINMENT EVENT TREE ANALY.

FIS FOR THE SEQUOY AH ICE CONDENSER CONT AINMENT. GILBERT,8 Q.NUREG/CR4639 V01 Al: NUCLE AR COMPUTERIZED LIBRARY FCR

ASSES 9NG REAMM RWABW @mRR) hwy DescreEG C 731 V02 RESIDUAL LIFE ASSESSMENT OF MAJOR

UGHT WATER REACTCR COMPONENTS OVERVIEW ^ NU G/CR4639 V4PtR2' NUCLEAR COMPVTERIZED UDRARY rORASSESSING REACTOR REUADIUTY (NUCLARR) Users Guk1e Part 1:GARNTRAW,

NURJG/CR4731 V02- RESIDUAL UFE ASSESSMENT OF MAJOR CNemew Of NUCLARA Detr Retneval

UGHT WATER RFACTOR COMPONENTS OVERVIEW NUREG/CR4619 V4P2R2 NVCLEAR COMPUTERIZED UBRARY FORNVREG/CR-5556- REVIEW OF CURRENT LnERATURE RELATED TO ASSESSING REACTOR REUABluTY (NUCLARR) Us#s Guule.Part 2.

GENERIC SAFETY ISSUE 15. Gvut To Operatx>naNUREG/CR4639 V4P3R2. NUCLEAR COMPUTERIZED UBRARY FOR

# " ^ "' ' "

NUR G 5436: BASIC CONSIDERATIONS IN PREDICTING ERROR N SsPROBABluTIES 1N HUMAN T ASK PERFORMANCE. NUREG/CR4639 V5P1R3. NUCLEAR COMPUTER ZED UBRARY FOR

ASSESSING REACTOR REUA81UTY (NUCLARRLData Manual Part 1:GASSERAD. Suneary Desenptm

NUREG/CR466& DAMAGED FUEL EXPERIMENT OF.1.Results And NUREC/CRs.,39 V5P2R3 NUCLEAR COMPUTER 12ED LIBRARY FORAna4ses

NUREG/CR4671: THE OF4 FUEL DAMAGE EXPERIMENT IN ACAR ASSES 9NG REACTOR REUABlufY (NUCLARR).Deta ManualPart 2.

W1TH A BWR CONTRO(. BLADE AND CHANNEL DOX.Human Enor Probability (HEP) Data

NUREG/C44639 V5P3A3. NUCLEAR COMPUTER 12ED UBRARY FORGAUNTTAO. ASSESSING REACTOR REUA01UTY (NUCLARR) Data ManuaLPad 3

NUREGICR4668. DAMAGED FUEL EXPERIMENT DF.1 Results And Ha@nare Component Fadure Data (HCFD;Analyses

NUREG/CR4671: THE OF4 FUEL DAMAGE EXPERIMENT IN ACRR gitgg,q,gWITH A BWR CONTROL BLADE ANC CHANNEL BOX. NUREGIC45360 HTAS2. A THREE-OtMENSIONAL TRANSIENT SHIP-

PING CASK ANALYSIS TOOL.GAYLEAN,W.J.NUREG/CR-4639 V5P2R3: NUCLEAR COMPVTERtZED UBRARY FOR GILMORE,W L

ASSESSING REACTOR REUADtuTY (NUCLARR) Data ManualPart 2. NUREG/CR4639 V01 R1: NUCLEAR COMPUTERIZED UDRARY FORHuman Error ProbaMty (HEP) Data ASSES $1NG REACTOR REUABluTY (NUCLARR)Sumrnary Descrp-

GEE,0.W. teort

NVREG/CR-5523 DEVELOPMENT OF AN INFILTRATION EVALUA. NUREG/CR4619 V4P1R2. NUCLEAR COMPUTERIZED UBRARY FORTlON METHOOOLOGY FOR LOW LEVEL WA3TE SHALLOW LAND ASSESS NG REACTOR REUABluTY (NUCLARR) User's Gude Part 1:BURLAL SITES- Owrwsw Of NUCLARR Data Retnevat

NOREGICR4639 V4P2R2. NUCLEAR COMPUTER 12ED UBRARY FOR#b8 8 " ^ ^""} ' * ^

EG/C 5395 V02; MULTILOOP INTEGRAL SYSTEM TEST (MIST): d T a sNUREG/CR4639 V4P3R2 NUCLEAR COMPUTERIZED UORARY FORY11 U l INTEGRAL SYSTEM TESTNU E / 5 ASSESSING REACTOR REUABluTY (NUCLARR) User's Gukin Part 3

(MIST) FINAL REPORT MIST Phaw IV TestsNUREG/CR 5395 V11 AD- MULTILOOP tNTEGRAL SYSTEM TEST

NUCLARR System DesenptioitNUREG/CR4639 V5PtR3. NUCLEAR COMPUTERIZED LIBRARY FOR

(MIST) FINAL REPORT MIST Phase IV Testa. ASSESSING REACTOR REUABluTY (NUCLARR). Data Manual.Part 1:GEUNAS R. Summary Desenption.

NUREG/CR-5613 PALEOUQUEFACTION FEATURES ALONG THE AT. NUREG/CR4639 V5P2R3 NUCLEAR COMPUTERIZED UBRARY FORLANTIC SEABOARD. ASSES $1NG REACTOR REUABluTY |NUCLARR). Data Manual.Part 2.

Human Enor Probatxtity (HEP) Data.NUNCR6 WW NMEAR NWW UBM M

N G C'R 4t539 V01 R1: NUCLEAR COMPUTERIZED UBRARY FOR ASSESSM REAN EAM WW% Data ManuaWad 1ASSESSING REACTOR REUA8luTY (NUCLARR) Summary Descnp- Hartfware Component Failure Data (HCFO).

NUREG/CR4639 V4PIR2, NUCLEAR COMPUTERIZED UDRARY FOR* "

UR G/C45659 CONTROL ROOM HABITA01UTY SYSTEM REVIEWe Of N R ta al MODELS,

NUREGlCR4639 V4P2R2 NVCLEAR COMPUTERIZED UORARY FORASSESSING REACTOR REUABluTY (NUCLARR) User's Gurde Part 2 OLENN.W.LGugte To Operanons

NUREG/CR-4639 V4P3R1 NUCLEAR COMPUTERIZED UBRARY FOR NUREG 1415 V03 NOI: OFFICE OF THE INSPECTORASSESSING REACTOR REUA8luTY (NUCLARR) User's Gude Part 3 GENERAL. Semiannual ReportApnLSeptember 1990.

NUCLARR System Desenptiort GOLDEN,0.W.GERTMAN,D.I. NUREG/CR 544h DEPRESSURl2ATION AS AH ACCIDENT MANAGE.

NUREG/CR4639 V01 Rl: NUCLEAR COMDUTERIZED UBRARY FOR MENT STRATEGY TO MINIMl2E THE CONSEQUENCES OF DIRECTASSESSING REACTOR REUABluTY (NUCLAAA) Summary Desenp- CONTAINMENT HEATINGtion.

NUREG/CR4639 V4P1R2: NUCLEAR COMPUTERlZED UBRARY FOR GOMEZ,RAASSESSING REACTOR REUA01UTY (NUCLARR). User's Guide.Part 1: NUREG/CR4794. EXPERIMENTAL RESUL,TS OF CORE CONCRETE

2 NU LEYbMPUTERIZED UBRARY FOR INTERACTIONS USING MOLTEN STEEL WITH ZlRCONIUMNU E R 639 V P

ASSESSING REACTOR REUABILITY (NUCLARR). User's Guide Part 2: GOOD.M.S.

h3R2: NUCLEAR COMPUTERIZED LIBRARY FORNUREG/CR4469 V08 NONDESTRUC11VE EXAM; NATION (NDE) REU-

N /CR 9 ABluTY FOR INSERVICE INSPECTION OF UGHT WATERASSESSING REACTOR REUABlUTY (NUCLARG). User's Guide Part 3 REACTORS Sermannual Repon October 1987 March 1988NUCLARA System Descnptm

NUREG/CR4639 V5PtR3- NVCLEAR COMPUTERIZED LIBRARY FOR NUREG/CR4469 V09 NONDESTRUCTIVE EXAMINATION (NOE) REU-

ASSESSING REACTOR REUABluTY (NUCLARR) Data Manual Psit 1: AB1UTY FOR INSERVICE INSPECTION OF UGHT WATERREACTORS.Semiar:nual ReportApni-September 1980.

Summary Deartp6on.NUREG/GR4639 V5P2R3: NUCLEAR COMPUTERIZED UDRARY FOR NUREG/CR4469 v10: NONDESTRUCTIVE EXAMINATION (NDE) REU-

ASSESSING REACTOR RELIABluTY (NUCLARR). Data ManuaLPart 2: ABluTY FOR INSERVICE tNSPECTION OF UGHT WATERHuman Error Probapty (HEP) Data REACTORS.Sermannual Report,0ctober 1968 - March 1999

.

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_ _ . __ . . _ _

Personal Author index 67

lGOOORICH M.T. GUTJ AHR.A.L

NUREGICA-5256 COMPONENTS Or AN OVERALL PERFORMANCE NUREG/TR 5393 A REVtf W OF TECHNOUE S FOR PROPAGA11NGASSESSMENT METHODOLOGY. DAT A AND PARAMETER UNCERTAINTIES IN HiGH LEVEL radio,

NUREG/CR.5398 TECHNCAL BASIS FOR REVIEW OF HiGH4EVEL ACirvt W ASTE REPOStTORY Pf RrORM ANCE ASSESSMFNTWASTE REPOSITORY MODEUNG MODEt.S

GORE.B.F. GUZOWSKLR V.NUREG/CR 5616 AUX 1UARY FEEDW ATER SYSTEM RISK. BASED IN' NUREG/CR 1667 R:SK METHODOLOGY FOR 3EOLOGIC DtSr,OSAL

SPECTON GUCE FOR THE DIADLO CANYON UNIT 1 NUCLEAR OF haDOACTIVE W ASTE. Sceneno Scieccon proceduiePOWER PLANT. NUREG/C45256 COMPONENTS OF AN OVERALL PERrORMANCENUREG/CR 5617; AUXiuARY FEEDWATER SYSTEM RISK BASED IN-

ASSESSMENT METHOEOLOGYSPECTON GVOE FOR THE J M FARLEY NUCLEAR POWERPLANT. H AA S,P.J.

NUREG/CR.5568 V01 INDUSTRY BAACD PERFORMANCE INDICA.

E G'/ $ " *' * '

4551 V2RI P1. EVALUATON OF SEVERE ACCCENTR!SKS: QUANTIFICATON OF MAJOR INPVT PARAMETERS EmpertOpnon Ehettabon On in-Vessei lasues HApion Ag igo

NUREG1CR 8403 PRESSURE-DEPENDENT FRAGIUTF.S FOR P6PtNG

REdC 5635 CELLULAR ANO MOLECULAR RESEARCH TO COMPONENTS Ptiot Study On Ouyts Desse Nuclear Po*er Statson.

REDUCE UNCERT AINTIES IN ESTIMATES OF HEALTH EFFECTS HAGEMEYER D.FROM LOW-LEVEL RADIATION A FeesMty StudiNUREG47t3 V00 OCCUPATONAL RADIATICN EXPOSUHE AT Cou.

GRAHN,0, MERCIAL NUCLEAR POWER RE ACTORS AND OTHER F ACitrTIESNUREG/CR-4704 v03 RELATIVE BOLOGICAL [FFECTIVENESS (R3E) 1967 Twentseth Annual Report

OF FISSON NEUTRONS AND GAMMA RAYS AT OCCUPATONALEXPOSURE LEVELS Studes On The Gross And Microscopic Pe% HAGEN'G/CR 6374

E_ W

NURE SUMMARY OF INADEQUATE CORE COOUNG INpf Observed At Death Of Mce ExNeed to 60 Eoual Once-WeeklyDoses of Fisson.... STnVME NT ATON FOR UNITED STATES NUCLE AR POWER

pgy73GRAVE S.C.C.

NUREG 1372- REGULATORY ANALYSIS FOR THE RESOLUTION OF HAGGAGJ MGENERIC ISSUE C-8. " MAIN STEAM ISOLATION VALVE LEAKAGE NUREG/CH 5511 IRRADt AT ON iFFECTS ON bfRENGTH AND

'AND LCS FAILURE.a TOUGHNESS OF THREE W1RE SERIES ARC St AINLESS STEEL

WELO OVERLAY CLADOiNGGREEN.EA

NUREG/CR-4469 Yo8 NONDESTRUCTIVE EXAMINATON (NDE) REll. HA GRMAN.D.L.ABluTY FOR INSERVICE INSPECTION OF LIGHT WATER HUREG/CR-5273 V04 SCDAP/RELAPS/ MOO 2 CODEREACTORS Semannuai ReportOctober 1987 March 1988 MANUALVOLUME 4 MATPRO A UBRARY OF M ATERIALS PROP-

NUREG/CR-4469 V09 NONDESTRUCTIVE EXAMINATION (NDE) REU. ERTIFS FOR UGHT.W ATER REACTOR ACCOENT ANALYSISABluTY FOR INSERVICE INSPECTON OF UGHT WATERREACTORS Sermannt al Report Aprs-September 1988 HALDEMAN.W R

NUREG/CH-4469 V10 NONDESTRUCTIVE EXAM:NATON (NOE) REU- NUREG/CR 5482. LASORATORY AhALYSIS OF FLU 10 FLOW ANDABluTY FOR INSERVICE INSPECTION OF UGHT WATER SOLUTE i.tANSPORT THROUGH A VARIABLY SATURATED FRAC-REACTORS.Sernannual ReportOctober 1988 March 1989 TURE EMBEODED IN POROUS TUFF h

GRF OORYJ.J. HALL,K.W.NUAEG/CR-4551 V2RIPO EVALUATON OF SEVERE ACCOE NT NUREG/CR 4550 V7 A01. ANALYSIS OF CORE OAMAGL FREOVEN-

R!SKS OUANTIFICATON OF MAUOR INPUT PARAMETERS Expert CY. ZON. UN,i 1. INTERN A' EVENTSOnnen Ehotation On WVesset issues.

NUREGICR4551 V5 RIP 1: EVALUATON OF SEVERE ACCIDENT MALL.P.C.AtSAS' SEO'OY AH.UNfl I Mac Report NUREGliAm12 RELAPS/ MOO 2 CALCULATONS OF OECD-LOFT

NUREGICA 4551 V5R1P2. EVALUATION OF SEVERE ACCOENT TEST LP.SO41.RISKS SEQUOYAH. UNIT 1. Appendices NUREGnA402t RELAPS/ MOD 2 CALCULATONS OF OECD LOFT

NUREG/CR 5586: MITIGATON OF 04 RECT CONTAINMENT HEATING TEST LP-$84AND HYDROGEN COMBUSTION EVENTS IN ICE CONDENSERPLANTS Analyses Witn The CONTAIN Cooe And NUREG-1150 PRA HALLBERT,B.P.Methodokgy NUREGICA-5447 DEPRESSUR12ATON AS AN ACCOENT M ANAGE.

MENT STRATEGY TO M1 nim:ZE THE CONSEQUENCES OF DIRECT"^

CRI 45 VICTORIA: A MECHAN:STIC MODEL OF RAOtONU-R 55CUDE BEHAVOR IN THE REACTOR COOLANT SYSTEM UNDER H AMPTON.N.LSEVERE ACCOENT COND(TIONS NUREG/CR-5273 YO4 SCOAP/RELAP5/ MOO 2 CODE

MANUALVOLUME 4 MATPRO - A UBRARY OF M ATERIALS PROP.

NUNEG CR4639 V01 R1: NUCLEAR COMPUTERIZED UDRARY FOR ERTIES FOR UGHT.W ATER-REACTOR ACCOENT ANALYSISASSESSING REACTOR REUABILITY (NUCLARR) Summary Descry

HANSON.D.J.t*R

NUREG/CR-5447 OEPRESSURIZATION AS AN ACCOENT MANAGE-GUNTAY,S. MENT STRATEGY TO MINIM 12E THE CONSEOUENCES OF DIRECT

^BREAK E PERIME LP B NU EG/ 55 3 01 ACCOENT MANAGEMENT INFORMATION

NEEDS Volume 1 Methodology Deve6opment And Applicahon to AGUNTHER.W. Pressunred Water Reacter WWR) With A Large, Dry Cor%nment

NUREG/CR-5507: RESULTS FROM THE NUCLEAR PLANT AGING RE- NUREGICR 5513 V02 ACCOE NT MANAGEMENT INFORMATIONSEARCH PROGRAM.THEIR USE IN INSPECTION ACTIVITIES NEEDS Volume 2 Appentlices

GUPPYJ.G. H ARPE R,F.T.

NUREG/CR 3668 M NET CODE DOCUMENTATON NUREG/CR.4550 Voi RI: ANALYSIS OF CORE DAMAGE FREQUEN-CY INTERNAL EVENTS METHOOOLOGY.

GUPTA.A.K. NUREG/CR-4551 V2RIPI- EVALU A TION OF SEVERE ACCOENTNUREGICR 5627- ALTERNATE MOCAL COMBINATION METHOOS IN RISKS QUANTIFICATION OF MAJOR INDUT PAR 4 METERS Expert

RESPONSE SPECTRUM ANALYSIS Openon Eliatahon On in-vessei Issues

________._ _ - - - _ _ _ _ _ _ - - _ _ _ - _ _ _ _ _ _ - - - _ _ _ _ _ ._

. -


HACRIBON,D G. NOREG/CR4551 V6R t Pt: EVALUATON OF SEVERE ACCIDENTNUREGICR~5610 AUXlilARY FEEDWATER SYSTLM RISK-BASED IN. RISM QR AND GULF. UNIT I Man Fienn

SPECTION GUIDE FOR THE DiAPLO CANYON UNtf 1 NUCliAR NUREu/044551 V6R1P2 EVALUATION OF SEVERE ACQDENYPOWER PLAN 1, fitSKS GRAND GULF, UNIT t. Apperdcon

NUREG/CR 561L AUXIUARY FEEDWATER SY'TTEM RISK. BASED IN- NUREG/CR 5253 PARTITION A PROGRAM FOR DfTINING THE$PECTION GUIDE F081 THE J M FARLEY NUCLEAR FOWER SOU5KE TERM / CONSEOVENCE ANALYSIS INTERFACE IN THEP(ANT 4 NUREG-1150 PROBABILisi C RtSA ASSESSMENTS UWs Guuta

NUREG'CR th3 RECRITICAUTY IN A E,WR FOLLOWING A CORE NUREG/CR G2 PRAMIS PROBAdluTY FUSm ASSESSMENT MODELDAMAGEFvtNT- IN1EGRATON SYSTEM UWa Gude.

HAfgTFIELO.R.A. HENUICK A.NUREG4020 Vid 403 LICENSED OPEHATING REACTORS STATUS W R W M 25 NEOUT W E DULWW $4 03REmNGSUMMARY REPORT.Dete As Of Fettuary 28.1990 (Gray Book i) CAVITY WATER SEAL

NURE G/CR Mel: CLOSEOUT OF lE BULLETIN 8503 MOTOROPER.HdtTYANURt G/csh5640 PERFORMANCE TESTING OF EXTREMfTy ATED VALVE COMuGN MODE FAltVRES OU80NG PLANT 1RAN-

ECSIMETLRS. STUDY 2 SIENTS DUE TO IMPRCOER SWITCH SETinNGSNUREGIC%5236 CLOSCOUT OF IE OULLETIN 19-17 PIPE CRACAS IN

HARWOOD,C- STAGNANT DORATED WATER SYSTEMS AT PWR PLANTSNUREG/l A4013 MLAD5/ MOO 2 CALCULATONS OF OECD-LOFT NUREG/CR 6269 CLOSCOUT OF lE OtALETIN 79 23 POTENilAL

TEST LFs SD-03 F AILURE OF EMEC1GENCY OtESEL G(NERATOR FIELD f XCITERTRANSFORMER

HADHEMIAN,H M NUREG/CR 5295 CLOSEOUT OF IE COMPLIANCE Bln.LETIN 60-03NUREG/CR 5560. AWNG OF NUC6 EAR PLANT RESfSTANCE TEM- POTENTIAL F AILURE OF MULTIPLE ECCS PUMPS OUE TO S!NGt.E

PERATURE DETECTOR $_ F ALLURE OF AIR OPERATED VALVE IN MtNiMUM FLOW RtCIRCO-LATlON UNE-HADHIMOTO,P.O.

NUREG/CR.4550 V3 RIP 3 ANALYS!S OF CORE DAMAGE FREQUE!4 NUREG/CR 5297. CLOSCOL.fi OF IE DutLLiiN 8305 ASME NLCLEAR

CY: SURRY POWER STATION. UNIT 1 EXTERNAL EVENTS CODE PUMPS ANO SPARE PARib MANUFACTURED BY THE HAY.RUREG/CR4550 V441P3 ANALYSIS OF CORE DAMAGE FREQUEN- WARD TYLER PUMP COMPANY.

CY, PE ACH BOTTOM.UNii 2 EXTERNAL EVENTS NUREG/CR 5298. CLOSEOUT Of IE DULLETIN 85 01. STEAM BtNCLING OF AUXIUARY FEEDW ATER PUMPS

HAWTHORNEd.R. NUREG/CR 5302 CLOSEOUT OF IE BULLETIN 8010 CONT AMINA-NUREG/CR 5402 iNVESTIGATONS OF IRRAD(ATON ANNEAL REIR. TON OF NONRADtOACTtvE SYSTLM AND RESUt.flNG POTENTIAL

MADIATION (IAR) PROPERTIES TRENDS OF HPV WELOS Phase 2 FOf1 UNMONITOREO, UNCONTROLLED RELEASE OF RADtOACTIV.Fnal Report ITY TO ENVIRONMENT

NUREGICR 5403 INFLUENCE OF FLUENCE RATE ON RADtATON-IN- NUREG/CR 5306 CLOSEOUT OF IE DULLETIN 7916 AUOluluTYOUCED MECHANICAL PROPERTY CHANGES IN REACTOR PRES- PROBLEMS ENCOUNTERED ON EVACUATON OF PERSONNELSURE VESSEL STEELalvW Report On Espurstery E@enments FROM HIG4 NOISE AREAS-

NUREG/CR-5307. CLOSEOUT OF IE BULLETIN 8402 INADEOUAIEHA9 ES,K.F. OUAUTY ASSURANCE FOR NUCLEAR SUPPUED EQUIPMENT,NUREGICR 5547: APPUCATION OF SURFACE COMPLEXATION NUREG/CR 5308. CLOSEOUT OF 1E DULLETIN 6ats POSSIBLEMODELS FOR HADIONUCUDE ADSORPTION Senaatrvtty Analyws Of

LOSS OF EMERGt.NCY NOTIFlCATION SYSTEM (ENS) W11H LOSSModel input Pa/ameters,OF OFFStTE POWER

C AME S.T.J.NUREGICR-5545 VICTORIA: A MECHANISTIC MODEL OF RADIONU. HIGGINSJ

CUDE DEHAVOR IN THE RE ACTOR COOL. ANT SYSTEM UNDER NUREG/CR 5527 RISK SENSITIVITY TO HUMAN ERROR IN THE LA-SEVERE ACCIDENT CONDITIONS SALLE PRA

NUREG/CR 5572 AN EVALUATION OF THE EFFECTS OF LOCALHEABLER,P.O. CONTROL STATION DESIGN EONFIGURATIONS ON HUMAN PER-

NUREGICR4460 V08. NONDESTRUCTIVE EXAMiNAtlON (NDE) RELi- FORMANCE AND NUCLEAR POWER PLANT RISK.ADIUTY FOR INSERVICE INSPECTION OF UGHT W ATERRE ACTOR $ Sonwannual Report,0ctober 1987. Match 1988 HIGGINS,SJ

NUREGICR4469 V00- NONDESTRUCTIVC EAAMINATON (NDE) RELi- NUREG/CR4551 V5R t P t' EVALUA TION OF SEVERE ACCIDENTADiLIEY FOR INSERVICE INSPECTON OF UGHT WATER RISKS SEQUOYAH. UNIT I Mam Rapat

HUREG/CR4551 V5R t P2: EV At U ATON OF SEVERE ACCIDENT46N JNff1VCT [E AMIN ON (NOC) REll,N S EG F RISKS SEQUOYAH.UNii 1 AppmlicesADILITY FOR INSERVICE INSPECTION OF LIGHT WATER NUREG/CR-4551 V6A1P1: EY AI.U ATON OF SEVERE ACCIDE NTRE ACTORS Somaannual Report,0ctober 1986 March 1999 RISKS GRAND GULF.UNii 1 Main Report

NUREGICR490n. ULTRASONIC INSPECTION REUABluTY FOR IN. NUREG/CR 4551 V6RI P2. EVALUATON OF SEVERE ACCIDENTTEROMANULAR STRESS CORROSON CRACKS A Round Robin RISKS OFLAND GULF, UNIT 1. AppendicasStudy Of The Effects Of Personnet, Procedures, Equipment, A/d CrackChara:tonalics

NUREG 1377 R01 NRC RESEARCH PROGRAM ON PLANT AGINGHEDGES,D,NUREG 1383 GUIDANCE ON THE APPLICATION OF QUAUTY ASSUR, USTINGS AND SUMM ARIES OF REPORTS ISSUED THROUGH MAY

ANCE FOR CHARACTERIZING A LOW. LEVEL RADIOACTIVE WASTE 1990

DISPOSAL StTE Final Repo 1.HILLS,R.G.

HELTONJ.C. NUREG/CH-Se0L FLOW AND TRANSPORT AT THE LAS CRUCLSNURE G/CR4551 V2 RIP 7: EVALUATION OF SEVERE ACCIDENT TRENCH SITE Espenments 1 And 2-

RISKS. QUANilFICATION OF MAJOR INPUT PARANETERS MACCSIr put. HISE R.A.

NUREQ/CR 4551 V3R t P1: EVALUATION OF SEVERE ACCIDENT NUREG/CR 504 CORRELATION OF IRRADLATON1NDUCEO TRAN-^ "^ ^"

N l'C 45 AtP2 EVA ATION OF SEVERE ACCIDENT T FRISKS SURRY UNIT I Apperdcet

'

NUREG/CR 4551 V4RIPt: EVALUATON 08 SEVERE ACCIDENT HISER,A LNUREG/CR 5492. INVESTIGATIONS Or IRRADIATION ANNEAt RElH-NF G/C 4551 4| 21 E A UATON F SEVERE ACCIDENT

RADIATON (IAA) PROPERTIES TRENDS OF RPV WELDS Phase 2RISKS PEACH Dorf 0M UNIT 2. ApperecesNUREGICR 4551 V5P I P t. EVALUATION OF SEVERE ACCIDENT Final Report|

NUREG/CR 54G1 INFLUENCE OF F LUENCE HATE ON RADIATION (N.RISKS SEOVOYAH, UNIT 1 Main ReoortHUREG!CFI4551 V5HtP2: EVALUATION OF SCvf RE ACCIDENT DUCED MECHANICAL PROPERTY CHANGES IN REACTOR PRES.

RISK $ SEQUOYAH, UNIT 1. Appenthces SURE VESSEL STEELS Final Report On Esonorawy Empooments.

|.

_ - _ _ _ _ _ _ _ _ _ _ -


HOEG8ERQ,LQ. J AMISON,J.D.NUREG 1420 SPECIAL COMMITTEE REVIEW OF THE NUCLEAR REG- NUREG/CR4397 VALUE-lMPACT ANALYSIS OF REGULATORY OP.

ULATORY COMMISSOfS SEVERE ACCOENT RISKS REPORT TIONS FOR RESOLUTION OF OENERC ISSUE C 8 MSly L.EAAAGE(NUREG- 1153). AND LCS F ARVRE,

HOFMAYER.C.H.

J ASKE,C E[CR 5314NUREb V03 LIFE ASSESSMENT PROCEDURES FORT NTS ( SE S chgear l&C P a SS)And R@ MAJOR LWR COMPONENTS Cast Stainless Steel Components

Hosonyt,Jx J ASTROW,J.D.NUREG/CR4273 V04: SCOAP/RELAPS/ MOD 2 COOE NUREG/CR 5229 V02 TML2 EPICOR41 RESIN /UNCR INVESilGATON

MANUAL VOLUME 4 MATPRO A LIBRARY OF MATERIALS PROP. LOW-LEVEL W ASTE DATA BASE DEVELOPMENT PROGRAM FORERTIES FOR UGHT.W ATER REACTOR ACCOENT ANALYS:S. FISCAL YEAR 1989 Annual Report

NUREG/CR 5229 V03 EPCOR.li RESIN / LINER INVESTIGATON LOW-E $540 PERFORMANCE TESTING OF EXTREMITY y 3 p,

DOSIMETERS. STUDY 2-

HORA.S.C.NUREG/C% 5411: ELCITATON & USE OF EXPERT JUDGMENT IN NUREG/CR4515 UGHT W ATER REACTOR PRESSURE ISOLATION

PERFOhMANCE ASSESSMENT FOR HOH-LEVEL RADIOACTIVE VALVE PERFORMANCE TESTINGWASTE REPOSITORES

HORST,C.LNUREG/CR4254 BIAS IN PE AK CLAD TEMPERATURE PREDICTONS

NUREG/CR 5583 PREDOTION OF CHECK VALVE PERFORMANCE DUE TO UNCERTAINTIES IN MOOEUNG OF ECC BYPASS AND OIS.AND DEGRADATO4 IN NUCLEAR POWER PLANT SYSTEMS SOLVED NON-CONDENSABLE GAS PHENOMENA.WEAR ANO IMPACT TESTS Fens; ReportSeptember 1988. Apnl 1990

JOHANSSON.LB.

NUR G C 69 MOO!U2ATON AND TRANSPORT OF URANIUM AT NUREG/CR 5451 CRACK ARRESY BEHAvtOR IN SEN WOE PLATESURANIUM MILL TAIUNGS OISPOSAL SITES Apphcation Of A Cherm Or LOW UPPER. SHELF BASE METAL TESTED UNDER NONISOTH-W Tre W ERMAL CONDITONS WP-2 SERIES.

HSIEH,BJ, JOHNS,MNUREG/CR-5599 OYNAMC TESTING OF A CIRCULAR FOUNDATON NUREG/CR 5545 VCTORIA. A MECHANISTIC MODEL OF RADIONU.

AND ANALYSES OF SOIL / STRUCTURE INTERACTON CUDE BEHAVOR IN THE REACTOR COOLANT SYSTEM UNDERSEVERE ACCIDENT CONDITONS

NUREG/CR4368 REACTIVITY ACCIDENTS A Reassessment Of the JOHNSON,A.B.Owy> Basis Events-

NUREG/CR4401. SHIPPINGPORT STATION AGING EVALUATON

HUANG P' CR 5484 PH SENSORS BASED ON IRCIUM OxOE.NUREG/ JOHNADANUREGICA 5229 V03 t PICOR41 RESIN /UNER INVESTIGATION LOW.

HUDSON.D.S. LEVEL WASTE DATABASE DEVROPMENT PROGRAM FOR FISCALNUREG/CR 5607; FLOW AND TRANSPORT AT THE LAS CRUCES YEAR 1990.Anruel ReportTRENCH SITE.Expenments 1 And 2

NUREGICR 5504 RADIATION DEORADATON IN EPCOR44 ION EXHUGHES AA

NUREG/CP4108 PUBUC WORKSHOP ON NUCLEAR POWER PLANT JOHNSON,0.LLCENSE RENEWAL

NUREG/CR 5644 CONSEQUENCE EVALUATON OF RADIATON EMIMAN,R.L BRITTLEMENT OF TROJAN REACTOR PRESSURE VESSEL SUP.

NUREG/CR $253 PARTITION A PROGRAM FOR DEFINING THE PORTSSOURCE TERM / CONSEQUEPCE ANALYSIS INTERFACE IN THENUREG 1150 PHOBABlusTic RISK ASSESSMENTS User's Gucw JOHNSON,J.0,

NUREG/CR 5462 PRAMIS PROOABluTY RlSK ASSESSMENT HOOEL NUREG/CR 5253 PARTITON A PROGRAM FOR DEFINING THEINTEGRATON SYSTEM User's Guide SOURCE TERu/ CONSEQUENCE ANALYSIS INTERFACE IN THE

NUREG-1150 PROBA81USTC RISK ASSESSMENTS. User's Gum 1e

NUR G -47 5 V06. EVALUATION AND COMPILATON OF DOE E RAT SYS User s GWASTE PACKAGE TEST DATA. Dianrual Report August 1968 Ja*NUREG/CR-5453 V05. BACKGROUNO INFOP'JATON FOR THE DE-

N EG/CR-5638 TECHNCAL CONSCERATIONS FOR EVALUATING VELOPMENT OF A LOW LEVEL WASTE PERFORMANCE ASSESS.SUBSTANTIALLY COMPLETE CONTAINMENT OF HIGH-LEVEL MENT METHOOOLOGY. Computer Code impiementauon And Asses *WASTE WTTHIN THE WASTE PACKAGE. **"'

iSKANDER,81 JOHNSON.JJNUREG/CR 5450: HIGH. TEMPERATURE CRACK ARREST TESTS NUREG/CR-4550 V3 RIP 3 ANALYSIS OF CCHE DAMAGE FREQUEN.

US!NG 152-MM THICK SEN WlOE PLATES OF LOW-UPPER-SHELF CY; SURRY POWER STATON,UNfi 1 EXTERNAL EVENTSBASE MATERIAL: TESTS WP 2 2 AND WP.2 6 NUREG/CR-t$50 V4RtP3 ANALYSIS OF CORE DAMAGE FREQUEN-

NUREG/CR 5451: CRACLARREST BEH AVIOR IN SEN WOE PLATES CY. PEACH BOT TOM. UNIT 2 EXTERNAL EVENTSOF LOW UPPER-SHELF RASE METAL TESTED UNDER NONISOTH-ERMAL COND(TIONS WP 2 SERIES JOHNSON,R1

NUREG/CR.5584 RESULTS OF CRACK ARREST TESTS ON TWO IR.RADIATEO HIGHCOPPER WELDS. NUREG 1339 RESOLUTON OF GENERIC SAFETY ISSUE 20 DOLTING

OEGRADATION OR FAILURE IN NUCLEAR POWER PLANTSJACOBSON.J.

OWRRNUREG/CR.3145 V00. GEOPHYSCAL INVESTIGATIONS OF THEWESTERN OHC-tNOLANA REGION Annual Report,0ctober 1988 NUREG 1394 EMERGENCY RESPONSE DATA SYSTEM (EROS) IM.September 1989. PLEMENTATION.

JACO60S.M.J. JONE S.C.G.NUREG/CR 5461: AGING OF CABLES. CONNECTONS, ANO ELECTRI- NUREG 1396 ENVIRONMENTAL ASSESSMENT OF THE THERMAL

CAL PENETRATION ASSEMBUES USED IN NUCLEAR POWER NEUTRON ACTIVITATION EXPLOS!VE DETECTON SYSTEM FORPLANTS CONCOURSE USE AT U S AIRPORTS

l

- _ _ _ _ _ _ - __ _ _ _ - _ _ _ _ _ _ _ - _ _ _ - - _ _ - - - - - - - - -

. _.


NUREG/CR 5451: CRACKARREST BEHAV600 IN SEN WOE PL A1ESJONES,KAMUREG/CR 5508 AN ASSESSMENT OF BWR M ARK 11 CONTAINMENT OF LOW UPPER SHELF DASE MET AL TESTED UNDER NONGOTR

CHALLENGES, FAILURE MODES, AND POTENTIAL IMPROVEMEfCS ERMAL CONDrilONS WP 2 SERIESIN PERFORMANCE

NUREG /CR-5575 OUANTIT ATIVE ANALYSIS OF POTENTIAL PER- KELEY,0.L

FORMANCE IMPROVEMENTS FOR THE DRY PWR CONT AINMENT. NUREG/CR 5528 AN ASSESSMENT OF BWR MARK ll CONT AINMENTCHALLENGES FAILURE MODES, AND POf LNTIAL IMPROVt'MENTS

JORDAN,H. IN PERFORMANCENUREG /CR4624 V06 RADONUCLIOE RELEASE CALCULATONS NUREG/CR 5575 OVANTIT ATIVE ANALYSl$ OF POT [ NTIAL PER-

FOR SELECTED SEVERE ACCOENT SCENAROS Supp6cmental cal FORMANCE IMPROVEMENTS FCR THE ORY NI CONT AINMENTculatKms

"IM'NEJOC,4N. NUREG'CR4624 V06 RADIONUCLtDE REL E ASE CALCULATONS

NURE G/CR4551 V2R1P7- EVALUATON OF SEVERS ACCIDENT FOR SELECTED SEVERE ACCID ( NT SCENAROS S(4Wimental Cal-RISKS OUANTIFICATION OF MAJOR INPUT PARAMETERS MACCS culebonsInput

NUREG/CR4551 V4R1P1 EVALUATION OF SEVERE ACCOENT KEMNER,MLRtSKS PEACH BOTTOM. UNIT 2 Man Report

NUREG/CR4551 v4R1P2 EVALUATION OF SEVERE ACCIDENT NUREG/CR$169 MOD!L12ATION AND TRANSPORT OF URAN 1UM ATURANIUM MILL TA! LINGS DISPOSAL S11ES.Apphcauon Of A Cremt

( RISKS PEACH BOTTOM, UNIT 2 AppendicesNUREG/CR4691 V01: MELCOR AGGIDENT CONSEQUENCE CODE cat Transport Model

SYSTEM (MACCS) Volume 1' Usvo GudeNUREG'CR 4691 V02. MELCOR ACCOENT CONSEQUENCE CODE KEMPPINEN,H.

I SYSTEM (MACCS) Volume 2 Model Desenphon NUREG/CR5613 PALEOLIQUEFACTION FEATURES ALONG THE AT.

| NUREG/CR4891 V03 MELCOR ACCOEht CONSEQUENCE CODE LANTIC SEABOARD.SYSTEM (MACCS). Volume 3 Programmer's Reference Manual.

KENNEDY,WLNUREG/CR-5512 DAF FC RESOUAL RADCACTIVE CONTAMINATION

NU G/CR4551 V6R1P1: EVALUATON OF SEVERE ACCIDENT N DEWWMG TemaI Basis For Transuung ContanR:SKS GRAND GULF, UNIT 1 Main Report naten Levets To Annual Dose Dratt Reort For Comment

NUREG/CR4551 V6AiP2. [ VALUATION OF SEVERE ACCIDENTRISKS GRAND GULF UNIT 1. Appendices. KHAN,T.A.

NUREG/CP-Ot to- PROCEEDINGS OF THE INTERNATIONAL WORK-JULIUS,J,A,NUREGICR4550 V3 RIP 1: ANALYSIS OF CORE DAMAGE SHOP ON NEW DEVELOPMENTS IN OCCUPATONAL DOSE CON

FREQUENCV SURRY UNTT t,1NTERNAL EVENTS TROL AND ALARA iMPLEME NT ATION AT NUCLEAR POWERNUREG/CR4550 V3 RIP 2 ANALYST $ OF CORE DAMAGE FREQUEN- PLANTS AND SIM:LAR F ACILITIES

CY: SURRY, UNIT 1,1NTERNAL EVENTS APPENCICES NUREG/CR 3469 V05 OCCUPATONAL DOSE REDUCTON AT NU-CLEAR $OWER PLANTS ANNOT ATED Ot0LIOGRAPHY OF SELECT,

NU EG CR5583. PREDICTION OF CHECK VALVE PERFORMANCEAND DEGRADATION IN NUCLEAR POWER PLANT SYSTEMS + K|y,4J,WEAR AND IMPACT TESTS Final Report.Septerncer 1986. Apr611990- NUREGtlA4030 ASSESSMENT OF RELAPL/ MOO 2 CODE USING

LOSS OF OFFSITE POWER TRANSIENT DATA OF KNU #1 PLANT.KAM,F.B.K NUREG/lA 003t: ICAP ASSESSMENT OF RELAP5/ MOD 2, CYCLE

NUREG/CR 4816 PR-EDO POWER REACTOR EMORITTLEMENT 3605 AGAINST LOFT SMALL OREAK ExPERtMENT L3 7.am Descr NUREG/lA-0032. ASSESSMENT OF RELAPS/ MOD 2 CYCLE 36 04DAT A BASE. VERSION 1. P[rEXPOSUR[tx>riPARAMETERS FOR THENUREG/CR-5409 NEUTRO USING LOFT LARGE DREAk EXPERIMENT L2 5

METALLURGICAL TEST SPECIMENS IN THE SIXTH HEAVY SEC.| TION STEEL IRRAD:ATION SERIES KINCAID,C.T.' NUREG/CR 5449- DETERMINATON OF THE NEUTRON AND GAMMA NUREG/CR5522 DEVELOPMENT OF AN INFILTRATION EVALUA-

FLUX DISTRIBUTION IN THE PRESSURE VESSEL AND CAVITY OF TION METHODOLOGY FOR LOW LEVEL W ASTE SHALLOW LANDA DOMLNG WATER ACACTOR BURIAL SITES

KASSIR,MLNUREG/CR4659 V03 SEISMIC FRAGILITY OF NUCL'iAR POWER

KlPP,TAPLANT COMPONENTS (PHASE II)Switchgear, IAC Panels (NSSS) NUREGICR 5603 PRESSURE-DEPENDENT FRAGILITIES FOR PlPING

COMPONENTS P90t Study On Davis Besse Nucioar Power Stauon.And Reiays

K ASSNER,T F. KIRKLAND,MA

NUREGICR4667 V07: ENVIRONMENTALLY ASSISTED CRACKING IN NUREG/CR$607: FLOW AND TRANSPORT AT THE LAS CRUCE9LIGHT WATER REACTORS Sermannual Report,Apnl.Scotember 1988 TRENCH SITE.Expenments 1 And 2.

NUREG/CR4667 V08 ENVIRONMENTALLY ASSISTED CRACKING INj LIGHT WATER REACTORS Sermannual Report, October 1988 March KIRKWOOD.B.J.I 1969 NURE9/CR4731 V02: RESOUAL LIFE ASSESSMENT OF MAJOR

LIGHT WATER REACTOR COMPONENTS , OVERVIEWKASTENDERG ME.

NUREG 1420 SPECIAL COMMITTEE REVIEW OF THE NUCLEAR REG- KIRKWOOD,R.ULATORY COMMISSION'S SEVERE ACCIDENT RISKS REPORT NUREG 1316. TECHNICAL FINDINGS AND REGULATORY ANALYSIS(NUREG-1150)~ RELATED TO GENERIC 6SSUE 70 Eva6uabon Of Power-Operated

Rehef VaNo And Blocli Valve ReliatAty in PWR Nuclear Power PlantsKGTHREN.RL

NUREG/CR5566. EVALUATON OF HEALTH EFFECTS IN SEQUOYAHUAE /C $ 55 V10. MULTILOOP INTEGRAL. SYSTEM TEST (M:ST)

TO URAN M HEX LU FINAL REPORT. HELAP5/ MOO 2 MIST Anatysis Compensons

KE ENEY,R.L KN APP,R.W.NUREG/CR-5411: EllCITATION & USE OF EXPERT JUDGMENT IN NUREG/CR.5629 MICROEARTHOUAKES IN FANSAS AND NEHRAS-PERFORMANCE ASSESSMENT FOR HIGH-LEVEL RADCACTIVE KA 19771969 Final Report.

WASTE REPOSITORIES

REENEY WALKER KOCHIS S-

NUREG/CR 5450- H6GH-TEMPERATURE CRACK ARREST TESTS NUREGlCR 5280 V02 AGE RELATED DEGRADATION Or YvESitNG-USING 152-MM-THICK SEN WOE PLATES OF LOW-UPPER SHELF HOUSE 480-VOLT CIRCUIT OREAKERS Mechamca! Cychng Of A DS-

DASE MATERIAL: TESTS WP-2 2 AND WP 2 6 416 Breder Test Results

Personal Author Index 71

KONOlCAM,LAMONTAGNE.M.

NUREG-1377 RO1: NRC RESEARCH PROGRAM ON PLANT AGING NUREGICR.4753 YO3 CANADIAN SEISMIC AGREEMENT AnnualLISTINGS AND SUMMARIES OF REPORTS LSSUED THROUGH MAY Report- 1967 19881990

NUREG/CR 4753 V04. CANADIAN SEISMIC AGREEMENT AnnualKOWEK,0 J.

NUREG/CR0672 A0004: TECHNOLOGY, SAFETY AND COSTS OF LANO.JJ.DECOMMISSIONtNG A REFERENCE BOluN3 WATER REACTOR NUREGIC45483 EFFECTS OF MINERALOGY ON SORPTON OFPOWER ST ATION Compenson Of Two Decomrnassoneng Cost Este STRONTIUM ANO CESIUM ONTO CAUCO HILLS TUFF,mates Developed For The same Commercial Nuclear Reactor PowerStation. LAPOlWTE SA

NUREG/CR 2001 AD001: TECHNOLOGY,$AFETY AND COSTS OF DE.NUREG/CR4753 V04 CANADIAN SEISMIC AGREEMENT.Anrmal. COMMIS$ONING REFERENCE UGHT WATER REACTORS FOL. Report 1986 1989

LOWING POSTULATED ACCCENTS Re Evolvation Of The CleanupCost For The Bothng Water Reactor (BWR) Scenaqo 3 Accident From LA f.T.NUREG/CR2601. NUREG/C43145 V08. GEOPHYSICAL INVESTIGATONS OF THE

KOT,C A- WESTERN OHO INDIANA REGION Annual Report. October 1988September 1969.

NUREG/CR-5599 DYNAMIC TESTING OF A CtRCULAR FOUNDATONAND ANALYSES OF SOIL / STRUCTURE INTERACTON Lt P.T.

KOUTS,HAC- NUREGiCR 5622 ANALYSIS OF REACTOR TRIPS ORIGINATING INBALANCE OF PLANT SYSTEMS

NUREG-1420. SPECIAL COMMITTEE REVIEW OF THE NUCLEAR REG-ULATORY COMMISSON'S SEVERE ACCCENT FuSKS REPORT LECKIE J.O.(NUREGr t150) NUREG/CR554h APPUCATON OF SURFACE COMPi,ExATON

MODELS FOR RADONUCUDE ADSORPTON SenttMty Anaryws OfNU E 45453 V05. BACKGROUND INFORMATON FOR THE DC- *

VELOPMENT OF A LOW LEVEL WASTE PERFORMANCE ASSESS- LE E.8.S.MENT METHOOOLOGY. Computer Code implementation And Assess.

NUREG/CRS280 V02: AGE.RELATED DCORADATON OF WESTING.mentNUREG/C45532: A PERFORMANCE ASSESSMENT METHOOOLOGY HOUSE 480-VOLT CIRCUlf BREAKERS Mechanical Cychng Of A OS-

FOR LOW 4EVEL WASTE FACiUTIES. 416 Breaker. Test Results

LEE,C.E.

N G'/C 5484 PH SENSORS DASED ON IRIOtUM OX1DE. "KRUPKA K.M. LE E,E .J.

NUREG/CR5548. REVIEW OF GEOCHEMICAL PROCESSES AND NUREG/lA 0031: ICAP ASSESSMENT OF RELAP5/MOU.L CYCLECODES FOR ASSESSMENT Or RADIONUCUDE MIGRATION PO. 36 05 AGAINST LOFT SMALL BREAK EXPERIMENT L3 7.TENTIAL AT COMMERCIAL LLW SITES. LEE H.K.

NUREG/CR 5480 DATA SUMMARY REPORT FOR FISSON PRODUCTN REG 5479' CURRENT APPUCATIONS OF YtBRATON MONt-

TORING AND NEUTRON NotSE ANALYSIS Outection And AnaNsis of Lgg,x,w,Structural Degradation Of Reactor Vessel Irornale From OperetsonalA "9- NUREG/CR4624 V06. RADONUCUDE RELEASE CALCULATIONS9

FOR SELECTED SEVERE ACCIDENT SCENAROSSupp6amental Cai-KUDRICK,JA #*

NUREG 1417; SAFETY EVALUATON REPORT RELATED TO HYDRO-GEN CONTROt. OWNERS GROUP ASSESSMENT OF M ARK lit CON-

gggy,TAINMEM- NUREG/lA 0032- ASSESSMENT OF RELAP5/ MOO 2 CYCLE 36 04

USING LOFT LARGE BREAK EXPERIMENT LS5KULL6 ERG,C.M.

g . y,a'G/lA-0030-NUREG!CR5557; RELAPS THERMAL HYORAUUC ANALYSIS OF THE *

NtlRE ASSESSMENT OF RELAP5/ MOO 2 CODE USINGSNUPOS PRESSURIZED WATER REACTOR.LOSS OF OFFSITE POW 5R TRANSIENT DATA OF KNU #1 PLANT.

KURTH M .NUREG/CR$510: EVALUATONS OF CORE MELT FREOUENCY EF- 'IN"IN M

FECTS DUE TO COMPONENT AGING AND MAINTENANCE. REG /M74. ASSESSMN & CAMATE ACCON NAGEMENT STRATEGtES-

KURT2,R.J.

NUREG/CR$117: STEAM GENERATOR TUBE INTEGRITY PROGRAM / LE ONARD,M.T.

STEAM GENERATOR GROUP PROJECT.Fnal Protect Su m NUREG/CR.4624 V06 RADONUCUDE RELEASE CALCULATONSpg FOR SELECTED SEVERE ACCIDENT SCENARIOS Supp(emental Cal-culatsort

LAATSIT.NUREG/CR $273 V04- SCOAP/RELAPS/ MOO 2 CODE LESAGE.LO.

MANUALVO(UME 4 MATPRO A LIBRARY OF MATERIALS PROP, NUREG-1420 SPECIAL COMMITTEE REVIEW OF THE NUCLEAR REG-ERTIES FOR UGHT WATERREACTOR ACC10ENT ANALYSIS. ULATORY COMMISSION'S SEVERE ACCCENT RISKS REPORT

(NUREG 1150).LAMBERT,H.E.

NUREG/CR5477. AN EVALUATON OF THE RELLABILITY AND USE. LLC.Y.FULNESS OF EXTERNAL.lNITIATOR PAA METHOOOLOGIES NUREG 1417: SAFETY EVALUATION REPORT RELATED TO HYDRO-

NUREG/CRS644 CONSEOUENCE EVALUATON OF RADIATON EM- GEN CONTROL OWNERS GROUP ASSESSMENT OF MARK til CON-BRITTLEMENT OF TROJAN REACTOR PRESSURE VESSEL SUP. TAINMENT.PORTS.

LISBY,RALZDBRIGHT,J.A.

NUREG/CR 5653 RECRITICAUTY IN A BWR FOLLOWING A CORENUREG/CR4550 V3 RIP 3 ANALYSIS OF CORE DAMAGE FREOVEN. DAMAGE EVENT.

CY SURRY POWER STATION, UNIT 1 EXTERNAL EVENTSNUREG/C44550 V4 RIP 3 ANALYSIS OF CORE DAMAGE FREQUEN- LIST.AL !

CY PEACH OOTTOM UNfT 2 EXTERNAL EVENTS NUREG/CR.5001. EFFECTS OF MANUFACTURING VARIABLES ON,

NUREG/CR4840 PROCEDURES FOR THE EXTERNAL EVENT CORE PERFORMANCE OF HIGH. LEVEL WASTE LOW CARBON STEELi

DAMAGE FREQUENCY ANALYSES FOR NUREG-1150 CONTAINERS

'

! l

:i

. . - - - ~.- - .- - -.- -..-.-.- _ ..-._ - - . - _

=72 Personal Author index

LYONS.JALIGON,0.M.. NUREG/CP4108: PUBLO WORKSHOP ON NUCLEAR POWER PLANT NUREG/CR4753. V03 CANADIAN SEISMC AGREEMENT Annual

- LCENSE RENEWALReport 1967,1968

N AR NT h

LIPINSKLR.E **NUREG/CR 5556. REvtEW OF CURRENT LITERATURE RELATED TO

GENERC SAFETY ISSUE 15. MACDONALD,P.E. -NUREO/CR 4731 V02; RESIDUAL LIFE ASSESSMENT OF MAJOR

' LO,T. LCHT WATER REACTOR COMPONENTS . OVERYtEW.NUREG/CR-45M V06. SCANS (SHIPPING CASK ANALYSIS SYSTEM),A

MICROCOMPUTER BASED ANALYSIS SYSTEM FOR SHIPPtNG MACDOUGALL.E.CASK DESON REVIEW. Volume 6. Theory Manual Bucklin0 Of Cirev. NUREG/CR-52eo V01: AGE RELATED DEGRADATON OF WESTING-lar CAndocal Shens . HOUSE 480 VOLT CIRCUIT BREAKERS A 'ng Assesamord And Roc-O

NUREG/CR-4554 V07: SCANS (SHIPPING CASK ANALYSIS SYSTEM) ommendellona For improdng Brooker Relistwkty.A M'CROCOMPUTER BASED ANALYSIS SYSTEM FOR SHIPPING NUREG/C45280 V02, AGE RELATED DEGRADATION OF WESTING-CASK DESIGN REVIEW Volume 7: Theo.y Manual Puncture Of Stup. HOUSE 480 VOLT CIRCULI BREAKERS Mechancal Cychng Of A OS-peng Casks. 416 Breaker. Test Results.

LOGNER,P,NUREG/C45640' OVERVIEW AND COMPARISON OF U S. COMMER- MACLELLAN.JA

CtAL NUCLEAR POWER PLANTS Nuclear Power Plant System Sou'' NUREG/CR 5516 CAUSES OF FAILING THE ORAFT ANSI STANDAR0Nt3.30 RADOBOASSAY PERFORMANCE CRITERlON FOR MINI-cetaA WUM DETECTABLE AMOUNT,

LOFORENL^ NUREG/C45472: A RISK BASED REVIEW OF INSTRUMENT AIR SYS- ggggggy,g,j

- TEMS AT NUCLEAR POWER PLANTS HUREG/CRb550 V01 R1: ANALYSIS OF CORE DAMAGE FREQUEN-CY; INTERNAL EVENTS METHOCOLOGY,

LONG.LT.NUREGIC45258 V02 GEORGIA / ALABAMA REGIONAL SEISMO- WANAKT ALA H.K.

GRAPHIC NETWORK. Annual Report. July t966. June 1967, NUREG/CR-Sc38- TECHNCAL CONSOERATONS FOR EVALUATING- NUREG/CR 5258 V03 GEORGIA / ALABAMA REGIONAL SEISMO. SUBSTANTIALLY COMPLETE CONTAINMENT OF HIGSLEVEL- GRAPHIC NETWORK. Annual Report. July 1967. June 1968.

NUREG/CR5258 V04: GEORGIA / ALABAMA REGIONAL SEISMO* WASTE WITHIN THE WASTE PACKAGE.

GRAPHIC NETWORK. Final Report, August 1985. October 1990.MARCH 4EUSA.J.

LOMS.W. NUREG/CR 5421:LAPUR USER'S GUIDE.NUREG 1393- THE INCtNERATON OF LOW. LEVEL RADCACTIVE NUREG/C45605 LAPUR BENCHMARK AGAINST IN-PHASE AND

WASTE.A Report For The Adesory Comr.vttee On Nuclear Weste- OUT OF. PHASE STABluTY TESTS

LORENZ,R.A. MARCUS,A.NURE TA SUMMARY REPORT FOR FISSION PRODUCT NUREG/C45437: OAGANIZATON AND SAFETY IN NUCLEAR POWER

PLANTS.

LOYELACE.WR MARSHALLA.C,NUREG-0020 V13 N11: LCENSEO OPERATING REACTORS STATUS NUREG/C44668. DAMAGED FUEL EXPERIMENT DF-1 Results AndSUMMARY REPORT. Data As Of October 30,1969 (Gray Book gNUREG 0020 Vt3 N12. LICENSED OPERATING REAdTORS STATUS

ArWyses.

SUMMARY REPORT.Deta As Of November 30,1989 (Gray Book f)NUREG-0020 V14 N01: LCENSED OPERATING REACTORS STATUS

MARSHALL,NK

SUMMARY REPORT.Deta As Of Deember 31,1969 (Gray Book i) NUREG/C45378 QUALITY ASSURANCE AND YERIFICATION OF THE

NUREG4020 V14 NO2: LCENSED MTING REACTORS STATUS MACCS CODE Version 1.5SUMMARY REPORT.Cata As of Janw,31,19904 Gray Book f)

M ARTS S.T.NUREG/CR 56% NEVEL RADOME WASTE WOSAL FA-

NU Ed/C45450 .~ HIG* TEMPERATURE CRACK. ARREST ' TESTS CluTY CLOSURE.Part L Long-Term ErmtonmenW Conditions Affect-USING 152.MM-THfCK SEN WOE PLATES OF LOW UPPE4 SHELF Nh Waste W h %mance M R PhnceBASE MATERIAL-TESTS WP 2 2 AND WP 2 6. Monnoreg To Support Regulatory Decmons

NUREG/C45451: CRACK ARREST BEHAVIOR IN SEN W10E PLATESOF LOW-UPPER-SHELF BASE METAL TESTED UNDER NONISOT4 "A #ERMAL CONotTIONS:WP4 SERIES /C45376- QUALITY ASSURANCE ANO VERIFICATON OF THE

MACCS CODE. Version 1.5LU S.C.

. PREUMINARY - STRUCTURAL EVALUATON OFNUREQ/CR-5506. MASC 1ANTON40,A.TROJAN RCL SUfUECT TO POSTULATEt RPV SUPPORT FAILURE,

NUREG/CR 5644. CONSEQUENCE EVALUW10N OF RADIATION EM-NUREG 1424- SAFETY EVALUATON REPORT RELATED TO THE

. BRITTLEMENT OF TROJAN REACT * WESSURE VESSEL SUp- FULL TERM OPERATING LICENSE FOR PALISADES NUCLEARPLANT. Docket No. 50 255. (Consumers Power Company)

FORTS.MASON,RL

LUCERO.DA. NUREG/CR4794: EXPERIMENTAL RESULTS OF CORE CONCRETE NUREG/C45273 V04. SCDAP/RELAP5/ MOO 2 CODE

INTERACTONS OSING MOLTEN STEEL WITH ZlRCONIUM- MANUALVOLUME 4 MATPRO . A LIBRARY OF MATERIALS PROP.- ERTIES FOR LIGHT WATER REACTOR ACCIDENT ANALYSIS.

LUcKAS W.- NUREG/CR-547& ASSESSMENT OF CANDIDATE ACCtDENT MAN- MATTINGLY,P.A.

NUREG/CR 5453 V05: BACKGROUNO INFORMATON FOR THE DE.I- NUREG/CR5 SK SENSITIVITY TO HUMAN ERROR IN THE LA- VELOPMENT OF A LOW-LEVEL-WASTE PERFORMANCE ASSESS-

SALLE PRA. MENT METH000 LOGY. Computer Code Imp 6ementateort And Assess-= NUREGeC45572. AN EVALUATON OF THE EFFECTS OF LOCAL ' NL

CONTROL STATION DESIGN CONFIGURATONS ON HUMAN PER- NUREG/CR 5532: A PERFORMANCE ASSESSMENT METFOOOLOGYFORMANCE AND NUCLEAR POWER PLANT RISK. FOR LOW LEVEL W ASTE F ACiUTIES.

LUN0tN,C.D. MAURATH,0.NUREG/C43873 EFFECT OF WELDING CON 0fTONS ON TRANS. NOREG/C45613: PALEOUQUEFACTION FEATURES ALONG THE AT.FORMATION AFC PROPERTIES OF MEAT AFFECTED ZONES ON

LANTIC SEABOARD.LWR VESSEL STEELS.

._. _ , _ . _ . _ _ _ ___ _ __ _ _ ___ _._

- . . . . . -- - _ -


MCCLUNG.R.W.NUREG/CR 5568 V02 CARES (COMPUTER ANALYSIS FOR RAPONUREG/CR 5478 IMPROVED EDOY CURRENT INSPECTON FOR EVALUATON OF STRUCTURES) VERSON 1,0 SentmcSTEAM GENEMTOR TUBING. Progress Report For January 1965 To MWie User's Manual.Decemter1987.NUREG/CR 5588 VO3 CARES (COMPUTER ANALYSIS FOR RAPO

MCCOMAS.M L EVALUATION OF STAVCTURE S) VERSON 10 SesmscModule Sampie ProuemsNUREG/CR 5273 VO4: 6CDAP/RELAP5/ MOD 2 COOf

MANUALVOLUME 4 MATPRO A tlBRARY OF MATERIALS PROP- MtaE RJ.0,ERTIES FOR UGHT-WATER-REANTOR ACCIDENT ANALYSIS

NUREG/CR 5405: ANALYSIS OF SHELL RUPTURE F AILURE DUE TOMCCONNELLJ.W. HYPOTHETICAL ELEVATED. TEMPERATURE PRESSUH2ATION Or

NUREGICR 5229 V02. TMI-2 EPICOR-il RESIN /UNER INVESTGAtlON THE SEOVOYAH UNft t STEEL CONTAINMENT ButLDINGLOW LEVEL WASTE DATA BASE DEVELOPMENT PROGRAM FOR NURf G/CR 5447: DEPRESSURIZATON AS AN ACCOENT MANAGE-

! MENT STRATEGY TO MINIMJE THE CONSEQUENCES OF DIRECTC 5 9 VO E O ESIN/UNER INVESTIGATON LOW. CONTA1NMENT HEATINGNU

LEVEL WASTE DATABASE DEVELOPMENT PROGRAM FOR FISCAL MIRERLF.NVI EG/CR 5 A ON DEGRADATON IN EPICOR.ll ON Ex- NUREG/CR 5400 NEUTRON EXPOSURE PARAMETERS FOR THE

CMGE RES!NS' METALLURGICAL TEST SPECIMENS IN THE SIXTH HEAVY SEC.TON STEEL IRRADMTON SERIES.

MCCORD,J.7,

NUREG/CR 5453 V05. BACKGROUND INFORMATON FOR THE DE. MILLER.R.0,

VELOPMENT OF A LOW LEVEL WASTE PERFORMANCE ASSESS. NUREG/CR4629 MICROEARTHOUAKES IN KANSAS AND NEBRAS-MENT METHOOOLOGY. Computer Code ImFJementation And Assess. KA 19771969 Final Report

MILLER,R.LMCOUIRE S.A. NUREG/CR 5273 V04 SCDAP/RELAP6/ MOO 2 CODE

NUREG-139t DAFT FC: CHEMICAL TOxCITY OF URANIUM HEXA- MANUALVOLUME 4 MATPRO A UBRARY OF MATERIALS PROP-FLtOROE RELATED TO RADIATION DOSES Drs t Report For Com.ERTIES FOR UGHT WATER-REACTOR ACCIDENT ANALYSl$

e

me.,t

MILSTEAP .MCNAMARA,N.NUREG-0933 611. A PRIORITI2ATION OF GENERIC SAFETY ISSUESNUREG-0837 V09 NO4. NRC TLD DIRECT RADIATON MONITORING

NETWORK Progress Report Octoter Decomter 1989 MIN ARICK,J.W.NUREG-0837 V10 N01: NRC TLD OtRECT RAOLATION MONITORING

NETWORKProgress Report January-March 1990 NUREG/CR 4674 V00 FRECURSORS TO POTENTIAL SEVERE CORENUREG-0837 V10 NO2. NRC TLD DIRECT RAD 4ATON MONITORING DAMAGE ACCOENTS 1988 A STATUS REPORT Main Report And Ap-

NETWORKProgress Report Apr& June 1990 perd, A.

NOREG 0837 V10 NO3. NRC TLD DIRECT RADIATION MONITORING NUREG/CR 4674 V10 PRECURSORS TO POTENTIAL SEVERE CORENETWORK Progress Report July September 1991 DAMAGE ACCOENTS 1966 A STATUS REPORT.Apperoses D And

C.

MCNEILK.A. NUREG/CR 4674 V11: PRECURSORS TO POTENTIAL SEVERE CORENUREG/CR 5273 V04. SCDAP/RELAP5/ MOO 2 CODE DWAGE AMEMS 489 A STANS REW Main Rem And Ap.

MANUALVOLUME 4 MATPRO A UBRARY OF MATERIALS PROP,ERTIES FOR UGHT-WATER-REACTOR ACCOENT ANALYSIS NU /CR-4674 V12. PRECURSORS TO POTENTIAL SEVERE CORF

DAMAGE ACCOENTS 1989 A STATUS REPORT.Appendw;es 0 An5ME R KLE,J.G. G-

NURE G/CR-5552 AN OVERVIEW OF THE LOW UPPER SHELFTOUGHNESS SAFETY MARGIN ISSUE. ,D

g g gMEYER LC,

TRANSIENT WITHOUT SCRAMNUREG/CR4731 V02: RESOUAL UFE ASSESSMENT OF MAJOR

UGHT WATER REACTOR COMoONENTS OVERVIEW MITCHELL.D.B.NUREG/CR4181: NUCLEAR PLANT AGING RESEARCH THE 1E NUREG/CR4460: A CAUSE DEFENSE APPROACH TO THE UNDER-POWER SYSTEM.

STANDING AND ANALYSIS OF COMMON CAUSE FAILURES.t: EYER,M.A.

MITCHELL.D.W.NUREG/CR4424 ELICITING ANO ANALY2ING EXPERTJUOGEMENT.A Practical Guide. NUREGrCR.EW AGING OF NUCLEAR PLANT RESISTANCE TEM-

PERATURE DETECTORSMEYER O.R. MITTER,E.L

NUREG/CR 5513 V01. ACCOENT MANAGEMENT INFORMATONNEEDS volume 1. Methodology Development And Applecat,on To A NUREGICR 5399 SURVEY OF STATE AND TRIBAL EMERGENCY RE.Preuurned Water R4 actor (PWR) With A larpe. Dry Containment SPONSE CAPADluTIES FOR RADIOLOGICAL TRANSPORTATION

INCOENTSNUREG/CR-5513 V02. ACCIDENT MANAuEMENT INFORMATONNEEDS volume 2 Appendicat

MOHAMMED.S.

NUREG/CR 3873 EFFECT OF WELDING CONDITIONS ON TRANS-NUREG'/CR-6463- EFFECTS OF MtNERALOGY ON SORPTON OFM^

STRONTIUM AND CESIUM ONTO CAUCO HILLS TUFF. g yE L S EELS

ME2NARICH,H K. MOK.O.C.

NUREGICR 5631: CONTA:BUTON OF MATERNAL RADONUCUDE NUCCR C1 V06 SCANS (SHIPPING CASK ANALYSIS SYSTEMI ABURDENS TO PRENATAL RADIATION DOSES intenm MICROCOMPUTER DASED ANALYSIS SYSTEM FOR SHIPPtNGRecommendations.For Corment CASK DESIGN REVIEW Volume 6. Theory Manual Ducung Of Circu-

lar Cylindncai ShousCtWAN,LW.

NUREG/CR-3444 VD7. THE alPACT OF LWR DECONTAMINATIONS MOORE,0.

ON SOUDtFCATION. WASTE DISPOSAL AND ASSOCIATED OCCU NUREG/CR-5613 PALEOUOUEFACTON FEATURES ALONG THE AT-PATONAL EXPOSURE _ LANTIC SEADOARD.

MILLER,C.A.MORELOCK T.C.

NUREG/CR 5688 V01: CARES (COMPUTER ANALYS!S FOR RAPO NUREG/CR 5374 SUMMARY OF INADEQUATE CORE COOUNG IN.EVALUATON OF STRUCTURES) VERSON 10 Soisrmc S TRUMENT ATION FOR UN!TED STATES NUCLEAR POWERModule.Theoretral Manual = PLANTS

- - - . - . . . _. - - .


NEYMOTIN,LY,MORGAN,H.A.

NUCEG/CR 5273 V04 SCOAP/RELAP5/ MOO 2 CODE NUREG/CR 5254 BIAS IN PEAK CLAD TEMPERATURE PREDICTIONS

MANUALVOLUME 4 MATPRO . A LIBRARY OF MATERIALS PROP-DUE TO UNCERT AINTIES IN MODELING OF ECC OYPASS AND DIS-

ERTIES FOR UGHT.WATERREACTOR ACCIDENT ANALYSIS-SOLVED NON-CONDENSABLE GAS PHENOMENA

N)CHOLS.M.MOYERSJ C.

NUREu/C45519 YOl' AGING OF CONTROL AND SERVtCE AIR COM-NUREG/CR5437. ORGANIZATION AND SAFETY IN NUCLEAR POWER

PRESSORS AND DRYERS USEO IN NUCLEAR POWER PLANTSPLANTS

NfCNOL8,R T.MRAZ,M.J.

NUREG/CR4550 V3R1P3 ANALYSIS OF CORE DAMAGE FREQUEN- NUREG/CR $373 A DEMONSTRATON EXPER' MENT OF STEAM

CY: SURRY POWER ST ATON. UNIT 1 EXTERNAL EVENTSORIVEN, HIGH-PRESSURE MELT EJECTION The HIPS-10S Test

NUREG/CR4550 V4 RIP 3 ANALYSIS OF CORE DAMAGE FREQUEN- NOURB A KHSH.H.P,CY: PEACH BOTTOM. UNIT 2 EXTERNAL EVENTS NUREG/C45589 ASSESSMENT OF ICE CONDENSER CONT AINMENT

t:UNRO,P.$- PERFORMANCE ISSUES

NUREG/CPc4753 V03 CANADIAN SEISMIC AGREEMENT Annual O'DGNNELL,E,Report 1967 1968

NUREGICA-4753 V04 CANADLAN SEISMIC AGREEMENT. Annual NUFiEG/CR4916 V04 CONTROL OF W ATER INFILTRATON INTONE AR SURFACE LLW DISPOSAL UNITS Progress Report On Fw6d Ex-

Report 1988 1989-penments At A Humed Region Site,Beltsville.Marytend

NUREG/CR4551 V3 RIP 1; EVALUATON OF SEVERE ACCOENT O'HARA).NUREG/CR 5527. RISK SENSITIVITY TO HUMAN ERROR IN THE LA4RISKS SURRY UNIT 1 Main Report

NUREG/CR4551 V3 RIP 2; EVALUATON OF SEVERE ACCIDENT SALLE PRA.RISKS. SURRY ON!T 1 Appendees NUREG/CR 5572 AN EVALUATON OF THE EHECTS OF LOCAL

NUREG/CR4551 V5 RIP); EVALUATON OF SEVERE ACCIDE NT CONTROL STATION DESIGN CONFIGURATIONS ON HUMAN PER.FORMANCE ANO NUCL.E AR POWER PLANT RISK.

NU EGICR4 51 EVAL ION OF SEVERE ACCOENTRISKS: SEQUOY AH,0 NIT 1. Appendices. O'KELLEY.Q.O.

NUREG/CR5463 EFFECTS OF MINERALOGY ON SORFTION OFSTRONTluu AND CESIUM ONTO CAUCO HILLS TUFF.

NU EG 4882. QUAllhCATON PROCESS FOR ULTRASONICTESTING IN NUCLEAR INSERVICE INSPECTION APPUCATONS- 0%AL,BL

NUREG/C45517. IMPACTS-BRC. VERSION 2 0 Program User's ManuelCUTH,T.R.

NUREO/CR5001, EFFECTS OF MANUFACTURING VARIABLES ON OLAGUE,N.E.

PERFORMANCE OF HIGH-LEVEL WASTE LOW CARBON STEEL NUREG/CR 5398 TECHNICAL Basis FOR REVtEW OF HIGH LEVELCONTA:NERS. WASTE REPOSITORY MODEUNG

NAKAK1,0.K. OUVE.K LNUREG/CR 5603. PRESSURE DEPENDENT FRAGIUTIES FOR PIPING NUREG-1350 V02. NUCLEAR REGULATORY COMMISSON INFORMA.

COMPONENTS Pdot Study On Devis-Besse Nuclear Power Statort TON DOEST A990 Eh

NAKAMURA,T, O CSNURE TA SUMMARY REPORT FOR FISSON PRODUCT

MANUAL, VOLUME 4 'AATPRO A UBRARY OF MATERIALS PROP +ERTIES FOR UGHT WATER. REACTOR ACCOENT ANALYSIS

NANSTAD R.K.NUREG/CR5511: !RRADIATON EFFECTS ON STRENGTH AND OLSONJ.

TOUGlNESS OF THREE-WIHE SERIES ARC STAINLESS STEEL NUREG/CR5437, ORGANt2ATON AND SAFETY IN NUCLEAR POWERWELD OVERLAY CLADOING. PLANTS.

NUREG/CR-5584. RESULTS OF CRACK ARREST TESTS ON TWO 1R.RADlATED MIGH-COPPER WELDS OR M A

NUREG!CR1667: RISK METHCOOLOGY FOR GEOLOGIC DISPOSALNAUS,0.J. OF RADCACTIVE W ASTE. Sceneno selection Procedure.

NUREG/CR5450: HOH-TEMPERATUPE CRACK. ARREST TESTSUSING 152-MM THICK SEN W1DE PLATES OF LOW UPPERSHELF OSBORNABASE MATERiALTESTS WP4 2 AND WP 2 6. NUREG/CR 5437. ORGANIZATION AND SAFETY IN NUCLEAR POWER

NUREG/CR5451: CRACK. ARREST BEHAVIOR IN SEN WOE PtATES PLANTS.OF LOW UPPER SHElr BASE METAL TESTED UNDER NONISOTH.ERMAL CONDITIONS- WF 2 SERIES OSBORNE M.F.

NUREG/CR5480' DATA SUMMARY REPORT FOR FISSION PROOOOTNEASEA RELEASE TEST VI.3.

NUREG 1214 R05: HtSTORtCAL DATA SUMMARY OF THE S/STEMAT.IC ASSESSMENT OF LICENSEE PERFORMANCE' OT ADUY,PJ.

NUREG/CR5421 LAPUR USER'S GUIDE.NEELY,H.H.NUREG/CR-5515 UGHT WATER REACTOR PRESSURE ISOLATION OTis M.D.

VALVE PERFORMANCE TESTING. NUREG/CR-5615 LOW-LEVEL RADIOACTIVE W ASTE DISPOSAL FA.CILITY CLOSURE.Part I: Long Term Envronmental Conditions Attect.

NEILL,A.P. ing Low-level Waste Disposal Sde Performance Part 11 PerformanceNUREG/lA 0022. TRAC PFl/ MOO 1 POST TEST CALCULATONS OF Monitonng To Support Peguialory Docts ons

THE OECO LOFT EXPERIMENT LP.58-3.OTT,LJ.

NELSON,WA NUMG/CR4671. THE DF4 FUEL DAMAGE EXPERIMENT IN ACRRNUREG/CR55') V01: . ACCIDENT MANAGEMENT INFORMATON WITH A BWR CONTROL BLADE AND CHANNEL BOX.NEEDS.Voh ..e 1. Methodolcv/ Development And ApphcaDon To A

Pressurim Water Reactor (PWR) With A large, Dry ContainmentNUREG G5513 V02- ACCIDENT MANAGEMENT INFORMATON

P AF FOR D,0.J.

NUREG/CR 5575 OUANTIT ATIVE ANALYSIS OF POTENTIAL PER-NEEf iVolume 2 Appendos FORMANCE IMPROVEMENTS FOR THE ORY PWR CONT AINMENT,NUREG/CR 5802. SIMPUFIED CONTAINMENT EVENT TREE ANALY.ucD%E,T.C. SIS FOR THE SEOVOYAH ICE CONDENSER CONTAINMENT.

NUREG/CR3%8 MINET COOE DOCUMENTATION

.

_ . _ . -

Personal Author index 75i

PALMER.Q R. PHILDIN.J.S.NUREG/CR SM6 BASIS FOR SNUBRER AGING RESE ARCH NUCLE. NUREGICR 5381 ECONOMC RISK OF CONT AMINATION CLE ANUP

AR PLANT AGING RESEARCH PROGRAM COSTS RESULTING FROM LARGE NONREACTOR NUCLEAR MATE.4AL UCENSEE OPERATIONS

P ALME R.J. A.

NUREG/C45399 SURVEY OF STATE AND TR!BAL EMERGENCY RE. PHILIPPACOPOULOSPONSE CAPABILITIES FOR RADIOI.OGCAL TRANSPORT ATON NUREO/CR 55A8 YO1 CARES (COMPUTER ANALYSIS FOR RAPOINCIDENTS EVALUATION OF STRUCTURE S) VE RSON 10 Se stmc

Mc<1ute Theoretical ManualP ARE CE,W.V. NUREG/CR 5588 V02 CARES COMPUTER ANALYSIS FOR RAPID

NUREG/CR 5395 Vio MULTILOOP INTEGRAL SYSTEM TEST (M!ST) E V ALU ATION OF ST RUCTURE S) VERSON 1.0 SeestmcFim REPORT. RELAP5/ MOO 2 MtST Anayses Compensons Modu 6e Usss Manual

NUREG/C45588 V03 CARES (COMPUTER AN ALYSIS FOR RAPIDPARK.C. EVALUATON OF STRUCTURES) VE RSION 10 Seeserve

NUREG/CR-5629 MICROEARTHOUAKES IN KANSAS ANO NEBRAS Moduie Sampie ProtdemsKA 19771989 Final Report.

PILCH.M.PARK,.EY, NUREG/CR4373 A DEMONSTRATION E XP( RIME N T OF STEAM

NUREG/C44657 V07. ENVIRONMENTALLY ASSISTED CRACKING IN ORIVEN, HIGH PRE SSURE MEL T EJECTON The HIPS.10S TestUGHT W ATER RE ACTORS Sermannual Report.ApntSeptemtier 1988

NUREG/C44667 V08 ENVIRONMENTALLY ASSLSTED CRACKING iN PITTIGLIO.C.LUGH'T WATER REACTORS Semiannual Report.Octot.et 1988 March NUREG 1363 GUCANCE ON THE APPUCATON Of OU ALITY ASSUR.1909 ANCE FOR CHARACTERIZING A LOW. LEVEL RADIOACTIVE WASTE

DISPOSAL SITE. Finar ReportPARRY,G.

NUREG/CR4460 A CAUSE-DCFENSE APPROACH TO THE UNDER. PfTTW A N,J.

S'ANDING AND ANALYSIS OF COMMON CAUSE F AILURES NUREGO933 S11. A PRORITl2ATION OF GENERC SAFETY ISSUES

P ATE.J.R. PLANSKY,LE.NUREG/CR 5553 COMPUTER PROGRAMS FOR EDOY. CURRENT NUREG/CR 5542 MODELS FOR ESilMATION OF SERVICE LIFE OF

DEFECT STUO4ES CONCRETE BARRlERS IN LOW 4EM RADIOACTIVE W ASTE DISPOSAL

PAULA,H.

NUREG/CR 5460. A CAUSE-DEFENSE APPROACH TO THE UNDER. PLOUFFE M

STANDING AND ANALYSIS OF COMMON CAUSE FAILURES NUREG/CR.4 753 V03 CANADIAN SEISMC AGRELMLNT AnnualReport 1967 1986

PAYNE,A.C. NUREGICR-4753 V04 CANADIAN SEISM C AGREEMENT. AnnualNUREG/CR 4551 V281P1: EVALUATON OF SEVERE ACCIDE NT Report.19C 969

RISK.S OUANTIFCATION OF MAJOR INPUT PARAVETERS Empert

%'g'CR 5500Operson Encitabon On IrvVessel issuesNUREG/ ASSESSMENT OF THE COMBUSTON MOOCL INNUREG/CR-4551 V4R1P1: EVALUATION OF SEVERE ACCIDENT

RISKS PEACH BOTTOM.UN;T 2 Ma.n Report THE HECTR CODE.NUREG/C44551 V4 RIP 2. EVALUATION OF SEVERE ACCIDENT

RISKS PEACH OOTTOM,0NW 2. Apper@cesR CR 5213 V01 THE CJGS 'lVE ENVIRONMf hi SIMULATON

PEDE RSON,C.D. AS A TOOL FOR MOOitPO HUMAN PE RFORM ANCE ANDNUREG.1395 DRFT. INDUSTRY PERCEPTONS OF THE IMPACT OF RELIABILITY Esecutive Sunm iry

THE U S. NUCLEAR REGULATORY COMMISSION ON NUCLEAR NU EG/CR5213 V02: THE G 3NITIVE ENVIRONMENT SIMULATIONAS A TOOL FOR MO hlNG HUMAN PE RF ORM ANCE ANDPOWER PLANT ACTIV1 TIES Draft Report.REllABluTY Maan Repor*

PELAYO.F.PORROJNUREGRA.0019- TRAC PF1/ MOO 1 POST. TEST CALCULATONS OF

THE OECO LOFT EXPERIMENT LP.SB-2. NUREG/CR 560s asW AND TRANSPORT AT THE LAS CRUCESTRENCH SITE Espenments 1 And 2

PELUSSIER,W.PRICE,LL

NUREG/lA-0023 V01: ASSESSMENT OF TRAC.PF1/MOOI VERSONNUREGICR $211: UNCERTAINTIES ASSOCIATED WITH PER5ORM.14.3 USING SEPARATE EFFECTS CRITICAL FLOW AND DLOW.

DOWN EXPERIMENTS Voiume 1: Text And Tatde* ANCE ASSESSMENT OF HIGh. LEVEL RADIOACTIVE W AST EHUREGRA.0023 V07 ASSESSMENT OF TRAC.PF1/ MOO 1 VERSION REPOSITOR!ES A Summary Report

14.3 USING SEPARATE EFFECTS CRfTICAL FLOW AND BLOW. NUREG/CR-5256 COMPONENTS OF AN OVEnALL PERFORMANCEASSESSMENT METHOOOt.OGY.DOWN EXPERIMENTS Volume 2 Fgures

NUREG/CR 5398 TECHNICAL BASIS FOR REVIEW OF HIGH-LEVELWASTE REPOSITORY MODELING

NUREG/CR.5512 DAF FC: RESIOUAL RADIOACTIVE CONTAMINATON PUGH,R, '

FROM DECOMMISSIONING Techrwcal Basa For Transtahng ContA/S NUREG/CR 5617, AUxlLIARY FEEDW3 TER SYSTEM RISLB ASED IN.nahon Lowls To Annua 6 Dose Orart Report For Comment SpECTON GulOE FOR THE J M. FARLEY NUCLEAR POWER

PELTO.P.

NUREG/CR.54.37. ORGANIZATION AND SAFETY IN NUCLEAR POWER RASMUSON.D.M.PONTS

NUREG/C45111 INTEGRATED RELIAD4LITY ANO RASK ANALYSISSYSTEM CARAS) VERS:ON 2 0 USER'S GUCEPENNELL,W1

NUREG/C45460 A CAUSE OEFENSE APPROACH TO THE UNDER-NUREG/CR.4219 V06 N2 HEAVY SECTON STEEL TECHNOLOGY STANDING AND ANALYSIS OF COMMON CAUSE F ALLURES.PRCGRAM Sanuannual Progress Report For Apnl. September 1989RASMUSSEN.N.C.

PEPPER.S.E.NUREG.1420 SPECIAL COMM!TTEE REVIEW OF THE NUCLE AR REG-

NUREG/CR46% v03 SEISMIC FRAGluTY OF NUCLEAR POWER ULATORY COMMISSION'S SEVERE ACCIDE NT RISKS REPORTPLANT COMPONENTS (PHASE II) Sutchgear. l&C Paneis (NSSS) (NUREG-1150)And Retan

RASMUSSEN.T.C,PETE RSEN.K.M. NUREG{R 5482 LABORATORY ANALYSIS Of FLUID FLOW AND

NUREG/CR4560 AGtNG OF NUCLEAR PLANT RESISTANCE TEM. SOLUTE TRANSPORT THROUGH A VARIADLY SATURATED FRAC.PERATURE DETECTORS TURE IMBEDOED IN PORO'JS TUFF

- _ _ _ - - _ - _ - _ _ - . _ _ _ - - _ _ _ _ _ _ - - - - _ - - - _ _ _ _ _ - - - _ _ _ _ - - _ _ - _ _ - _ _ - - - _ - _ - - - - - - - - -- - - - - - - - - - - - - - - - - - - - -

- - - ._


NURL3/CR 5596 UNSATURATED FRACTURED ROCK CHARACTER- FtOLLBTIN,J.

IZATION METHODS AND DAT A SETS AT THE APACHE LEAP TUFF NUREG/CR-6381: ECONOMIC RISK OF CONT AM;NATON CLEANUP

S!TE. COSTS RESULTING FROM LARGE NONREACTOR NUCLEAR MATE-RtAL UCENSEE OPERATONS

gNUREG/CR4550 V3 RIP 3 ANALYSi$ OF CORE DAMAGE FREQUEN- ROLLSTIN,J.A.

CY SURRY POWE81 STATION, UNIT 1 EXTERNAL EVENTS NURE G/CR4551 Y2R1P7. EVALUATON OF BEWRE ACCOENTNUREGrCR-4550 v4R1P3 ANALYSIS OF CORE DAMAGE FREQUEN- RISKS OUANTIFICATON OF MAJOR INPUT PARAMETERS MA(XW

CY. PEACH DOTTOM UNIT 2 EXTFRNAL EVENTS InputNURE G/CR4691 Vot MELCOR ACCOENT CONSEOVENCE CODE

REDOENG.NUREG!CR 5547. APPtlCATON OF SURFACE COMPLEXATON NURE 89 V03 L CC T CONSEQUENCE 8:00E

MODELS FOR RADIONUCUDE ADSORPTION Sennitrvtty Analysis Of SYSTEM (MACCS)Voim 3 Programmers Reference ManualMooet input Parameters.

ROTH,E.EREE CE,W.D. NUREG/CR-5213 V01 THE COGNITIVE ENVIRONMENT SIMULATION

NUREG rCR-5540: PERFORMANCE TESTING OF EKTREMITY AS A TOOL FOR MODEUNG HUMAN PERFORMANCE ANDDOSIMETERS. STUDY 2 REUABldTY.EnscutN Survenary

NUREG/CR-5213 V02. THE COGNITIVE ENVIRONMENT SIMULATONREE CE.W.J,NUREG/CR-4639 V01 R1: NUCLEAR COMPUTERIZED UBRARY FOR AS A TOOL FOR MODEUNG HUMAN PERFORMANCE AND

ASSESSING REACTOR REUABluTY (NUCLARR) Summary Desenp. REUARITY. Main Report

tionNUREG/CR4639 V4PIR2: NUCLEAR COMPUTER! ZED UBRARY FOR ROTHLEDER.B.

ASSESr.NG REACTOR REUABluTY (NUCLARR) User's Guide Part 1: NUREGICR 5477 A RISiv6ASED REYtEW OF INSTRUMENT AIR SYS-TEMS AT NUCLE AR POWER PLANTSOvnew Of NUCLARR Data Retrwval

N7. MA4639 V4P2R2. NUCLEAR COMPUTERIZED UBRARY FOR NUGER,C.ASSESSING HEACTOR REUABluTY (NUCLARR) User's Ga.se Part 2. NUREG/CR 5471 A RISK BASED REVtEW Or INSTRUMENT AIR SYS-Guide To Operstens.

NUREG!CRW9 V4P3R2 NUCLEAR COMPUTERIZED UBRARY FOR TEMS AT NUCLEAR POWER PLANTS

ASSESSING REACTOR REUADIUTY (NUCLARR) User s Guide Part 3. NUREGICR 5572 AN EVALUATON OF THE EFFECTS OF LOCALCONTROL ST ATON DESIGN CONFIGURATIONS ON HUMAN PER.NUCLAAR Systern Descrpt on.

NUREG!CR409 V5PIR3 NUCLEAR COMPUTERLZED LIBRARY FOR FORMANCE AND NUCLEAR POWER PLANT RISK-

ASSESSING REACTOR REUABiUTY (NUCLARR).Deta Manual Part 1: RUSSELL.K.D.Summary DeurptiottNUREGICH46A v5P2R1 NUCLE AR COMPUTER 2ED UBRARY FOR NUREG/CR 5111. INTEGRATED REUABluTY AND RISK ANALYSIS

ASSESSING RE ACTOR REuABluTY (NUCLARR) Data Manual Part t SYSTEM (IRRAS) VERSION 2.0 USER'S GUIDE.Human Errcr Probatvirty (HEP) Data

NUREG/CR-4439 V5P3R3 NUCLEAR COMPUTER 2ED LIBRARY FOR RUTHER W.L

ASSESSING REACTOR REUADIUTY (NUCLARR) Data Manual.Part 3 NUREG/CR4667 V07. ENWONMENTALLY ASSISTED CRAChlNG INHardware Component F ailure Data (HCFD) UGHT W ATER REACTORS Sermannual Report.Apr* September 1988

NUREGICR4667 V08 ENVIRONMENTALLY ASSISTED CRACKING INREIL.K.O. UGHT W ATER REACTORS. Sermannual Report. October 1986 March

NUREG/CR 4668. DAMAGED FUEL EXPERIMENT DF 1 Resulta And 1989.Analysas-

SALOtOJ.H.RE YMANN,0.A. NUREGICR-5381: ECONOM!C RISK OF CONTAM!NAllON CLEANUP

NUREG/CR-5273 V04 SCOAP/RELAF5/ MOD 2 COOE COSTS RESULTING FROM LARGE NONRCACTOR NUCLEAR MATE-MANUALVOLUME A MATPRO A UBRARY OF MATERIALS PROP- RIAL UCENSEE OPERATONSERTIES FOR UGHT WATEF REACTOR ACCOENT ANALYSIS.

SANDERSAD." " "

NU G CR4918 V04: CONTROL OF WATER INFILTRATION INTO R NSNEAR SURFACE LLW DISPOSAL UNITS Progress Report On Fie6d Es-penments At A Hurmd Region $4Bettsvee.Marytand SATHE R,A.

NUREG/CR-5385 INITIAL ASSESSMENT OF THE MECHANISMS ANDRIGOSA StGNIFICANC OF LOW TEMPERATURE EGIT1 LE MENT OF

NUREG4933 S11: A PRORITIZATON OF GENERIC SAFETY ISSUES CAST ST AINutSS STEELS IN LWR SYSTEMS

RITCHIE,LT, BATT W RNUREGICR4691 V01, MELCOR ACCOENT CONSEQUENCE CODENUREG/CR 4550 V7 RCl' ANALYSTS OF CORE DAM.*GC FREQUEN-

SYSTEM (MACCS) Volume 1 Use s GMerCY: ZION. UNIT 1. IN4RNAL EVENTSNUREG/CR4691 VO? MELCOR ACCOENT CONSEQUENCE CODE NUREG/CR 5111: INTEGRATED REUABluTY AND RISK ANALYSISSYSTEM (MACCS)Vo4ume 2. Moded Desenpten.SYSTEM (IRRAS) VERSION 2.0 USER'S GUOE

ROBINSON,Q.C.NUREGICR-5451: CRACK ARREST BEHAVOR IN SEN WOE PLATES

SAWYER,C.NUREG-1404 UCENSEE USE OF T ACTICAL EXERCISE RESULTSOF LOW UPPER SHELF BASE METAL TESTED UNDER NONISOTH.

ERMAL CONDriONS. WP 2 SERIES SC AL20,6 M.NUREG/CP 5510: EVALUATONS OF CORE MELT FREQUENCY EF.ROGERS.R.D.

NUREG/CR-5229 VOL TMb2 EP1COR It RESIN /UNER INVESTIGATION FECTS DUE TO COMPONENT AGING AND MAINTENANCE.

LOW LENEL WASTE DATA BASE DEVELOPMENT PROGRAM FOR SCARMOUGH,T.G.FISCAL YE AR 1999 Annual Reprt

J NUREG/CR-5229 V03 EPICOR A RE%N/UNER INVESTIGATION LOW. NUREG 1351 ACTION PLANS FOR MOTOR. OPERATED VALVES ANDCHECK VALVES.LEVEL WASTE DATABASE DEVELOPMEN'T PROGRAM FOR FISCAL

YEAR 1990 Annual Report SCHMITT,R.C.NU*EG/CR-5649 V01: COMulX 1C: A THREE DIMENSIONAL TRAN-ROHAT GI,U.S.

NUREG/CR-5254 BIAS IN PEAK CLAD TEMPERATURE PREDtCTIONS SIENT SINGLE. PHASE COMPUTER PROGRAM FOR THERMAL HY.

DOE TO UNCERTAINTIES IN MOOEUNG OF ECC BYPASS AND OtS. FAAULIC ANALYSIS OF SINGLE-COMPONENT AND MULTICOM-SOLVED NON-CONDENSABLE GAS PHENOMENA PONENT ENGINEERING SYSTEMS Equebons And Numencs

NUREG/CR-5649 VOL COMMIX tC A THREE-OiMENSIONAL TRAN-ROLES,0.W- SIENT SINGLE. PHASE COMPLrTER PROGRAM FOR THERMAL HY-

NUREG 1418 CHARACTE RISTICS OF LOW-LEVEL RADOACTIVE DRAUUC ANALYSIS OF SINGLE COMPONENT AND MULTICOM-W ASTE OtSPOSED DURING 1547 THROUGH 1989 PONENT ENGINEERING SYSTEMS. User's Gusde And Manual

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- - _ - _ _ ___ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _

Personei Author Index 77

$CHetDEDt RJ A DHARMAV.NURE G/CR,6578 OVANTITATIVE ANALYtis OF PottNTLAL PtR. NUAt G/CR4663 PAf DICTION OF CHtCK VALVE PERFOHMANCt

FOHMANCE IMPROVEMENT $ FOR THE DRY PWR CONTAINMENT. AND DiGRADATON IN NLCLE AR POWER PLANT sy87 tut .NOREG/CA 6802 tiMP IPitD CONTAINMENT EVINT Tett ANALY. WEAR AND IMPACT TESTS FrW Rotat6aPtemlet Ipt . Neu 1993L

sis FOR THE $10VOYAH ICE CONDENBER CONTAINMENT.SHtif t.PJ.

SCHULTZ R.lLNURf G/CR 6696 UN&ATURATED FRACTURED PtOCK CHARACT[R.

NUREG/CR4618 VD4 OCNTROL OF W ATER INFILTRATON INTO 12ATON METHODS AND DATA 6ET8 AT THE APACHE LEAP TUBFNEAA SU6tFACE LLW D1580&AL UNITS Progress Aescr1 On Fm6d Eu- $tTE.pwinents #t A Huned Repon Sua.E6eltsvilla. Maya 4

$HIN Y.BCHUM ACHE R.P.M NU4EG/CA f436 V01: THE LhELOPMENT AND E VALUATON OF

NUREG/CA 4624 V06 RADONUCLOE Af LEtBE CALCULATONS PRconAMMATIC PERFOHMANCE NDICATORS AWOCtATEO WITHFOR E.ELEC7ED SEVERE ACCOENT SCENA8tch baguenemal CeMAiNilNANCE AT NUCLEAN 50WER PLANfB Main RePartcuteinria NU4tG'CFOS436 V02 THE DEVELOPME NT AND EVALVATON OF

6CHW ALLERA Q. PROGRAMMATIC PERFOAMANCE INDICATORS AMOC&ATED WITHMAINf(NANCE A1 NUO i AR POWLR PLANT $ Alge%cesNUREG/ CAM 16 LOW LEVEL RADIOACTIVE W ASTE Dl5POSAL F A,

CILITY CLOSURE Pa t i Lcryf erm Envircrimental C<<digt s ANect- $nitR,W.r

rg low Level W aiite Dragwal Sde Performa%e Fa'111 PerttrmateNUHf G/CFt6200 V01 AGE.NEL ATE D DEGRADATON Or WLSTING.MWkrng to suppyt 84epakry EWecna HOUSE ap> VOLT CIRCUlf DRf AKthS Agrg Assessment And fioc.

"SCHW ARTZ,C.W.

NUREGICR 646 L CRACOAHRIST DEMAYOH IN LIN WOE PLATE 5 SHivt RA W.OF LOW. UPPER SHELF BASE METAL itSf ED UNDEN NONISOTH. NUREG/CA 4661 V441Pt. EVALVATON OF 6t'YE RE ACCID ( NTENMAL CONDITIONS WP f EERIES RISAS PEACH DOTTOM UN!f 2 Main Heport

DCOTT.W* NUAE GICA-4651 V44tP2 EV ALV AT ON OF 6EVt kE ACOIDE NTAISES PEACH DOTTOM. UNIT 2 Agge%ces

NUREG/CA 643? OAGANIZATON AND $AFETY IN NUCLEAR POWL A NUHlG/CR4661 V6H1Pt. t VALVATON OF LEYE HE ACCIDt NTPLANTS hlStB SEQUOY AH. UNIT 1 Mam heportBCOTT,W.B. NUREG/CR.e661 Vf,841 P2 (VALUATON OF blVERE ACCCENT

niggg g togo 3 As vNig , App.,oc ,NUREG/CF446f f AECAITICALITY IN A BWR FOLLOWING A EORE NUHEG/CR4661 V64 t P t . EVALVATON OF SEVERE ACCID ( NTDAMAGE EVENT. AISAS G4AND GULF. UNIT 1 Main Hepyt

N+)Rf 0 CR4651 V0HtP2 E V AL UATION OF SEVE RE ACCIE(NTU4 C 6464 PH BENSOAS DASED ON IAIDIUM OAIDE *

6 ERNE TJ IHUM'O ''NURE G/CA 6546 REVIEW OF GEOCHEMICAL PROCEGCES AND NURE0 *Ch.bd73 INCLUSON OF VNST ADLE DUCTILE tt ARING AND

COOLS FDA ASSESSMINT OF RADONUCLIDE MiGRATON PO- FKTRAPOLATED CRACK-ARHEST TOUGHNESS DATA IN PWRTENTIAL AT COMMERCIAL LLW STILL YESSEL INTEGRITY AMES$ MENT.

$tavER W.L $ltGEMANUREG/CA 4731 V02 HESOUAL LIFE ASST % MENT OF MAJORNUREG/CH4731 V07 AESIDUAL trFE ASSEMMENT OF MAJOR

LlGHT WATER REACTOR COMPONENTS - OVERVIEW LIGHT WATER RE ACTOR COMPONENTS . OVERVIEW

SETH.S.& "

NUAEG/CP4104 PUDtIC WOAKSHOP ON NUCLE AR POWL A FLANT Ntl4'00/CR 6631- CONTHIDUTION Or MATEkNAL HADIOr*UCtIDELICENSE 3ENEWAL BURDENS TO PRLNATAL HADIATION EOSL61nterim

hecommendatens For CommentSELM RJL,

NVAIG-1392 LEAKAGE OF AN IHRADIATOR $OURCE . THE JUNE IONA1988 GEOFGIA R$1 INCIDENT. NUH1G/CR4469 VCS NONDESTRUCTIVE E AAMINATON (NDE) Hell.

AB!LfTY FOR INSENCE INSPECTION OF LIGHT W Ail R$HA,W.T. HE ACTORS Semiart 4.i Retxvt Oetc4er i98 7. March 1998

NUREG/CA 6tt49 V01. COMM%1C A THREE,DIMEN$ONAL TRAN. NUREG/CR4469 V09. NONDE STHUCTIVE E AAMINATION (NDE) AEll.'SlENT SINGLE. PHASE COMPUTE R PHOGRAM FOA THERMAL HY. ABluTY FOR INSEHVtCE INSPECTON OF LIGHT WATERCRAUUC AHAD646 OF GIGE.COf.lPChCNT AND ML"JiCO% NF'#2TO" b"M V *l Aerev1 Atwt Baptar'far 1968PONENT ENGINEE RING bYSTEMS Equatene And Numerins NUREG/CR4460 V10"HONDESTRUCTIVE EAAMINATON (NDE) At a

NUREG/CA 6649 V02. COMMik 1C A THREE. DIMENSIONAL TRAN. ADillTY F04 INSC HVICE INSPECilON OF LIGHT WATERBLENT SINGLE. PHASE COMPUTER #140 GRAM FOR THERMAL.HY, RE ACTORS bemiavual Hoport.Octoter 1988 + March 1989DRAULIC ANALYSIS OF SINGLE COMPONENT AND MULTICOM. NUREG/CA 6117. STEAM GENERATOR TUBE INTEGRITY PROGRAM /PONEN1 ENGINEERING SYSTEMS UWs Gum And Manual ST LAM GENERATOR GROUP PAOJE CT Final Ptolect Summary

Aeport$ HACK,WJ.

NUREG/CA4f47 VO h ENVIAONMENTAllv A$$1ST* n CRACKING IN SINHA,U.P.

LIGHT WATE R RE A CTOHS Semiannuai heport. AF 4Septamtiar 1968 NUREG/CA 4731 V02 Af SOUAL UFE ASSESS 84ENT OF MMORNURE G/CR4667 VOS ENVIRONMEN T ALLY ASS 4 FED CAAChlNG IN LIGHT WATER REACTOR COMPONEN19 OVERYlEW

(T WATER REA'.;TOAS 5ermannual Per.ortC ' toter 1988 March

NUREG/CH4661 V3R1P1: EVALVATON OF SEVERE ACC: DENTSHAH,V.N. Al&AS SURnY UNrT 1 Mam Hoport

NUREG/CA4731 VC2 RESIDUAL LIFE ASSESSMf NT OF MAJOR NUAE G/CA46,1 V3RtP2 EVALUATION OF SEVERE ACCIDENTLIGHT WATER HEACTOR COMPONENTS OVEHviEW HISAS SURRY UNIT 1. Appereces

NUREG/CA 6314 V03 LIF E ASSESSMENT PROCEDURES FOR NURf G/CH.4661 V4 RIP 1. EVALUATON OF 6EVERE ACCIDE NTMAJOA LWR COMPONENTS Cast Starvees Steel Components RISAS PEACH DOTTOM.VNIT 2; Ma n Retxvt

NUREG'C44661 V4RtP2 EVALVATON OF SEVERE ACCOENTSHANNON.WL RISAS PEACH DOTTOM. UNIT 2, Appereces

NUREG/CA-4763 V03 CANADIAN $ELSMC AGREE MENT. AnnualReport 1987 1968 SMfTH,R.E.

NUREG/CR4763 V04 CANADIAN SEitMC AGHEEMENT. Annual NURED/CR 6476 MODEL FEASI0luTY STUDY OF RADOACTIVEReport 1986 1989 PATHWAYS FROM ATMOSPHERE TO SURFACE WATER

_. - , - - - - ,

(

76 Porscnal Author index

bMf1HAL ST ALL M ANNf .W.NUMEGICF4472 ADD 04 YECH4GLCOY, $AF ETY AND COE16 OF NUHt G/C44316 PR E DD POWE H FiEACfDH E Wilf TLE MI NT

DiCOMM%OWNG A HEFlittNCE 101U40 W ATIR HEACTOR DAT A hA$t.VE RSON 1 Prqam DowytmPOWE ft $f ATON Covventan Of two Decwmanwwig Cost I sto NUHI G'CR f409 NEUTRON EsPOSUHE FARAMEllRB F OR THEfrets 4 Devoi4*d For TP4 bame Conviteruel tapar Rom tos 8' war MiT ALLUROCAL f(St 6PECIMEt45 Iti THE Skf H HI AVY-M G.

TON STt E L litRADiAT ON MiulBNaton#4UREG/CR 2001 AD001 TECHNOKOY.LUETY AND COSTE OF DE-

OOMMISSONnNG REFERENCE UGHT W ATER RE ACTOR $ FOL- STARWiR.RJLOWING POSTULATED ACCIDENTS Re E wluatm Of Tte C6ca%p NUREG 1383 GUIDANCE ON THE APPLCATON Of OUA'.lf v AMUR-

ANCl FOR CHARACTERillN3 A LOWLEVE L RADCActIVE W AS10Coat F or The ikuiny Water Rometor (BWh) is erwn 3 Ament F romDISPOSAL bl1[ Final HawtNUREG/CR 2691

BT E t PLE 8,D W.$MITH,n W.NUHEG/CRM42 MODELS FOR ES1tMATON OF SERVICE Lire OF NUHf G/CR 66?9 MICHOLARTHOUAAES IN AANSa$ AND NEDRAL

CONCRETE BARRIER $ IN LOW 4EVEL RADCACTIVE W A$TE Dib AA 19771W9 FvW Fsenvt

$TEINitRECHE R.H.

$MYTHJ D. HJHE G/CR4001 CLOSEOUT CW !E BULLE flN t&O3 MDTO40PEH.NUREG/CR$$23 DEVELOPME NT OF AN INFILTRATON EV ALUA- ATED V ALVE .':OMMON MDOE F AILURES DURIN3 PLANT thAN-

TON ME1HODOLOGY FOR LOW 4EVEL W ASTE SHALLOW LAND STENTS DUE f 0 lMPHOPEH bWiTCH 6E TTING&ElVRIAL SITES ST E TSON,F.T.

SOMMf R.S C. NUREG/cstM22 ANALYSIS OF REACTOR TRIPS ORIGiNAtlNG INNUREG!CRM44. CONSEQUENCE LvALUAtlON OF RADtATON EM- BAaNCg Of PMN1 $Y$1 EMS

DRitTLEMENT OF THOJAN RE ACTOR PREB5URE VEME L SUP,PORTS STRUCKMEYER.FL

NUREGW37 vo9 Noe NAC TLD DIRECT RADIATON MONITORINGSOO.P. NETWORA. Progress Report CNtoter Enocomtier 1969

NUREG/CR 3444 V07 THE IMPACT C# EWR DECONTAMINATONB NUHEG-0837 V10 N01 NRC TLD DlHECT RADIA10N MONNAINGON SOUDIFICATION W ASTE DISPOSAL AND A%OCIATED OCCU. NETwong progres. Report January March 1990PATONAL E APOSURF NUREGC637 V10 NU2. NHC TLD DlHECT RADJTON MONITORING

NETWORK Pecyons Repyt AproJune i993BOPPET.W K. NUREG 0637 V10 N')3 NRC TLD DIRECT RADIA10N MONITORING

NURf G/CR4607 VOL ENARONMENT ALLY AS$1STED CRACKING IN NETWOHK Prcyons hem My $eptember 1WOUGHT W ATE R RE ACTORS fmannual Report Arve Septemter 1986

NUREG/CR4667 V06. ENVIRONMENT ALL4 ASSISIED J4ACAIN3 IN gTyggE,EALIGHT W ATE R RE ACTORS Semes'vual Report Octoter 1968 March NURE G/LA 0034 ASSESSMENT BTUDY OF FtELAPS/ MOO 2 CYCLE1989 36 04 BASED ON PHES$URt2ER BAFETY AND REUEF VALVE

6SPANNERJ C.

NUREG/CR4469 VO8 NONDESTRUCTIVE F.XAMINATON (NDE) Hell' SUBUDHt M.ABlVTY FOR INSERVCE INSPE CTION 05 UGHT WAn 1 NunEG/CR t280 V01 AGE.RILATED DEGRADATON OF WESTING-

A m9 A4**ssrnent And neoR R 9NU5 E /C 4 9 Yb9 ET T E E $M NDE) FiEU.

gyQg*CR*

ABILITY FOR INSERVICE INSPECTON OF LIGHT WATER V02 E TED DATION OF WESTit4G-HM4M M BHE AtW With %g D A Wh TR 11 E AAM N ON (NDE) REll.NU EG CR 49

yy',N,*g* }" (c' A%ESSME NT OF INSTRUMENT AiH SYS-ABtUTY FOH INSERVICE IN$PECTON OF LIGHT W ATE RRt ACTORS Semennual ReportOctate 19M . March 1989 TEMS IN NUCLEA' PGvEk PLANT &

NUHE G/CH 4BB2 QU ALIF 6CATON PHOCE SS FOR ULTRASDNICTE STING IN NUCLE AR INSERVICE INSPECTON APPUCATIONS gyg ygg,g y'

NURE G/CR4908 ULTRA!OMC INSPECION REUABldTY FOR IN. T O RADCACTivEL Fn AS E[L1 YN R[ gyg 7TERGRANULAR STRESS CORROSON CRACAS A Hound Roten

Study Of The Ettocts 01 Portorvel, ProMses. E0Jpment, And CrackCtwoctenstca SWINT,i.tA

NUREG/CR 6566 LVALUA10N OF HE ALTH EFF ECTS IN SEOLOY AH$PE &SARO,R.L FUELS CORPORATON WoHAERS FROM ACCIDENT AL EXPOSURE

NUREG.1425 WELDING AND NONDESTRUCTfvE EXAMINATON TO URANIUM HEXAFLUORIDEISSUE S AT SEABROOK NUCLE.AR ST ATON An independent Reve.

$ Y PE.T.T.tM.EG.'CH C OVP Rt ANALYSIS OF C04E DAMAGE FHEE% EN.SPINDLE R,8.

CY INTERNAL EVENTS METroDOLOGY.NUREG!nA4023 V01: A%ESSMENT OF TRAC.PF1/ MOD 1 VERSON

14 3 USING $EFARATE EFFE. CTS CRITICAL FLOW AND B60W- TABATABAt.A.S.DOWN EXPERIMENTS Volume 1 Test And Tataes NUREG/CR 6397. V ALUE lMPACT ANALY$1S OF RFGULATO 4Y OP-

NUREGAA 0023 V02 ASSESSMENT OF TRAC FTt /68001 VERSION TONS FOR RESOLUTON OF GENERIC %UE C-8 MIV L',AAAGE14 3 USING SEPARATE E FFECTS CArtlCAL FLOW AND BLOW. AND LCS F AILUHILDOWN EXPERIMENTS Vokame 2 Fnpros

I AM.P 8-$PRUNGdL NUREG OM7 605 $AFETY EVAU. AT ON REPORT RELATEL TO THENUREG/CR4551 V2R1P7. EVALUATON OF SEVERE ACC4 DENTRISKS OUANTiflCATION OF MMDR INPUT PARAMETERS MACCS OPERATON OF W ATT$ BAR 7UCLE AR PLANT. UNIT 6 S AND

2 Docket Nc4 60 M0 And fo39' oennessee Yeoy Auttoity)input

NUREG/CR4691 V01: MELCOR ACCIDENT CONSEQUENCE CODE T AN,H.BySTE M (MACCS) Volume i UWs GodeNUREG/CR4891 V02. MEiCOR ACCOLNT CONSEQUENCE CODE NUREG/CR3469 V05 OCCUPATONAL EOSE REDUCTON AT NO-

SYbTEM (MACCS) Volume 9 Modei Dusenpton CLEA81 POWER PLANTS ANNOT ATED DiBLOGRAPHY OF SELE OT.ED READINGS IN RADIATON PROTECTON AND ALARA

BRINIV ASAN.M.G.NUREG/CR4699 DYNAMIC TESTING OF A CIRCULAR FOUNDATON TARLOV,M J

AND ANALYSES OF SOIL / STRUCTURE INTERACTON NURf G/CR-6464 PH SENSORS BASED ON IRIDIUM 01|DE

ST. EKER.K.T. t 60E R W.f4UREG/CR4MW DAMAGED FULL EXPER) MENT DF 1 Results And NUREG/CRM53 RECRITICAUTY IN A DWR F OLLOWING A CORE

Anahyses DAMAGE EVENT.

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b

Per$Onel Author %s 79

TAYLOR,64 TDIAVISJ RNURE G/CR 484 P4 EDS POWE R HEACTOA EMD*11TTLE ME NT NUhEG/CR S460 DATA SUMMARY AE PO84T FOR flbSON PRODUCT

DATA BASE.VEF4blCW % Program Dowription RELEASE TEST Vi $T A YLOR,J. TRAY:S,R

NUAE G/CR 6607 NESULTS P ROM THE NLOLEAR PLANT AGWG RE. NUREG/CA 6837. GENE 5HC RISK INSIGHTS FOR WESTNGHOUSEU " b ^ ""^NURE 6 N b i TS C E i N HOUSE g

AND COMBUSTION ENGWEERING PAESSURIZED W ATEN READTOAS T R0TTIE R.C.A.

TAYLORJJ W4W409 SACWTTING MLNESNURE31420 SPECnAL COMMITTEE REYlEr OF THE NUCLE.AR NEG.

ggggg[g,gULATORY COMMSSON'S SEVERL ACCIDENT RISAS REPOAT ggq G/CR M39 HUMAP, FACTORS % SUE $ ASSOCIATED WITH AD.(NUREG.t t 60)

% ANCED INSTRUMENT AflCW AND CONTROLS TECHNOLOQlES INT A YLOR.T.T. NUCLE AR PLAV1S

NUREG/CA4469 V06 NONDESTRUCflVE EEAMWATON (NDE) HELI-ABILfYY FOR INSERVICE INSPENON OF UGHT WATER V AN HE WMAE ACTORS femiannual RowtOctober 1967 March 1988 NUREG/CR 6M8 V01- INDUSTRY DA5ED PENFORMANCE IND6CA.

WREG/CR4409 V09 NONDL STFtVCTIVE EXAMWAf 0N (NDE) nEU. TOAS FOR NUCLE AR POWER PLANTS Ph46e 1 Report Jure 1969ABluTY FOR INSE RVICE INSPECTION OF UONT WATER February 1990.At ACTOR $ Semiennual Rowt,Agu4eptemtgr 1986

NUREG/CR4469 v10 NONDLSTRUCityt E AAMINATION (NDE) REll. VAN TUYLE.G4ABluTY FOR INSERVICE INSPECTON OF UGHT WATE R NUREG/CR-3668 M! NET CODE DOCUMENT ATONRE ACTORS Sermannual ReportActober 1DM Me<ch 1989

NURLG/CR4882 OUALIF ICAT ON PPOCESS FOR ULTRA 90NIC VANDENKIIbOOMTESTING IN NUCLEAR INSERVICE INSPECTON APPUCATONS NUREG/CR 6474 4fMSSMENT OF CANDIDATE ACCIDENT MAN-

NUREG/CR4900 ULTRASONIC INSPECTION HEUAfiluTY FOR IN. AGEMENT STRAllGIESTE RGR ANULAP STRESS CORROSION CRACKS A Hound RotenStudy Of The Effects Of Pwoonnel Procedures, tempment. And Creeg V ANHOE N ACKE R,L

Cte.aciensbCt. NURE G/lAe]34 ASSESSMENT STUDY OF HELAPS/MQD2 CYCLE36 04 BASED ON PRESSURIZEH SAFETY AND HEtt[F VALVETEAGUE,KJ. TESTS

NUREG-1420 SPECLAL COMMITTEE HEVIEW OF THE NUCLEAR REG.ULATORY COMMIS$ON'S SEYERE ACCIDENT RISKS REPORT YE tt L Y,W.E.(NUNEG.1160) NUREG/CA $610 t vALUATONS OF CORE MELT FAEOUENCY EF.

FECT$ DUE TO COMPONENT AGING AND MAINTENANCE

NUREG/CR 6654 RECOMMENDATONhl FOR THE SHALLOW. CRACK VILARDO,PJFRACTURE TOUGHNESS TESTING TASK WITHIN THE HSST PRO' NUREG/CR4399 SURVEY OF STATE AND 78uBAL EMERGE.NCY AE.GRAM-

SPONSE CAPADIUTIES FOR RADOLOGICAL TRANSPORTATIONTHOMASJT. INCOENTS

NUREG/CR47E4 V03 CANADIAN SEISMIC AGRE E ME NT. Annual ygtgAgAgg.

N FIG C V04 CANADIAN SEISMIC AGREEMENT, Annual WAEG/CRW AGWG ASMSM OF WSMNT OR 84Rom 1g66M TEMS IN NUCL EAA POWE A PLANTS

NUREG/CR4472 A RISK.ItASED HEviEW OF INSTRUMENT AIR SYS-THOMPSON.N G. TEMS AT NUCLEAR POWE A PLANTS

NUREG/CR4436 EWIRONMENTAL EFFECTS ON COHRO$lON W

[g, ,g g ggg g g gTHE TUFF REPOS.' TORY.8

THOMSONAF. THENCH BITE Esperiments 1 And 2NUREG/CT4704 V03 RELA 1;VE BOLOGICAL EFFECTfvtNESS (RBE)

OF FISSON NEUTRONS AND GAMMA RAYS AT OCCUPATONAL V0.T.V.ERPGs0RE LEYELS Stuclies On The Oroes And Meroecopic Patho 6o. NUREG/CR4489 V10 NONDESTRUCTIVE EKAMINATION (NDE) REll.gy Observed At Death Of Mice Espo6ed To 60 Eesel Once Weekly ABlMTV FOR INSERVICE INSPECTON OF UGHT WATEROoses Of Fms6 ort HEACTORS Semiwmas Heport October 1986. Much 1989

NW tG/C4 6397. VALUE.lMPACT ANALYSIS OF AEGULATORY OP.THURDERJ. TONS FOR HESOLUTION G GENE AIC ISSUE C-8 MSly LE AKAGE

NUREG/CR4437; ORGANIZATON AND 6AFETY IN NUCLEAR POWER AND LCS F ALLUREPLANTS NUREG/CR4616 AUXILIAAY FEEDWATER SYSTEM RISK BASED IN-

SPECilVN GUIDE FOR THE DiABLO CANYON LWIT 1 NUCLE ARTOKAR2,R.D.POWER PLANT.

NUREG/CR 6663. RECRr11CAlfrY IN A DWR FOLLOWING A CORE NUREG/CR 5017. AUXILIARY FEEDWATER SYSTEM AISK. BASED IN.DAMAGE EVENT- SPECTION QUOE FOR THE J M FAALEY NUCLEAR POWER90LUJ E. I

WUREG/CH4376 OVAUTY ASSURANCE AND VERIFICATION OF THE VON WINTERFE1DTMACCS CODE Version t.6'NUREG/CR 6411: ELICITATION & USE OF EXPERT JUDGMENT IN

TONG,W.R PERFORMANCE ASSESSMENT FOR HOH4EVEL RADOACTIVENUREG/CR 4660 V3 RIP 3 ANALYSIS OF CORE DAMAGE FREQUEN W ASTE RE POSITORIES

CY SURRY POWER STATON.UNrT 1 EXTERNAL EVENTSNUREG/CR 4660 v4R1P3 ANALYSIS OF CORE DAMAGE FREQUEN. WAGMR,K.C.

CY: PEACH BOTTOM.UNfT 2 EXTERNAL EVENT 8 NUREG/CR 6628 AN ASSESSMENT OF BWH MANA 11 CONTAINMENTCHALLENGES FAILURE MODES. AND POTENTLAL IVPROVEMENTS

TONG.Y. C. IN PERFORMANCENUREG/CR 6480, DATA SUMMARY AEPORT FOR FISSON PAODUCT

ALLEASE TEST VL3 WAHl K K-NURE G/CR 6211: UNCtRT AINTIES ASSOCIATED WITH PERFOR4

TRAUS.R4 ANCE ASSESSME NT OF HIGH LEVEL RADIOACTIVE WASTENUREG/CA 6631: CONTAIDUTON OF MATERNAL NADONUCLOC HE POSITORIE S A $ummary ReportBURDENS TO PAENATAL RAD 4ATION DOSE $ 1nterim NUREG/CR.6266 UOMPONENTS Or AN OVERALL P6RFORMANCERecommendehons For Comment ASSESSMENT METHODOLOGY.

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_ _ ____ _ _ _ _ _ _ . _ _ _ _ . _ _ . _ _ _ _ _ _ _ .

80 Pef $onal Author index

NUnitCR 5Nfi Ti rttNicAL BAS!$ f 04 REVIEW Of HIGHMVEL Wi&Lt Y,0 AW AMi Hi 9% Tom Mobt LIN3 NUHf WCf4 6h03 f*IbSUhr.D(PiNDE NT f 4AGilfTil8 F04 PIPING

NUHL UCR t!?t U$1 OF Pt H5 ORM ANCE ALM b6 MINT IN A6 COMPONE NT $ Pid $tsty On Dews flesse Naolear Powas 6talmetBl%ita COMMIANCE WITH THE CONT AINME NT HI OulhE -ME Ni$ IN 40 D H PANT 191 WETMILEENAJ

NUntG/ Cit 4163 V03 CANADIAN SEl6MIC AGht i Mi NT A inualCAHL.K K Repart t967.19tta

NUHLG CA EW A RIVtEW EW TICHNOUf $ FOh PAOFAGATING NUpi[G/Cn.4 ?b3 V04 CANADnAN $6&MIC AGREIMENT ArinualDAT A AND F @ AME tt H LA ERT AINTIE S IN HIGH LEVEL RADO- Repvt 19681k89ACitVE W Alii RFPCS MHY PE RF ORM ANCE ASSELLML NTM(Ot L8 WHARTONA.

NURf G 1214 Ft36 H!$TORICAL DAT A $UMMARY OF THE $Y$TIMA1'

W ALDREN.C A. C ASM BbMINT Or LICE NSI( Pt RFORMANCENJR1 GerA MJS CE L L ULAR AND MDLE CULAR HE $E Af 4CH TO

HFWCl UNei nT A'NTil s IN [ SitM4TE S Of HE ALTH [F FL CTS WHE ATLL Y.CJT HOV LOMf vf L RADlATON A f cautnMy Staty NUREG/CR 596 V6CTOhiA A MICHANISTIC MODEL OF HADONU-

CLIDE tiEHAVO81 IN THE NE ACTOR CCOLANT SYSTE M UNDiH% ALTON G BEvtHE ACCIDENT CONDITIONS

NUHtG t4M wti DWG AND FONDE $ T HUCTIVL E AAMiNatONiMINS At bf AbODOK NUCLEAR STATON An in:lasemient ficoes WHt E LE R.T.A.T e49 Report NUREG'C84 4550 V01 nt: ANALYSIS Or Cone DAMAGE rntOVEN

CY. INTE RNAL fYtNTS METHOLOLCOY

; NJhiGO 692 MODEt$ FOR ESTIMATON Or SErwiCE Lire Or WHITELI' goy.>ttit DAR5itEF45 IN LOW 4EVEL HADiOACTIVE WASTt dis- NURtG!Cf4 beth. LOW 4EVEL FMDIOACTIVE W A$1E Di&POSAL F A-

POSAL C1LITY CLO$UHE Pari i Lor $ Term Environmental Cy@ lions Af ect-vy Low Level Weste Deposer $ne Pedwmance Pa'i il Pedarmra

N(C /CA-f A e3 PREDtCTON Or CHICK VALVE PEMORMANCEN

AND Dt GRADATON IN NUQ T AR POWER PLANT SYG' EMS WIC KLIF E,0.S.WCAR AND iMn ACT TE STS Fna trot.Septamte 19h8. April 19ic NUREG/CH t.229 V03 ErtCOn* 8tE0lN/ LINER ltNESTIGATON LOW.

LEVEL WA$fK DATABALE DEVELOPMENT PROGRAM FCW4 flSCAL"'

I CR56R Alif hNATE MODAL COMDiNATON METHODS INRf SFONSE $PFCTNUM ANALY$lS. wiEntNGA,p),

NUDEG/CA46M, FLOW AND inANSPORT AT THE LAS CflVCl $# ** "''' I #

t iG f46613 V01 ACCIDENT M ANAGE MFNT INF OHM AT ONtdEDS Vee 1 Methodology Dwe+opment And AM4aton To A wtLHgEy,w,Preamrect Wetm Ansctor (PWh) With A Larpe Dry Comarvnent NUNEG/CR4200 V02 AGE #itt.ATLD DEGRADATON OF WESTING.

t4U4E G!CH 55t? Vo? AGCIDE NT MANAGLMENT IN5 OHM ATON HOUSE 480 VOLT ClHCUli 1640 At E 81S Mechavet Cycling Of A D5-NEEDS Volume 2 Appente$ die Eoce6er test Heasts3

It G CR 4 F3 t V02 HESIDUAL (IFE ASSESSM[NT Of' MAJOH NURE G 'CP-0109 PRNEEDINGS OF THE SEMINAh ON Lt AK.

LtGHT WATE A HE ACTOft COMPONENTS DVLHV!E W fiUORE DREAKlurther Developments in RegJetory Polace Andbupseng Amych

WATKIN$A ANUHE G< t415 - V0;I Noi . OF FICE Or THE INSPECTOR

(GfCR 646 VICTORIA A Mt CHANISTIC MODEL Or HADaONU." O'

GENLRAL $emiamuel Repet April Septemter 1990 NCLIDC DEHAVOR IN THE HE ACTOR COOL. ANT $YSTEM UNDE A

WE ATHlht.fJ R. BEVERE ACCIDENT CONDITIONSNUMG/CA 6470 POSTTEST AN AL Y S!S OF A 16 5CALE FiEIN-i OHCED CONCHETE Hf AC104 CON T AINML NT DUILDING WILLIAM $.D.C.

NUREG/CR f686 MfflGATON OF DiHtCT CONT AINMENT HE ATINGw g esit pEC.s. AND HYD400tH COMBUSTION IVENTb IN ICA CONDENSERNURLGm4 b440 DAT A SUNiMA4Y RE PORT FCnt risSON PRODUCT PLANTS Arwytet We The CONT AIN Cute And NUREO 1160 PRA

HEL EAM TEST VF3 MetW M gy

OtlL S.A.J.NUHLGrCb0106 V01: WOCE E DINGS OF THE SEVENTEENTH

WILI 1AW8 W LNL WQ/CH S449 DETI AMINATION OF THE NEUTHON AND GAMMA

w ATI R REACTOR SAFETY INFORMATON MEETINGNUPEG /CP-oi% V02 PHOCEEDINGS OF THE SEVENTLENTH FLUA DISTHIBUTION IN THE PRE %$URE VELSEL AND CAVITY OF

W ATER RE ACTOn SAF TTY INFOAMA HON MEEN A 84041NG W ATER RE ACTOR

NUHEG/CP 0105 V03 PHCCE EDINGS OF THE SEVENTE E NTH NUREG'CH 6630' ANALYB15 Of HD MIN $ON PAR V[$CELW ATER C ACTOR LAFETY INFOHMATON MF:ETING FLUENCE f Oft CYCLE 10 UTILMING PARTLAL LENGTH SHIELD AS-

NUREGrCP-Otti THANSACTIONS Or THE EtGHTEENTH WATER HE. $[MBLIESACTOR SAFTTY INFORMATION MEETIN3

NUREG/CR 2331 V09 t43 SAFETY RESE ARCH PHOGRAMS SPON WONG.C.

SORED DY OF F ICE Or NUCLEA4 AEOULATORY NUREG/CR-4763 V03 CANADIAN SEISMIC AGRE EME NT. AnnualAE SEARCH Progens AeportErbeptember 1969 Heport 1987 1966

4UREG/CR 2331 V09 Nw SAF EiY RESF ARCH PROGRAMS SPON-NUREG/CH-4 763 V04, CANAD!AN BE ISMIC AGREEMENT Annual

SMFS BY OFFICE OF NUCLE AR NEGULATORY Report 19ft61969

REM A4CH October Ducemte 197,9 WONG,$.NUAEG/CR $$27. HISK SEN$fTNITY TO HUMAN ERNOR IN THE LA.WtNDtL.M W.

NUHEG/CR 5306 HT AS2 A THREfbDiMENSIONAL TRANstlNT $ HIP- SALLE PCA..

PING CASK ANALYSIS TOOL WDCDS.D.D.NUhEG/CR 5213 vot THE CDGNtTIVE ENVIRONMENT SIMUL ATIONWERHY,E V.

NUNEG/CR 63B6 UA61S FOR SHUDDEF4 AGiN3 HESE Af4CH NilCLE- AS A TOOL FOH MODELING H' JM A'.4 ITAFO4MANCE AND

An PLANT AG|N3 HESE ARCH PMOG AAMHELIABRITY Esecuhve Furnmey -

NU4EGtCR5490 V01 REGULATOHV tNSTRUMEN* HEVIEW MAN- NUREG1CR L213 V02 THE COGNITIVE ENVIRONMENT StMULATION

AGEMl'NT OF AGING OF tv ' SA' ETY.HELAf t D COMPO- AS A TOOL &OR MODELING HUM AN PE RF ORMANCE ANDNE N Til

RELIADiLITY Mem Report

_-_,.___---_m- ._ ____.__.- _. _ _ . - _ - _ . , . _ _ . _ . . _ . m., , . _ _ _ . - , - _ . - . -

- _ _ _ . _ ___ __


wo0f0N.R D. NUHiG/CH b%6 v02 CAH( b (COul'Utt H ANAL Ytati f OH MAP!DNU8t(G/CH f463 N(CHITICAUTY IN A DWR $0LLOWING A COHi ( V ALV ATON OF $f HUCTUHf h) Vi ttMON t O f e nisc

DAMAGE LVLNT- Maus Um MarwalNUHLG/CH 6%8 v03 CAht 5 (COMI'Utl H ANALYS$ f 0H HAl'ID

WREATHALL.J.Nunl G/CH f.436 VD1 THE DIYtLOPMLNT AND f vALUAttON OF [V ALVA T ON 06 SfHUCTURES) vi hbiDN 1 (s kunnig

$HOGRAMMATIC PEF 4FOf4MANCf INDCATOHS AS$CCMT[D WITH Maus Sams4e P#ccomoMAINTINANCE At lACLE AH POWf H PL ANTS Main F,omwt

NUHEG/C4-6438 V02 THE DEVELOPME NT AND LvAtuATON OF Y ANG,J.W.

PHCKiRAMMAfC PERFOAMANCf.1NDICATORS A$$0CLAf t D WITH Npqt3i04 bM?. PWH DAY CON! AINMI N1 t%UL CHARAL flHi2A.iMAIN 1tNANCE At NVOLE AR POWER PL. ANTS Ap(m%w sigy

WU,8 YOUNG.CJ.NU8tf G/CR 3HO VDO. F UCL PERFORMANC.C ANNUAL Alf911 FOR NURLG/CA 3146 V00 GL OPH YSK,AL INyt SIIG ADONS W T HE.gggg

WE$1L RN OHIO INDANA RI'GiDN Annual heart.uc uw li+h6 |WULF F .W. SeptemLer 1969

NU810G/C4 $PM blAS IN PE AA CLAD TL MPERATURt Pft[D6CTONSDUt TO UNCERTAINUtS IN MODL LING OF f CC BYPASS AND DIS- giuut RM AN,DA,taVf D 190NCONDENEARLE GAS PHf.NOMLNA' NURLG/CR b)DJ A REVil W 08' Tf CHNoot D FOn FoorAGAUNG

gg J. DATA AND PARAME'iLN UNCU4TAINillB IN HKiH tlviL RADIO-NUREG/CR %68 Vol; CAACS { COMPUTER ANALYSIS Fon RAPID ACTIVE WASTE I4LPO5ff 0RY Pt.R8 0nM ANOC AS5t h5ML NT

EVALUATION OF STHUCTV4ts) VERSON 10 $ommec Ma9ftsMose Theoretecal Manual

||

'

- ... -. - . . - - , _ - - - . . . . . . - _ - - - - . . ~ . . - . _ ~ . - . . - - , - - . . - - . - - - . - . - . . - - .

a a u m, J e - - - - - - - A--".s ~AmSm ,A -,.a- en A,. - --A .A,n--- -- --nMAA-m-44. .a .A- ~ ,-s n--o. ,aA._2 mAm6,. n.-+ A -.--n-'

,

,,

1

1

.I

|

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,

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I. . . . .. .

>

|

; Subj:ct index

This Index was developed from keywords and word strings in titles and abstracts. During thisdevelopment period, there will be some redundancy, which will be removed later when a rea.sonable thesaurus has been developed through experience. Suggestions for improvementsare welcome.

,

40 CPR Port 101 NUREQ/CR4613 Wl: ACCOENT MANAGEMENT INFORMATIONNUREG/CR 6521: USE OF PERFORMANCE ASSE&BMENT IN AB. NEEDS Volume 1. MotNxkdogy Development ArW Appk.eton To A

SESSING COMPLIANCE WITH THE CONTAINMENT REQUIRE. Preneurttad Wster Reactor (PWH) With A Larpe. Dry Contarvnenti MENTS IN 40 CTR PART 101. NUREG/CR 6613 V0f ACCIDENT MANAGEMENT INFORMATION '

1 NEEDS Volume f . Apporxhces- '

? NUREG 1126 Vit: A COMPILATION OF REPORTS OF THE ADVISORY Acoldent Progroosion tenCOMMITTEE ON FtEACTOR SAFEGUARDS 1969 Annual NUREG/CR4262 PF AMIS PROBABILITY HISK A&SESSMENT MODEL

"AEOONUREG 1272 V04 N01:OFFCE FOR ANALYSl8 AND EVALUATION OF Accident toevenee

opt RATIONAL DATA 1989 ANNUAL REPORT.Ppwar Reactora NUREG/CR4660 V3 RIP 1: ANALYBIS OF CORE DAMAGENUREG 1272 V04 NO2: OFFCE FOR ANALY8tS AND EVALVAtlON OF F REOVENCY SURRY.UNff 1. INTERNAL EVI NTSOPERATIONAL DATA 1989 ANNUAL REPORT.Norreactors NUREQ/CR4660 V3RtP2. ANALYSf6 OF CORE DAMAGE FREQUEN.ALARA CY: $URRY. UNIT 1. INTERNAL EVENTS APPENDICES

NUREG/CP4110 PROCEEDINGS OF THE INTERNATIONAL WORK. Iy"M[h^$hNT $$[EN 88*

y TsSHOP ON NEW DEVELOPMENTS IN OCCUPATIONAL DOSE CON-NURE0/CR4b50 V4R1P3 ANALYB18 OF CORE DAMAGE FREQUEN- - s

TROL AND ALARA IMPLEMENTATION AT NUCLEAR POWER CY:PE ACH BOTTOM. UNIT 2 EXTERNAL EVENTS. !N A 0 I!. NU G 9Y A NAL DOSE REDUCTION AT NU. yfg 4ghy q gy

CLEAR POWER PLANT 6. ANNOTATED BIBuOGRAPHY OF BELECT* NUREO/CR4660 V6R1P2': ANALYb48 OF CORE DAMAOL FREQUEN. - I: ED READINGS IN RADIATION PROTECTION AND ALARA

CY: BEOVOYAH. UNIT 1 lNTERNAL EVENTS APPENDICE & IAgg, w mg NUREQ/CR4674 V09 PRECURSORS TO POTENTtAL SEVERE CORE

NUREG/CR4616 CAUSES OF FA! LING THE DRAFT ANSI STANDARD DAMAGE ACCIDENTS 1906 A STATVS REPORT, Main Report And Ap.

/h4674 V10 PRECurtSOR$ TO POTENTIAL BEVERE CORE_ N13 30 SA PERFORMANCE CRITERION FOR MINI- NU.*

OAMAGE ACCIDENT 8.1966 A STATUS REPORT.Appenhos B And.

Amnerne coeurronse C. '

NUMEG404 V12 NO3 REPORT TO CONORESS ON ABNORMAL NUREG/CR4674 V11; PRECURSORS TO POTENTLAL BEVERE CORE -OCCURRENClituly September 1989, DAMAGE ACCIDENT 6:1999 A STATUS REPORT. Main Report And Ap.

'NUREG4090 V12 IM MDORT TO CONGRESS ON ADNORMAL Pone A.

OCCURRENCES OctoberAcomber 1969 NUREQ/CR4674 Via PRECURSORS TO POTENTLAL BEVERE CORENUREG40WO V13 Not: REPORT TO CONORESS ON ABNORMAL DAMAGE AOCIDENT81969 A STATUS REPORT.Appenthces D And

OCCURRENCE 8.Jonuary. March 1990. C.NUREG0000 V13 NO2: REPORT TO CONGRESS ON ABNORMAL

OCCURRENCE 8.Aprildune 1990, - Accident beguence AnalysteNUREG 1272 V04 N02: OFFICE FOR ANALY$lS AND EVALUATION OF NUREG/CR4640: PROCEDURE 8 FOR THE EXTEFtNAL EVENT CORE

OPERATIONAL DATA ?989 ANNUAL REPORT.Nonreactot DAMAGE FREQUENCY ANALYSES FOR NUREO 1160.

Abetreet Ace 6dentel EmposureNUREG 0304 Vid N04- RE0VLATORY AND TECHNICAL REPORTS NUREO/CR45e6 EVALUATION OF HEALTH EFFECT8 6N SEQUOYAH

(ABSTRACT INDEX JOURNAL). Annual Corvaston For 1969 FUELS CORPORATION WORKERS FROM ACCIDENTAL EXPOSUHENUREG4304 V16 NO2: REGULATORY AND TECHNICAL REPORTS - - TO URANIUM HEXAFLUORIDE^(ABSTRACT INDEX JO' 'NAL) Compunhon For Second Quarter1990.Apr$4une. Aging

NUREG/CR4731 V01 RESIDUAL LIFE ASSESSMENT OF MAJORO"

G/CR-4214 R01 Pt HEALTH EFFECTS MODEL8 FOR NUCLEAR ghAEQ/CR 8'R DA80 A D G OF WESilNG.j POWER PLANT ACCIDENT CONSEQUENCE ANALYSISLow LET HOUSE 480 VOLT circuli BREAKERS. Aging Assessment And Reo. -

NU CR 6 7 P E CODE **'"*'d''*"' E 0' W"O O''*k '' N'"**MANUALVOLUME 4 MATPRO . A LIBRARY OF MATERIALS PROP- NM/ car 62,80 V07 AGE RELATED DEGRADATION OF WESTING-ERTIES FOR UGHT. WATER. REACTOR ACCOENT ANALYSIS.

- USE 484 W QRCuli BREAKERS Mechareal Cychng u A DS.4ie et.awt.c aw,c.

Aseedent Coneovnee Code System NUREO/CR4419 AGING ASSESSMENT OF INSTRUMENT AIR SYS.NUREG/CR4601 V01: MELCOR ACCIDENT CONSEQUENCE CODE TEMS IN NUCLEAR POWER PLANTS

SYSTEM (MACCS) Volume 1' User'e Guide. . NUREG/CR4448. AGING EVALUATION OF CLASS IE BATTERIES.NPfG/CR4691 V02. MELCOR ACCIDENT CONSEOVENCE CODE SElSMC TESTING- SYSTEM (MACCS) Volume 2 MMet Domenpbort NUREO/CR4461: AGING OF CADLES, CONNECTONS. AND ELECTRI-NUREG/CR4691 V03. MELCOR AOCIDENT CONSEQUENCE CODE CAL PENETRATION. ASSEM8UES USED IN NUCLEAR POWER

SYSTEM (MACCS) Volume 3. Programmers Reference Manuei --

Accident ' __ _ _ . .DEPRESSURl2AT10N AS AN ACCIDENT ALANAGE.NENTS. . 7

. AGEMENT OF AGING OF LWR MAJOR SAFETY RELATED COMPO-NuREQ/CR4447:

MENT STRATEGY TO MINIMl2E THE CONSEQUENCES OF DIRECT NUREQ/CR4619 V01: AGING OF CONTROL AND SERVICE AIR COM,CONTAINMENT HEATING. PRESSOAS AND DAYERS USED IN NUCLEAR POWER PLANTS

NUREG/CR4474; ASSESSMENT OF CANDIDATE ACCIDENT MAN- NUREO/CR %60 AGING OF NUCLEAR PLANT RESISTANCE TEM'AGEMENT STRATEGIES. - PERATURE DETECTORS.

83

i

m,-_.~-r,..- - - , , _m.... . _ _ . . ..,-w-_., - + . . . . . -4 4-~ . ~ , . - . . . ,_ . . _ , y .- , -.-v

__ _ _ _ ____. . _ . _ _ _ _ _ _ __ __ _.

84 Subject index

NUREG/CR f463 PRIDCTION OF CHECK VALVE PERFORMANCE POW (R ST A1ON Compensan Of Two Decomnmen0 Co#1 I *tFAND DEGRADATON 4N NUCLE AR POWER PLANT bYSTEMB mates Devel4*d For The Same Comrha* pal NMeat Reactw PowerWEAR AND IMPACT TESTS Fml ReporLSeptemter treb6. Asvil 1990 Staten

NVALG/CA4671 THE Dt.4 FUEL DAMAGE EKPt RIME NT IN ACNHAging And Maintenance WITH A liWR CONTROL BLADf AND CHANNEL DOE

NUREG/CR 5510 EVALVATONS Or CORE MELT F REOutt4CY EF- NUREG/CH 5397 LLUE lMFACT ANALYSl$ OF REGULA10RY OP-FECTS DUE TO EOMPONENT SGW3 AND MAINTENANCE TIONS FOR RESOLUTON OF GENERIC ISSUE C4 MSIV Lt AKAGE

AND LCS F AlWktA0 lng Wittpdon NUREG/CR 5421 LAPUR USER'S GUIDE

NUREG 1377 R01 NRC RESEARCH PROGRAM ON PLANT AGING NUREQ/CR beep DEt|RMINATION OF THE NEUTRON AND GAMMALISTINGS AND SUMMARIES OF REPORTS ISSUED THROUGH MAY FLUE DiSTRtDUTION IN THE PRESSURE VESSEL AND CAVITY OF1990 A B3fLilNG W ATI R RE ACTOR

NURIG/CR 6526 AN A?SF SSM(NT OF BWR MARK 11 CONT AINMENT

hAR R 5181 NUCLE AR PLANT AGtNG RE SE ARCH THE 1E RO t .

POWER SYSTEM NUREG/CR 5573 DORON FLUSHING UURING A BWR ANTCIPATEDTRANSIENT WITHOUT SCRAM

k ^ '" ^"h Sk tNIR G/ 4404 VOL AUXILIARY f EEDWATER SYSTEM AGING T TSS

STUDL NURE G /CR-5653 RECRITICAlifY IN A DWR FOLLOWING A COKEDAMAGE EVENT.Air Compressor

NUREG'CR.5519 V01: AGNU OF CONTROL AND SERVICE AIR COM- Backfitting Ou6delinePRESSORS AND DRYERS USED IN NUCLEAR POWER PLANTS NUREG 1400 BACKrITTIN3 GUIDELINES

Air FlowEG/CR 2 ANALYSIS OF RE ACTOR TRIPS ORIG!NATING IN

T SN EAR E NS BALANCE OF PLANT SYSTEMS

iir.0,.,eted veno Be60w Repuistry ConcernNUREGrCR 5295 CLOSEOUT OF IE COMPLIANCE BULLETIN B6-03 NUREG/CR-5517. IMPACTS DHC.VERSON 2 0 Program Utst Ma%al

IOTENTIAL FAILURE OF MULTIPLE ECCS PUMPS DUE TO SINGLEF AILURE OF AIR-OPERATED VALVE IN MINIMUM FLOW RECIRCU-

Ul /CR4516 CAUSES OF FAltlN3 THE DRAFT ANSt ST ANDARDN13 30 RADIO 0iOASSAY PERFORMANCE CRrTE RiON f OR MiNbAnnual Report

NURE G41145 V06 U S NUCLEAR REGULATORY COMMIS$0N 1969 MUM DCTECT ABLE AMOUNT.

ANNUAL REPORTNVREG-1363 V02' ATOMC SAFETY AND LICENSING DOARD PANEL 060*Gtal Radiat6on Effect

NUREG/CR 4704 V03 RELATIVE BIOLOGCAL EFFI CTh/ENESS (RDE)ANNUAL REPORT FISCAL YEAR 1989 OF FISSON NEUTRONS AND GAMMA RAYS AT OCCt/0 ATONALAnticipated TranWent Without $crom EXPOSURE LEVELS Studies On The Gross And Microecntuc Pathoto.

NUREG/CR 5573 BORON FLUSHING DURWG A BWR ANTICIPATED gy Oteerved At Death Of Mice Exposed to 60 Equal Orte WeeHyTRANSIENT wtTHOUT SCRAM Doses of Fission..

Apache Etap fu*f Bolling Water ReactorNUREG/CR 6596 UNSATURATED FRACTURED ROCK CHARACTER- NUNG 1372 REGULATORY A1ALYS'S FOR THE RESOLUTON OF

t/ATION METHODS AND CATA SETS AT THE APACHE LEAP TUFF OtNERIC ISSUE C-6. " MAIN STE AM ISOLATON VALVE LE AKAGESIT E- AND LCS F AILUREJ

f4UREG/CR-0672 ADOO4 fECHNOLOGY. SAFETY AND COSTS OFOttantle Seaboard DECOMMISSONING A REFERENCE DOILING WATER RE ACTOR

NUREG/CR 5413 PALEOUQUEFACTON FEATURES ALONG THE AT* POWER STATON Compenson Of Two Decommisstoning Coot Esti-LANTIC SEADOARD rnates Deve6oped for The Same Commerc.ai Nuclear Reactor Power

Station

NUR / 28 09 POPULATON DOSE COMutTMENTS DUE TO [[0 R D D tIRADOACTIVE RELEASES FROM NUCLEAR POWER PLANT SITES NUREG/CR 5307 VALUE IMPACT ANALYSIS OF REGULATORY OP.

IN 198 7- 10NS FOR RESOLUTION OF GENERIC ISSUE C-8 MSIV LEAKAGEAND LCS F AILURE.Atomic Safety And ucensing Board Pene! SER

NUREG 1363 V02: ATOMIC SAFETY AND UCEN3 LNG DOARD PANEL [ fy gg , THE NEUTRON AND GAMMAg gANNUAL REPORT FISCAL YEAR 1989 FLUX OISTRIDUTION IN THE PRESSURE VESSEL AND CAVITY Or

A DOltiLNG W ATER RE ACTORAurMary foodweler NURE G/CH 5528 AN ASSE SSMENT OF HWR MARK Il CONT AINMENTNURE G/CR4404 V01: AUXILIARY FEEDWATER SYSTEM AGING CHALLENGES.F ALLURE MODES AND POTENTIAL IMPROVEMENTS

STUDY IN PERFORMANCENURrG/CR 5616 AUXILIARY FEEDWATER SYSTEM RISK. BASED IN. NUREG/CR4573 DORON FLUSHING DURING A 06Tt ANTICIPATEDGrECTON OLHDF FOR THE DiABLO CANYON UNff 1 NUCLF.AR TmtaT MOUT WMPOWER PLANT' HUREG/CR 5605' LAPUR DENCHMARK AGAINST IN PHASE AND

OUT OF PHASE STADiLITY TEST 4Ausillary Feedwater PumpNUREG/CR 5653 RECRITICAUTY IN A DWR FOLLOWING A CORENUREG/CR 5298 CLOSEOUT OF IE BULLETIN 85-01: STEAM BINDL

ING OF AUxlLIARY FEEDWATER PUMPS DAMAGE EVENT-

Austhary Feedwater System Botting

s9UREG/CR4617 AUXILIARY FEEDWATER SYSTEM RISK. BASED IN- NURE G-1339 RESOLUTON OF GENEHC SAFETY ISSUE 29 BOLTING

SPEOTON GUIDE FOR THE J M FARLEY NUCLEAR POWER DEGRADATION OR F AILURE IN NUCLEAR POWER PL ANTS

PLANT Borlc Ac6d CorroponNUREG/CR 5576 SURVEY OF DORIC ACID CORROSON OF CARDONSWR

NUREG-1372. REGULATORY ANALYSIS FOR THE RESOLLff0N OF STEEL COMPONENTS IN NUCLEAR PLANTS

GENERC ISSUE C 8. " MAIN STEAM iSOLATON VALVE LEAKAGEAND LCS FAILURE a Boron FlusNng

NUREGiCR 0672 ADOD4 TECHNOLOGY, SAFETY AND COSTS Or NUREG/CR 5573. DORON FLUSHING DURING A DAR ANTICIPATED

D3 COMMISSIONING A REFERENCE DOluNG WATER REACTOR TRANSIENT WITHOUT SCRAM

. - . - - - - - - - - - - - ... - - - .-

. . .. -. . - - -

Subject Indem 66

| puoeot Circon n,onor

| NURLG 1100 V06 DUCOf T I ST'M A70 S F m.al iear 199 L NUHf G'CR fJ80 V01 AGl-Hi L ATt D DiGRADATON OF Wl $1INGHOUM 4h3 VOLT CiHCVIT DHL Ati H5 Apg A>wserneni Ari1 Hos

CARE $ onwnemaimne F & Improvo Ekeskee HanNI.tNUHEG/CH %ss Vol CARES (COWUTIR ANALY$16 FOR RAPID NUAL G/CH 6?B0 V02 AGE fit L A T E D Di oH AbA TION OF Wi bilN3

IT ALUATON ($ $ tRi C1URE $) VERSION 10 Seinwc HOUh! 483 VOL T CIRCulf DHL A> i H5 Med. arm ai ( vMg Of A DS-Mauie ThekveWH Mawal 4I6 (Feaker Test Roadla

NUHE G/CH 1666 V02 CAHf 6 (COMPUT[H ANALYbl$ 80R RAPIDEVALUATON OF WTRUCTUlitM VI R$ON 10 5 wene Circu6er Founost6anMxtu6e User s Mo%ai NURE G/Cfl SSue DYNAMIC 11 $ TIN 3 Of A C6HOUL Aft iOUNDATlON

NUREG/CR 6868 V03 CAR' 5 (COMPUTER ANALYSIS 7OR RAPID AND ANALYSE $ OF B31L/$titVCTURE INilRACTONEVALUATnN OF $THJCTUNES) VI RSON 10 $e a'reMcW6e Samp6e ivot loms Cteddmg

NUAl G/C84 f.tJ4 VN TMii VibLtl INvl 6TIGATION l'HDJiCT (VIP)COMMIX.1C MIT ALLUHGICAL PHOGAAM Puvens figat Octw 1k69 - June

NUREG/CR %49 V01 OOMMmtC A THRit-DiMENSONAL T8 TAN 1993bl(NT & LNG 60 PHA$l COMPVTL A PRCGRAM #0R THFHMAL HY.DRAJLIC ANALYBIS OF $14GLE COMPONENT AND MULTICOM Clase 1E SetterySONENT ENGINEERING $YSitu$ toostma And Numeros NUnt G/C4 6448 AGNG (VALVATON 08 CL Af.5 it bat 1t hit $

NUMG/CR %49 V02 COMhtC A THRE E OtMENSONAL TRAN. bilSMIC TL $11NG5tLNT SIN 3LE PHABE COM5VTER PRCORAM FOR THl.HMAL HY-DRAULC ANALY$19 OF $!N3LE COMPONENT AND MJLT6COM C6eavage FracturePONENT ENGINE E RING SYSTEM 5 User s GuHe AM Manual NU8tt G/CH f40 H63H tt MPE RA TUHE CRAC* AHHI ET T L $1fi

UhlNG 162 MM THICA Of N WlDL PL ATE S Of LOW UPPL P bHL L FCatde liASE MAitioALitSTb WP # P AND WP i 6

NVREG/CR f4til AGING OF CADLLS. CONNECTONS. AND ELECTRI.CAL PINETRATON AS$0MDLIES USED IN NUCLLAH POWLH C''"ut G 1402 CL OLL OUT 08

PWI

p(Ay7g NU NHC liutil TIN obM NONCONr ORMING M ATilu ALS BUPPUED liv PPiN 3 $UPPut B INC AT

Copinary Barr6er 8 OlsOM.NE W JE RSE Y,AND wt$1 Ji RLt Y M ANUF ACtVHIN3NUREG/ Chapt 8 V04 CONTROL OF W ATtst INtit,TRATON INTO COMPANY AT WILLIAMSTOWN NEW JI HSf Y

NEAR SURF ACE L(W DIWDSAL UN!TL Proyess hotut On Fio6d lit. NutG G/CR 4t?S CL OSE OUT Of it BULLlilN b4M Ht8 0LUN3penmenO At A Hurrud fiopn See boitselse Marytend CAVIIY **TI'lblAl

NUHLG/CR46ei CLOSIOUT Of IE ElVMIitN 6WI MDTOh 0PtH(,arbon $ teel ATED V ALVI COMMON MODE F AILUHE S DUHING PLANT 1HAN-

NUHEG/CR-!576 SURVEY 00 DOHtC ACID COHHOSION OF CARDON $1LNTB DUt TO IMPhDPt 84 $WfTCH bETTIN' t.STE E L ODMPONE NTS IN NUCli AR PLANTS NUHFG/C44?b6 CLOblOUT Of it DULLE TIN ?0 t ? Plot CHACAS IN

ST AGNANT DOHATED W Att R BvST1MS AT twH PL ANTSCovity Coollog 8ystem NURE G/Cri4tBD CL OSI OUT Of Il 14ULL E TIN 7k ?3 POf t NTIAL

NUREG/CR 6514 MODELING AND PERFOru ANCE (t THE MHTGR 8 AILURL OF E MLRGLNCY Dit sf L GLNt 4ATOH FILLD E stCf tt uREACTOR CAVITY COOLING SygTt M THANs80HMtR

NUHLG/CH t?96 CLO*dOUT OF If COMPitANCl DJLLE TIN B603Cavity Woler Seal POilNTIAL F AILUni OF MULTIPLL tCCS PUMP $ DUt TO SINGL L

NUREG/C44S?S CLOSLOUT CV IE DULLETIN b4 03 HlFUC UNG f AILU54E Of AIR OPihATI D V ALVI IN MINtMUM FLOW H(CIHOUCAViW AATER SE AL LATON LINE

NUHEG'CH4297 CLOst OUT Of li flOLLI TIN 63 06 AhME NUCLi AHCerttf6cete Of Competence CODE PUMPS AND SPAHL t' ART 5 MANut ACf untD Dr THE HAY.NUREOKtM V01 Rt3 D:45 CTORY Or CERTIFICATES OF COMPU. W ARD TYtt H PUMP COMPANY

ANCE FOR RADIOACTlvE MAYt HIALS PACKAGES Report Of NHC NUHLG/CH 6?M CLOSL OUT OF IE Dua[' TIN $6(a $tt AM CIND.Approved Packapas ING OF AunlUARY FI 0DW ATL H PVMP5

NUREG.0383 V02 R13 OIRECTORY OF Cf HTirCATI $ OF COMPU- NUHE G/CH 5302 CLOSE OUT OF 16 DULti1IN BS 1D LONT AMINAANCE FOR RAtlOACTIVE MATERLAL 5 PACAAGE S Certittaios Of TION OF NONRADOACllVE $Y$1[M AND HlBULTING POTlNiiALCompliance POH UNMONiTOHF D. UNCONfHOLLLD HI LI AS[ OF 4ADIDAC'Tfv'.

NUREGEnB3 V03 R10 DIRECTORY OF CEftTIFCAf ts Or COMPU- (TY TO t WiHONut NTANCE FOR RADCACTivl MATERALS PACAAGE S RpPort Of NHC NUHt G/CH 6336 CLO5t OUT OF IE 110tLETIN 7D te AUDlHILITYApproved Wality Astsance Programs For Rahactive Materws Pam PRODLE MS ENCOUNTE HLD ON Lv ACU A T ON OF PtHSONNELages F HOM HIGH NOlst AHE AS

NUR(G/CH 6307 CLOSLOUT OF lt. DOL LE TIN 00 0? IN ADlOU ATl'CMaum OVAUTY ASSURANCE F OH NUCl[ AR SUPPUED t OaPMI NTNURE G/CR 4483 LFFECTS OF MINERAL OGY ON SOHPTON OF NUHf O/CR $30H CLOSLOUT OF Il Butti TIN h316 PobMDLE

STRONilVM AND CESlVM ONTO CAUCO HLLB TUF F. LOSS Of EMEHGENCY NOTIFICATON SYbfLM (tNS) Wif H LOSSOF 08 F BITI POWE R

Check VatveNUREG 13S2 ACTION PLANS 804 MOTOR OPERATED VALVLS AND Combustion Model

CHECK VALVE $ NU'tt G/CR M90 ASSELSMENT Of THE COMBUSTON MODC L INNUHEGICA 5583 PREC,CTION OF CHECK VALVF PEHFORMANCE THE HECTH COOLAND DEG8uDUiOM IN NUCLEAP PCrNEH PL ANT Sy3TE MSWEAR AND IMPACT TE STS Final Report,Leptemtier t H8 Apnl 1990 Common Caun Fallure

NUHf G/CH 6460 A CAUSE-DiFL NSE APPHDACH TO Thi UND(RCtw al lndustry ST ANDING A"O ANAL Y$ts OF COMMON CAU$f f AIL UHE bNUREG/CH t%s VR INCOSTRY DASE D PERFORMANCE INDCA-

TORS FOR NUCLEAR POWER PLANTS Phase i Report Jurie 198g , Computer CodeFetruary 1990. NUHf G/CA 4%4 V06 6 CANS (SHIPPING CAhk ANALYbl5 $YSTE M) A

MCHOCOMPUTER BASID ANAL.YSIS SYSTl M FOH $4|PPINGChem 6 cal Tonicity CAbt DESIGN REvlEW volume 6 They Manow (whng O' CecaNUREG 1391 DRFT Fh CHEMICAL TOxlCITY OF URANtUM HEFA- larCy Wincai$hehe

FLVOROL RELATED TO RADIATON OOSES Drott AePort For Com- NUni G/CH,4*A.i V0 7 SCANS (SHIPPING CASP. ANALYSIS SystiMiment. A MICAOCOMPUTER hASE D ANALYEdS SYSTIM FOH SHIPPING

CASA DEblGN HLynt W Volume 7 Thoory Marun' Fvetwei Of $Np-Chronec Fatal!ty Wetent pm Caos

NURE G/CR4?t3 PARTITION A PROGRAM FOR DCFLNWO THE Nun (G%4463D V01 Ht NUCLE AR COMPUT[HJI D LIDH AHY F ORSOURCE TERM / CONSEQUENCE ANALYSIS INTEHF ACE IN THE ASSI $$1NG HL ACTOR 4( UADIUTY (NUCL AHH) hummry (muneNUREGd 150 PROBADILISDC RISK ASSE $5MENTS Usert Gum tm

_ ___ ___ - - - _ _ . _ - _ - _ _ - - - _ _ _ - - _ - - - - _ - _ - _ - - - - _ - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -_ _

. - - - - - - - - - - - - . ~ . - - - _ ~ . - - - - - . - . .

1

,

83 Subject index

4

NUHIG/ Cst,409 v4P2nt NUU._t AH COMPU1t H7ED LIDRAHy FOH Containment Hydrogen ComtrolAbhi$51NG HI ACTOR HLLIAAILITY (NLOLARHJ Uew e Geo Part F. NUHf G 1417 bat ( TY l 9 ALUATION Hi POHT F4 L A1L*) to HrDHO-Omte to EwahW GEN CONTHOL OWNI HS GHOUP AShi $5 MENT OF A AHK lli CON-

| NtrHLG/CR etJe v4PJ847 NUCtt AR COMPUttRil[D Lil.iRAS4Y FOR T AINMt NT.I AS$t $$1NG HEACTOH RR LIADILITY (NUCLAHH) User 6 Guade Part 9?

NXL ARR bestem twenpton Containment integrityNUHLGrCH 4tJP YbPm3 NUCLEAR COMPUTE nLZED LIDRAHY FOR NUNEG/CR Mie AN AkbE BLMENT OF tiWH MANA 11 CONT AINMt NT

AShibSINa HE ACTOR HELtAlitLITY (NKLAHR) Date Maqwd Pad 1. CHALLENGE 6 F AILURL 1640DE 6. AND FOf t NTLAL IMPHOVLMt NTS^

N 4t 2R3 NUCa E AR COMPUTERIZED LibRAHY F04 -

* ,

Asst $siNa nt ACTOH nEumurY (NUCunH3 Dete ue~el Po,i e Conism,ne on-

NCJi k e it 3 t4 NA ODMPUTER12ED LIDRARY FOR#I MA # OM ' M #

NASSESSING HE ACTOR REL4ADILITY (NUCLARAb Dete Manas 1 Pe4 3 g($ q y|g h f ![ DUAL RADCACTNE CONT AMINAtlON

A

F HOM DECOMMIS50NING Todmal BaPs For Transistog Cetes r

h 4 C th! E.DlWENtlON AL TRAN.N neWn Weis To Arvuol Dame Ewett Hoport F pr (#vnent! $1ENT $1NGLE.PHALE COMPUTE 4 PHOGRAM FOR 1HEhMAL.HV-

DRAutlC ANALYSit OF $lNGLE. COMPONENT AND MULTtCOM-

!! 2[O $$ [5NAL TRAN. 61 L ONOMIC RISA 08 CONTAMINATON CLE ANUPiN E CO$TS h[SULilNG FNOM LAFIGE NONnEACTOn NUCtE An MATE-BilNT 1. INGLE PHA$E COMPUTL A PHOGRAM FOR THEliMAL Hy.DRAuttC ANALY$lS OF $1NGLE(OMPONPIT AND MULT COM.

AtAL LICENSEE OPERATONS

PONENT ENGINEt RING SYSTLMS Usert Gunte And Marusi Control Room HabitehtutyNUHtG/CH459 CONTHOL 400M HADitAbluTY SYsit t,4 HEVIEW

i Computer ProgramNUHf G/CR%S3 COMPUTER PRCORAMS FOR EDDY CURHENT MODELS

DEFECT CTUDIES Control steuonConcrete Bemer NURtG/CR$t72 AN EVALUATION OF THE EFFECTS OF LOCAL

NuntG/CR M4P MuDELS FOR ESTIMAtlON OF BEH/ ICE LIFE OF CONTHOL si ATON D($G CONFlOURATONS ON HUMAN PCR-CONCR[tE BARHit HS IN LOW LEVEL RADIOACTIVE W AstE DIS- FonMANCE AND NUCLE AA NAER PLANT HISLPOSAL.

C6PPer Content; Corerete Containment NunEG/CR4%4 nt&ULTS OF CRACLAHht.61 TEST $ ON TWO tR-

NUHtG/C4S476 POSTil 5T ANALY$t$ Of; A 16 SCALE htiN- RADIATED HCH.COPPEH WELDSFORCED CONCHETE HEACTOR CONT AINMENT DUILDING

Core DamageNUHEQ/CH-4%0 V01 Al ANALYSIS OF COHE DAMAGE FREQUEN-

| E R 9 THE SEtSMic CATEGORY I STHUCTURES PRO. CY INTERNAL EVENT $ METDODOLOGY9gg RE G/CR-4%0 - V341Pt. ANALYblS Or COHE DAMAGENL r (Ng 7 ST A$lhktfCYClE TESTING OF A LOW-ASPECT,4 F REOVENCY $UHHYMNtf 1,1NTEHNAL EVENTS

FOURINvH W ALL' TAG. TYPE 6tnUCTURE TRO tr4 NUREG/CR 4%0 V3 RIP 2 ANALYBtS OF CODE DAMAGE B REQUEN-4,AT ON RIG /C!! %33 ST ATIC LOAD CYCLE TESTING OF A VERY LOW.

CY- SURRY,UN:T t.INf L RN AL EVE NTb APP! NDICESggNURIG/C4 4%0 V3 RIP 3 ANALYSIS OF CORE DAMAGE F ALOulN-i

ASPECTJtATO SILINCH W ALL TFilfYPE $tRUCTURE TAG 6-6 CY: SURRY POWER ST ATisN UNIT 1 E xTEHNAL EVENTS*

p g7' g g NUHEG/Csi 4%0 v4H1P3 ANALYSIS OF CORE DAMAGt F HE QUEN.CY rE ACH BOTTOM UNri t DTF HNAL EVE NTS

Contakwnent NUREG/CR 4%0 VSRtPt: ANALYSIS OF COHL DAMAGE FhEQUEN.NVREG0800 03 61 R2 Bf ANDARD HEVIEW PLAN FOR THE HFVIEW

Of SAF ETY ANALYSIS HEPOPf6 FOR NUCLEAR POWER CC 6tOUOYArtDNit f.INfEHNAL EVENTSNUREG/CH 4%0 vbRtP2 AN ALYSIS OF COHE DAMAGE FHEOutN4PLANTE LWR Edition Hovison 2 To SRP bocton 3 61. Plant Design CY SEOUOY AH. UNIT t,1NTE AN AL EVE NTS APet NDict 8

For Petection A0ainst Postulateo Pipeg Features in Fluid Systems 091 NURsO/CH 4%0 V7 H01 ANALYSIS OF COHE DAMAGE FREQUE N-m_NUHEG/CR.45$1 V3RtPI' EVALUATION OF SEVERE ACCID (NT

CY ZION, Unit 1, iNTE RNAL Eyg NisNUREG/OR467a V09 PHECURSOAS TO POTENTIAL SEVEHE CORE3 HIEk b SUHHY UNif 1 Maan heport*

NUHEG/C44%1 V3 RIP 2 E'y ALUAT ON OF SEVE RE ACCIDENT DAMAGE ACCIDENTS 1988 A ST ATU$ HLPORT Main Repart And Ap.

RISAS $UHRY Unit 1. Aptwnhet pomts ANUHIG/CFbb4CC. ANALYhd 06 BHELL 40FtVRE F AILURE DUE TO NUHEG/CR 4674 v10 PRECURLO4S TO POTENilAL 6tVt RE CORE

HYPOTHl'TICAL ELEVATED.TEMPERATVHE PRES $UR12ATON OF DAMAGE ACCIDENTS 1968 A STATUS REPOHf Appendues O Ard

THE $EQUOYAH UNif 1 ) TEEL CONF AINMEN' DOILD!NG CNUREG/CH M21 USE OF PEHF08tMANCE ASSESSMLNT IN AS- NUREG/CR 4674 V11 PRtCURSORS TO POTENTIAL SEVLHE COHE

St SSING COMPLtANCE WitH THE CONTAINMENT R&QUlHE* DAMAOi ACCCENTB 19t*9 A ST ATUS Rt PORT Main Heport And AP-"

MENTb IN 43 CF A PARY 191 peru $m ANUHEGrCR4Mt PWR D4Y CONTAINMENT ISSUE CHARKTEHl2A' NUHEG/CR-4674 V12 PHECURSORS TO POTENTIAL $EVERE C04E

SWA AMem D AndNUF /CH 6675 OUANt!TATIVE ANALYCIS OF POTENTIAL PEH.

N EG/CH4a40 PROCEDURES FOR THE EXTEHNAL EVENT COHETNT IF h1N OF NM i GNU EG 6 DAMAGE FREQUENCY ANALYLES FOR NUnEG 1150AND HYD40 GEN COMDUSTON EVENTS IN ICE CONDENSER NUREO CR MS3 RECHITICALITY IN A BWH FOLLOWING A COREPL ANTS Anaynes Wrth ite CONT AIN Code And NUREG 1160 PRA DAMAGE EVENTymq

NUHt'G/CHdos DYNA *C TESTING Or A CiHCULAH FOUNDAtlON #' '"AND AN ALYSES Or 00tL/$1MICTUHE INTERACTON NUHEG/CH %10 EVALUATONS OF COHE MELT FHEOVENCY EF-

NUREG/CR M38. TECHNICAL CONSIDERATONS FOR EVALUATING FECTS DUE TO COMPONENT AGING AND MAINTENANCEBUBST ANitALLY COMPLETE CONTAINMENT OF HIGH. LEVELWASTE WITHIN THE WASTE PACAAGE Core Meltdown

NUHEG/CR %9P IN VEESEL ZlRCALOY OXIDATON/HfD40GE N.Containment Event tree GENERATION DEHAVOR DUHING LEVERE ACCIDENf 6NUREG/CR-%02 SIMPLIFIED CONT AINMENT EVENT TREE ANAlbstb FOR THE SEQUOYAH ICE CONDEN5ER CONTAINMENT.

| Core-ConueteNUREGiCH-4704 EXPERIMENTot hESULTS OF CORE CONCRETEContainment Heat 6ng

NUHEG/CH4373 A DCMONSTRATION DFERIMENT OF STE AM- INTE4 ACTION $ US!NG MOL TEN $TEt t WITH 21RCONIUM

DHrVEN HIGr4 PRESSURE MEl T !)ECTON TPe HIPS-105 TestNUPEG/CR 644L DEPHESSURl2ATON AS AN ACCIDENT MANAGE- Conoston

MENT STRATEGY TO MiNtMl2E THE CONSEOVENCES OF DIRECT NUHEG/CR 5435 ENVIRONMENT AL EF FECTS ON COAROSON IN' CONT AINMENT HE ATING THE TUFF REPOSITOHY-,

!

,

%.e, e - -+-r--n-- e n .,-----w<- v.,...v.-- n ,.e-.--e-,,-,ewwww, www---. aw--.v--,-w,a -p.-,v , , e.w 14e,--,-ww-. -re v

- . - - - _ - - - . - - - . - _ - - - - _ - - - - - _ - - . -

)

Subject indOx 87

CrgA Arrest NURE G/CR F483 PREDICTION OF CHECK VALVE Pt Ri JAMANCENOREO'OR 42t9 V06 N2. HE AVV bECTON STE EL ?iGHNOtOGY AND DEGRADAT60N IN NUCLEAR POWE A PLANT SysTE MS .

PHOGR AM benannual Pnee se Remrt For Ap#4.cetember 1969 WE AR AND IMPACT TE ST& f ria' hesort baptember 1988 Asti 1990NUREG/CR 64Dl4 NLUTRON LAFObURE PARAMLTE RS FOR THE ,

MET ALLURGICAL TEST $PECIMENS IN THE blATH HEAVY $CC- Dep4ted uran 6pm t

| TION STE E't IRRADi ATON I4 Rlt S . NUREG t406 INADVE RTE NT SHIPMI NT OF A RAD 6X8tAPHICi NUFdGICR 6413 INCLUSON OF UNST ABLE DUCTILE TE ARING AND SOURCE FROM AORLA TO AMERSHAM

EXTRAPOLATED CRACLARRf ST TOUGHNE$$ DAT A IN PWR cogpORATION,BURLINGTON MASSACHUSC1T SVESSEL INTEGRITY ALSISSMENT,

Depressurtsst6on |WRWCR f.447 DEPRESSUR12ATON AS AN ACCIDENT MANAGE. *

N / 0112 V01: PROXEDINGS OF THE THIRD INTERNATON. I T M NIMilE THE CONSEOVE NCts Or DIRECTAL ATOMIC ENERGY AGEN0Y SPECIALISTS' ME ETING ON SUB. 4 g'

CRffCAL CRACA GROWTH.Operung Genson And Techrucal Sesason

b( icd i S THE THIRD INTERNATON. "'8" * * "'N t /NURWM6M RE AUW AMNTS A Realsos6 ment d heAL ATOMC ENERGY AGENCY SPECIALISTS' MEETING ON SUW

CR!TCAL CRACK GROWTHiochrscal Eessons 11, til. Aruf IV And DeWase bentsRecommendatons AruJ Corcunons Seawon V. Held At opg,

NU [CF 7 hhi C MENTALLY ASSISTED CRACKING INNUREGMM D06 A06 UNITED ST ATES NVCLEAR REGUL.ATORYI 'tHT W ATE R RE ACTORS Sewannual ReFirt Arrs beptemter 1986 COMMISSION STAFF PRACTICE AND PRCCEDURE

N u 1/CR-4067 V00 ENYlRONMf Nf ALLY A&SISTED CRAChlNG IN DIGEST Comnuswon, Aptoni Bohrd And Licensing Eberd/.,HT WATEH REACTOR $ Somerywat RepcrtOctoler 1M6. March DC#0'* My 1972 Septencer 19ti9

4 D69 tel $yetemt

6.rech Arrest NUREG/CR 6439 HUMAN F ACTORS ISSUES ASSOCIATED WITH AD.NUREG/CR 6461: CRACK ARREST BEHAVOR IN $EN WIDE PLATES VANCED INSTRUMENT ATON AND CONTROLS TECHNOLOGIES IN

OF LOW UPPER SHELF BA&E METAL TESTED UNDER NONISOTH- NUCLEAR PLANTSERMAL CONDITIONS WP 2 $ERIES

NUREG/CR-6t44 RESULTS Of CRACK AR8 TEST TESTS ON T'WO 14 Dose E etamateRACNATED HtGH. COPPER WELDS NUREG/CR 6480 EIOLOGICAL CHARACTER 12ATON OF RACHATION

EXPOSURE AND COSE ESilMATES FOR INHALCD URANtVM MILL.Crock Arrect foughne** ING EFFLUENTS', NURE G/CR 6450- HIGH TEMPERATURF. CRACCARREST TESTS

USING 162 MM THICK 6EN WIDE PLATES OF LOW UFPER $HELF Dryer'

BASE MATERIALTESTS WP 2 2 AND WP 2 6 NUREG'CR 6619 VQt AG)NG OF CONTROL AND SERVICE Allt COM.

CHhal FW PRE SbORS AND DAYERS USED IN NUCil AR POWER PLANTS.

NUREG/tA40M V01: ASSESSMENT OF TRAC-PF1/ MODI VERSON Dynamic Testing14 3 USING SEPARATE EFFECTS CRiflCAL FLOW AND DLOW. NUREq/CR 6599 DYNAMIC TESTING OF A CIRCULAR FOUNDATON *

NU E i V2 SS M T F1/ MOD 1 VERSON AND ANALYSES OF BOIL / STRUCTURE INTERACTON

14 3 USING BEPARATE EFFECTS CRITCAL FLOW AND BLOW. ECCS PurrpDOWN EAPERIMENTS Votume 2. Fgwes

NUREQ/CR 6296 CLOSEOUT OF IE COMPUANCE IlULLETIN 8603DOE Weste Package Teel Data POTENTIAL FAILURE OF MULTIPLE ECCS PUMPS DUE TO SINGLE

NUREG/CR 4735 V06 EVALUATON AND COMPILATION Or TOE r ALLURE OF AIROPERATED VALVE IN MINIMUM FLOW REciRCUWASTE PACKAGE TEST DATA. Baannual Report August 1986 Janu. LATON LINC

"7 #EPICOR41

Decay Heat Removal NUREG/CR 6220 V03 EPICOR il RESIN / LINER IWESTIGATON LOW.NUhEG/CR 6614. MODELING AND PERFORMANCE OF THE MHTGR LEVEL WASTE DAT AHASE DEVELOPMENT PROGRAM FOR FISCAL

RE ACTOR CAVITY COOLING SYSTEM YEAR 1990 Annual Report

Decommloe6oning EarthquakeNUREG/CR4072 ADDod, TECHNOLOGY, SAFETY AND COSTS OF NUREG/CH-6258 V02. GEORGIA /ALADAMA REGIONAL SEISMO-

DECOMMISSONING A REFERENCE BOILING WATER REACTOR GRAPHIC NETWORA Annual Report.My 1986. June 1987,POWER STATION Compennon Of Two Decommesworang Cost Esto NUREG/CR6h8 V03 GEORGIA /ALAtlAMA REGONAL $EIBMO.mates Deve60 ped For The Same Commercel Nx4 ear Reactor Power GRAPHIC NETWORK Annual ReportJuty 1987 + June tM8.Staten. NURE G/CR 6258 V04 GEORGIA / ALABAMA REGONAL SEISMO.

NUREG/CR 2601 AD001: TECHNOLOGY. SAFETY AND COSTS OF DE- GRAPH 4C NETWORnfinal Fieport Aumat 1985 October 1990COMMIS$ONING REFERENCE LIGHT WATER FtEACTORS FOL. NUREG/CR4477 AN EVALUATION Of THE REllADIUTY AND USE.LOWING POSTULATED ACCIDENTS. Re Evaluaton Of The Cleanup FULNCES OF EXTERNAL INITIATOR PRA METHOCOLOGIE SCoat For The Boilang Water Reactor (BWR) Scenano 3 Accident From NUREG/CR 6467. STATIC LOAD CYCLE TESTING OF A LOW ASPECT.NUREG/CR 2001. RATO FOURINCH W ALLT AG TYPE STRUCTURE T AG-6 4

NUREGICR4401 SHIPPINGPOR7 STATON AGING EVALUATION O O 0 %)NUREG/CR-6612 DRF FC: RESIDUAL RADCACTIVE CONTAMINATON NURIG/CR 6533 ST ATC LOAD CYCLE TESTING OF A VERY LOW.FROM DECOMMIS$1ANG Techrscal Danes For Translating Conterr*ASPECT RATIO SIX. INCH W ALL TRG TYPE STRUCTURE TRG 6 6nahon Levels To Annual Dnae Droft Report For Comnent(0 27. 0 LO)

Decontamination NUREG/CR 5613. PALEOLOVEF ACTION FEATURES ALONG THE AT.NUREG/CR4444 V07. THE IMPACT OF LWR DECONTAMINATONS W C SE W A %

ON SOLIDtFICAflON. WASTE DISPOSAL AND ASSOCIATED 00C0 g,,nomi, p,,gPATONAL EXPOSURE.

NUREG/CR S361: EODNOMIC MK OF CONTAMINATON CLEANUPDegresation COSTS RESI ~ TING FROM LAHOE NONRL ACTOR NUCLEAR MATE-

NUREG 1339 RESOLUTION OF GENERIC $AFETY ISSUE 29 BOLTlNG RIAL LICENSEE OPERATIONSDEGRADATION OR F ALLURE IN NUCLE AA POWER PLANTS

NUREG/CR 6280 voi; AGE RELATED DEGRADATION OF WESTINo. Eddy CurrentHOUSE 480 v0LT CIRCulT DREAKERS A(ptvJ Aasessment And Rec. NUREG/CR 6478 IMPROVED EDDY CURRENT INSPECTON FORommentiatons For impronna Breaker Rehatniq STEAM GENERATOR TUDING Proyees Repori For January 1M$ To

NUREGIC45200 V02: AGEJ1 ELATED DEGRADATON OF WESTING. Dw4mber 1967.HOUSE 460 VOLT CIRCult DRE AKERS Mechanecal Cychng Of A DS- NUREG/CR 5553 COMPUTER PROGRAMS FOR EDDY CURRENT416 Breaker. Test Resuita DEFECT STUDIES

i ~- - - . ~ . - . . , --. - ,.. - - _.- - . - _ - - _ . .

. _ _ . _ _ __ _ _.

88 Subject Index

tiewu F.neironon E niernei NeversNURE G/CR4461: AGING OF CABLES. CONNECTIONS. AND ELE CTRL + NURIG/CR 4640 PROCE DURES FOR THE EXTL RNAL EVE NT (X)RE

CAL PENETRATON Al>$EMDLIES Uf.ED IN NUCLE AR POWER DAM AGE F REQUE NCY ANALYSE S F OR NURE G 1160PLANTS

Estremtty Dontmeter

[n gyg y gRE 4744 YO3 Nt' LONG-TER4 EMDRITTLEMENT OF CAST $DUMEX $1 AINLE SS STEELR IN LWR SYSTEMS SemiennualReport Oc taber its ? . Ma'ch 1968 7eNuro Mode

NURt G/CH4744 V03 N2 LONG TERIA [MDRITTLEMENT OF CAST NUREG/CR 6628 AN ASSE SSMENT OF BWR M ARK 11 CONT AINME NTDUPLE % ST AWLE SS STEELS IN LWR SYSTEMS $pmwrual CWE WSI AH URE MODE S. AND POTENTIAL IMPROVL ME NTSIN PERFORMAdCENLR C 16 R L POWER REACTOR [MDRITTLE MENT

V NW THE MECHANISMS AND hreanne DetecuonNU E i L ASNUREG/CP 0107. PROCEE DINGS OF THE UNITED ST ATE S NUCLE.ARSIGNiFCANCE OF LOWTE MP( RATURE E MBRITTLE ME NT J

REGULATORY COMMISSON SECURIT Y TRAWINGCA67 STAtNLESS ST[[L$ IN EWR SYSTEMS

NUREG/CR 5644 OONSEOVENCE EVALVATON OF RADIATON EM. SYMPOSIUM Me* ting The Challengef roarms And Endosives Recog-ORITTLEMENT OF TFtO.lAN REACTOR PRES $URE VESSEL Sup, rdton And Detectort

Flecal f eerEme perwy Roeporite NUREO.11Co V06 DVDGET ESilMATES Fiscal Year 1991

NURE G/CH-4661 Y2R t P F. E VALVATON OF SEVERE ACCIDE NTRISKS, OUANTWCATON OF MAJOR INPUT PARAMETERS MACCS Repon Productinput NUREG/CR4480 DA1 A SUMMARY REPORT FOR FISSON PRODUCT

NUREG/CR4399 SURVEY OF ST ATE AND TRIBAL EMERGENCY RE- ptLE ASE TEST Vt3SPONSE CAPABluTIES FOR RADIOLOGICAL TRANSPORT ATONINCOE mS. noon.. Reis

NUREGrCh4491 INFLUENCE OF FLUENCE RATE ON RADIA10N IN.

db,E,394,,,E, R ENDMD A RM HA S R RE S-

E PONSE DATA SYSTEM (ERDS) IM. SunE vtS$u STEuS rnal rep 10n E.~.i-, tN-.mN*d b

Enforcement AcuonNUREG 0940 V06 N94 [NrORCEMENT ACTIONS SONihCANT AC, NUREG/CRot6e M NET CODE DOCUMENT ATION

NUREG/CR4462 LABORATORY ANALYSIS OF F LUID FLOW ANDIO RESOLVED Quarter'y Progress ReportOctate Decomte,

T, p,N, S Sol,UTE TRANSPORT THROUGH A VARIABLY SATURATED FRAC-

NUREG.0940 V09 N01: ENFORCEMENT ACTONS. SIGNIFICANT AC. TURE E MDEDDED IN POROUB TUFF,

NU 0 VO EN C7ML fNW6 ICAN AC. HuW SystemsTIONS RE SOLVED Quartorg Proyees Report.Arv@e 1990 NURE G 0800 03 6 i R2. 67 ANDARD REVIEW PLAN FOft THE REVIEW

NUREG-0940 V09 NO3 ENFORCEMENT ACTIONS. blGNIFICANT AC- OF SAFETY ANALYSIS REPORTS FOR NUCLEAR POWERTIONS RESOLVED (karterty Progress ReportJuh4eptember 1990 PLANTS LWR EslortRevison # to SRP bettion 3 61, Plant Desagn

" ' " " "8 ' " ' " " " V'Environmental Aseesoment "

NURE G-1396 [NYlRONMENTAL ASSESSMENT Cf THE THERMALNEUTFON ACTIVtT ATON EXPLOSIVE DETECTON SYSTEM FOR Fracture

N### NUNM @ M NAN M M A*NU 9 FT FC V4 ENT AL ASSESSMENT FOn enO. flEFORE DALAK Furthew Devotopmenta in Regantory Policies And

POSED ROLE ON NUCtEAR POWER PLANT LICE NSERENEWALDraft Report f or Comment- NU E G 0 EUTFtDN EXPOSURE PARAMETERS FOR THE

METALLURGICAL 1EST SPECIMENS IN THE SIXTH HE AVY.SEC.Envirorwnental ttfectNUREG/CR 64M [NVIRONMENT AL EFFECTS ON CORROSION IN TON $ TEEL fRRACHATON SERIES

NUREG/CR 6462 LABORATORY ANALYSIS OF FLUID FLOW ANDTHE TUFF REPOSITORY. SOLUTE TRANSPORT THROUGH A VARIADLY SATURATED FRAC.Evocuat6on TURE EMDEDDED IN POROUS TUFF.

NUREG/CR 6306 CLOSEOUT OF IE DULLETIN 79-18 AUDIDiLffYPROBLEMS ENCOUNTERFD ON r/ACUATION OF PE RSONNEL Fracture MechaniceFROM HIGH NOISE ARE_AS NUREG 1339 RtSOLUTON OF GENERIC SAFETY LSSUE 29 BOLinNG

DEGRADATON OR F AILURE IN NUCLE AR POWER PLANTSE8P*'t Ju&mement NUREG/CR4tS V06 N2 HE AVY.St CTION STEEL TECHNOLOGY

NUREG/cR $424' ELICITING AND ANALYZING EXPERT PROGRAM SoWanrual Progress Report For April Septemtuw 1969JUDGEM(NT.A Practcal Gaue NURE G/CR $450 HIGH TE MPERATURE CRACK ARREST TESTS

USING 162.MM-THICK SEN WIDE PLATES Or LOW.UPPEn. SHELFIN # '''* BASE MATERIAL TESTS WP 2 2 AND WP 2 6f

NUREG/CR 6$72. AN EVALUATON OF THE [FFECTS OF LOCAL NUREG/CR4451: CRACK ARREST BEHAVIOR IN SEN WIDE PLATESCONTROL STATION DESIGN CONh0VRATONS ON HUMAN PER' OF LOW UPPER-SHELF DABE MET AL TE STED UNDER NONISOTH.FORMANCE AND NUCLEAR FQWER PLANT RISK [RMAL CONDITONS WP.2 SERIES

NUREG/CR 6M4 RECOMMENDATONS FOR THE SHALLOW CRACKEmplosive Detecto,FRACTURE TOUGHNESS TESTING T ASK W1 THIN THE HSST PRO-NUREG 1396. ENVIRONMENTAL ASSESSMENT OF THE THERMAL

^ NU EG CR6691 V01 N1- HEAVY SECTION STEEL IRRADIATONISE U t S I PROGRAM $arraannual Prog'oss Report f or Octater 1989 . March

Emplosive Devices 1990.

NUREG/CP 0107: PROCEEDINGS OF THE UNITED STATES NUCLEARREGULATORY COMMISSON SECURITY TRAINING Fracture Toughness

SYMPOStVM Meeting the Chanonge.hrearms Arx1 ErNowes Recog NUREG/CR 4744 V03 N1: LONG-TERM EMBRITTL EMENT OF CAST

rvtion And Detectiort DUPLEX ST AINLE SS STEELS IN LWR SY$1E MS SomearvualReportOctober 1987. March 1988

External tvent NUREG/C44744 V03 N2 LONG-TERM EMDRITTLEMENT OF CASTNUREG 1407 DRFT FC PROCEDURAL AND SUDMITT AL GUIDANCE DUPLE X ST AINLESS STEELS IN LWR SYST E MS Serraannual

FOR INOlVOUAL Pt. ANT EXAMINATON OF EXTERNAL EVENTS ReportApro-September 1988(IPEEE) FOR SEVERE ACCCENT VULNERA81UTIES Draft Report For NUREG/CR 6314 V03 Lif E ASSESSMENT PROCEDURES FORComment M AJOR LWR COMPONENTS Cast StaWess Steel Components

i

.- - _ - ,- -.

_ _ - - __ _ _ _ __ __ _ _ _ _ ._ _ __ _ _

Subj ct inds 89

NUREG/CR 6385 INITIAL ASSEfAME NT OF THE MECHO44MS AND Geologic DisposalSsGNir CANCE OF LOW TEMPERAttlHE EMBRITTLt MENT OF NUREG/CR the? AtSA METHODOLOGY FOR GE OLEclC D&CSALCAST STAINLESS Sif ELS IN LWR SYStFMt OF RADCACitVE WASTE. fuere Selection Procedirei NUREG/CR 6492 INVESilGATIONJ OF lANAthAtlON ANNEAL.AlIR.RAthATION (IAR) PROPERilES TRENDP OF RPV WELDS Phase 2 0*ologic RepositoryFrW Remrt NUREG!CRL258 COMPONENTS OF AN Ovt RALL PE RFORMANCENUREG/CR f>4p3 INFLUENCE OF FLUENCE P, ATE ON RADiATON IN ASE.ESSME Ni METFOOOLOGY.DUCED MECHANGAL PROPE RTY CHANCES IN REACTOP PRES. f4UREQ/CR 6398 TECHNICAL BASIS FOR F4EVIEW OF HIGH LIVELSURE VE SSEL STEELS Frial Repyt On E Nwatory E sPenments w ASTE REFOSITORY MODELING

NURE G/CR4494 CC*iRELATON OF IRRAbATION INUUCEU TRAN-SITON TEMPERATURE INCREASES FROM C(V) AND APC)/NIC) Oooloplesl DisposalDAT A FinaI Report NUREQ/CR4636 TECHNCAL CONSiDE RATONS FOR EVALUATING

NLtREG/CR 6611: IRR ADI AtlON EFFEC 16 ON $1RENGTH AND SUDST ANTIAL LY COMPLETE CONT AINME NT OF HOH4 EVE LTOUGHNESS OF THREE WIRE SERIES-ARC STAINLESS STEEL W ASTE WITHIN THE W ASTE PACAAGEWE LD OvEnLAY CLA7 DING

NUREG/CR4tS4 NE'XMMLNDAtlONS FOR THE GMALLOW CRACK HECTR CodeFRACTURE TOUGHNESS TESTING TASK WITHIN THE HSST PRO- NUREG/CR 65M ASSESSMENT OF THE COMBUSTON MODEL INGRAM THE HECTR CODE

Fuel Demepe HIPS 108 TestNUREG/CA 4660 DAMAGED FUEL EXPERIME NT DF.1 Resulta ArW NUREG/CR6373 A DEMONSTRATON E xP(RIMENT OF S T E AM-

Ana W es DfWEN, HCH PRE SSURE MELT [J(,CTON The WP$-10$ TestNUREG/CR-6400 DATA SUMMARY REPORT FOR FISSON PPOOUCT

RELEASE TEST Yt 3 HS$7 P*ogramNUREG/CR 5564 RECCMMENDAflONS FOR THE SHALLOW CRACKFuel Performance FRACTURE TOUGHNESS TESilNG T ASk. WITHIN THE h3St Pfu

NUhEQ/CR 3950 V06 FUEL PERFORMANCE ANNUAL REPORT FOR GRAY1988

Hestth EHectGamma Flus

NUREG/CR 4214 Roi P1 HEALTH EFFECTS MOCALS FOR NUCLEARNUREG/CR 6449 DETERMINATION OF THE NEUTRON AND GAMMA POWt A PLANT ACCIDE NT CONSEOUENCE ANALYSIS Low LE TFLUX DISTRIDUTON IN THE PRESSURE VESSEL AND CAvtTV Of Rotaton Pad lintrorAction, intepohon Ard Summry

A DOILILNG WATER REACTOR NURE G/CR 6566 EVALUATON OF HE ALTH EFFE Cf 8 IN SEOUOYAH

Qamma Sour" FUELS CORPORAtlON WORKERS FROM AOCIDENTAL EXPOSURET0 URANIUM HE AAFLUORCE

NUREQ/CR404 V03 RELATIVE DIOLOGCAL EFFECTIVENESS (RDO NUREG/CR4636 CEL LUL AR AND MOLECVLAR RESEARCH TOOF FISSON NEUTRONS AND GAMMA RAYS AT OCCUP ATONALREDUCE UNCERT AIN?lES IN ESTIMATES Of HEALTH ElfECTSEXPOSURE LEVELS Stu$es On The Gross And Mecioscopic Patw pnog toggygL gAniatoN A rpmy $wygy Observed At Death Of Mice Esposed to 60 Equat Orte Wee %

Doses Of Fiss>on~.. Heat TransferNUREG/CR 3668 MINET CODE DOCUMENT ATONOe PhenomenaNUREG/CR 6%3 Hi AS2 A THRE E DiMENSONAL 'RANSIENT SHIP-NLREG/CR 62$4 DtAS IN PEAK CLAD TEMPERATURE PRELWfnND PING CASr. ANALYSIS TOOL

D. It TO U'lCERTAINTIES IN MODELING OF ECC DYPASS AN'1 DIS-SO.VED NON-CONDENSADLE GAS PHE NOMENA Heavy Sect on Stoot irredtation Program

NUREG/CR4591 YO1 N1 HEAVY St.CTON STEEL IRRADIATIONGeneric CommunicottonNUREG-1409 DACKFITTING GUOELINES.

pF,ocRAy S mirinov Propeu Report For Odoter 1969 Mcchipg

bRL E T G RIC E 70 E Of or aRelet VaNo And D60ck Valve Roltatniny in PWR Nacicer Power Piants annual %ss Repm1 Apn1Sep w 89

Gener6c luue C 4 Hig%evel Red 6oactive Waele

NUf4EG/CR 5397. VALUE lMPACT ANALYSl$ OF REGULATORY CP- NVUEO~1423 V01: A COMPILATON Or REPORTS OF THE ADVISORYTONS FOR RESOLUTION OF GENERfC ISSUE C 6 MSiv LEAC AGE COMMi tTE E ON NUCLE AR W AST E July 1966 . June 19M

AND LCS F ALLURE. gigg4 ,,,,p3dio.ct,y, w ,g,p ,p ,,,,,,yGener6c Rid NURE G/CR $211' UNCE Rf AINilES ASSOCIATED W'TH PERFORM-

NUREG/CR463?: GENEHC RISK INSOHTS FOR WESTINGHOUSE t.NCE ASSE SSut NT OF HOH LEVEL RADOACTIVE W A$iEA COMDOSTON ENGINEERING PRESSURllED W ATER REAC f $ f ^ ''

NURE / 3A Q TECHNOUE$ FOR PROPAGATINGDATA AND PARAMETER UNCERT AINTIES IN HIGH LEVEL RADIO-

Generne Safety teous ACirVE WASTE REPOSITORY PE RFOnMANCE ASSESSMENTNUREG 0933 $11: A PRORITIZATON OF GENERIC SAFETY IS$US d

NU C 6411: EllCITATION & U%E OF EXPERT JUDGMENT INGeneric Safety leeue 16 PERFORMANCE ASSESSMENT FOR HO$tLEVEL RAD 40 ACTIVE

NUREG/CR 6556 REVIEW OF CURRENT UTERATURE RELATED 10 WASTE REFOSfTORIESGENERIC SAFETY ISSUE 15.

Fhgh4evel WasteGeneric Sately issue 29 NUREG/CR 6001: EFFECTS OF MANUFACTURING VARIADLES ON

NUREG 1339 RESOI,UTON OF GENERC SAFETY ISSUE 29 DOLTING PERFORMANCE OF HOH4EVEL WASTE LOW CARBON STEELDEGRADATION OR FAILURE IN NUCLEAR POWER PLANTS CONTAINERS

NUREG/CR 5398 TECHNOAL BAS 19 FOR REVIEW OF HOH LEVELGeneric Safety issue C-4 WASTE REPOSif 0RY MODELINGNUREG-1372 REGULATORY ANALYSIS FOR THE RESOLUTON OF NUREG/CR 6630 TECHNICAL CONSIDERATONS FOR EVALVAtlNG

QENERIC (SSUE C 8. " MAIN STEAM ISOLATON VALVE LE AKAGE SUBST ANTIALLY COMPLETE CON'TAINMENT OF HOH LEVELAND LCS FAILURE " W ASTE WITHIN THE W ASTE PACKAGE.

Geochemical Process High4evel Weste DisposalNUREG/CR 5548 REVIEW OF GEOCHEMCAL PROCESSES AN9 NUREGICR $$21 USE OF PERFORMANCE ASSESSMENT IN AS-

CODES FOR ASSESSMENT OF RADIONUCUDE MORATON PO- SE SSING COMPLIANCE WITH THE CONT AINMEN T REQUIRE,TENTLAL AT COMMERCIAL LLW BITES MENTS IN 40 CFR PART 191.

. - , _ ._ __ -_ _ _ _ - , _ - - _ -

__ . _ __ __ _ _ _ _ _

90 Subject inCox

m e m .e Are. iCAP ProremeNVRI G/CR 6306 CLOSEOUT OF lE DVLLETIN 7b lB AUDOLITY NURI O/lA 0023 V01' ASM SSME NT Of TRAC PI t /MODt VlR$lON

" FHoudMS E NCOUNTERED ON EV ACUATION OF PERSONNEL 14 3 USING St PARATE EfitC18 CRITICAL FLOW AND DLOW,FROM HIGH NOISE ARE AS ()OWN EFERIMENTS volune t Test AM TaNet

NVRE G/6A410/3 V02 ASSLbSMENT Of TRAC-PF 1/ MODI vt RSIONHeph Preneure Melt Streamin$ 14 A USING BEf'ARATE EFFECTS CRITICAL FKM AND Dt04

NVREG/CR 6373 A O(MONSTRATION EXPERIMENT OF STE AM. DOWN E APE RIMENTS Voume 2 FqJetDRIVEN. HIGH4HISSURE MELT LECTION The HIPS-108 Test

IE Buholm 7D 17Human Erre' NUREGICR 6286 CLOSEOlJT OF 10 DULLETIN 7917 PIPE CHACKb IN

NUREG/CR 6627. FilSK SEN$lflVITY TO HUMAN ERROR IN THE LA' ST AGNANT BORATED W ATER SYSitMS AT PWR PLANTSSALLE PRA

Supeun 7WHuman Ettor Probability NUREG/CR 6336 CLOSLOUT Or IE DVLLETIN 7918 AUDiBILftY

NUREG/CR4639 V4P2R2. NUCLEAft COMNTERIZED LIBRARY FOR fHOOLEMS ENDOUNTt rid ON Ev ACUATION 08 PERSONNELASSE$$1NG REACTOR RELIABILITY (NUCLARR)UWs GuMe Part 2 FROM HIGH NOISL ARE A$Go To OperMons

NUREG/CR 4639 v4P3R2. NUCLE AR COMNTEfti2ED LIBRARY FOR ' 0ASSE St E C OR RE ADILITY (NVCLARA) Users Gude Part 3. NU G 6% CLOht OUT Or IE EtVLLt' TIN 79 23 POTENTIAL

NURE G/CR-b438 BAb6$$1DE81ATIONS IN PRIDICTING ERROR FAILURE Of EMERGENCY DIESEL GINLRATOR fi!LD ERCITEf4

PROBABluTIES IN HUMAN T ASA PERF ORMANCE TRANSFORME R

.E Be, con .mnurn.,,,et.,NUREG/CR 6213 V01; THE COGNITM ENVIRONMENT SIMULATION NVREG/CR 6307. CLOSLOUT OF IE BULLE TIN 6002 INADEOVATE

AS A TOOL FOR MODELING HUMAN PERF ORMANCE AND OVALITY AS$VRANCE FOR NUCLE AR BUPPLilD EOVIPML NT,

13$bH $ TiVE FfMRONMENT SIMULATION It Bubetin 8010f / 4AS A TOOL FOR MODELING HUM AN PERFORMANCE AND NUREG/CH 6302 Ct.OSEOUT OF 10 DOLLETIN 6010 CONT AMINA-REllAnitrfY Man Repwt ilON OF NONRADIOACTIVE SYSTEM AND RESULTING POTENT AL

NUREG/CR 6439 HUMAN FACTOHS ISSUES ASSCciAtED WITH AD- FOR UNMONITORE D, UNCONTRoutD fit LE ASE OF RADIOACTIV.

VANCED INSTRUMENT ATION AND CONTROLS TECHNOLOGIES IN (TY TO ENVIRONMENT.NUCLE AR PLANTS a Os, con .m

Human Portorynence NUREGICR 6336 CLOSCOUT OF IE OVLLETIN 60-16 POSSIDLENUREG/CR 6672 AN FVALVATION OF THE EFIECTS OF LOCAL LOSS OF EME RGENCY NOTIFICATION b) STEM (ENSI WITH LOSS

CONTROL STAflON DEstGN CONFIGURATIONS ON HUMAN PER- OF OFf SITE POWERFORMANCE AND NUCLE AR POWER PLANT HISN

~

IE Bohetin 4H6Human Renemy NUREG/CR 6297 CLOSEOUT Of it BULLETIN 83 06 ASME NVCLEAR

NUREG/CR 6213 Vot: THE COGNITIVE ENVIRONMENT S'MULATION CODE PUMPS AND SPARE PARTS MANUF ACTURED BY THE HAY.AS A - OOL FOR uODELING HUMAN PERFORMANCE AND W ARD TYd R PVMP COMPANY.FtElLAB:LITY Enocutwo Summary

NUREQ/C46213 V02- THE COGNITWE ENVIRONMENT SIMULATION IE Buneun 64-03AS A TOOL FOR MODELING HUMAN PERFORMANCE AND NUREG/CR4526 CLOSEOUT OF IE DunETIN 6443 REFUELINGRELIABILITY. Main Report CAVITY WATER SEAL-

Human Renemy Data lE BubeUn $6-01NUREG/CR-4639 YO1 R1: NUCLEAR COMPUTERIZED LlDRARY FOR WREGICHW @$N OF E DMTW p STN N

ASSES $ LNG REACTOR REUABiUTY (NUCLARR) Summary Dexte M OF AUMRY FNATER PUMPSton

NVREG/CR 4639 V6PIR3 NUCLEAR COMNTEnl2ED LIBRARY FOR R Bubeun 4WASSES $1NG FIEACTOR REllABluTY (NVOLARR) Data ManuaLPart 1: NVREG/CR441: CLOSEOUT OF IE BULLETIN 66-03 MOTOROPE R.

ATED VALVE COMMON MODE F AILURES DURIN3 PLANT TRAN-NU 1 63 2R3 NVCLEAR COMPL/TER!1ED UBRARY FOR SIENTS DUE 10 IMPROPER SWITCH SETTINGS

AS$ES$ LNG REACTOR AELIABluTY (NUCLARR) Data Manual Part 2

N f N 463 VP 3 R COMPUTERIZED UBRARY FOR NUREG/CR 6296 CLOSEOUT OF lE COMPLIANCE BULLE TIN 6603lE Compliance BuNeun 66 03

ASSE S$1NG RE ACTOR RELIABluTY (NUCLARRI Data Manual Pa t 3 POTENTIAL FA! LURE Or MULTIPLE ECCS PUMPS DUE TO SINGLEHardware Component Failure Data (HCrD)_F AILURE OF A14 OPERATED VALVE IN MINIMUM FLOW RECIRCU.

Human Tsen Performance LAflON LINE.NUREG/CR 6438 BASIC CONSIDERATIONS IN PREDICTING EftROR

PROBADILITIES IN P * AN T ASK PERFORMANCE.E Power System

NURE G /CR.6101. NUCLEAR PU 9T AGING RESE ARCH THE ttHytirogen Combuetion POWER SYSTEM

NOREG/CR6566 MfTIGATION OF DIRECT CONTAINMENT HEATINGAND HYDROGEN COMBUSTION EVENTS IN ICE CONDENSER IMPACTS-BAC

PLANTS A%rses With Tbs CONT AIN Code And NUREG 1160 PRANUREG/C46617. IMPACTS BRC, VERSION 2 0 Progam User's Manual

IRAAS

Hygrogen Genereuon NUREG/CR-6111: INTEGRATED REUADiUTY AND RISK ANALYSl$NUREG/CR6597; IN VE SSEL ZlRCALOY.OxtDATION/ HYDROGEN- SYSTEM (IRRAS) VERSON 2 0 USER'S GUIDE.

GENERATION BEHAVIOR DURING SEVERE ACCIDENTStco Con 0enser

LAEA NUREG'CR 6686 MITIGATON OF DIRECT CONTAINMENT HEATINGNUREG/CP 0112 V01: PROCEEDINGS OF THE THIRD INTERNATION- AND HYDROGEN COM0VSilON EVENTS IN ICE CONDENSER

AL ATOMIC ENERGY AGENCY BFECIAUSTS' MEETING ON SUB- PLANTS Anavies with The CONTAIN Code And NUREG 1160 PRACRITICAL CRACK GROWTH Opening Session And Techncal Seswn Methnology| Head At Moscow, USSR.May 14 17 1990 NUREG/CR 6602. SIMPUFIED CONT AINMENT EVENT TREE ANALY-

NUREG/CP 0112 V02: PROCLEDINdS OF THE THIRD INTERNATON- SIS FOR THE SEQUOY AH ICE CONDENSER CONT AINME NTAL ATOMIC ENERGY AGENCY SPECIAUSTS' MEETING ON SUB-CRITICAL CRACK GROWTH Techncal Sessions li, Ill. And IV And ice 4cndenser ContainmentRecommendabons And Conclusons Seshon V He6d At NUREG/CR 5689 ASSESSMENT OF ICE CONDE NSFR CONT AINMENTMonm*, USSR.May 14 17, 1990 PERFORMANCE ISSUE S

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Subject index 91

enedeouste Core Cochng instrumentation inter 9tenu6er CrackhsNURE G/CR4374 BUMMARY OF INAEOUATE OORE COOLING IN NURE GrCR 3873 EFFECT Or WELDING CONDiTONS ON TRANS

STRUME NTATON FOR UNITE D STATE 8 NUCLE AR FOWL R FORMATON AND PROPERTIES OF HE Al A7 FECTLD TCWE b ONPLANTS LWR VESSEL STEEL $

tricinerehon inter 9' anular Strees Corro*6on CrackNUREG 1393 THE INCINERATION OF LOW 4EVEL RADOACTIVE NURE G/C4408 ULTRASONIC INSPECTION REUAlttufY FOR IN-MSIE.A Rewt f or Tte Adnewy Commttee On N46 ear Wasie TERGRANULAR STRESS CORROSION CRACAS A Rowuf R;en

IndWlual Plant Etaminat6on Study Of The i Hects Of Permtrol. Procches, Egapnunt. And Cre3Chmenma

NUREG 1407 DRFT FC. PROCEDUFtAL AND SUBM!TTAL GUCANCEFOR INEvVIDUAL PLANT E AAMINATON OF EKTERN AL [VE NTS Ingentory Differsace Dett(IPEEE) FOR SEVERE ACCOENT VULNERABILITIES Evatt Repar1 For NUREG4430 V09 V12 LCENSE D FUEL F ACILIT Y STATUSComment REPORIinventory Etherence Data Jdy 19ft6. June 1989(G*ey Etwh

H)inf9trationNUREG/CR $$23 DEVELOPMENT Or AN tNrlLTRATON EVALVA- lon Enchange

TION METHODOLOGY FOR LOW 4EVEL WASTE SHALLOW LAND NUREG/GR $594 RADIATON DEGRADATON IN EPCOR il ON C A-DURIAL SITES CHANGE RESINS

Information D6goet Irldsum OstdeNUREG 1360 V02 NUCLEAR REGULATORY COMMISSON INFORMA. NUREG/CR M64 PH SENSORS BASED ON IROtVM OxlDE

TION DIGEST.1990 Edeten.trfedlet60n

Inservice inspectionNUREG/CR $492. INVESTtGAtlCWS OF IRRADIATION ANNE Al-RElfo

NUREG/CR4469 V06 NCWDESTRUCTIVE EAAMINATON (NDi} REU. RADIATION (nAR) FHOPERflES TRENDS OF WV WEtttS Pbene eABluTV FOR INSE RVICE INSPECTON OF LlGHT WATER Final RetratRE ACTORS Genuarinual RePortOctober 1987. March 1968 NUREG/GRSSt1 4HRAD4ATON EFF[ CTS ON STFIE NG TH AND

NU8tEG/CR-4469 V09 NONDf STRUCTIVE EAAMINATlON (NDE) RELl- TOUGHNiSS OF_ THREE. WIRE SERIES ARC STAINLESS STE FLABluTY FOR INSERVICE INSPECTON OF LIGHT W ATER WE LD OVERLAY CLADDINGRE ACTOP.S Se% annual RoPortAps Septemter 1988

NUREG/CR4409 Vt0 NONDESTRUCTNE EAAMINATION (NDE) REll, irradiation EffectABluTY FOR INSE RVICE INSPECTON OF LIGHT WATE R NURE G/CR 6409 NEUTRON EXPOSURE PAFtAMETERS FOR THERE ACTORS Sermannual RetrartOctober 1988. March 1989 METALLURGOAL TEST SPECIMENS IN THE sixth HEAVY.MC.

NUREG/CR 4731 V02: RESIDUAL LIFE ASSESSMENT OF MAJOR TION STEEL iRRADIATON SERIE SUGHT WATER RE ACTOR COMPONENTS . OVERvlEW

NUREG/CR 4862- OVAUFICATON FHOCE SS FOR ULTRASONIC Irred6storTE STING IN N JCLE AR INSERVICE INSPECTON APPUCATONS NUREG 1392 LEAK. AGE OF AN IRRADIA100 SOURCE . THE JUNE

NUREG/CRS11e STEAM GENERATOR TUDE INTEGRITY FHOGRAM/ 1986 OEOROLA ASIINCIDENT.STEAM GENERATOR GROUP PROJE CT. Final Prtyuct Surnma'yp,pg J-R Curve

NUREG/CR 6662 AN OVEnvi[W OF THE LOW OPPER SHE LFinaerv6ce Testing TOUGHNE$5 SAFETY MARG |N ISSUE,NUREG/CP 01' f: PROCEEDINGS OF THE SYMPOSIUM ON INSERV-

ICE TESTIN'J OF PUMPS AND VALVES Held Al ite Hyoft Regency Jet Impingement LeadHotel, Wash,ngton.DC, August 1 3,1900' NUREG/GR 6679 VALUE/lMPACT ASSESSMENT OF JEI IMPINGE.

MENT LOADS AND PIPE.TO PtPE IMPACT DAMAGE Remed Mothinspection oos And CriteneNUREG43040 V13 N04. LICENSEE CONTRACTOR AND VENDOR IN-

SPECT ON TUS REPORTi QuarterY ReportOctote December LA)'

g CRM WR DE NCHM ARK AGAINST IN PHASE ANDNUREG 0040 Vid 2 UCENSEE CONTRACTOR AND YENDOR IN. OUT.OF PHADE STABIUTY TESTS

S ON STATUS REPORT. Quarterty Report. April-June 1990.(WhiteLAPUR UWs Guide

NUREG4040 V14 N33 UCENSEE CONTRACTOR AND VENDOR IN- NURLd/CR 6421 LAPUR USER'S GUOE,SPECTON STATUS REPORT, Quanony ReportJuty Septamt* LBLOCA

N O ESULTS FROM THE NUCLEAR PLANT AGING RE. 4y q g 4 gp ySEAPCH PROGRAM THEIR USE IN INSPECTION ACTIVITIES.

tropection Guide LE.R

NUREG/CR 6617: AUXILLARY FEEDWATER SYSTEM RISK BASED IN- NUREG/CR 2000 V00N12 UCENSEE EVENT RLPORT (LE R)COMon ATQ For um Ot Emmte 1989SPECTION GVIDE FOR THE J M FARLEY NUCLEAR POWER

NUREG!CR 2000 V09 Nt: LICENSEE EVENT REPORT (LL FI)PLANT,COMPILATON Fcv Month Of Jerue'Y 1990

triepect6on bok NURI G/CH 200(I V09 N2 UCcNSEE EVE NT REPOPY (LER)COMPILATON Frr Morm Of Fetruary 1990.NUREG/CR 6616 AUXIUAry FEEDW ATER SYSTEM RISK DASED IN.

NUREG/CR 2000 V09 N3 UCENSEE E VENT REPORT (L E R)SPECTION GUIDE FOR THE DIABLO CAN' ON UNIT 1 NUCLEAR COMPIL ATON For Month Of March 1990POWER PLANT,NUREG/CR-2000 V09 N4 LICENSt[ LVENT REPORT (LER)

instrivnent Air System COMPILATON For Month Of Apr81990NUREG OR,2000 V09 NS LICENSEE EVENT REPORT (LER)

NUREG/C46419 AGING ASSESSMENT OF INSTRUMENT AIR SYS- COMPILATON For Month Of May 19'.80TTMS 6N NUCLEAR POWER PLANTSNURE G/CR 2000 V09 N6 UGNSE E EVENT REPORT (LL R)NUREG/CR 6472 A RISK BASED REVIEW OF INSTRUMENT A!R BYS- COMPILATION For Month 01 Jure 1990

TEMS AT NUCLEAR POWER PLANTS.NUREG/CR-2000 V09 NE LCENSE E EVENT REPORf (LER)

lOtrumentation And Contro' COMPILATION For Month Of July 1990NUREG/C42000 V09 NB UCENSEE EVENT REJORT (LE R)NUREG/CR-6430 HUMAN FACTORS ISSUES ASSCOIATED WITH AD. COMPILATON For Month Of Aooust 1990

VANCED INSTRUMENTATION AND CONTROLS TECHNOLOGIES IN NufsEG/CR 2000 VOD N9 UCENSEE EVENT FiEPORT (t E R)NUCLEAR PLANTS COMPILATON For Month Of Sociemter 1990NUREG/CR 2000 V09Nt0 UGE NSEE EVENT REPORT (LE R)integret6on System

COMPILATON For Month Of Octoter 1990NUREG/C462ti2. PRAM + PROOADIUTY Risr, ASSESSMENT MODELNURE G/C42000 V09Ni t : LICENSE E EVENT REPORT (LER)INTEGRATON SYSTEM Users Guide COMPILATON For Month Of Novemt et t990

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- - - . -- .. _ - - _ _.- - . . - - - _. - - . _ _ - - -

4

92 Subject Indax

LOCANUAEG/CR f,616 LIGHT WATEH NE ACTOR PHESSunt th0L ATION

NURE G AA-0021 RELAP6/ MOD 2 CALCULATONS OF OECD Lori VALVE PERFOHMANCE TESTING

TEST LP.$D 2Las Cruces Trench $lta

LOFT NU4EG/CR b(01. FLOW AND TRANspont AT THt LA$ CfluCESNORE G/lA-0031: ICAP ASSI$$ MENT Or RtLAP6/ MOD 2, CYCLE TRENCH slTE EHe$ rents 1 And 2.

36 05 AGAINST LOrt $ MALL ltRE Ak ERPt AlMENT L3 7IdUREG/tA4033 ASSESSME NT OF $4 ELAPS / MOD 2 CYCLE 36 04 Laek Flata

AGAINST LOTT $ MALL DREAK f.KPERIMENT L3 6 NURE G/CP.0t09 PROCEED!NGS OF THE gg M NAR ON ggAL"""" " "#Y -** *

4.WRIdVHL&Opa0 03 61 R2 ST ANDAAD HEVIEW PLAN FOR THE REYlEW

OF SAF E TY ANALYSIS HEPORTB FOR HUCLE AR POWER w .p,,,,,.g,,,g

PLANT $ LWR EeticeHeeson # To SRP 6ecton 3 61.Piant Des 9" NUFH/CP.0109 PROCEI DINGS Or THE M MW A4 ON LLACFtv Protecton Agdunat PostJated Ptpng FalNres in Flud Byttems Wt' BE F C#tt .DRE AK F urthee Develogants in HegJahry FWes Arvt

MN #NU 000017.3 R30 GT ANDARD HEVIEW PLAN FOR THE REVIEW

OF $AFETY ANALYSl$ FtE PORTS FOR NUCLEAR POWER (,,g,9, cong,,i gy, temPLANTb tW81 E$ ion Reenon 0 To $tlP Secton 17 3. "Qualtty Atm s- NUHEG-1372. REGULATOHY ANALYLIS 504 THE Hf ROLUTON OF

NU EG C A ECHNOLOGY. SAFETY .tND COST $ OF DE. $ UdQ;8, " MAIN sTE AM ISOLATON VALVt LE AAAGEC

COMMi$ BONING REFERENCE LIGHT WATEFt F4E ACTORS F04 NVALG/C4 6397 VALUE IMPACT ANALYSIS OF REGUL ATOHY 09LOWING POSTULATLD ACCOENTS Re Evaluabort Of The Cleanup TONS FOR RESMUTON OF GENERIC IS9UE 04 MLiv LE AKAGECoat For The Boehng Water Apactor (EtWR) Scenaro 3 Accdont From AND LC$ F AILU40NUREG/CH P901.

MUNEG/CH 3444 V07. THE IMPACT OF LWR DECONTAMINATONS g,gng gg,,,L F WASTE DISPOSAL AND ASSOCIATED OCCU' NURM 1397 LE.AtAGE Of AN IHRADiATOR SOURCE . THE JUNE

966 GEOHWA RSI INCOE NLNUREG/CH 3673 Ef FECT OF WELDING CONDITIONS ON TRANS-

FORMATON AND PROPERTIES Or Ht AT.AFFECTED 20NES ON Le8el leauancesLWR VE ESEL STE tts NUREG47b0 CIOP INDEKEB TO NUCt.t AR REGU( ATOHf COMMIS-

MUHEG/C4.4469 V06 NONDESTRUCTIVE EXAMINATION (NDE) REll- SiON ISSUANCES . tannery 1.1980 itywp Nicemtw 31,19%ADtuTY FOR INSEHVICE INSPECTON OF LIGHT WATE51 INDE KES TO HvCtE AH Nt aut.ATORY OOM-

NUMEG 07$0 V30 601|6 JuYbartemte the9HE ACTOR $ 5ertwannuti Actort.0ctote 1967 March 1986 Mi& SON isSU ANCfNUNEG/CR-4469 V09 NONDE STRUCifVE EXAMINATON (NDE) REll. WRM750 V30 M INDEkES TO NtK;LE AH RE GUL ATOHY CCR

ABILITY FOR INSERVICE INSPECTON OF LIGHT W ATE R MISDON ISBUANCE B July Decomter 1969HE ACTORB Semannual Aervat Atwil Emptemtet 1966 NUREG 07f.0 V30 NOI: NUCLEAR HEGULATOHY COMM6510N 14

NUtiEG/C44400 V10 NONDE STHUCTIVE EKAMINATON (NDE) REll. 8UANCE 8 f D'' JULY '988 P"0"* 1-64ABILITY FOR INSE RVIC[ INSPECTION OF lGHT WATER WREG 0160 V30 NO2 NUCLEAR NEGUL ATORY COMM|$ SON iS-Fit ACTORS Senuannual Hoport.0ciate 1904 March 1999 8UANC a FOR AUGUST 1960 Paves e5 IM

NUnEG/CM4t47 V07. E NViHONMENT AL1Y AS$1STED CRACKING IN NUNIO-0'760 V30 ND3 HUCLE AH HEGULATORY COMM6 SON 15LIGHT W ATER RE ACTORS serrnarmat AeportApril September 1968NUHEG/C44W7 V06 ENVIRONMENT ALLY ASSISTED CHAChlNG IN

SUANCE S FOH 6EPit MDEh iba9 Pues 107 PP9NunEG4760 V30 N04 NUCLEAR Dt dVLATORY COMM6 SON IS-ilGHT WATER REACTOR $ Lomennual Report.Ottober 1988 March $UANCf S FOH OCTODER 19f!9 Pages 231-323

1969 NUMEG4760 V30 NOS HUCLE AR HEGUt ATORY COMMtSSON l$NUftEG/Cf14674 V00 PRECUFtSORS TO POTENTIAL BEVERE CORE BUANCES FOR NOVf MULH 1989 Pages 325 70sDAMAGE ACCIDENTS 1986 A STATUS HEPORT Mem Fteport And Ap. NUREG0760 V3C toe NUCLE AR REGULATOfly COMMiS5 TON 14

perda ANUHf G/CR 4374 V10 PRECURLOAS TO POTENTtAt $ EVERE COHE

SUANCES FOR DECEMDEH 1989 Pages 704411.NUHEG4760 V31 101 INDEXES TO NUCLE AR Hl.NLATORY COMDAMAGE ACCIDENTS 1968 A STATUS REPOHT.Appen&es B And M6$10N ISSUANCE & Jnery March 19%

C NUHEG0760 V31 102 INDEXES TO NUCLE AR hl GULATONY COMNUHEGIC64674 VII. PHECURSOnt TO POTENTIAL BEVERE COhE Mf1 SON ISSUANCE S January. June tenDAMAGE ACCIDENTL 1369 A STATUS itEPOf1T Man Report And Ap.

NOREG 0750 V31 NOI: NUCLFAR REGUL ATOftY COMM6GON 15pards ANUHEGICR 4674 VW PREOURSOH$ T0 POfENTIAL BEVERE CORE GUANCEs FOR JANUARY t990 Peans t.t30

NUREG-0760 V31 NO2 NUCLE AR (tEGULATOHY COMMISSON ISDAMAGE ACCOENTS 1969 A GTATU9 REPORT Appemhtes B AndSUANCFB FOR Ff DHUARY 1990 Pa s t3t tn

NUREG4760 V31 NO3 NUCLE AR HyGULATOHf COMM6blON 16CNUHEG/CR 473 I V02. AESIDUAL UFE ASSELSMENT Or MAJOR

.

LIGHT WAf t R CEACTOR COMPONENTS + OVEFtVIEWBUANCE S FOR MARCH 1990 Paps 197 332

NUHEG/CR 4744 V03 N1; LONG TERM EMDRITTLEMENT OF CAST NUREG 0760 V31 f404 NUCLEAH HrGULATORY COMM6SION IS-

DUPLEX 61AINLEBS STEELS IN LWH 8YSTE MS Lermannual BUANCES FOR april.19J0 Paps 34370NUREG-0750 V31 N05 NUCLE AR HEGULATORY COMMihSiON IS.Aepart October 196? , Merch l9M

NURFG/CH4744 V03 N2 LONG-TERM EMDFtiTTLEVENT OF CAST SUANCE S IOH MAY 1990 Pages 371481

DUPLEX ST AINLE S$ STEELS IN LWR SYST EMS $emannual NUREG4760 V31 N06 NUCLE AR HEGULATOHY COMM6SION IS-$U ANCE 6 7 OH JUNE t990 Pops 4ft3 604

Retort. April-Septemter 1988NUCEG/CH 6273 V04 - SCDAP/RELAPS/ MOO 2 CODE NUAEG 0760 V32101 INDEXES TO NUCLE AH HEGULATOHV COM

MANUALVOI.UME 4 MATPRO A LORA8tY OF MAf f HLALS PROP. M6 SON ISSUANCt & July E.eptomter ItnoNUREG.0750 V32 N01: NUCLEAR REGUL ATOHY CouM654GN IS.EHilES FOR LIGHT. WATER REACTOR ACCIDENT ANALYSig

NUREG/CR 6314 YO3 LIF E ASSE SSMENT PHOCEDURES FOR SUANCEs FOR JULY 1990 Pages 1 MNUREG4750 V32 NO2 NUCLt AR REGULAfORY COMMisSON IS-M AJOR LWH COVDONENTE Casi Stairwest Steel Component,

NUREG/CH43B5 INITIAL ASSE% MENT OF THE MECHANISMS AND SUANCES FOR AUGUST 1990 Pages f4 t2e

SIGNIFICANCE OF LOW-TEMPERATURE E MDRfTTLE MENT Or NUREG47b0 V32 f403 NUCLEAR RE GULATO4Y COMMISSON IS-CAST ST AINLEi$ STEELS IN LWR BYSTEMs SUANCES f 04 SEPTEM6f A 1990 Pages tro 199

NUHEG/CR-6406 ANALYSIS Of SHELL RUPTURE FAILURE DUt TO 14UREG 0750 V32 N04 NUCt E AR Rt GULATORY COMussON 15HYPOTHETICAL EL.EVATEDTEMPERATUPE PRELSURIZATON OF SUANCES FOR OCTODER 1990 Page 201331

THE SEQUOYAH UN:T 1 STEEL CONTAINMENT DUILDINGNUREG rCR-6451 CRACK ARREST DEHAVIOR IN SEN WOE PLATES UC*rtae R*gulatlon

Or LOW. UPPER-SHELF DASE MET AL TESTED UNDER NON SOTH. NUREG/CP.0iD6 PUBUC WORKSHOP DN NUCLEAR POWlH PLANT

ERMAL CONDITONS WP.P SERIES LICENSE RENEWALNUREG/CR 5476 POST TEST ANALYSIS OF A 16 SCALE HEIN-

FO40E0 cot 4CRCTE RE ACTOH CONTAINMENT 00tLDING Ucense RenewalNUREG/CH $490 V01. HEGULATOHY INSTRUMENT REVlEW MAN- NUHf G 1299 ORFT FC ST ANDAFO REvilW PLAN roh THt ACVitW

AGEMENT OF AGING OF (WR MAJOR SAFETY hELATED COMPO- OF UCENSE HENEWAL APPUCATIONS FOR NUCLE AR POWERNENT$ PLANTS Droft Repor1 For Cornment

- __ ____ __ , _ _, - . _ _ . _ . . , _ _ _ _ . _ . _ _ . . _ _ , _ _ _ _ _

.. _ . . . - _

i

Subject index 93

NUREG 1362 DRF FC ER Eresta to "Regmatory Anaysas Int Proso6ed NUREG/Cf44469 V09 NONDE STRUCTfvE E AAMINATION (NDE RE L6} Rse cm Nuciw Power hant LKonse RenewaLDreN fiept for Com. ABillTY FOR INSE RVICE IN5PE CTON C# EIGHT W AT! R

mentf revismg Secton 7 2 on Pe2e E3 to 'eMi #8 l'stonRE ACTORS Senwaywel Repwt A;vp Septemtier 1968NURI G 1389 DRfi F C E.NVIRONVENT AL ALE b5 MENT FOR PRCLi

NUREG/CR44ti9 V10 NONDL STftOCTM LAAMINATON (NDE) RELLPO5f D RULL ON NUCLE AR POWER PLANT LICE NSE ABILITY FOR INSL RVICE INSPECTON OF UGHT W AT E RRF NE W AL Eran her<rt F or Ccmment $tt ACTORS Semtantual ReportOctote 1988. MWeh 19R9NURE41411- RESTONSE TO PUBUC COMMENTS RESULTING FROM NUREG/CR.4M7 V07 ENVIRONMLNT ALLY ASb4TED CHACAING IN

THE PUBLIC WORASHOP ON NUCLE AR POWER PLANT LICENSERf NF W AL LIGHT W ATE R RE ACTOR % bem6arrwat Reptet Aprti September 1968

NUHLG.to12 DRFT FC. FOUNDATON FOR THE ADEQUACY OF THE NUREG/CR 4M7 VD6 ENVllONMENT ALEY A$SISTED CHACAING INLICENSING BASES A Sugvement To The Statement CW Cons @ LIGHT WATE R RE ACTORS Semwinual ReportOctate 1988 March

mgstgr$ For The Praso6ed Rate On Nuciw Power Plant LKense Re-

NUREG/CR4674 V09 PRECNRS TO POTENTIAL SEVERE COREL)A81 POATP PLANT ^ ^ " "NU 8 Ut C OF

LICENSE RENEvv AL-NUREG/CR4674 V10 PRECURSORS TO POTENTIAL SEVERE CORE

Lkensed Fuel FacH!tY DAMAGE ACCIDENTS 19B8 A ST ATUS RE PORT AMendne B AndNUREG O4D VN NO2 LICENSE D FUEL FACILITY STATUS C

i EPORT truentcry DWerence Data July 1968 June 1999 (Gray Book gvREG/CR4674 V11: PRECURSORS TO POTENTIAL f EVERE COREDAMAGE ACCIDENTS 1999 A ST ATUS REPORT Main hercrt And Ap-gee A

Licensed Operatmg Reactors NUREG/CR-4674 VIP PflECURSORS TO POTENTIAL SEVERE CORENUHFG Co?O vn Nit: LICENSED OPERATING RE. ACTORS STATUS DAMAGE ACCIDENTS 1999 A STATUS REPORT Apgerxiges El And

SUMMAM pf TORT Deta As Of Octaber 30.1999 (Grav Inx* I) CNURI G 0020 V13 N12 UCEN5ED OPLRATING RE AC* TORS STATUS NUREG/CR 4731 V02 RESIDUAL LIFE ASSI SSMENT Or MAJOR

SUMMARY RE50RT Dats As Of Nove%er 101989(Grar Bxe 4 LIGHT W ATER RE ACTOR COM8CNI NTS OVf RVIEWNURE GE?O V14 N31. LCEPSED OPERATIN5 RE ACTORS ST ATUS NUREG/CR 4744 V03 N1. LON3 TERM EM080TTLE MENT OF CAST

SUUM ARY RSPORT Data As Of Decemter 311969 (Grey Da.9 ft DUPLE X S TAINLE SS STEELS IN LWR SYSTE MS bennantualNUREG4020 vid N02 UCENSF D OPEftATIND hE ACTORS ST ATUS Repr.rtOctoter 1967 March 1988

SUMMARY REPORT Dsta As CW Ja way 311990 (Gray Rm* O NURLG/CR 4744 V03 N2 LONG TE AM EMBRITTLEMEVT OF CASTNUHf GOJ20 V14 433 LICENSED OPERATING RE ACTORS STATUS DUPLE X ST ONLE SS ST[h8 IN WR SYM EMS tana malSUMM ARY RE PORT Data As Of Fetruary 26.1993(Gray Book I) n,pygprg.s.pi ng,,1968Wnsee bent RW NURf G/CR4273 V04 SCOAP/RELAP6/ MOD 2 CODE

NUREG/CR 2000 Vf*N12 L4 CENSE E EVENT REPORT (LE R) MANUALVOLUME 4 MATPRO . A LIBRARY OF MATERLALS PROP-ERTIE S FOR EIGHT-W ATER 8tE ACTOR ACCfDE NT AN ALYSIS

L EN E EVENT REPORT (LER) NURE G /CR4314 VD3 LIF E ASSESSMENT PROCEDURLS FORNU VJ9t990 . MA.OR LWR COMWNTS Cam Paness W GmponentsCOMs

mATION Ftr Myth Of Janua75EENUREG/CR 2XO V09 42 LICE t EVENT REPORT (LE R) NUREGICR $365 IN!TIAL ASSE 5SMENT C$ THE MI CHANGMS ANDCOMPit ATON $ or Month Of Foteuary 1990 StGNWICANCE OF LOW.T E MPt RATURE E MDRITT L E MEN T Or

NJRIG/CR Koo VW N3 L 6CE NBE E EVENT REPORT (LER) CAST ST AINLE SS STE E LS IN LWR SYSTEMS(OMPILATON For Month Of March tWO NUREG/CR 5405 ANALYSIS CW SHELL RUPTURE F AILURE DUE TO

NUREG/G42300 ' V00 N4 UCE NSE E EVE NT REPORT (LE R) HYFOTHETICAL E LEVATE D TEMPE RATURE PRESSURt2ATON OrCOMML ATION For Maeth Of Apnl 1DVJ THE SEOOOY AH UNIT 1 STE E L CONT AINMENT HUILDiNG

NURE GICA2000 V09 NS UCENSE E EVENT REPORT (LE R) NUREG/CR4451: CRACK-ARRE ST DEMAVIOR IN GEN WIDE PLATE SCouptLATON For Month Of May 1990 OF LOW UPPER-SHELF BASE METAL TESTLD UNDER N(WSOTPNUREGICA 2000 V09 N6. LIJNSE E EVENT REPORT (LE R) ERMAL CONDITIONS WP 2 SERIESCOMPIL A'ON For Month Ot Jure 19ta0 NURE G/CR4476 POSTTEST ANALYSIS Or A i tLSCALE REIN-NJRE GICR 2000 V0J N? LICENSE E EVENT REPORT (LE R) FORCED CONCRETE RE ACTOR CONT AINMENT UUILDINGCOMPIL ATON ror Manth 0f Juty tWO

NUREG/CR4490 V01 REGULATORY INSTRUMENT REVIEW. MAN-NUREG/CR 2W0 V09 NB UCE NSE E EVENT REPORT (LE R) AGEMiNT OF AGING OF LWR MAJOR SAFETY RELATED COMPaCOMPILATON For Month Of August 1Wo yg gNURE G rCR,2000 VO9 N9 LK ENSE E EVENT REPORT (LE R)COMPILATON For Month 04 Sepament 1993 NUREG/CR45t$ LIGHT W ATER REACTOR PRESSURE 150LATON

VWN10 UGL NSE E EVE NT REPORT (LER) VALVE PERFORMANCE TESTINGNUREG/CR FOOCOMPit, ATON For Manth Of OctoNir 1990

(%CMi i F or 08 e 19 NUREG/CR4229 V03 EPtCOR-li RESIN / LINER INVESilGATON LOW-

LEVEL WASTE DAT ABASE DEVELOPMENT PROGRAM FOR FISCALLlfo Asaasament YE AR 1990 Annual Report

NUREG/CR 5314 VD3 UFE ASSESSMENT PROCEDURE S FORM AJOR LWR COuPONENT S Cast Staness Steel Components Lose Of Coolant

NUREG/CR4254 BtAS IN PEAK CLAD TIMPERATURE PREDICTIONSUght Water ReactorDUE TO UNCERTAINTIES IN MODEL'NG OF ECC BYPASS AND DIS.

NUREG-OOO 03 61 R2 ST ANDARD REVIEW PLAN FOR THE REVtEW SOLVED NONCONDENSABLE GAS PHENOMENACF SAFETY ANALYSS REPORTS FOR NUCLEAR POWER NURE G/CA5474 ASSESSMENT OF CANDOATE ACCIDENT M AN.PLANTS LWR E&tson Revisen 2 To SRP Secton 3 61.P44nt Des *gn AGEMENT STRATEGIESFor Protecten Agamt Postulatesi Peng Fadures to Fknd Systems Out. NUREG/CR4637: GENERIC RISK INSIGHTS FOR WESTINGHOUSEue . AND COMBUSTON ENGINEERtNG PRESSURIZED W ATER RE AC-

NURE GM3017.3 RO& ST ANDARD RE VIEW PLAN FOR THE REVIEW TORSOF SAFETY ANALYS15 REPORTS FOR NUCLE AR POWERPLANTS LWR Eston Revmon 0 to SRP Section 17 3. "Quanty Assur. Lose-Of4oolant Acc6 dentance Program Descreton"

NUREG/CR 5395 V02- MULTILOOP INTEGRAL SYSTEM TEST (MIST)NURiG/CH 260) ADOct iECHNOtOGY. SAFETY AND COSTS OF DE- FINAL REPORT. Test Orcup 30. Mapping Tests

COMMISSION NG RE FERENCE UGHT WATER REACTORS FOL. NUREG/CR 5395 V10 MULTILCOP INTEGRAL Sv$ TEM TEST (M!ST)LOWING POSTULATED ACCOENTS Re Evaluation Of The Cleanup FINAL REPORT. RELAP5/ MOD 2 MrST Analyses CompensonsCost For The Smng Water Rea: tor (BWR) Swnano 3 Accxv.t From NUREG/CR 5395 V 11. MULTILOOP INT E GRAL StSTE M TESTNUREG/CR 2601. (MIST) FINAL REPORT MIST Phase IV Tests

NUREG/CR 3444 V07 1HE IMPACT OF LWR DECONTAMINATONS NUREGrCR4395 V11 AD MULTILOOP INTEGRAL SYSTEM TESTON SOLOlf tCATON. W ASTE D:SPOSAL AND ASSOCIATED OCCU, (MIST) FINAL REPORT M!ST Phase IV TestsPATONAL E xPOSunt NUREG/CR4603 PRESSURE DEPENDENT FRAGILITIES FOR PIPING

NUREGrCR 367J EFFECT Or WELDING CONDfTONS ON TRANS- COMPONENTS F%:>t Study On Dam Desse Nuclear Power Stahon.FORMATON AND PROPE ATIES Or HE AT AFFECTED ZONES ONL WR VE ESEL STEELS LoeLevel Radiation

NUREG/Cha409 von NONDESTRUCTIVE EXA%NATON (NDE) RELL NUREG/CR 5635 CE LD )LAR AND MDt ECULAR RESEARCH TOABILITY FOR INSE RVICE INSPE CTON OF LIGHT WATER REDUCE UNCERTA!NTIES IN EstlMATES OF HEALTH EFFECTSRE ACTORS Senvannuai RecorLOctater 198 7 March 1968 FROM LOW-L EVEL R ADIATION A Feasstality Study

__ _ _ _ _ _ _ - _ - - _ _.-_ - - -- ---

_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ - _ _ _ ___ _ _

94 Subject index

tow 4evei Ree eteve we.ie Msiv to kepeNUREO 1360 THE INCINLRATON OF LOW 4EVEL NDOACM NJREG/CR 6397, VALUE-lMPACT ANAll'Sl$ OF REGULATORY OP-

WASTE A Rnort For The Adewry Comervttee On Nucwar Weste TsONS FOR RESOLUTON OF GENERIC ISSUE C.8 M$ly LEAKAGE

NUREGiCR4f42 M4XIEL8 FOR EStiMATON OF bERVCE L4F E OF AND LCS F AILURECONCRETE BARRIERS IN LOW 4EVEL RADCACTIVE W ASTE DIS-POSAL Maintenarwe Approach

NUHEG/CR4616 LOW LEVEL RADIOACTIVE WASTE OtSPO! AL F A* NUREG 1333 MAINTENANCE APPRCACHES AND PRACTCES IN SE-CILITY CLOSURE Pert L Lort o m Environmental CAsiditons Alte:t- LECTED FOREIGN NUCLEAR FOWER PROGRAMS AND OTHERT

mg Low 4evel Weste Disposai Site Portormate Part il Povnance U S INDUSTRIES REVIEW AND LESSONS LE ARNEDManwing To Support Reptawy Demos e

Mechan 6 cal Property4 V01. TMI.2 VESSEL INVESilGATON PROJECT (VIP)law 4evet Resoective Waste Disposal

NUREG 1383 GUIDANCE ON THE APPUCATON OF OVALITY ASSUR. NUREG!CR f42, CAL PROGRAM Progress Repcrt.JanuaySeptemteryt74tgungANCE FOR CHARACTEFilllNG A LOW 4EVEL RADCACTNE W ACTE 3ggg[ASFOSAL SITE Fml Report

NUREG/CR6617. IMPACTS.BRC.VERSON 2 0 Prvam User's Manual gg, pg,eNUREG/CH4668 DAMAGED FUEL EXPERIMENT OF 1.Ressts AndLow Level Resosctive Weste 06eposed

NUREG 1418 CHARACT ERIST 6CS Or LOW 4EVEL HADCACTIVE ^^*YS**NURI;G/CR467N THE Ord FULL DAMAGE EEPEFUMENT IN ACRR

WASTE DtSPOSED DURING 1967 THROUGH 19t>9 WITH A DWR CONTROL BLADE AND CHANNE L BOX.NURFG/CH $316. MELT PROGRESSON.OxlDATON. AND NATURAL

Low 4evel Waste CONVECTION IN A SEVERELY DAMAGED RE ACTOR CORE.NUREG/CR4453 V06 BACAGROUND LNFORMATION FOR THE DE.

VELOFMENT OF A LOW 4EVEL WASTE PERFORMANCE ASSESS-MENT METtOOOLOGY.Comsvtor Code 6mplementaten And Asses., y|em p

NUREG/CH 6t23 DEVELOPMENT OF AN INFILTRATION EVALUA.METALLURGICAL PROGRAM Progress RepartJanuary Septerrdier1980NN METHODOLOGY 'OR LOW 4EVEL WASTE SHALLOW LAND NUREG/CR 5624 V02 TMi 2 VESSf L INVEbTIGATION PROJECT (VIP)BURIAL SITES, MET ALL URGICAL PROGRAM Progreat Report.O:1cter 1989 June

Law 4evel Weste Dets Baos 1990

NUREG/CR4229 V02 TML2 EPCOR 11 RESIN /UNE R INVESDQ ATIONLOW LEVEL WASTE DATA BASE DEVELOPMENT PAOGRAM FOR

M4croeerthquakeNUREG/CR4629 MICF OEARTHOUAAES IN KANSAS AND NEBRAS4FISCAL YEAR 1989 Annual Rep:st

NUREG/CR-6229 V03 EPICOR,il RESIN / LINER INVESTIGATON LOW. KA 19771989 Final ResortLEVEL WASTE DATABASE DEVELOPMENT PROGRAM FOR FISCALYEAR 1990. Annual Report Madroop Operstion

NUREG-1410 LOSS OF VITAL AC POWEP AND THE RESIDUAL HEATLew4evel Woote D6eposal REMOVAL SYSTEM DURING MID400P OPERATIONS AT VOGTLE

NUREG/CR4532 A PERFOAMANCE ASSESSMEP(f METHODOLOGY UNIT 1 ON M ARCH 20,1990.

FOR LOW LEVEL WASTE FACILITIESNUREG/CR 6f48. MEVIEW UF GEOCHEMICAL PROCESSES AND Minerosogy

CODES FOR ASSESSMENT OF RADONUCUDE MiGRATON PO' NUREG/CR4463 EFFECTS OF MINERALCKW ON SORPTON OrTENT %L AT COMMERCIAL LLW StTES. STRONTIUM AND CESIUM ONTO CAUCO HILLS TUFF.

Leminescence Wodal Comb 6netton MethodNUREG/CR 5574 DETERMINATION OF THE CHEMICAL FORM OF NUREG/CR4627: ALTERNATE MOOAL COMutNATION MET >OOS IN

TRITIUM IN SELF4UMINOUS SIGNS- RESPONSE SPECTRUM ANALYSIS

t' ACCS Computer Code Mo6+ cuter Redwt>to6NUREG/CR4S51 V2R1P7; EVALUATION OF SEVERE ACCIDENT NUREG/CR 6635 ELLUtAR AND mot [CULAR RESE ARCH TO

RISKS OUANTIFICATION OF MAJOR INPLff PARAMETERS MACCS REDUCE UNCERTAINTIES IN E STIMATES OF HEALTH EFFECTSFROM LOW. LEVEL RADtATON A Feesststy Study

NU G/CR4691 V02. MELCOR ACCOENT CONSEQUENCE CODEVolume 2 Model Desc vt on

SYSTEM (MACCS)03 MELCOR AOCIDLkT CONSEQUENCE CODEMolten CoreNUREG/CR4601 v NUREG/CA 4794 EXPERIMENTAL RESULTS OF CORECONCHETESYSTEM (MAOCS) Volume 3 Programmers Reference ManualNUREG/CR4376 OVAUTY ASSURANCE AND VERIFICATION OF THE

INTERACTONS USING MOLTEN STEEL WITH ZlRCONIUM.

# Motor Operated ValveNUREG-1352 ACTON PLANS FOR MOTOR-OPERATED VALVES ANDMELCOR

NUREG/CR4691 V01. MELCOR ACCIDENT CONbiOVENCE CODE CHECK VALVESNUREG/CR4661: CLOSEOLTT OF tt BULLETIN 8543 MOTOROPER.SYSTEM (MACCS) Votume 1: User's Gude

NUREG/CR4691 V02- MELCOR ACCIDENT CONSEQUENCE CODE ATED VALVE COMMON MODE FAILURES DURING PLANT TRAN.

SYSTEM (MAOCS) Volurne 2 uodel Desenttion. STENTS DUE TO IMPROPER SWITCH SETTINGSNUREG/CR4691 V03- MELCOR ACCIDEru CONSEQUENCE CODE

SYSTEM (MACCS) Volume 3 Programmers Reference Manual, Multiloop integral System TestNUREG/CR 1.395 V02 MULTILOOP INTEGRAL SYSTEM TEST (MtST)

MELPROG Code FINAL REPORT.Ted Group 30%pping TestsNUREG/CR4316 MELT PROGRESSON OxlDATON, AND NATURAL NUREG/CR4395 V10- MULTILOOP INTtGRAL SYSTEM TEST (MIST).

CONVECTON IN A SEVERELY DAMAGED REACTOR CORE FINAL REPORT. RELAPS/ MOO 2 MIST Ana9ss Compensor.NUREG/CR 5395 Vil: MULTILOOP INTEGRAL SYSTEM TEST

^L E RT M ST e,

NUHEG/CR4514 MODEUNG AND PERFOAMANCE OF THE MHTGR N(E 53REACTOR CAVITY COOUNG SYSTEM (M:ST) FINAL REPORT MlST Phase IV Tests

MINET CodeNUREG/CR-3668. MINET CODE DOCUMENT ATON OF W MW M NUM

ING MATERIALS SUPPUED BY PnPING $UPPUES.INC..ATDST

NUREGICR4305 V02. MULTitOOP INTEGRAL SYSTEM TEST (MIST)F OLSOM,NEW JE RSEY.AND WEST JERSEY MANUF ACTURING

FLNAL REPORT. Test Group 30.Ma. Tests COMPANY AT WILUAMSTOWN.NEW JERSEY.

HUREG/CR 5395 Vi t: MULTIL INTEGRAL SYSTEM TESTNRC OperatW>ne Center(M:ST) FINAL R; PORT MIST Phase IV Tests

HUREG/Ca6395 Vil AD MULTILOOP INTEGRAL SYSTEM TEST NUREG-1394 EMERGENCY RESPONSE DATA SYSTEM (ERDS) IM-

(MIST) FINAL REPORT. MIST Phast 4 Testa. PLEMENTATON

, .

_ _ _ . _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

Subject index 96

NRc Punac.non. Nuc4 ear Power PianiNUREG4650 R01 PUBUSH!NG DOCUMCNT S IN THE NUREG NUREG-13tJ DRF FC ER [rrota to 'Regalescry AhaYes tw ProsonedSE RIE S

Rate on N resar Power siant Leerse Renewat,Oren F4ept 6ar C4rn.N888 ment" reveng Sectun 7.2 on Pa,pe 7 3 to tsa;f as listed

NUREG/CR4659 V03 SEISMC F RAGIUTY CW NUCLE AR FOWER NUREG 13W8 DHFT FC ENVt40NMENTAL ASSE SSMENT FOR PFO.POSE D RULE ON NUCLEAR POWER PUNT LCENrAFtANT COMPONENT $ (F%ASE II)Smitchgear, 6&C Panels (NSSS)

And R' M Fil NEW AL Ekett Regrt For EXmunentNUREG t411 RLINN5E TO PultLC COMMENT $ RESULTING FRCM

NUC MRR THE PUtiLIC WORKSHOP CW NUCLE AR POWER PLANT LCENSENUREGrCR4639 V01 At NUCLEAR CO6dPUTERCEO UDRARY FOR NINF W AL

ASSESSING REACTOR RELRBiUTY (NUCLARALSunwnery Eencm NUREG-1412 DRrt FO FOUNDATON FOR THE ADEQUACY OF THEw LCENS:NG BASES A Swament to The Statement Of Comter.NUREG'CR-4639 V4P2R2 NUCLE AR COMPUTER 2ED LID %RY FOR stors f or The PetweF1 Row On Nwhat Power 5%4 Leone Re-

ASSE SSING RE ACTON RELLABluTY (NUCLARR) User s Ouve Fai t he*al 00 CF R F'a1641 Dram 84ePurt F or CommentGw To CWaue NUREG/CR 6640 OVERvilW AND COMPARIKW CW U 8 COMME R-MUREG/CR4bw v4P3R2. NUCLEAR CCA"*)TEF42ED L$MRf FOR CLAL NUCLEAR POWER PLANTS Nwiear Poww Plant System te ,

ASSESSIN3 RE ACTOR RE UABUTY (NUCLARR) Users Gude Pa13 cetaA. NUCLARR System tweerotort! NUREG/CR 46J9 V5P143 NUCLEAR COkt%1TERJED UERARf FOR Wesear Safety

ASSESSING REACTOR REilABlUTY (NUCLARR) Data Manual Part 1NUREG/CP4113 TRANSACTONS C# THE E GHTEt NTH e ATER RE-

i NL 4$ t$ 2R3 NUCLEAR COMPUTERCED LIBRARY FOR'

AMESSW3 REACTOR RELIABluTY (NUCLARR) Data Manua: Part 2 Newer weeteHuman Enor Proba9tdy (HE P1 DetaNUREG/CR4639 v5P3R3. NUCLE AR CouPUTER2ED UBRARY FOR NUREG 1423 VOt: A COMPILATON CF REPORTS Cut THE ADVtSORY

ASSESSW3 REACTOR REUABlVTY (NUCLARR) Data Marval Pad 3 COMMITTE E DN NUCLEAR WASTE Asly 108 June 19WHm owe <e Comporwnt Face Data (tCFD)

OECDNUREO &ertes HUREQ/tA o019 TRACJV t /uDD1 POST TEST CALCULATONS OF

NURE G+oSO A01 PUBUSHING DOCUMENTS IN THE NUREG THE QEOD LOFT EXPERIMENT LP SB2.SEHiES

keutron SourceNUREG/LA4011: TRAC PF1/ MOD 1 POST TEST CA'.CULATONb (*

NV54EG/CR 4704 V03 RELATIVE BIOLOGCAL EFFECTfVENESS (RBE) THE OECD LC#T EXPERIMENT LP40 t-OF FISSON NEUTRONS AND GAMMA RAYS AT OCCUPATICWAL NURE Gr6A 0C21 ftE LAP 6/MCO2 CALCULATIONS C# OECD LOFTEXPOSURE LEVELS Staties on The Grou Ard Mcroeconc Pathrx> TEST LP48 2p Obserwd At Dusth Of Mce Esposed 70 DO Equal CwnWeeUy NURE G/LA 0022 TRACJT tiMODI FOST.TE ST CALCULATIONS OFUoses Of Fetson. THE Of Cp (Ori EXPEFirMENT LP SB-3

Nonconfortrdreg Matertal Occupauonal Ouse Contro4NUREG 1402 CLOSEOUT OF NRC $ULLETIN 6845 NONCONFCWiM- NUREGICP 01to P50CEEDlNGS OF THE INTERNATONAL WOf%ING MATERIALS SUPPUED BY PtPWG SUPPUE S INC .AT EutOP ON NEW DEVELOPMENTS IN OCCUPATONAL DOSE CON.FOt.SOM.NEW JERSEY,AND WEST JERSEY MANurACTUftlNG

TROL AND ALARA iMPLEMENTATON AT NUCLEAR POWEFICOMPANY AT WILLtAM$ TOWN.NEW JERSEY PLANTS AND SIMILAR F ACIUTIE $Normlectructive Caaminetton Occupational Dooe Reduct6on

NUREG-1425 WELOWG AND NONDESTRUCTfVE CAAMINATONISSUES AT SEAanCOM NUCLEAR STATON An indererdent Rece* NUREG/CR 4409 VOS OCCUPATIONAL EOSE REDUCTON AT NU-

CLE AR POWER PLANTS ANNOT ATED BIBLICORAiHY OF SELECT.NU / tis V06 NONDESTRUCTIVE EXAMWATON (NDF) REU- CD READWGS W RADMTON NTECTON AND ALARA

ABJUTY FOR INSERVICE INSPECTION OF LOHT WATER Occupettonal Redsation E sposureNU EG/CR 4 v0 N T $ NM A NDE) REll. NUREG4718 V09 OCCUPATONAL RADATON E XPOSURE AT CCM-

AB UTY FOR INSERvCE INSPECTION Or LOHT WATER MERCAL NUCLE AR POWER REACTORS AND OTHER F ACluTIESRE ACTORS Sanannual ReNrt.ATW Septemter 1988 UO " *'"I# A""d'' N''"I

MUREG/CR4469 V10 NONDESTRUCTIVE EXAMINATON (P.DE) RELLA81UTY FOR IN=ERVCE :NSPECTON OF UGHT WATE R h*8'" O*"*''IREACTORS Sermannual Report. October 1968 Merch 1989 NUREG-14 t B YO3 N01: Of FICE OF THE INSPECTOR

GENERALSerniennual Report Aprin-Septenter 1pMNondestrwenn Teeung

MJREG>CR 4M8 ULTRASONC NSPECTION REUABlUTY FOR IN. Ottelte PowerTERGRANVt,AR STFIESS COR540 SON CRACAS A Round Rotan NUREG/CR4300 CLOSEOUT ($ IE DVLLETIN 1016 POSSIBLEStudy Of the Ettects Of Personnoi Procodres E4spment. And Crea LOSS OF EMERGENCY NOTIFCATION SYSTEM (ENS) W:TH LOSSChara:terge

OF OFFSriE POWL R.NURLG/CRS54 SURVEY OF BORC ACID CORROSON OF CAR 80N

STEEL COMPONENTS IN NUCLEAR PLANTS Offette Power TransLMNURE G/LA4030 ASSESSMENT OF RELAP6/ MOD 2 CODE USINGNonreactor

NUREG-1272 V04 NO2 OFFCE FOR ANALYSIS AND EVALUATON OF LOSS OF OFFBITE POW [R TRANSIENT DAT A C# KNU f1 PLANTOPERATONAL DATA 1989 ANNUAL REnggy No, Yea: tors Operating Eapertence

Nclear Plant Ageng NUREG-1272 V04 Not OrFICE FOR ANALYSl$ AND Eir ALUATON CWNUREG/CR 5161: NUCLEAR PLANT AGING RESE ARCH THE 1E DPERATIONAL DATA 1969 ANNUAL ALPORT Power Reactors

NUREG/CR4619 Vot AGWG Or CONTROL AND SERVICE AIR COM-NU d/C SHiPPiNGPORT STAflON AGWG EVALUATION PRESSORS AND DRYERS USED IN NUCLEAR POWER PLANTSNUREG/CR4507, RESULT 6 FROM THE NUCLEAR PLANT AGING RE.

SEARCH PROGRAM THEIR USE IN lh SPECTON ACTIVITtESpp,,gon,, g g

NURED/C34U4 V09 PRECURSORS TO POTENTIAL SEVERC COREW lear Plant Apeng Reneerch Program DAM'.GC ACCIDLNTS 1966 A ST ATUS REPORT Maan Resort And Ap-NUREG/CR S306 BASIS FOR $NUBBER AGING RESE ARCH NUCLE, perd A

jAR PLANT AG4NG RESEARCH PFOGRAM NUREG/CR4674 V10. PRECUFtSORS TD POTENTIAL SEVERE CCWE i

Nuclear Power DAuAGE ACCOENTS 19 tie A STATUS REPORT.Appendries D AndC INUREG/CR4566 V01 INDUSTRY BASED PERFORMANCE INDICA.

NUREG/CR4674 VII PRECURSOR $ TO POTENTIAL SEVERE CORETORS FOR NUCLEAR POWER PLANTS Phase 1 Report June 1999February 1990- DAMAGE ACC1 DENTS 1989 A STATUS REPORT Main Rosat Ard Ap

perda A

!

! 1<

. __ __ __ _ _ _ _ _ _ ._ . _ _ _ _ _ __ ___. . .__

|.

! H Subject inder

NUREG/CR4ET4 Vit PRECUf40RB TO POTENTIAL 6 event OORE NUNEG/09469T GFNEmic R4K INSiOHTS FOR WESTINGHOU$[DAMAGE AOCIDENTS 16/.3 A STATU6 REPORT App.%o.e ti And AND COVBUSTION ENGINEE*NG PREktVRtIED W ATER REAC-

Toa$RELA >6/ MODI CALCVLAT60NS OF OECD40FTC.

NU8t[G 4A,.00 t tu.n mO ,.,.t., u ,.in. E.. ~ n.,NUREG 10tt R36 OPERATOR UCEN6tNG EKAMINER $TANDARDSi W u. . ,

^ '^ "|

NAG 4643T. ORGAN 1 ATION AND LAFETY IN NUCLE AR POWER " h [ N RD

PLANTS.r A e,a. T. ..iur.

NUREG/CR4264 DiAt IN PE AK CLAD TF7ERATURE PREDICTONSRG3 19 U $ NUCLE AR REGULATORY COMMISSON FVNC. DUE TO UNCERT AINTIE$ IN MODEUN3 Or ECC 9YPABS AND DIS-

TONAL 090AN:ZAYON CHART $ Apnl1.1990 SOLVED NON CONDENSADLE GAS PHENOMENANURL3 0325 R14 V $ NUCLE AR Fit GULATORY COMMi$$0N FUNC.

TONAL ORGAN:Z ATON CHARTS Au; pat 16.1990 p g ,, g,gNUREG/CR4211: UNCERTAINTIES ASSOCIATED WITH PERFORM-

AtCE AbSE SSME NT OF HIGH4EVEL RAD 40ACitvE W A$f EPP,A

NUREG-14?O $PECnAL COMMTTEE RFV:EW OF THE NUCtEAft REG. REPOSITORIES A Summary ReportULATORY COMMIS510N'S BEVERE ACCIDENT FtiSKS REPORT NUREGrCR4?66 COM59NENT6 OF AN OVt RALL Pt RFORMANCE(NURE 3. t t $ot ASSESSMENT METHODOLOGY.

NUREGrCR 4MO tr01 Rt: ANALYSIS OF CORE DAMAGE FREQUEN. NUREG/CR 6453 VD5 BACKGROUND INFORMATION FOR THE DE.CY INTERNAL EVENf6 METHOOOLOGr.

NUREG/CR 4MO V3RIPt. ANALYBi$ OF CORE DAMAGE VELOPMENT 05 A LOW 4EVEL W ASTE PERFORMANCE ASSESS-MENT MEf>ODOLD3Y Computer Code ImrAementahon And A6tess-

FAFOUENCY SURRY.UMT 1. INTERNAL EVENTSNUREG/CH 4MO V3A1Pt ANALYSit OF CORE DAMAGE FREQUEN- rnent

CY 6UR84Y UNrf 1 INTERNAL EVENT $ APPENDICESNUREG/C4 M21 USE OF PERFORMANCE ASSESSMENT IN AS-

NUREGICR.4MO V3htP3 ANALYDiB CW EORE DAMAGE FREQUEN- SE SSING COMPuANCE WITH THE CONT A'NMENT RE QUIRE-CY $URRY POWEH $1 ATON,UNrf 1 EXTERNAL EVENTS MENTS IN 40 CFR PART 101.

WREG/CR 4MD V4 RIP 3 ANALYSl$ OF CORE DAMAGE FREOVEN.qgqggicg g3; A pgnpopy49cp Agggggygqy y(ygogg(ggy

CY: PE ACH DOTTOM UNIT # EXTERNAL EVENT 6 FOR LOW LEVEL W ABTE f ACluTIESWREG/CR-4M0 V5HiPt: ANALYblS OF EDRE DAMAGE FREQUEN-

Cv' EEOVOY AH. UNIT 1JNTERNAL EVENTSP.rtormente H6 story

WREG/CR-420 V6AtP2 ANALYSi$ OF CORE DAMAGE FREQVEN' NUREG it14 RD5 HISTORCAL DAT A SUMMARY OF THE SYSTEMAT.CY. SEQUOYAH,UNrf 1,tNTERNAL EVENTS APPENDCES IC ASSESSMENT Or LICENSEE PE RFORMANCE

NUREG/CR 4550 V7 Not: ANALYblS OF CORE DAMAGE FREQUEN. NURtG itte Rao HISTORICAL DAT A BUMMARY OF THE SYSTEMAT.C ASSE SSMENT OF LICENSEE PERFORMANCEL

N RE / lb $3 A Tl A P OGRAM FOR DEFINING THESOURCE TERM / CONSEQUENCE ANALYSl$ INTERF ACE IN THE P.rtormance Ind6catot

NUREG/CRb436 V01 THE DEVELOPMENT AND 8' val,UATON OFNU L C 4 SU 1 i A IL N M GE- PROGRAWAM MRMNE EAT @S WWARD WTH

MENT STRATE (.a TO MINIMIIE THE C(WSEOVENCES Or DIRECT MAINTENANCE At NUCLE AR POWER PLANTS Mam RotwtCONT AINMENT HEATING NUREG/CR4436 V02 THE DEVELOPMENT AND EVALVATON OF

NUHEG/CH 6477 AN EVALUATION OF THE REUAB1UTY AND USE, PROGRAMMATIC PERFORMANCE INDCATOp* ASSOCIATED WITHFULNESS OF EXTIFtNAL INITIATOR PRA ME1HOIOLOGIES MAINTEN ANCE AT NUCLEAR POWE R PLANT L Apperdeen

WREG/C4 5527. RlLK bENSIflVITY TO HUMAN ERROR IN THE LA. NUREG/CR 6437 ORGAN:2 ATON AND SAF ETY IN NUCLE AR FOWERSALLE PRA PtANTS

WHEG/CR 6003 PRESSURE OEPENDENT FRAGlWTIES FOR PtPING NUREG/C4 M68 VO1- 6NDUSTRY DASED PERFORMANCE lNO4CA.COMPONENTS hiot stady On Deos Base Nuclear Power Statmn TORS FOR NUCLE AR POWER PtANTE Phase 1 Report Jure 19A9WREG/CR 5616 AUXILIAhY FEEDWAt[R BYSTEM RI5LBASED IN-

SPECTON OUIDE FOR THE DIABLO CANYDN UNIT 1 NUCLEARFetruary 1990.

POWER PLANT, Petttione For RulemakingNVREG/CR Set 7: AuxtLIARY FEEDWATER BYSTEM RISK.DASED IN-

SPECTON QUOE FOR THE J M FARLEY NUCLEAR POWERNUREGO936 V06 ND4 NRC REGULATORY AGENDA Ouanerty

RotwtOctobst Oscomter 1989PLANT. NOREGO936 YOD N01 NRC REGULATORY AGENDA Ouarterty

PRAMit Report.JanuaTMarch 1990

NUREG/CR4252 PRAMIS PROBABluTY RISK ASSESSMENT MODRNunt.G O936 V09 NOR NRC RE GULATORY AGsNDA Ouanerty

INTEGRATON SYSTEM User's GuvaeReport.Atr#4une 1990

NUREG4916 V09 NO3 NRC REGULATORY AGENDA Ouartetty

JREG 1316 TECHNICAL FIND 4NGS AND REGULATORY ANALYSISRELATED TO GENERIC LSSUE 70 Evaluate Of Poweroperated Phyo6eal SewrityHehet VaNo And Block vaNo Rehateitty in PWR Nuclear Power Plants NUREG-1404 LICENSEE USE OF T ACTCAL Ex[RCISE RESULTS

NUREG/CR 5798 CLOSEOUT OF 10 SULLETIN 85 01: STEAM DIND- NURL G/CP-Ot07. PRCCLED!NGS OF THE UNITED ST ATE $ NLCLE AR

ff," *N ** * ' "NN GC NCL ON U A! LE DUCTILE TEARING AND

V tTRAPOLATED CRACOARREST TO)GHNESS DATA IN PWRvtSSEL INTEGRITY ASSESSMENT,

NUREG/CR M13 V01: ACCIDE NT MANAGEMENT INFORMATON ppyNEEDS Volume t . Methodology Deve6apmoqt And Apphcation To A NUREG/CR4579 VALUC/ IMPACT ASSESSMENT OF JET IMPINGE.

MENT LOADS AND PIPE TO-PIPE IMPACT DAMAGE Recnod Meth.N E CR 55 VD C D T N L T TON paa AN Cmria

NEEDS Volume 2. ApperdcasNUREG/CR M30- ANALYSIS OF HB ROBINSON PWR VESSEL P

F UEN t FOR CYCLE 10 UTIUZING PARTIAL LENGTH SHIELD AS- g gg gCOMPONENTD Poot Study On Dav+Beste Nuckar Power Stat.on,

NUREG/CR 5557. RELAPS THERMAL HYDRAUUC ANALYBfS Or THESNUPPS PRE SSURitED W ATER RE ACTOR Pip 6ng Fake

NUREG/CR $567 PWR DRY CONT AINMENT ISSUE CHARACTERIZA. NUREG 0800 03 A 1 R2. ST ANDARD R[vif'W PLAN FOR THE REVIEW

NUREG/CR4575 OUANTITATIVE ANALYSIS OF POTENTIAL PER, OF SAFETY ANALYSIS REPORTS FOR NUCLEAR POWERTONPLANTS LWR Editon Rews.on 2 To SRP boction 3 61. Plant Design

FORMANCE IMPROVEMENTS FOR THE DRY PWR CONTAINMENT.NUREGrCR.M89 ASSESSMENT OF CE40NDENSER CONTAINMENT

For Protecton Against Postuistad P ping Failures in Fked Systems Cut.sde ..

PERF ORMANCE ISSUES

_- _ _ _ , . - . . -_ _ , _. __.. _ _ - _ _ _ . , . _ - _ - . _ _ _ _ _.

_ _ . _ _ - _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _

Subject index 97

Papbg SystemNLHEG/CR f409 NEUTRON ExPOSUHE s>ARAutitRS EDH THENUliEG.1402 CLOSEOUT OF NRC DVLLETIN 8646 NONCOr#ORM- MET ALLURGICAL TIST SP(CIMENb IN THE SMTH HEAVY fdC-ING M ATEHIAL S BUPPLIE D BY PIPING SUPPL l( S.ING ,A T llON STEEi lRRADtATON $t Hil $FCMW,NEW JE ASE Y.AND WEST JERbCY MANUf ACTU5tlNG NURIG/CH 6449 DETEHM4AfloN OF THE NEUTRON AND GAMMA

COMPANY Al Wit.LIAMSTOWN.NIW JERSEY. FLUX LMTHIDUTON IN THE PHESSURE VI$$tt AND CAVITY OFA 150lulNG W AiE R HE ACTCVIPlant Aping

NUHL GICH f460 HIGH-Tt MPE R A TUHE CRACA ARAEST TtSTSNUHlG-1777 H01: NRC RESEAHCH IHOGR AM ON PLANT AGINGLISTINGS AND SUMMARIE S OF HEFVHTS ISSUt D THHOUGH MAY USING '62 MM-THICK SE N WIDE PLATES OF LOW.UfPER SHELF

DA*,r MATERIAL TESTS WP.2 2 AND WP 2 e1990.

NUAEU/CR f461- Ci ACK ARRt ST 84 HAVOR IN SEN WOE PLATESt

Piant Maintenanc* OF LOW.UfhR SHELF BASE METAL TESTf D WDER NONfSOTH.NUREG/CH f436 V01: THE DEVELOPMENT AND EVALUATON OF EHMAL CONDITONS WP 2 St HIE $

gggggfcn.$,44 ECHHELATON OF IRRAD4ATON INDUCED TRAN-PROGRAMMATIC PERFOHMANCE IND8CATORS ASSOCIATED WITHMAINTENANCE AT NUCLEAR POWER PLANTS Mae R@ ort SITON TE MPERATUNE INCHE ASIS FROM CN) AND K(JC)/KpC)

t.AEG4H 6436 V02 THE DEVLLOPMINT AND EVALUATION OF DAT A Fnel Report

NURE G/CH-M01 V01 N1. HEAVY $ECTON STEEL lhRADIATONFHOGRAMMATIC PERFCMMANCE INDICATOHS ASSOC 4ATED WITHMAINTENANCE AT NUCLEAR POWEH PLANTS Apparutces PHOGRAM 6enwvul Pwou Hoport For cwt er 19fte . March

g gg

NURE G/CH4644 CONr40VENCE EVALUATON OF RADIAflON EM.RE / M21 ANALY$15 OF RE ACTOR TRIPS OnlGINATING IN I UN

BALANCE Of PLANT SYSTEMS.*

pgni 7,,ngn, Pressure-Dependen* Fr8614trNUHEG/CR-4661. CLO$EOUT OF lE BULLEllN 8%03 MOTOR-OPER. NUHEG/CR 58018RESSUHE DEPENDE NT FRAGluTIES FOH PIPING

ATED VALVE COMMON MODE F AllUAES DURING PLAVT TRAN. COMPONENTS Pht StuJy On Dewe Desse Nelear Power Staton,SIENr5 DUE TO IMFHOPER SMTCH SETTINGS

Pressurtred Water flooctorPoint Kernel NUREG 1316 TECHNICAL FINDINGS AND AEOULATORY ANALYStB

NUHEG/CR 64M OADS. A MUtilD:MENSIONAL POINT KEHNEL FiELATED TO GENERIC trSUE 70 Evaluston Of PoweroperatedANALYSIS MODULE. Raket Valve %nd piort Vatve Hebatslity in PWH Nudas' Power Plants

NUREG/CR4668. DAMAGED FVil E APEHIME NT EOt heeults AtxtPopulation Do6a AnalyseeNUREG/CR.2950 V09 POPULATON DOSE COMMfiMENTS DUE TO NUREG/CH 6298 CLOslOUT OF IE fiULLETIN 8641 STEAM DIND-

8tADIOACTfvE RELEASES FHOM NUCLEAH POWEH PLANT SffES ING OF AUxlLIARY FEEDWATI R PUMPSIN 1967,

NURI G/CH M73 INCLUSON OF UNSTADLE DUCTlLE TE AAING ANDEXTRAPOLATED CRACK AHHEST TOUGHNESS DAT A IN PW HPoroue Tuff VESSEL (NTEGl. 'Y ASSI.SSVtNT.

NUREG/CH4482. lAFORATORY ANALYSIS OF FLUID FLOW AND NUHEG/CH 6613 V01: ACCIDL NT MANAGE MLNT INFOHMATw1NSO'.UTE TRANSPORT THROUGH A VARIADLY SATURATED FRAC. NEEDS Vo#wne t . Methodegy Devntuptnent And Aps6cahon ' \TURE E MBEDDED IN POROUS TUFF,

Pressurtred Watew Roactor (5'wsq With A Larpe. Dry ContarvnantNUMEG/CH 6613 V02 AECIDENT MAN AC4L MENT INF ORM ATONPower ReDelor

NEEDS Voloma 2. ArmendKeeNUHE G/CR4816. PR EDO POWER REACTOR E MBRITTLEMENT NUHEG/CH M3 *. ANALYSIS OF HB HODINSON PWR VEBSELDAT A DABE,VERSON t Program Desulpton

Flut NCE FOH CYCLE 10 UTUllNG PARTIAL LINGTH SHIELD ASSE MuttE SPetetice And Procedure D6 gest

NUNEG 0386 006 R06 UNITED STATES NUCLEAR REGULATORY NUHLG/CH M67 RELAP6 THERM AL HYDRAULIC ANALYSIS Or THELNUPPS PHf SSUHilED WATEH HE ACTOPCOMMISSON STAF8 PRACTICE AND P40CE DURE

NUHEG/CR 6%7. "WR DHY CONT AINMENT ISSUE CHAHACTER12A-DIGE ST.Cornrrussori, Atteal Board And Lker*6n0 Board itONDectsons July 1972. SeMUNEG4386 DOS Hoo. ptemt se 1909 NUHFG.tH 6576 OUAN*)T ATIVE ANALYSIS OF POTE NTIAL PER-UNITED STATES NUCL. EAR REGULATORY

FOHMANCE IMPHOVEMENTS FOR THE DHY PWH OONTAINMINTCOMu!SSON STAFT PAACTICI AND PHOCfDUHE NUHIG/CA %89 ASSESSMENT OF #Ct CONDENSER CONT AINMENTDIGES T Cornnvason. Amoal Board And uceneng Board PEHFOAMANCE ISSUESDecipons July 1972 December 1989 NUHEG/CA 647 GENf HIC H;SK INSIGHTS FOH WESTINGHOUSEWHEG4366 ED6 R07, UNITED ST ATES NUCLEAR REQULATORYAND COMBUSTION ENGINf EHING PHESSURIZED WATEH HE AC.COMutsSION STAFF PR ACTIC(, AND PHOCEDUAE TORS

DIGEST Comnusson, Aproel (wd And Lkonaang Board NUHEG/lA4012. HELAP6/ MOD 2 CALCULATIONS Or OECD LOf TDec$stons Juty 1977. March 1%d TEST EP SD41.NUHEG4386 D06 Hoe UNrtE D STATES NUCLE AR REGULATORYCOMMISSON STAF8' PHACTICE AND PHOCEDURE Pressurtser Safety And Rste VelveDIGEST.Convrwasson, Arveial Board And Licenseng board NUREG/lA4034 ASSESSMENT GTUDY OF HELAP6/ MOD 2 CYCLEDoctesons July 1972 . June 1900.

36 04 BASED ON PHES$Unl2EH SAFETY AND RELIEF VALVETTSTSPrenatal

NUREG/CR 6631: CONiniDUTION OF MATERNAL RADIONUCLIDE Probabilistic Risk AnalysioBURDENS TO PnENATAL RADI ATION DOSE S interwn NUHEG 1160 V01: SEYf RC ACCnE NT HISKS AN ASST SSMENT FORHocommendations For Cwoment f fvE || 0 NUCLE AR PObEH PL AN TS Final Sumnwy Remrt

Pressure isolation Velve NUREG 1160 v02 SEVERE ACCIDENT HISKS AN ASSESSMENT FORFIVE U S NUCLEAA POWER PL ANTS Apperdcas A.D, And C Final

NUREG/Ca 5616- LIGHT WATER REACTON PHESSURE ISOLATON HaportVALVE PEHFOAMANCE TE STING.

Pressure Vesset Probabsouc Hish Assesstnent

NUHEGICP.0t12 YO1: PAOCEEDINGS OF THE THlHD INTEANATON' HUREG/CR 4%0 V01 Hl: ANALYSIS OF CORE DAMAGE FREOVEN-CY. INT! RNAL EVENTS ME THODOt OGY,

AL ATOMIC ENERGY AGENCY SPECIALIST $' MEETING ON SUD- NUHEG/CH 4%0 V3H t P t . AN AL T SIS OF COHE DAMAGECRITICAL CAACK GROWTH Operung Seesson And Techrecal Session FREQUENCY SUHRY.UNil 1,1N1ERNAL EVENTSt Hand At Moscow.USSH.May 14-171990

NUREG/CP 0112 V02 PROC 4EDINdS OF THE THlHD INTERNATON- NURE G/CH 4%0 V30tP2 ANALYLis OF COHE DAMAGE FfCOU(N.CY' SURHY UNIT 1JNTERNAL EVEt#5 APPENDICI SAl ATOMIC ENERGY AGENCY SPECLALISTS' MEETING ON SUO' NUHEG/CH 4%0 V3R1P3 ANALYSIS OF CORE DAMAGE FREQUEN-CFUTICAL CRACK GROWTH.Techrucal Sc6 sons 11. Ill, And IV AndCY SURRY POWlH STATON UNIT t Er1[HNAL EVENTSRecomme#xtetons And Condusons Session V. Held Al NUREG/CH4%0 V4RtP3 ANALYSIS OF CORE DAMAGE FREOUEN.Macow USWMay 14-17, iD90CY. PEACH HOTTOM UNIf 2 EkTERNAL [VE NTS.

NUHEG/CH4219 VD0 N2 HEAVY SECTION STEEL TECHNOLOGY NUFIEG/CH 4%0 Vf.ntPt ANALYSIS OF CORE DAMAGE FFWOUEN.PROGRAM Semiannual Prtyens Report For ApriLSeptember 1969. CY' SEQUOY AH. UNIT t,1N1ERNAL EVENTS

__ __ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _. --. , ,_

_ ._ _ _ _ _ _ _ _ _ _ . _ _ _ _ . .- _ _ _ __ __ _ _ __ _ _ .

"1

98 Subject index

NUHLG/CR.4%0 VSRtP2 ANALYfdS C$ CORE DAMAGE F RtOutN-Approved Quahty Antwrne Progams For hahactive Motonais Pad

CY SECAIOY AH.UN!T 1,1N11 RNAL EVE N1B APPi NDICI S are,

NURLG/CH-4bh0 V7 A01 ANALYblS Of CORE DAMAGL FREQUEN M LAP 6Cr 2ON UNIT 1,INTIHNAL EVt NTS~

NURIG/CRat41 Y2HIPl: I V AL UAT ON OF SE VE HL ACCIDE NT NUH[ G/Cft $567 RE LAP 5 THtflMAL HYtHAUUO ANALYSIS OF THERISAS OUANilFICATION OF MAJOH INPUI PARAMETIR$ E yo-1 bNUPPS D8tf SSURIZED W ATE Ft HLAC104

Cer on f lotaton On Irvvessai losuesvNUHEG/CH 4561 V3R t P1: L v ALVA Y ON OF SEVERE ACCOENT Fit LAP 5/MDD2

RISAS SURHY UNIT I Main Report NURE G/lA@ t ? FIELAP5s MOD 2 CALCULATONS OF OE CD LOFTNUHLG/CH 4551 V34 t P2- t v AL VAtlON OF SEVERL # CCOL NT ig st Lp sg ot

HISAS SUllRY UNff 1 App m kes NUHt G /6ACQ t3 RE LM% MOD 2 CALCULATONS Or Or cMOrtNURE G/CR 4$51 V4RtPt: L vALV ATON CW SEVEHE ACCIDE NT TEST LP SD43

RISKS PE ACH fOTTOM UNIT 2 Man Rept NUHEG/LA-00te HELAPS/ MOD 2 ASSESSMENT,OLCO LOrt I, MALLNUALG/CR 45SI V4RtP2 EVAL UAf TON OF Styl RL ACCOENT (mE AA EXPERMLNT LP.SBc3

LU N OF Sivf RE ACCIDf NTN E C 4551 1 P1 iNUHE O''##0 0 #bbEbbulNI O' NILA"b'MOU# CDUE US'N3

V$L N OF SEVERE ACCID ( NT LOSI OF OF Flutt POWER TRANSIENT DAT A Or 6 NU #1 PLANTNU / t $5 V H1NURE G /l A-(A131 CAP ASSLSSMLN1 OI- HELAPt/ MOD 2, CYCLE

NL GC46 V 1 Ev U A ON OF SEVERL ACCIDENT 36 0$ AGAINST Lori SMALL UHE AA E API HMENT L3-FNURE G/lA 0032. ASSESLMI N T OF hE LAPm MOD 2 CYCLE 36 04HiSAS GRAND GUL F INIT 1 Main Ab1 OF SEVLHE ACCfDENTWNG WT LARM BRL AK E MHMLNT L2 62 EVALUATNUHlG/C 44651 V6R

RISAS GRAND OULF. UNIT 1 Appenkes NUHl G/lA 0033 AbSLS$Mt NT OF RELAPL/ MOD 2 CYCLC 36 04NUREG/CR 4640 PROCIDURES Post THE LATERNAL EVENT CORE AGAINST Lort SMALL DHE AA ERPihlVEN1 L3 6

DAMAGE FREQUENCY ANALYSES FOR NUREG 1150 NURE G/lA4034 ASSLSSMENT STUQY Or Fl[ LAPS / MOD 2 CYCLENuitLGrCH 5213 V01. THE CCONdivl ENVIRONMENT S'MULATON

AS A TCOL FOft MODE UNG HUMAN PL HF ORM ANCE AND30 04 UASED ON PALS $UHl2EH SAFETY AND REUEF VALVEIIbIbREUABlufY l secuttvo Sema'y

NUREGiGFt $213 V02 THE CCONtifvE (NVIRONMENT SMJLATON HamsknAS A TCOL FCH MODELING HUMAN PE RFORM ANCE AND NORE G/C44214 401 Pt HLAltH EF FECTS MODE Lb f OH NUCLE AR

NUMEGrCH 6253 PAHil10N A PROGRAM FOR DtF;NiNG THE POAER PLANT ACCOENT CONSEQUI NCE ANALYSIS tom LETAlltAbillTY Ma#n ReportRataton Part ilntroducion inlevanon And Sumrewy

SOURCE TERM / CONSEQUENCE ANAliSIS INTERF ACE IN THE NUHIG/CH M44 CONSEQULNGE EVALUAi60N OF RADiATON EM.NURf G-itSO PROBAHlUSitC RISK ASSESSMENTS User s Guxte

NUREG/CR b447. OtPRESSU4l2AllON AS AN ACCID (NT MANAGE-DRilTLIMENT OF TROJAN HLACTOR PRESSUHE VI SSR buP-

MENT STRATEGY TO MINIM 12E THE CONSEQUENCE S OF DIRECTPOMS

CONT AINME NT HE ATINGNUREG/C46003 PRE LSURE DE PLNDENT FRAGluTIES FOR PIPING

Radiation DamageNUREGICR fa0 ANALYSi$ OF HB HOulNSON PWR VE SSELCOMPONENTS P4at Staty On Daes Desse Nuclear Power Staton

FLUETE FOR CYCLE 10 Ullu2iNG PARilAL L[NOTH SHIELD AS.Drobabiltty Risit Aase6 ament $tunuts

NUREG/CR b262 PRAMIS. PROBAutLITY RISA ASSESSMENT MODEL Romanort DoesINTEGRATON SYSTEM Ueera Guoe NUHtG 1391 DRFT FC CHIMICAL TOMCitY Of URANIUM HL AA-

UE /CR 4640 PROCEDURES FOR THE EXTERNAL EVENT COREDAM AGE FRCOVENCY ANALYSES FOR NUR[ G 1150

NUHf G/CH $617 tMPACTS-BRC,ViRSON 9 0 Provam Uner a ManualNUREGICR %31 CONTRIBUTON OF M Alt HNAI, RADONUCUDE

^ *

E (M FC [R. Errata to " Regulatory Analysis for Proposed 79,Rule on Nuclear Power Piant LKense HonewalDraft Rept b Com.ment? tevraing Secton 7 2 on Page L3 to feed as knied Radapon Embetttlement

NUHEG-1412 DHFI FC FOUNDATON FOR THL ADEQUACY OF THE qvnt a,CR4404 CORRELATON OF IHRAD6ATION INDUCLD TRANLICENSING BASES A Supp6ement To The Statement 01 Cons,das. Sif 40N TEMPERATURE INCREASEfi F HOM CM AND APC)/ A(IC)atons br the Proposed Rule On Nc6 ear Power Piant trense Re" DAT A final Reportrwwn!(10 CFR Part f 4) Draft Report F or Comment

Rad.ation E Poture ^UAEG!CP-0111. PROCEEDINGS OF THE SYMPOSIUM ON 6r4 SERV. DOSE ESTIMATES FOR INHALLD VRANtUM MILL.

|ICI TESTING OF PUMPS AND V ALVES Heid At the Hyatt Regency hxh(Re

Hotel, Wash 6ngtan.DC, August 1 3.1980j A*d''D" ''''d'*"- OADS NJREG/CP 0110 PROCEEDINGS OF THE INTERNATIONAL WORb'

NUHEGeCR b468 QADS A MULTID4MENSONAL POINT DERNEL SHOP ON NEW DEVELOPMENTS IN CCCUPATONAL DOSE CON.ANALYSIS MODULE' TROL AND ALARA IMPLE MLN T A flON AT NUCLLAR POWE R

PLANTS AND SIMILAR F ACluTIESQuality Assurance NUREG/CR-3409 VOS OCCUPATONAL DOSE REDUCilON AT NU.

NUREGen0017.3 ROU $f ANDARD REVIEW PLAN FOR THE REVIEW CtE AR POWER PLANTS ANNOT ATED 0!BLOGRAPHY OF SELECT.OF SAF (TY ANALYSIS REPORTS FOR NUCLEAR POWE R t D READINGS IN RADiAtlON PROTECTON AND ALARAPLANTS 1WR Edvtion Revison 0 To SRP Section 174 "Quabty Assur-ence Program Desept.on" Radioactive Material

NURLG 1383 GUIDANCE ON THE APPUCATON OF QUAUTY ASSUR. NUREG-0383 V01 R13 DIRECTORY OF CE RTIFCATES OF COMPLFANCE FOR CHARACTERl2iNG A LOW 4Evn RADIOACTIVE W ASTE ANCE FOR RADIOACilVE MATERIALS PACAAGES negrt Of NRCDISPOSAL SITE FM Report APD'oved Panages

NUREG/CR 6310- QUAUTy ASSURANCE AND VERIFICATON OF THE NUREG'0383 V02 R13 DIRECTORY OF CERTIFICATES OF COMPU-MACCS CODE. Version 15 ANCE FOR RADIOACTIVE MATERIALS PACAAGES Certificates Of

ComphanceOuellty Assurance Program NUMEG 03s3 V03 Rtb DIRECTORY OF CERiiFICATES OF COMPU.NUREG-0383 V01 R13 DIRECTORY OF CERTiflCATES OF COMPU-

|ANCE FOR RADCACTIVE MATERtALS PACKAGES Repart Of NRC

ANCE FOR RADCACTIVE MATERtALS PACAAGES heport Of NRCi

Approved Quaty Atsurance Programa For RaSoactive MatorWs Pa&Approved Panages'

| NUREG 0383 V02 R13 DIRECTORY OF CERTIFICATES QF COMPU. agat

ANCE FOR RADOACTIVE MATERIALS PACAAGE S Carteates Of Ramosctive Pathway

NUREu o383 V03 R10 DLRECTORY OF CERTirlCATE$ '$ COMPU- NUREG/CR 6475 MODEL F E ASiBldTY STUDY OF DADICACTIVE |Comparce

ANCE FOR RADOACTivE MAtliRiALS PACAAGES Report Of NRC PATHA AYS FROM ATMOSPHERE TO SURF ACE W AflR

i

e r.py r-nD w* - . . " #1--g- - - - -- -g -we-, m- - -*--w-y-.-------r

__ .__ __ __ _ .. _ __ _ _ _ __. . .__ _ __

,

Bubject Index 99

Rad 406ctivs Renesee NUHE G/C84!41 V20tPF E V ALU AT10N OF SEVf ul ACCID ( NTNUHt G/CH-aWI VC1 MELCOFi ACCIDENT CONSEOVENCE CODE Hl!AS OUANilflCAllON OF M AJOR INPUT PARAMiil Hb MACCS |

,

S YST E M (M ACCS) VAnno 1. User's Gude l'WINUHE G/CA4691 VD1 MELCOH ACCIDEN1 CONSEQUENCE CODERodeoective Waste SYSilu (MACCS)vchme i User's Gade

NUREG/CR tfs67 Risk METHOOOLOGY FOR GEOLOGIC OISFOSAL NUHE G/CA 4691 Vty? MELCOH ACCIDENT CONS (OVENCE CODE |OF AADCACTIVE W ASTE Scenew Seieeuan Procedse SYSTE M (MACCS) Vokame F Ma.tel DnwiptionlNVAEG/C4 6001 EF FiCTS OF MANut ACTURING vAH6ABLEE ON NUHE G/CJ44fi9i V03 Mt LOOH ACCIDEN1 EONSE QUENCE CODE jPERFORMANCE OF HIGH. LEVEL W ASTE LOW CARDON STEEL SYSit M (M ACOSI Voume 6 Progaminers Raference Manuel '

CONT AINEHSNUAEG/CR 6254 DIAS IN PE AK CLAD TE MPL HATURE fHL D6CT40NS

NUAEG/CR 6381- 1CONOMC RISK OF COtif AMINATION CLE ANUP DUE TO UNCERT AINTIES IN MODELING OF ECC flyPASS AND DIS.COSTS FIESULTING FROM LARGE NONHEACTOH NUCLE AR MATE. SOLyED NON CONDt NsApt E GAS PHE NOM [ N ARIAL LICENSEE OFERATONS- NUHEG/CA f>474 A%E % MENT OF CANDOATE ACCIDENT MAN-

Modtoactive Weste Disposal AGEMINT STRAttGlES

NURIG/CR-5532 A PEP 50nMANCE ASSESSMENT METHODOLOGYNUREG/CH $$27, Ft!SK SENStilVITY TO HUMAN ERHOH IN THE LA.

SAuEpgAFOR LO& LEVEL WASTE FACIUTilB NUniG/CR4f47; PWR DHf CONTAINMENT ISSUE CHARACTE Al2A-

TIONRadioactivityNUAE G'Cn 6302 CLOSEOUT Or IE DULLEflN 8010 CONTAMINA* NUHEG/CR 6589 ASSE SSME NT OF ICE-COND( NSER CONT AINMLNT

PE HFOHMANCE l& SUE STON OF NONRADCACffyE Sa' STEM AND AESULTING POTENTIALtWREG/CA 5500 ASSESSMENT OF THE COMDUSTON MOL(L IN

FOH UNMONITORED. UNCONTROLLED RELEAliE OF HADCACTIV- THE HECTR CODC IfTY TO ENVIAONMENT.I

Reectet ComponentRadaotdologY

NUREG/CH f.41g AGING ASSFSSMENT OF INS 1FtVM[:NT AIR SYS-NUREG/CH4704 V03 RELATIVE BOLOGICAL Ef FECTIVE NI SS (RBE) TEMS IN NUCLE Ali POWE R PL ANTS

OF FISSON NEUTRONS AND GAMMA HAYS AT OCCUPAflONAL NUH(G/CH (MF ALilHNATE MODAL COMBINATON Mi'THODS INEXPOSURE LEVELS Stu$es On The Gross And Microscopic Pettdo- RESPONSE SPECTRUM ANALYSISgy Oteervns Al Death of Mee Emposed To 60 EcNal once Ween 4Ooses CW Assaart,. Fleector Contalnment

NUHEG/Cn 6476 POSITEST ANALYSl5 OF A 16 SCAL E HEIN-Red 6o(gspenc BourceFOHCED CONCAt fE HE ACTOR CONTAINMENT DUILDING

NUHt G 140$ INADVERIENT SHIPMF.NT OF A RADOGRAPHICEOURCE F FOM KONEA TO AMERSHAM Reactor CoolantCOAPOR A T ION.DURUNG T ON. M ASSACHUSE TT g NUNE GICIM374 $UMMARY OF INADEOuATE CORE COOLING IN-

STRUME NTAtlON FOR UNITED ST Af[$ NUCLEAR FOWEHRad 6ographyPLANT S

NUREG 1426 WELDING AND NONDESTRUCTIVE EXAMINATIONISSUES AT SEABROOK NUCLEAR STATION Ah independent Aence Reector Coolant SystemTeam Repart

NUREG/CR 6546 VICTOHLA A MECHANISTIC MODEL OF RADONU.CLIDE BEHAVOR IN THE HE ACTOR COOLANT SYSTLM UNDEHRad 6ological ReloaeoStVEHE ACCIDt NT CONDITIONS

NUREG/CR4659 CONTROL ROOM HADITADlutY SYSTIM REVIEWMODELS R*ector Core

Rediolog6 cal Traneportation inc6 dent NUAEG/Cn4316. MElf PROOFILSSON.OKIDAflON AND NATURALCONVECTION IN A St VEAL LY DAMAGED AE ACTOR CORENURtG/CR4399 SUAVEY OF ST ATE AND TRIBAL EMEHGENCY RE-

SPONSE CAPADILITIES FOH RADOLOGICAL TRANSPORTATON Reactor MetnteneraINCOE NTS NUHEG/Cn 6507. HESULTS FROM THE NUCLE AH PLANT AGING HE-

Radlorwcude SE ARCH PHOGRAM THEIR USE IN INSPECTION ACirYlT!ES

NUAEG/CR4545. VICTORIA A MECHANISTIC isCOEL OF RADONU. Reactor Pruture VoteelCLOE BEHAVIOR IN THE RE ACTOR COOLANT SYSTEM UNDER NUMEG/CR 6493 (NFLUENCE OF F1UENCE RATE ON RADIATION-IN<SEVERE ACCIDENT CONDITIONS. DUQD MECHANICAL PHOPERTY CHANGES IN FiEACTOR PHf 4

NU4E G/CR4031. CONTRIBUTION OF MATERNAL RADONUCLIDE SulE VI SSEL STI ELS Final Hopcyt On Eupkwalary EspenmentsBURDENS TO PAENATAL RADIATION DOSES intenm NUHEG/CH 6606 PHE UMtN AR Y S1HUCTURAL E VAL UAllON OFRecommendsbons For Comment TACUAN RCL SUtVErt TO POSTULA1ED HPV SUPPORf f ALLURE

NUREG/C8 6652 AN OVFHVIE W OF THE LOW UPPE R SHELFRadlonuchoe AdeoepuonTOUGHNE SS SAFE TV MARGlN ISSUENUREG/C8 6547; APPUCATON OF SURFACE COMPLEAATON

NVAEG/CH 5564 HESULTS OF CHAC0ARNEST TESTS ON TYv0 ln.MODELS FOR RADONUCLOE ADSORPTON Sens4tryny Anaysis Of RADIATED HIGH COPPER WELOSModed input Parameters

f4URE G 'CA.5548 HEVIEW OF GEOCHEMICAL PROCESSES AND R* actor Protection SystemCODES FOR ASSESSMENT OF RADONUCLOE MIGRATION PO. NUAEG/CR4474 ASSESSMENT OF CANDIDATE ACCOENT MAN.TENTIAL AT COMMERCIAL LLW SITES. AGEMENT STRATEGIES

Rad 60tiuchde Release Reactor SafetyNUREG/CR.2050 V09 POPhCN EOSE COMMITMENTS DOE TO NUnEG/CR4551 V2R IP t- EVALUATION Of bEVERE ACCOENT

HADIOACTivE RELEASES FROM NUCLE AA POWER PLANT SITES HISAS OUANTIFICATON OF MAJOR INPUT PARAMETERS E.nportIN 1987. Operwon Elicitation On in4esset lesses

NUREG/CR 4624 V06 RADIONUCLIDE RELEASE CALCULATONS NUHEG/CH 4551 V4R1Pt' EVALVAllON OF SEVERE ACCCENTFOR SELECTED SEVERE ACCOENT SCENAAIOS bappiementat Cat RISKS PEACH BOTTOM. UNIT 2. Man Repytcutabons NURt G/CH 4561 V4 RIP 2. EVALUATION OF SEVERE ACCIDENT

RISAS PEACH OOTTOM, UNIT 2 ApparutcasReactivity AccidentNUREG/CR-4561 V58 t PI' EVALUAllON OF StVEHC ACCIDENT

NUHEG/CR4M8 RE ACTMTV ACCIDENTS.A Reasonstment Of The H6KS SEQUOYAH UNIT I Man neportDesgn-Dasis Events NUAE G/CH 4561 V5A1P2 EVALUAllON OF SEVERE ACCOENT

RISKS SEQUOYAH. UNIT 1. AppeecesReactor Accident

NUHEGICR-4551 V6 RIP 1 [VALUATON OF SEVERE ACCOE NTNUREG/CP 0106 V01: PROCEEDtNGS OF THE SEVENTIENTH RISKS GRAND OULF UNIT I Main HeFrt

WATER REACTOH SAFETY INF0FIMATON MEETIN3 NUREG/CR 46El V6 RIP 2. EVALUATON OF SEVERE AOCIDE NTNUREG /CP-0105 V02 PROCE EDINGS OF THE SEVENTEENTH RISKS GRAND GULF,0 NIT 1. Appe%c.es

W ATE R HEACTOR SAFETY INFORMAtlON MEETING NVAEG/CR 6280 vot: AGE . RELATE D DE GRADATION OF WESTING-NURE G/CP 0105 V03 PROCE ED4NGS OF THE SEVENTEENTH HOUSE 460-VOLT CIRCUIT BREAKERS Arq Assessnwnt And Hoc.

W ATER REACTOR SAFETY INTOHMATON MEETING ommendations For impoving Breaker Rehntatrty

|

|

_ _ _ - . _-. -- - - - - - . _ ..

__ -. _

J

; . 100 Subject inden

NURfG/CR 6368- REACTMTY ACCIDENT $ A Reemosaement Of The hepert To CentroesNURE04093 Vit NO3 REPORT TO CONGRESS ON ADNORMALDeep enw E ventsp

NVHfu/CR 6472. A RISK. BASED REVIEW OF INSTRUMENT Am SYS" OODURRENCES A itember 1989TEMS A7 NUGE AR KIWER PLANTS NURL04Kl90 Vtf . *EPORT TO OONGRESE ON ADNORMAL

NUniGrCf44607; hi3ULib FROM THE NUCLE All PLANT AG NG RE' OCCURRENCE S October December 1969 '

SEARCH PROGRAM THEtR UBE IN INSPECTON ACTMf|ES- NURE GOO 90 Vt3 N01:- REPORT TO cot 4GRESS ON ADNORMAL000VRRE NCE B January. March 1990

E TO CO W W ON AB N 4R CP t F NBACTONS OF THE EIGHTEENTH WATER RE. [

ACTOR &AFETY INFORMATON MEETING.ReeW Noet homoval

Meector Thermal Nydrevhc NWiEO 1419 LOSS OF VIT AL AC POW!ft AND THE RE SIDUAL HE AT'

NUREG/lA4031: ICAP ASSESSWNT OF RELAP6/ MOD 2, CYCLEREMOVAL SYSTEM DURING MID400P OPERATIONS AT YOOTLE36 05 AGAINST LOFT BMALL BREAK EX8'[RIMENT L3,y, UNIT 1 ON MAFICH P0,1990

Rooctor TripNUREQ/CR4622 ANALYS!S OF REACTOR TRIPS OR10lNATING IN Ame66uel Damaaettve

DALANCE OF PLANT SYSTEMSNVREQlCH $$tf EM PC; RE SLDUAL RADIOACTIVF CONT AMINATON

FROM DECOMMIS$0NING Techrscat Dates For Trenaisting Conte *

R$0/ 374. SUMMARY OF INADEOUATE CORE COOLING IN-tSTRUMENTATON FOR UNITED STATES NUCLEAR POWER RoeinPLANTS NURf G/CR4PP9 V03 EPICOR il f1ESIN/ LINER INVESTIGATON LOW.

NVIMG/CR.E479 CURRENT APPLICATONS OF VIBRATON MONi' LEVEL WASTE DATADASE DEVELOPMENT PROGRAM FOR FISCALTORIN3 AND NEUTRON HOISE ANALYSIS. Detection And Anotyws 01 YEAR 1990hsel ReportStructural Depa3eten Of Rosetor Yeonel internets From OperstonalAmio heeln Degredetton

NU4G/CR 6foO ANALYS:S OF HD ROBINSON PWR VESSEL NUREO/CR424 RADtATION DEGRADATION IN EPICOR il ION EX.-FLUENCE FOR CYCLE 10 UTIll2tNG PARTIAL LENGTH SHIELD AS' CHANGE FIESINSSEMBLIE S.

Mee6stence Temperature DetetterMUREQ/C844S60 AGING OF NUCLEAR PLANT RESISTANCE TEM.

b4663 RECRITICALITY IN A DWit FOLLOWING A CORE VA" U N8DAMAGE EVENT,

VFt[04933 811: A PRORitt/ATON OF GENERIC SAFETY ISSUESCR4576 CLOSEOUT OF IE BULLITIN 84 03 RErVELiNOCAVITY WATER BEAL . g,,g g,,,y,,, g,,,,,

NUREO/CR 6111: INTEGRATED REllADILIT) AND RISK ANALYSISReg 6enet MwG NetworkNUREQtC8142S8 V04 GEORGIA / ALABAMA DE%AL SElBMO- SYSTEM (IRR AB) VEllSON P O USE R'S OUIDE

ORAPHIC NETWORK Fnal Report, Auguer 1966. October 1990<

NUFtE0/CP4106 V01: Pf0CEEDINGS OF THE SEVENTEENTHMogulet6enNUREG-1266 V04= Nfl0 f>AFETY R%EARCH IN SUPPORT OF REOV- WATER REACTOR SAFETY tNronMATON MEttiNo

EATON FY 1999 NURIG/CP4105 V02. PROCEEDINGS OF THE SEVE NTEENTHW ATE R REACTOR SAFETY INFOftMATION MEETING

M*putatory Agende NUREG/CP Ol06 V03 fHOCEEDINGS OF THE StVENTEENTHNUREG4936 V06 N04 NRC REGULATORY AGENDAOuarto'% WATER REACTOR SAFETY INFORMAflON MEEllNG

RomstOctober December 1989 NUREO/CR 6572 AN EVALUATON OF THE EFFECTS OF LOCALNURIQh936 Vos Not; NRC REOULATORY AGE NDA Quenerty CONTROL STATON DESIGN CONFIGURATIONS ON HUMAN PER-

NIW9'36 9 NRC REGULATORY AGENDAOuedeny NU 0C t i GE R R S H I WESTIN060VSEAND COMBUSTION ENGINEERINO PRESSURIZED WATER REAG.NURN 3 NRC REQULATORY AGENDAOuartertyIONS

Report. July 4eptember 1990.R6ek Methode40gy

. Moguletory Analyees NUREQ/LAteef. RISK METHODOLCGY f OR GEOLOGIC DISPOSALNUREG 1409. BACKFITTOG GUOELINESOF RADIOACTIVE WASTE. Escenarm Selecton Procedure.

Megulatory And Technical ReportNUREG4304 V14 N04: REQULATORY AND TECHNICAL REPORTS Rulee

PBSTRACT INDEX JOURNAL) Annual CompAstion For 1989 NUREG4936 V06 N04 NRC RIOULATORY AGENDA OuanertyNvREG4F4 V16 N01: REGULATORY AND 1ECHNICAL ftEPORTS Reportodober Decembur 1989

(ABSTRACT INDEX JOURNAL). Complietion For Frst Quarter NURE04936 YO9 No t. NRC REGULATORY AGENDA Ouaderty

NU 304 V NO2. REOULATORY AND TECMNICAL REPORTS NUR NRC REGULATORY AGI NDA.Ouenerty(ABSTRACT INDEX JOURNAL). Compnston For Bocond Quarter R AprtWune 1990-

^ ^ "* "

NU G 304 6 NO3 REOULATORY AND TECHNICAL REPORTS R . m 990(ABSTRACT INDEX JOURNALL Compilaton For Ttwd Charter1990. July September, Ru6ee Of Proctice

NURE04366 D06 R05: UNITED STATES NUCLEAR REQUWORYCOMMISSION STAFF PRACTICE AND PROCEDURE

l DF FT: INDUSTRY PERCfPTIONS OF THE (MPACT OF DOESLComnusson, Appeal Board And Ucenaang BoardTHE U.S NUCLEAR REQULATORY COMMISSION ON NUCLEAR *

Q%6 TES MEAR REQUuTORY -POWER PLANT ACTMTIES. Draft Report pgCOMMISSON STAFF PRACTICE ' AND PROCEDURE

payNUREG/CH 4659 V03 SEISMIC FRAGILITY OF NUCLEAR POWER

DIGEST.Comrrasson. Appeal Doard And Licanang - Board.

'

PLANT COMPONENTS (PHASE li)Seitchgear, t&C Penene (NSSS) DoessorwJutv 1977. December toce .

NUREG 0306 DO6 807 UNifED STATES NUCLEAR REGULATORYAnd Relays, COMMISSION STAFF PRACTICE AND PROCEDURE

Menef VetveDIGEST.Commisson, Appeal Board And utenamg Board

NUREG 1316: TECHNICAL FINDINGS AND REQULATDRY ANALYSIS Decisons July 1972 March 1990RELATED TO GENERIC ISSUE 10 Eva'unton Of Power Operated NU5tEG 0386 DO6 R08 UNITED STATES NUCLf AR REGULATORYRelief Vahre And Block Va.ive Reisarality in PWR Nuclear Power Pianta COMMISSON STAFF PRACTICE AND PROCE DURE

__-m-. ___ ._ _.._ m - .__ _ --. _ , _ , _ . _ . _ _ _ _ _ _ - , _ _ _ _ . . . _ _ . _ _ _ _ _ _ . ,

_

|| Subject inden 101

DwGE ST.Commeon, Appeat B:e'd And Elcensing boe'll NUREQ/CR4H1 VDG h4 SAf ETY REBEARCH PROGRAM 6 BPON-Dess.ons July 1972. June 1991 M*E D BY 08 FICE OF NUCLEAR REGUuTOHYFiE6LA40' Octobe4 December 1840

NUREG 1914 R06 H!BTORICAL DATA SUMMARY OF THf $YSTEMAT. balety.fbeleted CemPorsent6C ASSESSMENT OF LICENSEE PERFORMANCE NUnEGrCR.fa90 vp RE3JLAtostY INSTRUMENT FtEviEW MAN.

SCALE ADEMENT OF A31N3 OF LWR MMOR LAFETY.RELATED COMfoNUREG/CR.5366 HTA52 A THREE DIMENSIONAL TP.AN$itVT SHIP. MNT6

PING CASA ANALYSIS TOOL. beiemgSCANS NJHEQ/ 443ti9 THE BEiBMIC CATEGORY l $TRUCTURES PRO-

NU4EG/CR4M4 V06 BCANS (SHIPPING CASK ANALVE.S SYSTEM A A M, I9 g t O T% FEMURE$ MW TM EMICACCOM8VTE R BASED ANALYBi$ $YSTEM FOst guiPPiNO

CASK DELON REVIEW Vob.sme 6. Theory Manual DucHing Of Circ # gg7,g g,gggggg~k C ,t - Shees

.e,e. E ,,ee,NUREG/C44654 VOL GOANS ($HIPPIN3 CASK ANALY$1$ $YSTEM)

A MICROCOMPUT[R BASED ANALT$il SYSTEM FOR INPPIN3 yggg3,C4HU ALTE4NATE MDDAL COMBINATON METHOOS INCAS*. DESON 81CVIEW Volume 7; Theory Manuel Panctu'o O' $No ggg,39qq g;pgg7ggy gq4gygg'P, Ceeks. .e,a . ,,e,II,,,

NU8tEQi(.R.4009 V03 SElbM6C FRAQ!LTTY OF NLOLCAH FOWEf4NJ8 E C 62t VO4 SCDAP/RELAP6/MDD2 CODE PLANf OOMPONENTS (PHABI It) Switchgest I&C Panels (NSSS)

MANUAL. VOLUME 4 MATPRO . A LIDRARY 08 MATERIAL $ PHOP. "E4 TIES FOR UGHT. WATER ALACTO*4 A9COENT ANALYblS beam 4 Haute

Safegueros Summary Event Uet NU8ttG/C4%30 TECHNFAL CONSIDERATONB FOR EVALUATINGNURf G 0616 R16. SAFEGUARDS SUMMA 8tY EVENT Li$7 ($$Eu $Ut ST ANTtALLY COMP ETE CONTAINME NT OF HIGH LEVELL

W A6TE W fHiN THE WASTE PACNAGE.Safety

N' G R 5437. ORGANt2ATON AND $AFETY IN NUCLE All POWEH

EVALUATON OF GTRUCTURE S) VIHSON 1.C SeismicSafety Evaluation Report Mxtee Themetgei Ma%.nlNU4tG0797 S?? SAFETY EVALUATION HEPORT HELATEE TO THE NuRI G/CR Mtie VO? CAhf 6 (COMPUTER ANALY$18 FOR RAPO

OPERATON OF COMANCHE PEAK $TE AM ELE CTnlO EV ALUATON OF STHUCTU8tE S) VERSON 10 6eesme$T ATON. UNITS 1 AND P Docket Nos fA446 And fe446(Teens Utik MMJ8 Use t Ma%8Wr

ks Doctnc Company et a:) NUHlG/C4-Mh6 V03 CAREG (COMPUTE R ANALYSIS F081 RAPONUHEG 0797 673 SAF ETY EVALUATON REPORT RELATED TO THE EVALVATON Or $TRUCTURE S) VE R$10N 1 t Setemr

OPE RATON OF COMANCr4E PLAK BTE AM ELECTRIC Mouse baniPto Protnem6StATON, UNITS 1 AND # Docket Nos $4446 Arid 60 446 (Touan Uuliks Eisetnc Compey at W ) 6*'*m35 N't*0'h

NUREG4F97 524 SAF E TV EVALVATON 84[POHT 84 ELATED TO THE NURE O!CR4 7t,3 V03 CANADIAN $(ISMIC AGREEMENT AnnualOPERATON OF COMANCHE PEAK STE AM ELi(TittlO lit ATION hetWt 1987d9MUNITS 1 AND 2 Docket Nos 60-445 Asid (0 446.(Texas Utlities Elec. NUhE Q'Ch4163 V04 CANADIAN SEISMIC AG84LE MENT AnnualInc Compelet al) Hopst 19hB 1969

NUREGM47 dv5 SAFEW EVALUATION REPOnf At LAft D TO THEOPERATON OF W ATTS BAR NUCLEAR PLANT. UNITS 1 AND bM8*W ID'II"92 Duket POs f43M And to 391.(Tennesome Valler AuthoHty) NUhEG/046448 AGING EVALUATON Of CLASS 'E DATTERIE8

NUREGeise 609 SAFETY EVALUATON HEPOHf HP LATED TO THE SEISMIC YESilNGOPERATON OF $[ ADROOK STATICM UNITS 1 AND P Docket NosEfN 60 443 And STN f,0-444 (Putec Sonnte Coqeny Of New Harne 6* ' "I

NUR 1732 V04 SAFETY EVALUATON REPORT ON TENNESSEE wt BTERN OHOINDIANA REGON Annual ReportOcbter 1988V ALLE Y AUTHORITY: WATTS BAR NUCL[ AR PE RF08tM ANCE baptnter IMDPLAN NURt G'0447 b3 V03 CANADLAN SEISMIC AGRE EME NT.Armal

NUREG 1390 SAFETY EVALUAflGN REPORT 81 ELATED TO THE HE. Report 1987d900NEWAL OF THE OPERATING LICENSE FOR THE THIGA TRAINING NU8tlG/CH+47t.3 V04 CANADtAN SEISMIC AGRE E MENT. AnnualAND RESEARCH REACTOR AT THL UN'VERSITY OF Report tono 1989AHl2ONA Docket No fo113 (Urwerssty of Ansonal NU8tlG/Cf4 f>PSB V03 GEORGIA / ALABAMA Rt GONAL SEISMO.

NUf 4EG 1403 SAFETY EVALUATON REPORT RELATED TO THE G8tAPHIC NETWORetAnnual ReportJutv 1987. June 1968.FULL.TE RM OPERATING LICENSE FOR DRESDEN NUCLE AR NURf G/Ch 62hb V04 G( ORGiA/ ALAhAM A HEGONAL SE;SMGPOWER ST Af 0N. UNIT 2 Docket No f 0 237.(Commonwea'th Edson GRAPHO NETWORK hnal heswt August 1985. Octoter 1990Company) NUREG/CR 6t?9 MICROLARTHOt/%tS IN AANSAS AND NEDRAS.

NUREG.1417. SAFETY EVALUATION Rf PORT RELATED TO HYDRO. KA 19774989 Final ReportNC THDL OWNERS OROUP ASSESSMENT OF MARK 111 CON.

Setemogroptoc hetworkNURE Ga 424' SAFETY EVALUATION PEPORT PELATED TO THE NUREGiC452SB Vot GEORGIA /ALADAMA REGONAL SEISMO.

FULL TERM OPERATING UCENSE FOR PAltSADES NUCLEAn ORAPHIC NETWORK. Annual ReportJury 1966 June 1987.NU8 IG/Csd?f>B V03 GE ORGIA/ ALADAM A RE GON AL EEISMSPLANT Docket No f6765 (Consumers Power Company) 4

GRAPHIC NETWORK. Annual ReportJuly 1967 June 1986f.afety Margin

NUREG/C45557 AN OVERVlf!W OF THE LOW UPPER SHELF %'"**'TOUGHNESS SAFE TV M ARGIN ISSUE, NUllEG/CR 5464 PH SENSORS BAS (:D ON IRIDIUM OAIDE.

Safety Rouarch GerY6ce LHeNUREG-1266 V04. NRC $AFETY RESE ARCH IN SUPPORT OF REGU. NUREG/C46642 MODELS FOR EST!MATON OF SERVICE LIFE Or

LATON . FY infle CONMETE BARRIERS IN LOW 4EVEL RADOACTivE W ASTE DIS-NUREG-1423 V01. A COMPtLATON OF REPORTS OF THE ADVISORY FOSAL

COMM!TTLE ON NUCLEAR W ASTEJuly 1966 June 1990Bevere AcNdont

Safety Reparch Program NUREG 1407 DRr1 FC PROCEDURAL AND SUDMITTAL GUCANCENUREGICR2331 V09 N3 SAFETY RESEARCH PROGRAMS SPON. FO4 INDIVIDUAL PLANT EKAMINATON OF EXTERNAL EVENtBSORED BY OF FICE OF NUCLEAR REGULATO81Y OPECO FOR SFVE Rf ACCIDENT VULNERADIUTIES Draft heport for

RE SE ARCHProgress ReportJuiy September 1969 Comment

|

_ .. __

. _ _ _ _ _ _ . . _ . _ _ _ _ _ __ _ _ _ _ _ _ _ ___ __ _ _ _ _ _ _ __ _ ._ _

102 Subject index

NUREG 1420 SPECLAL COMMITTEE F4EviEW OF THE NUCLEAR REG- SNeld AssembliesULATORY COMMISSON'S SEV(RE ACCOENT RISAS REPORT NURE GrCR B30 ANALYSTS OF HG FtOtiiNSON PWR VESSEL(NUREG 11506 FLUt NCE FOR CYCLE 10 UTILillNG PARTLAL LiN3TH SHIE LD AS-

NURE G/CRob t V2R1Pt: EVALUATION OF SEVERE ACCIDENT St MLtLIE SRISKS- OUANYlFICATON OF MAJOR INPUT PARAMETER $ EnpetOcwran i lestaten On irrVe, nel lesume $Nonding

NURE G/C$14bs t V2R t P7. LVALUA10N OF SEVERE ACCOENT NUREO/CR 6468 OADS A MUlflD4ME NSiONAL fonNT KERNELFtlSKS QUANTIFICAttON OF MA.OR INPUT PARAME f[ftS MACCS ANALyges ug(gE

NU /CR 4661 V3 RIP t; EVALUATON OF SEVERE ACCittNT ghlpment

fg [f,[3#NLt C4 66 R F2 EV ATION OF SEVERE A(X:lC(NT ,

CORPORATION 0VRLINGTON. MASSACHUSETTSNU OC 465 R1P L AYON OF SEVERE ACCIDENT

RISKS PEACH BOTTOM.UNG 2 Main Report C kU O/ 4%4 V06 SCANS (SHIPPING CASK ANALYSl$ Sv8TEMi A

i KS PEAC Y [UNf 2 ,

NURE G/CR 4%1 V6 RIP 1: LVALU ON OF SEVERE ACCIDENTMICROCOMPUTE R BASED ANALYSIS SYSTEM FOFt SHIPPINGCASK DESIGN REYliW. Volume 6 Twy Manual bxAling 01 Carou-

RISKS SECROY AH UNIT 1 Main ReportNURE O/CR-4%1 V6AIP2 LVALVATON OF SEVEftt: ACCIDENT lar Cylincirx.al Shelle

NUREG/CR 4%4 V07 SCANS (SHil' PING CASK ANALY6|S SYSTEM)RISKG SEOUOYAH UN111 AppenchcesNUREG/CR4651 V6H1% EVALUATION Or SEVERE ACCIDENT A MICROCOMPUTER BASED ANALYAIS SYSTEM FOR SHIPPING

RfSKS ORAND Gutt,0 NIT 1 Main Report CASK DESIGN REVIEW.Voume 7. Theory Manual Purcture of SNp.NURE G/CR4661 V6 hip 2. EV ALU ATION OF SEVERE ACCIDENT geno CeMe

RISKS ORAND OULF, UNIT t. Appendees NUR(G/CR 6366 HTAS2 A THREE DIMENSIONAL TRANSIENT SHIP-NURE G/CR4624 V0ft RADONwLIDE RELEASE CALCULATIONS PING CAFK ANALYSIS TOOL

FOR SELECTE D SEVERE ACCOENT SCENAROS Supp6emental Ceculatons Small Break

NUREO/CR 6613 V01: ACCOENT MANAGEMENT INkORMATON NUREG/t/ 004 RE. LAP 6/ MOD 2 CALCULATIONS Of OECD-lor 1NEEDS Volume 1 Methodology Devotopment And APphcohon To A TEST LP SB 01

#7gsI[phh. T MA 47 ATIONNU IE C8 66 C

NMECHANISTIC MODEL OF RADONU- E F F N PN FE /C 6 6 VICCLlDE DEHAVOR IN THE REACTOR COOLANT SYSTEM UNDER NURf G/lA4031; 6 CAP ASSESSMENT OF RELAP6/ MOD 2, CYCLE

SFVERE ACCIDENT CONDITONS' ANALYSIS OF POTENT 1AL PER*36 06 AGAINST LOFT SMALL DRE AK FXPERIMENT L3 7NUREG/CR 6676 OUANil1 ATIVE

FORMANCE IMPROVtMFNTS FOR THE DAY PWR CONT AINMENT, AGAINST LOFT SMALL DREAK EAPERIM' LAP 6/ MOD 2 CYCLE 36 04NUREO/LA 0033 ASSE SSMENT OF RE

ENT L3 6.NUREG/CR %86. MITIGAflON OF DIRECT CONT AINMENT HEATING

AND HYDROGEN COMBUSTKW EVENTS IN ICE CONDENSER *enab Dreeli EOCA-

PLAN 15.AnaYeee With The CONT AIN Code And NUREO 1160 PRA NURE G/lA.0018 RELAP6/M002 ASSESSMLNT,OECD LCW1 SMALLDREAK EXPF RIMENT LP SB.03.

NUR O 53 RECRITICALITY IN A DWR FOLLOWlHO A COREDAMAGE EVENT. Snubt>er

NUREG/CR 6386 BA$l8 FOR SNUOHER AGING RESEARCH NUCLE.Severe Accident R6ek AR PLANT AGING RESEARCH PROGRAM

NUREG-1160 V01: SEVERE ACCOENT RISKP AN ASSESSMENT FORFIVE U S NUCLEAR POWER Pt. ANTS Fenal Sunvnery Repot SoWater Rotenuon

NUREG 1160 Vnt SEVERE ACCIDENT RISKS.AN #5SESSME N' FOR NUREO/CR 6607: FLOW AND TRANSPORT M THE L AS C90CESf fvE U S. NNLEAR POWER PLANTS.Appe%ces A.B. And C Fenas TRENCH SITE Emporrnente 1 And PReport

NUREO/CR 4661 V3R1P1: EVALUATION OF SEVERE ACCIDENT Boll / Structure interecuenRISKS SURRY UNIT 1 Ma*n FiepartNUREQ/CR 4661 V3R1P2: EVALUATON OF SEVERE ACCIDENT NUREQ/CR 6699 DYNAM6C TE STING OF A CIRCULAR FOUNDATION

AND ANALYSES rv SOIL / STRUCTURE INTERACTKWRISKS: SURRY UNIT 1. Appendwee

Severe Accidente SondlficationNUREO/CR 6697. IN-VESSEL ZlRCALOY OxtOATON /HYDROGE N- NUHEO 141B CHAR ACTE RISTICS OF LOW LEVEL RADOACTIVE

OLNERATON DEHAVOR DURING SEVERE ACCOENTS. WASTE DISPO SED DURING 1987 THROUGH 1989

beste Fpl Damage Solute TrensportNVREO/CR-467): THE OF 4 FUEL DAMAGE EXPERIMENT IN ACAR NUREO/CR.6482. LABORATORY ANALYSIS OF FLUID FLOW AND

WITH A OWR CONTROL BLADE AND CHANNEL DOX. SOLUTE TRANSPORT THROUGH A VARIABLY SATURATED FRAC.TURE EMBEDDED IN POROUS TUF F.

Sheltow FlawNUREGrCR 6%4. RECOMMENDATONS FOR THE SHALLOWCRACK Sorpuon

FRACTURE TOUGHNESS TESTING T ASK WITHIN THE HSST PP.0- NURE0/CR 6463 EFFECTS OF MINERALOGY ON SORPTION OFGRAM STRONTIUM AND CE$1UM ONTO CALPLO HILLS TUFF.

SMkw bM SwW Me '' y

NUREO/CR %23 DEVELOPMENT OF AN INFILTRATON EVALUA- ggEG7R4263 PARTITON A PROGRAM FOR DEFINihQ THETON METHODOLOGY FOR LOW. LEVEL WASTE SHALLOW LAND SOURCE TERu/ EONSEQUENCE AN ALYSIS INTERF ACE IN THEBURLAL $1TES. NUREG 1160 PROBABILISTIC RISK ASSESSMt NTS User's Ouute

Shear Wall 88**' * ANUREQ/CR 6369- THE SEISMIC CATEGORY l STRUCTURES PR4 NUREGICA-%40 OVERVIEW AND COMPARISC'N OF U S COMMER-

ORAM RESULTS FOR FY t967. CIAL NUCLEAR POWER PLANTS Nacisar Power Plant System Sour-cetxx*.ShettToughnese

. NUREO/CR-6662 AN OVERVIEW OF THE LOW UPPER SHELFTOUGHNESS SAFETY MARGtN ISSUE.

Special Nuclear MatertalNUREG-1404 LICENSEE USE OF TACTICAL EXERCISE RESULTS

SheikRupture FehoreNUREQ/CR 6406 ANALYSIS OF SHELL RUPTURE FAILURE DUE TO Spectrum Analyste

HYPOTHETICAL ELEVATED * TEMPERATURE PRESSURIZATON OF NUREG/CR 6627. ALTERNATE MOD /1 COMBINATION MET >ODS IN

THE SEQUOYAH UNIT 1 STEEL CONTAINMENT DUILDING RESPONSE SPECTRUM ANALYSl$

- -, - - , - _ _ _ _ - -

_._ _ _ __ _ _ _ _ _ . _ _ _ _ . _ _ _ _ _

Subject index 103i

Stability feet Recommendetes ArW Conctueluno Setem V.He6d AlNURhG/CR b606. LAPUR BENCHMARK AGAINST IN4HASE AND Moeme. USSR Mov 14 17,1990.

t OUT OF-PHASE STABluTY TESTS NUREG/CR4067 V07. ENVIRONMENTALLY ASSISTED CMCMNG IN'

Steintese Steel LIGHT WATER REACTORS Semennual Refot.Apre &eptemter 1968.NUREG/CR4807 Vos ENVIRONMENTALLY AS$1STED CRACNNG IN

,

NUREG/CR4469 V09 NONDESTRUCTIVE EXAMINATON (NDC) RELL- LIGHT WATER RE ACTORS Semie'veaal ResortOdotw 1988. Much,

ADILITY FOR INSERVICE INSPECTION OF LIGHT WATER 1969RE ACTORS Semennual Report Agrti4eptember 1966,

Y. NUREGICR4a69 V10. NONDLSTRUCTin E AAMINATION (NDE) REll- StronetiumADILITY FOR INSERVCE tNSPECTON OF LIGNT WATER NUREQ/CP4463 EFFECTS OF MINERALOGY ON SORPTON OF

^ "N FL CR 7 3 1: GE E Rf ME OF CASTDUPLEK ST AINLE SS STEELS IN i,Wst SYSTEMS $emennual Structurel DegradotenRemrtOctober 1967 March 1966

NUMG/CR-4744 V03 N2 LONwfERM EMBRITTLEMENT OF CAST NL,3EG/CR4479 CURRENT APPLICATONS OF VIBRATION MONi-

DUPLEK STAINLESS 'tT EELS IN LWR SYDTEMS Sem enrwel TORING AND NEUTRON NOISE ANALYSIS. Detection And AneWe OfSmel DegradM Of Reactor Vueel interna From Opsmal

MURYG C A "9P3 L ASSESSMENT PROCEDURES FORa

'MAJOR LWR COMPONENTS Cast Stein 6eos Sleet ts

88^ SuPpwt Feeure

"i GNI ICAN L UE WBRITTLE ENT NUREQ/CR 6506 PRELIMINARY STFtVCTURAL EVALUATON OFCAST STAINLESS STEELS IN LWR SYSTEMS. TROJAN RCL SUBJECT TO POSTULATED RPY SUPPORT FAILURE-

Steintees Steel Weed Sudeos Composeemen M- NUREG/CR4611; IRRADIATON EFFECTS ON STF4ENGTH AND NUREG/CR 6647. APPLCATON OF SURFACE COMPLEAATON

TOUGHNESS OF THREE WIRE SERIES-ARC STAINLESS STEEL MODELS FOR RADONUCLIDE ADSORPTON Sensit% AneWe OfWELD OVERLAY CLADDtNG **' 8'N Premvers,

Standard Review Plen Sudeos CreekNUREG4800 03 6.1 R2- STANDARD FtEVIEW %AN FOR THE REVIEW NUREG/CR 6624 V07 TML2 VESSEL INVESTIGATON PROJECT (VIP). OF SArETY ANALYSl$ REPORTS FOR NUCLEAR POWER METALLURQlCAL PROGRAM Progress Repor1,0ctober 1989 June

PLANTS LWR EditionRevision 2 To SRP Section 3 6.1, Plant Dorgn 1990.Protection Against Postuteted Piping Failures in Flud Systems Out-

NUREG 060017.3 ROO STANDARD REVIEW PLAN FOR THE RE' VIEW NUREG/CR4476 MODEL FEASIBILITY STUDY OF RAD 60 ACTIVEOF SAFETY ANALYDIS REPORTS FOR NUCLEAR POWLR PATHWAYS FROM ATMOSPHERE TO SURFACE WATER.PLANT & LWR Ettion Revmon 0 lo SRP Section 17,3, *OusHy Assur. .

NkEG DR : NDARD REVIEW PLAN FOR THE REV'TW NURIG/CR 4669 YO3 SEISM C FRAGILITY OF NUCLEAR POWER-

OF LCEN$E RENEWAL APPLICATONS FOR NUCLEAR POWER PLANT COMPONENTS (PHASE 10 Swnchgear, IAC Pnnels (NSSS)PLANTS.DreN Report For Comment And Ro6eys

Steue Leed SymposiumNUREGICR4487: STATIC LOAD CYCLE TESTING OF A LOW ASPECT. NUREG/CP 0111: PROCEEDINGS OF THE SYMPOslVM GN INSERV.

'

RATO FOUR-INCH W ALL,TFIG. TYPE STRUCTURE TAG 6-4 ICE TESTING OF PUMPS AND VALVESHeld Al The Hyatt Regency(1.0.0 66) Hotei,Wenhengton.DC, Aupset 1 3,1969

Steuc Lead Pycle Systematic Aaseeement Of Usensee PettermanceNUREGICH4533 STATC LOAD CYCLE TESTING OF A VERY LOW- NUREG 1214 R06 HISTORCAL DATA SUMMARY OF THE SYSTEWT.ASPECT RATO SlK INCH WALL TAG TYPE STRUCTURE TAG 64 IC ASSESSMENT OF LCENBEE PERFORMANCE.' (0.27, 0.60).

NUREG 1214 Roo HISTORCAL DATA SUMMARY OF THE SYSTEMAT.IC ASSESSMENT OF LOENSEE PERFORMANCE.

NUREGiCR 6396 VCt MUL,TILOOP INTEGRAL SYSTEM TEST (MIST): TLDFINAL REPORT. Test Group 30.6,4epping Testa

NU9EG/CR4396 V10: MULTILOOP INTEGRAL SYSTEV TEST (MIST)- NUREG0837 V09 N04 NRC TLD DtRECT RADLATON MONITORINGNETWORK.Pr ese Report October Decermer 19e9

I TYE ANALY. " [[jNU / 2 L E C N N E #StS F0Fi THE SEQUOYAH CE CONDENSER CONTAINMENT.

NUREQ4837' YkNO2: NRC TLD DIRECT RADLATON MONITORINGS h Gonwetw NETWORK Progrees Report Apr#Jme 1990

'lVHEG/CR-6117. STEAM GENERATOR TUDE INTEGRITY PROGRAM / NUREG4837 V10 NO3 NRC TLD DIRECT RADIATION MONITOR.NQSTEAM GENERATOR GROUP PROJECT Final Pflject Summary NETWORWne w ww er m

N t CR & 29 V02 TMk2 EPICOR il RESIN / LINER INVESilGATIONNL E M ST IV T eN EG CR4396 vit AD MULTILOOP INTEGRAL SYSTEM TEST LOW LEVEL WASTE DATA BASE DEVELOPMENT PROGRAM FOR

(MIST) FINAL REPORT MIST Phase IV Testa FISCAL YEAR 1969 Annual ReportNUREG/CH W78. IMPROVED EDDY CURRENT INSPECTON FOR

GEN ATOR TLIBING Progress Report For January 1966 To T AC tj 1 '

pTHE OECO LOFT EXPERIMEMT LP 881.

Stoet ContennerNUREG/lA 0019 TRAC PF1/ MOOT POST. TEST CALCULATONS OF

NUFtEG'CR4001: EFFECTS OF MANUFACTURING VARIABLES ON THE OECO LOFT EXPERIMENT LP-SB-2PERFORMANCE OF HIGH4EVEL WASTE LOW CARBON STEEL NUREG/M-0022 TRACPFt/ MODI POST.TES' CALCULATONS OFCONTAINERS. THE OECD LOFT EXPERIMENT LP SB-3

NUREG/M4023 V01: ASSESSMENT OF TRAC PFt/MO0t VERSONStrese Corroe6cn Creektng -14 3 USING SEPARATE EFFECTS CRITICAL FLOW AND BLOW.

NUREG/CP4112 V01: PROCEEDINGS OF THE THIRD INTERNATON- DOWN EXPERIMENTS Vo6ume 1: Text And Tobies.AL ATOMC ENERGY AGENCY SPECIALISTS' MEETING ON SUB. NUREG/A-0023 V02. ASSESSMENT OF TRAC PF1/ MODI VERSIONCRITICAL CRACK GROWTH Opening Session Ard Technscal Seeson

14.3 USING BEPARATE EFFECTS CRITCAL FLOW AND BLOW.i. Held At Moscow, USSR May 14 17 1990NUREG/CP 0112 V02: PROCEEDINdS OF THE THIRD INTERNATON.

DOWN EEPERIMENTS Vokame 2. Figtres

AL ATOMIC ENERGY AGENCY SPECALISTS* MEETING ON SUB- Tactical heeponse EserceneCRITCAL CRACK GROWTH Technscal Sessions !!, lit, Ard lY Ard

NUREG 1404. LCENSEE USE OF TACTICAL EXERCISE RESULTS

- , . _ , _ - . . - . . . . _ . _ . _ .__ ._ .__=___-,_-.-m- _ _ , _ . , _ . _ - . _ _ _-- _ _ _ . . _

. _ _ - _. - .----- .--.-~--- _ - - - - _ _ _ . -

104 3ubject index

T**rtas a***laa*e Tren* PetNUNEGICR 68 1: tRRA06ATION EFFECTS ON ETRENGTH AND NUREG/CR4169 MCDIU2ATION AND TRANSPORT OF URANIUM AT

TNGHNESS OF THREE Wif4E SEniES A81C STAINLESS STEEL URAN'UM MILL T AluNGS D:SPOSAL BrTES Aprestion Of A Ctow

WELD OVE RLAY CLADDING Ca' Tr6nsport MDdel

Technical Spoo*fication Transportetlen AceloentNURE G-1361: TE CHNICAL bPECIFICATONS. COMANCHE PEAK NURE G'CR 4477 AN EVALVATON OF THE REUAbluTY AND USE.

STE AM ELE 0TRIC ST ATON UNIT 1 Dcoot No. 60 445,Appe%s " A" FULNE $$ Or trTERN AL-INtT6ATOR PRA METHODOLOGit STc Ueense No 94PF PS

NUREG 1386 TECHNICAL SPECIFICATONS FOR SEABROOM ST A- TritiumTION. UNIT 1 Appo%s " A" To Lt( 4eNo NPF46 NUREG/CR 6574 DETERMINATON OF THE CHEMICAL FORM OF

NUREG 1390 TE CHNCAL hPECinCATONS. COMANCHE PEAK intilVM IN StLF.LUMINOVS SIGNSSTE AM ELECTRC ST ATON.UNTT 1 Ekdot No 60-446,AppeMa "A"To Uconee NPF 47fioist Utdities bectnc) Tube irdegrity

NUREG/CR 6117 STE AM GENERATO54 TUDE INTEGRITY PROGRAM /"''[N E G/CA-3145 V08 GEOPHYSICAL INVESTIGATIONS OF THE

WESTERN OHtCaNDiANA FIEGON Ahnual Flepart. October 1988SepternMr 1989 Tubing inspec tion

NUREG/CR f429 MCFtOEARTHOVAt[8 IN KANSAS AND NEBRa,(L gggggfcn ga7g, gypHOVED E.DDY CURRENT INSPE CT ON FORAA 19771969 FirW Report- STI.AM OENER ATOR TUDING Prog one Report For January 1985 70

** #Telemetred Network

NUREG/CR 4763 V03 CANADIAN SEISM'C AGREEMINT Annual yg p,po,noryRecrt 19971968 NUREG/CR M36 ENViHONutNT AL EF F ECTS ON CORROSON IN

IHL W MNWTtiermal Neutron Activatlon

NUREG-1396 ENVIRONMENT AL ASSESSME NT Or THE THERMAL Ultraeorde lnepectionNEUTRON ACTIVIT ATON E APLCSfVE DETECTION SYST[W FOR NURE G/C$b4908 Ut,TRASONIC INSPECTON REUAB'UTY FOR INCONOOURSE USE AT U S AIRPORTS TERGRANULAR STRESb CE#tROSION CHACkS A Round fluten

$% 0 The I t O Pomet Neues t egment And Cred9tiermal Hydraulic 'd'""**

NUREG/CR $567: RELAP6 THERMAL-HYDRAUUC ANALYSIS OF THESNUPPS PRES $UHilED W ATEft RE ACTOR Unremonic Test >n8

NUREG/ Cit!449 v01. COMMtA 1C A THREE ulMENSONAL TRAN- N ^ OSIENT SINGLE PHASE COMPUTER PROGRAM FOR THERMAL-HY. H WG W NM M M RM MCM ANNA'

DRAUUC ANALYSIS OF SINGLE COMPONENT AND MULTICOM'PONENT ENGINEERING SYSTFMSIquatone And Namence Unostuteled Fractured Rock

NUREG/CH449 V02 COMMIA 1C A 1HREE-DIMENSIONAL TRAN NURIGrCRIM6 UNSATURATED FRACTURED HOCK CHARACit RSIENT SINGLE. PHASE COMPUTER PROGRAM FOft THERMAL HY. IZ,ATIDN METHODS AND DAT A SETS AT THE APACHE LE AP TUFFDRAUUC ANALYSIS OF SINGLE COMPONENT AND MULT00M- g 7gPONENT ENGINEERING SYSTEMS User s Ouv$e Ana Manual

Uneatureted Zone

G 0837 V09 4 NF C T 0 DIRECT RADlATION MONf tORING f, e h [hNETWORK Progreed Report October-Orwernter 1989

NUREG 0837 V10 N0l NRC TLD DiHECT RADlATION !DdfTORING Utentum

NU E 7Y 02 N C L ER RA ATION MONITORING ^ #b b *D0" ^ C#NETWORK Pr esa Report A .16 Jane t990

NURE G 0837 Y Na3 NRC T D OtRECT RADIATION MONITORING N 8 ROGiCAL CHARACTERi2ATION OF RADlATONNE TWORKProgiens Report July Septernber 1990 EXPOSURE AND DOSE ESTIMATES FI,W4 INHALED URANIUM MILL +

INO IIf kUINI6Ytt6e Wet

NUREG-OS40 Vit N10 TITLE UST OF DOCUMENTS M ADE PUBUCLY Uran 6um Honshuoride

NURE OV N1 TlN ST OF DOCUMENTS MADE PUBUCLYNUREG 139t DR8 i FC CHI MICAL TOx CITY OF URANIUM HEMA-

HWM MAM M RAuATON MS Deh Nm16 hAVAILABLE NOVt MBER 1 30.1980

NU E CH 5566 EV ALUATKW OF HE ALTH EF F ECTS IN $[OUOY AHA LA LE C BE 1 31 989 FUELS CORPORATION WORKERS f ROM ACCO(NTAL EXPOSURENUREG 0540 V12 NOI: Ti1LE UST OF DOCUMENTS MADE PUDUCly

TO UR ANIUM HE XAFLOORIDEAVAILABLE Januay 1 31,1990NUREG4MO V12 N07 TITLE LtST OF DOCUMENTS MADE PUUUCLY Ura@m W TaMg

Av AILABLE Fetruary 1 28.1990 NUREG/CH 6169 V" 'l2AflON AND TRANSIORT OF URANIUM ATNUREG 0540 V12 Noa TITLE UST OF DOCUMENTS MADE PUBLICLY URANIUM MILL * S DISPOSAL blTES Appkaton Of A Chem.

AV AILABLE March 131,1990NUREGCS40 V12 N04 TITLE UST OF DOCUMt NTS MADE PUBUCLY

cel Transport M

AVAILABLE Apnl 1 30,1990 VICTORLA VodeNUREG-0MO V12 N05. TITLE L'ST OF DOCUMENTS MADE PUDUCLyNUREG/CR 5MS VCTOR'A. A MECHANISTIC MODf L OF RADIONU.i

i AVAILABLE.May 1-31,1990NUREG-090 Vt2 N06 TITLE UST OF COCUMENTS MADE PUDUCLY

CUDE DEHAVOR IN THE RE ACTOR COOLANT SYSTEM UNDERSEVERE ACCIDE NT CONDtilONSAV AILABLE. June 130 1k90

NUREG490 V12 N07. TITLF LIST OF DOCUMENTS MADE PUBLICLY VefveAVAILABLE.Juty 1 31.1990NUREG OS40 V12 NOB TITLE UST OF DOCUMENTS M ADE PUBLICLY NUREG/CP 0111- PROCEE DINGS OF THE SvMFOslVM ON INSERV-

ICE TESitNG OF PuuPS AND VALVES Heid At The Hyatt RegencyAVAILABLE August 1 31.1990

NUREG4MO V12 N09 llTLE UST OF DOCUMENTS MADE PUBUCLY HoteLWashington.DC, August 1415:09

AV AILADLE September 1 30,1990NUREG-0540 V12 N10 TITLE UST OF DOCUMtNTS MADE PUBUCLY

Velve LeakageNUREG/CR4516 UGHT W ATER RE ACTOR PRESSURE ISOLATONAV AILABLE. 0ctoter 131,1990

VALVE PERFORMANCE TESTINGTonic Weste

NUREG/CR 4918 VO4 CONTROL OF W ATER I4rlLTRATON INTOVendor inspechon

NEAR SURFACE MW OtSPOSAL UNITS Prog est Repori On f eed Es. NUREG 0040 V14 Not. UCENSEE CONTR ACTOR AND VENDOR IN.SPECTON ST ATUS REPORT. Oaarierty Report.Janaary March 1990

ponments At A Humed Repon hie.Dettsee Mayand

I

|

I.- - _ . - - _ - , - , . _ - - - , , _ _ _-- _ ,

Suoject index 105

Ventilat6on System Water Reactor BatetyNUREG/CR 5472 A RISK. BASED REVIEW OF INSTRUMENT AIR SYS- NUREG/CP4105 vot: PROCEEDINGS OF THE SEVENT(ENTHTEMS AT NUCLE AR POWER PLANTS

WATER REACTOR SAFETY INFORMATION MEETINGD"**I NUREG/CP4105 V02. PROCEEDINGS OF THE SEVENTEENTH

NU;iG/CR4673 EFFECT OF WELDING CONDITONS ON TRANS WATER RE ACTOR SAFETY INFORMATION MEETING

FORMATION AND PROPERTIES OF HEAT AFFECTED ZONES ON NUREG /CP.0105 V03- PROCECOtNGS OF THE SEVENTEENTHLWR VESSEL STEELS WATER REACTOR SAFETY INFORMATON MEETING-

Vessel integrity West And impactNUREG/CR 5473 INCLUSON OF UNSTABLE DUCTILE TEARING AND NUREG/CR $583 PREDICTION OF CHECK VALVE PERFORMANCE

EXTRAPOLATED CHACK ARREST TOUGHNESS DATA IN PWR AND DEGRADATON IN NUCLEAR POWER PLANT SYSTEMSVESSEL INTEGRITY ASSESSMENT. WEAR AND IMPACT TESTS Frei Report September 1988. April 1990.

Ylbration Monitoring WoldNUREG/CR-5479 CURRENT APPt|C/. TONS OF VIBrtATON MONb

NUREG/CR-5492: INVESTOATONS OF IRRADtATON ANNEAL REIA.TORING AND NEUTRON NOISF ANAth1Sheection And Analysis OfMADtATON (IAR) PROPERTIES TRENDS OF RPV WELDS Phase 2Structwal Degradaten Of Racer Vesaw internais From Operatonaf Final Report.

AprgNUREG/CR $$84 RESULTS OF CRACK ARREST TESTS ON TWO IR.

Y1tal AC Fower RADIATED HOH COPPER WELDSNUREG-1410 LOSS OF VITAL AC POWER AND THE RESIDUAL HEAT #Rc V S STEM Ri MO LOOP OPERATONS AT VOGTLE

G-1425 WELDING AND NONDESTRUCTIVE ELAMINATONISSUES AT SEADROOK NUCLEAR STATON An independent Review

Caste Class Team Repryt.NUREG-1418 CHARACTERISTICS OF LOW LEVEL RADOACTIVE NUREG/CR 3873 EFFECT Or WELDING CONDITONS ON TRANS.

W*STE DISPOSED DURING 1987 THROUGH 1989 FORMATON AND PROPERTIES OF HEAT AFFECTFC ?ONES ONLWR YESSEL STEELSCaste Diepossa

NUREG/CR 4018 VO4 CONTROL OF WATER INFILTRATON INTO Wes tnghoveee

NEAR SURF ACE LLW DISPOSAL UNITS Prtg< ens Report On Feld Ex.NUREG/CR-6280 V01 AGE RELATED DF090ATON OF WESTINGpervnents At A Hurred Regon Site,Bettsville Marylana

HOUSti 480-VOLT CIRCUIT DRF AkEPt'mancal Cycling Of A DS. <

Deme Fe Testy die Broder Test Results.NUREG/CR E229 V02: TMI 2 EPICOR-il RESlN/ LINER INVESTIGATION

SCA EAR 1 9 Anr al A EG/ 97. IN VESSEL ZlRCALOY-OXIDATION / HYDROGEN-1ENERATION DEHAVOR DURING SEVERE ACCOENTS

Cater intittrstionNUREG/CR 4018 V04 CONTROL OF WATER INFILTRATION INTO Zh m

NEAR SURF ACE LLW DISPOSAL UNITS Progress Report On Feld Ex- NUREG/CR-4794 EXPERIMENTAL RESULTS OF CO%ONCRETEpenments At A Hume Region Sate,Bettsvole.Marytard INTERACTONS USING MOLTEN $TFEL WITH ZIPCONIUM.

R1

,

II

.

_ . ._ - _ _ _ _ _ __ __ _ . -_. _ . _ _ _ _ _

NRC Originating Organization Index (Staff Reports)

'This Index lists those NRC organizations that have published staff reports. The index is ar.ranged alphabetically by ma or NRC organizations (e.g., program offices) tnd then by sub. -

- sections of these (e g., dMs ons, branches) where appropriate. Each entry is followed by aNUREG number and title of the report (s). If further information is needed, refer to the main'

citation by NUREG number,

4

ADVISO#1Y COMMITTEE (5) NUREG4540 VII N10 TITLE LIST OF DOCUMENTS MADE PUBLCADVLSORY COMMITTEE ON NUCLEAR WASTE LY AVAll ABLE October 1 31.1989NUREG 1393: THE INCINERATION OF LOW.LEVD, RA00 ACTIVE NUREG 0540 V11 N11: TITLE LIST OF DOCUMENTS MADE PUBLIC-

W AsTE,A Report For The A:tmory Cynmities On Nuclear Weste LY AVAILABLE NovtMBER iM 1989NUREG 1423 Vol: A COMPILATON ! 8 REPORTS OF THE ADVISO- NUREG-0540 V11 N12: TITLE UST OF DOCUMENTS MADE PUBLO

RY COMMITTEE ON NUCLEAR W' JTE July 1988 . lune 1990, LY AVAILABLE. DECEMBER 1 31,1989ACRS ADVISORY COMMITTEE OP 4 ACTOR SAFEGUARDS NUREG 0540 Yt2 N01: TITLE UST OF DOCUMENTS MADE PVOLC

NUREG 1125 V11: A COMPtLATU OF REPORTS OF THE ADVISO- LY AVAILABLE. January 1-31.1990RY COMMITTEE ON REACTOR SAFEGUARDS 1909 Annual NUREG4540 V12 NO2 TITLE UST OF DOCUMENTS MADE PUBLC

LY AVAILABLEfebrwy 1 28. 1990.OTOMIC SAFETY DOARD(S) & PANEL (S) NUREG 0540 V12 NO3. TITLE UST OF DOCUMENTS MADE PUBLCATOMIC SAFETY AND UCENSING '"ARD P+NEL LY AVAILABLE March 1 31,1990

NUREG 1363 V02: ATOMIC SAFE . - AND LICENSING DOAnDNUREG 0540 V12 N04. TITLE UST OF DOCUMENTS MADE vuoLCPANEL ANNUAL REfCRT FISCAL YEAH 1960' LY AVAILABLE Aprt 1 30.1990

OFFICE OF EXECUTIVE DIRECTOR FOR OPERATIONS EDO) - NUREG4540 V12 NOS. TITLE UST OF DOCUMENTS MADE PUBLC

G 41 F VI L AC D t E RESIDUAL N REO OV12 i LE ST OF DOCUMENTS MADE PUDLCAT RE L YS M DURIN3 McLOOP OPERATIONS AT N REG 0 Tl L'E T OF DOCUMENTS MADE PUBLIC-

^v 0LNUREG-1425: WELDING AND NONDESTRUCTIVE EXAMINATON N[EG jiTLE_ ISSUES AT SEABROOK NUCLEAR STATON An indepercent 0V ST OF DOCUMENTS MADE PUBLC

LY AVAILADLE. Aupat 1 31.1990.h NUREG4540 V12 Noe. TITLE UST OF DOCUMENTS MADE PUBLCREG ( 1)

E YO9 NRC T RA O MONITORING N EG O 0 2 0 E S DOCUMENTS MADE PUBUC-^

NUREG 50 Rd1 PU U Hl' G DOCUMENTS IN THE NUREGN '

N a M 1

NUR 7Y N02: NRC TLD DI ECT RADIATION MONITORINGNU 750 C802. INOCXES TO NUCLEAR REGULATORY COMMIS.

NUREG4837 b NWT CT RA' tATIOb TNITORING SiON ISSUANCES. January 1,1980 Through December 31,198501 ONETWORKProgress Report July-September 1990. NUREG 0750 V30101: INDEXES T ) NUCLE AR REGULATORY COM-

REGION 3 (POST 820201) MISSON ISSUANCES.Juty-September 1989-NUREG 1395 DRFT: INDUSTRY PERCEPTIONS OF THE IMPACT OF NUREG4750 V30 602: INDEXES TO NUCLEAR REGULATORY COM-

THE U S. NUCLEAR REGULATORY COMMISSON ON NUCLEAR MISSION ISSUANCES.Ju& December 1969- POWER PLANT ACTIVITIES Draft Report . NUREG-0750 V30 N01: NVCLEAR REGULATORY COMMISSON IS-

OFC OF ENFORCEMENT (POST 870413) SUANCES FOR JULY 1989 Pacca 184- NUREG-0940 V06 N04: ENFORCEMENT ACTONS: SIGNIFICANT AC. NUREG 0750 V30 NO2: NUCLEAR REGULAYORY COMMISSION IS.

'

RESOLVED Owterty Progress Report. October December S Ay[FOR A VT 9 Ps 5g- NUREG 0940 V09 N01: ENFORCEMENT ACTONS: SIGMDCANT AC. SUANCES FCA SEPTEMBER 1989 Pages 167 229

March 1990 NUREG 0750 V30 N04. NUCLEAR REGULATORY COMMISSON IS-NUREG 0940 V09 NO2: ENFORCEMENT ACTIONS:TiONS RESOLVED Cuarterly Progress Report, January NIFICANT AC.SUANCES FOR OCTOBER 1989. Pages 231323SIG

TONS RESOLVED.Ouarterty Progress Report,Agril. June 1990. NUREG-0750 V30 NOS: NUCLEAR REGULATORY COMM:S$10N IS.NUREG-0940 V09 NO3: ENFORCEMENT ACTONS: SIGNIFICANT AC. SUANCES FOR NOVEMBER 1989 Pages 325 708

TIONS RESOLVED.Ouarteriy Prograd Report. July-September 1990. NUREGM50 V30 N06' NUCdAR REGULATORY COMM6SSION IS-OFC OF PERSONNEL (POST 870413) - SUANCES FOR DECEMBER 1989 Psges 700 811.

NUREG4325 R13: U.S. NUCLEAR REGULATORY CCMMISSON NUHEG-0750 V31101: INDEXES TO NUCLEAR REGULATORY COM-FUNCTIONAL ORGANIZATION CHARTS Apnl 1.1990 M'SSON ISSUANCES. January March 1990.

NUREG-0325 R14: U.S. NUCLEAR REGULATORY OF*%SSION NUREG-0750 V31102. INDEXES TO NUCLEAR REGULATORY COM-FUNCTONAL ORGANIZATION CHARTS. August 15 * a MISSION ISSUANCES. January June 1900

NUREG4750 V31 N01: NUCAEAR REGULATORY COMMISSION IS--EDO OFFICE OF A!WINISTRAT10N (PRE $70413 & P( m ,e) SUANCES FOR JANUARY 1990. Pages 1130. -

OFFICE OF ADMINIS(RATON (POST 390205) NUREG-0750 V31 NO2: NUCLEAR REGULATORY COMMISStON IS-.NUREG-1145 V06. U S. - NUCLEAR REGULATOR) COMMISSION SUANCES FOR FEBRUARY 1990. Pages 131 195.

1989 ANNUAL REPORT. NUREG 0750 V31 NO3: NUCLEAR REGULATORY COMMISSON IS.DIVISION OF FREEDOM OF INFORMATION & PUBUCATIONS SERV- SUANCES FOR MARCH 1990 Pagen 197 332,

ICES (POST 890205 ~ NUREG-0750 V31 N04: NUCLEAR REGULATORY COMMISSION IS-NUREG4304 V14 N04. REGULATORY AND TECHNICAL RhPORTS SUANCES FOR APRll 1990.Pages 333-370

(ABSTRACT INDEX JOURNAL). AnnualCompilation For 1989 NUREG-0750 "31 N05: NUCLEAR REGULATORY COMMISSON IS-NUREG-0304 V15 NOI: REGULATORY AND TECmCAL REFORTS SUANCES FOR MAY 1990.Pages 371481.

(ABSTRACT INDEX JOURNAL). Compelation For Frst Quarter NUREG 0750 V31 N06 NUCLEAR HEGULATORY COMMISSION IS-1990, January-Marctt SUANCES FOR JUNE 1990.Pages 483-004

NUREG4304 V15 NO2: REGULATORY AND TECHNICAL REPORTS NURFG-0750 V32101. INDEXES TO NUCLEAR REGULATORY COM.(ABSTRACT INDEX JOURNAL). Complation For Second Quarter MibSON ISSUANCES. July September 19901990 April-June. NUREG4750 V32 N01 NWLEAR REGULATORY COMMISSON IS-

NUREG4104 V15 NO3. REGULATORY AND TECHNICAL REPORTS SUANCES FOR JULY 1900 Peges 155.(ABSTRACT INDEX JOURNAL). Complation For - Third Quarter NUREG4750 V32 NO2 NUCLEAR REGULATORY COMMISSION IS-1990. July-September. SUANCES FOR AUGUST 1990. Pages 58-128

107

.

- . . - - .- - . _- - - - . - -- -- - .-

104 NRC Originating Organization Index (Staff Reports)

NUREG-C750 V32 NO3 NUCLEAR REQULATORY COMMISSION 15 OfVISION OF INW' TRIAL & MEDICAL NUCLEAR SAFETY (POSTSUANCES FOR SEPTEMBER 1990 Pa9es 129-199. 070729)

NUREG 0760 V32 N04 NUCLEAR FIEGULATORY COMMISSON IS- NUREG 13@. ENvA9UTAL ASSESSMENT OF THE THERMALSUANCES FOn OCTOBER 1990. Pa9es 201431; NEUIRON .'CTIVITATON EOLOSIVE DETECTON SYSTEM FOR

. NUREG4936 VL8 N04: NRC REGULATORY AGENDA. Quarterly CONCOURSE E 'T U S AltPORTSReport. October.Decernber 1989. DVISION OF HIGH-LEVEL iMe MANAGEMENT (POST 870414

. NUREG4936 V09 Not: NRC REGULATORY AGENDAOuarterly NUREG/CR4638. TECHNICll CONSOERATIONS FOR EVALUAT.ReportJanuary-March 1990, ING BUBSTANTIALLY COMPLETE CONTAINMENT OF HIGH-

NURLG4936 VOG NO2; NRC REQULATORY AGENDA. Quarterly LEVEL WASTE WTTHIN THE WASTE PACKAGE.ReportAprEJune 1990. DIVISON OF LOW LEVEL WASTE MANAGEMENT & DECOMMISSION-

~ NUREGM36 V09 NO3: NRC REGULATORY AGENDA.Ouarterly ING (POST 870413)Report, July September 1990. NUREG-1383: GUCANCE ON THE APPUCATON OF OVAUTY AS-

SURANCE FOR CHARACTERIZING A LOW LEVEL RADCACTIVE -EDO. OFFICE OF THE CONTROLLER (PRE 820410 & POST 800206) WASTE DISPOSAL SITE nnel Report.

DVISION OF BUDGET & ANALYSIS (POST 890205) NUREG-1418 CHARACTERISTOS OF LOW LEVEL RADIOACTIVE' NUREG 1100 V06. BUDGET ESTIMATES hscal Year 1991. WASTE DISPOSED DURING 1987 THROUGH 1989.

NUREG 1350 V02 NUCLEAR REGULATORY COMMISSION INFOR -MATON DOEST.1990 Editsort U.S. NUCLEAR R$GULATORY COMMIS8CN

OFFICE OF THE GENERAL COUNSEL (POST 860701)EDO. OFFICE FOR ANALYSl8 4 EVALUATION OF OPERATIONAL NUREG4386 DOS 805: UNITED STATES NUCLEAR REGULATORY

DATA COMMISSON STAFF PRACTICE AND PROCEDUREOFFICE FOR ANALYSIS & EVALUATION OF OPERATONAL DATA, DI- DIGEST.Cornmession. Appeat Board And Ucensing Board

RECTOR Doctosons J 1972 September 1989NUREQ4000 V12 NO3. REPORT TO CONGRESS ON ABNORMAL NVREG4386 5 A06 UNITED STATES NUCLEAR REGULATORY

OCCURRENCES. July September 1989 COMMISSON STAFF PRACTICE AND PROCEDURENUREG-0000 V12 N04. REFORT TO CONGRESS ON ABNORMAL DIGEST.Comrwasort Appeal Board Ar1 Ucensang Board

OCCURRENCES. October Decemt.or 1989. Decmona Jur1972 December 1989NUREG4000 V13 N01: REPORT TO CONGRESS ON ABNORMAL NUREQ4386 wS R07; UNITED STATES NUCLEAR REGULATORY

OCCURRENCES. January-March 1990. COMMISSON STAFF- PRACTICE AND PROCEDURENUREG0090 V13 NO2: REPORT TO CONGRESS ON ABNORMAL DIGEST.Commiteen, Appeal Board And Licenssng Board

OCCURRENCES Apr$ June 1990 Decesons 1972. March 1990NUREG 1272 V04 NO1: OFFCE FOR ANALYSIS AND EVALUATON NUREG 0386 5 A06 UNITED STATES NUCLEAR REGULATORY

OF OPERATIONAL DATA 1989 ANNUAL REPORT. Power Reactors. COMM:SSION STAFF PRACTCE AND PROCEDURENUREG 1272 V04 NO2 OFFCE FOR ANALYSIS AND EVALUATON DOEST.Cornrmswon. Appeal Board And Ucenssng Board

OF OPERATIONAL DATA 1989 ANNUAL REPORT.Nonreactors. OmessaansJuly 1972. June 1990.NUREG-1394. EMERGENCY RESPONSE DATA SYSTEM (ERDS) IM- OFFICE OF INSPECTOR GENERAL (POST 890417)

PLEMiiNTATOtt NUREG-1415 YO3 Nol: OFFICE OF THE INSPECTORNUMEG 1409: BACKFlTTING GuiDEUNES. GENERAL Semiannual Repon AprLSeptember 1990.

NRC4NO DETAMO AmuATON GWENOFFICE OF GOVERNMENTAL & PUSUC AFF AIRS (POST 870413) NVREG-1405: INAOVERTENT SHIPMENT OF A RADOGRAPHic

OFFICE OF GOVERNMENTAL & PUBUC AFFAIRS (POST $70413) SOURCE FROM KOREA TO AMERSHAMNUREG 1392- LEAKAGE OF AN IRRADIATOR SOURCE THE JUNE CORPORA TION,BURUNG T ON,MASSACHUSETT S

1988 QEORGIA RSI INCOENT. NUREG/CR 5637: GENERIC RISK INSIGHT!. FOR WESTINGHOUSEAND COMBUSTON ENGINLERWG PRESSURIZED WATER REAC-

EDO. OFFICE OF INFORMATON RESOURCES MANAGEMENT & ARM TORS.(POST 8811001

' DVISION OF COMPUTER & . TELECOMMUNICATIONS SERVICES EDO. OFFICE OF NUCLEAR REGULATORY RESEARCH T8t0436)OFFICE OF NUCLEAR REGULATORY RESEARCH 860720)(POST 800235) NUREG-1266 V04. NRC 6AFETY RESEARCH IN PPORT OF REG-- NUREG4020 V13 N11: UCENSED OPERATING REACTORS STATUS

NU EG 2 3 . E OP RAT EC70RS TATUS N8 91 DR C: CHEMICAL TOxlCITY OF URANIUM HEXA-FLUORIDE RELATED TO RADATON DOSES. Draft Report ForSUMMARY REPORT.Deta As Of November 30,1989 (Gra Book 1)

NUREG 0020 V14 N01: UCENSED OPERATING REACTOf(S STATUSCommentNUREG 1411: RESPONSE TO PUBUC COMMENTS RESULTINGSUMMARY REPORT. Data As Of December 31,1989 (Gray Book ()

NUREG-0020 V14 NO2: LICENSED OPERATING REACTORS STATUS FROM THE PUBLO WORKSHOP ON NUCLEAR POWER PLANT Ll-

SUMMARY RELORT. Data As Of January 31.1990.(Gray Book 1) NU E 4 PE lAL COMMITTEE REVIEW OF THE NUCLEARNUREG4020 Q NO3. LCENSED OPERATING REACTORS STATUS REGULATORY COMMISSON'S SEVERE ACCOENT - RISKSSUMMARY FsEr0RT. Data As Of February 28,1990.(Gray Book 1)

REPORT (NUREG 1150)NUREG/CP 0113 TRANSACTIONS OF THE EIGHTEENTH WATEREDO OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEQUARDS

OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS REACTOR SAFETY INFORMATON MEETING.NURE34430 V09 - NO2; UCENSED FUEL FAC4UTY STATUS NE A N 04 3

RREPORT inventory Dfterence Data. July 1988 . June 1989.(Gray LISTINGS AND SUMMARIES OF REPORTS ISSUED THROUGH

.NU R-4735 V06: EVALUATION AND COMPtLATION OF DOE NUREG 882: OVAUFICATON PROCESS FOR ULTRASONICWASTE PACKAGE TEST DATA Bannual Report August 1988TESTING IN NUCLEAR INSERVICE INSPECTON APPUCATONS.

#DVI ON F A EGUARDS & TRANSPORTATION (POST 870.a3) NUREG CR 918 C OL OF WATER INFILTRATON INTO

NUREG 0383 V01 R13. DIRECTORY OF CERTIFICATES OF COMPU' NEAR SURFACE LLW DISPOSAL UNITS. Progress Report On FieldANCE FOR RADIOACTIVE MATERIALS PACKAGES Report Of NRC Expenments At A Humid Region Site.Beltsville Marytand.Approved Packages. DIVISION OF REGULATORY APPUCATIONS (POST 870413)

NUREG-0383 V02 R13; DIRECTORY OF CERTIFICATES OF COMPU. NUREG-0713 V09: OCCUPATIONAL RADIATON EXPOSURE ATANCE FOR RADOACTIVE MATERIALS PACKAGES.Certifcates Of COMMERCIAL NUCLEAR POWER REACTORS AND OTHER FA.Comphance- CluTIES 1967 Twentietn Annual Report

NUREG4383 YO3 R10: DRECTORY OF CERTIFICATER OF COMPU- NUREG-0933 S11: A PRORITIZATION OF GENERIC SAFETYANCE FOR RADOACTIVE MATERIALS PACKAGES RepM Of N9C ISSUES.Approved Quality Assurance Programs For Radioactrve Matenals NUREG 1333. MAINTENANCE APPROACHES AND PRACTICES INPackages. SELECTED FOREIGN NUCLEAR POWER PROGRAMS AND

NUREG 0525 R18: SAFEGUARDS SUMMARY EVENT UST (SSEL). OTHER U.S TNDUSTRIES REVIEW AND LESSONS LEARNED.NUREG-1404. UCENSEE USE OF TACTICAL EXERCISE RESULTS. DVISON OF SAFETY ISSUE REDLUTON (POST 880717)HUREG/CP 010h I'ROCEEDINGS OF THE UNITED STATES NUCLE- NUREG 1318. TECHNICAL FIN 9tNGS AND PEGULATORY ANALYSIS

AR RESULATORY COMMISS!ON SECURITY TRAINING RELATED TO GENERC ISSUE 70 Evaluation Of Power OperatedSYMPOSIUM. Meeting The Challeng>Flrearms And Explosives Rec. Rehet Valve And Block Valve Rehatahty in PWR Nuclear Powerognition And Detection. Plants.

. . , _ . . _ . _ -. _. , , , . . _

.-. - - - - ~

NRC Orl0lnating Organization Index (Staff Reports) 109

NUREG 1330 RESOLUTION OF f dNERO SAFETY ISSUE 29 BOLT. COMANCHE PEAK PROJECT DIVISION (890101900602)(NG DEGRADATION OR FAllt RE IN NUCLEAR POWER PLANTS. NUREG4797 S22. SAFETY EVALUATON REPORT RELATED TP

NUREG 1382 DAFT FC: REGUL ATORY ANALYSIS FOR PROPOSED THE OPERATON OF COMANCHE PEAK STEAM ELECTR 'RULE ON NUCLEAR POWE 4 PLANT LICENSE RENEWALDraN STATON. UNITS 1 AND 2 Docket Nos 50 445 And 50446(TesesRepo't For Comment. Utihnes Electric Company.et at )

NUREG 1372: REGULATORY WALYSIS FOR THE RESOLUTION OF NUREG 0797 623. SAFETY EVALUATON REPORT RELATED TOGENERO thSUE C 8, %N STE AM ISOLATON VALVE LE AKAGE THE OPERATON OF COMANCHE PEAK STEAM ELECTRO

NUREG 9 i F ENVIRONMENTAL ASSESSMENT FOR PRO. ut tPOSED ROLE ON NUCLEAR POWER PLANT UCENSE NUREG 0797 S24 SAFETY EVALUATION REPORT RELATED TORENEWALDrafi Report For Comn.onL THE OPERATON OF COMANCHE PEAK STEAM ELECTRO STA.

NUREG 1407 DRFT FC: PROCEDURAL AND SUBMITTAL QUOANCE TON UNITS 1 AND 2IWhat Ncs S0445 And 50-448(Teias UWFOR !NDIYl'10AL PLANT EXAMINATON OF EXTERNAL EVENTS(IPEEE) FOR SEVERE ACCIDENT VULNERABlUTIES Draft Report NU 3 'SPECIFICATONS, COMANCHE PEAK

STEAM ELECTRIC STATON, UNIT 1. Docket No 50-445,AppendaDIVISION Y TEMS RESEARCH (POST 880717)

NUREG 1150 V01: SEVERE ACC4 DENT RISKS AN ASSESSMENT A" To Leense No. NPF 28FOR FIVE U S. NUCLEAR POWER PLANTS Fina! Summary Report NUREG 1399 TECHNICAL SPECIFICATIONS. COMANCHE PEAK

NUREG 1150 V02: SEVERE ACCIDENT RISKS AN ASSESSMENT STEAM ELECTRIC ST ATON.UNti 1. Docket No 50 445, AppendsFOR FIVE U S. NUCLEAR POWER PLANTS.Appensees A,B, And "A" To Loenee NPF 87.(f enas Utilibes Electnc)C Friel Report TVA PROJECTS DIV: SON (890101900602)

PROBABluSTIC RISK ANALYSIS BRANCH NUREG 1232 V04- SAFLTY EVALUATON REPORT ON TENNESSEEHUREG/CR-5111: INTEGRATED RELIADIUTY AND RISK ANALYSl$ VALLEY AUTHORITY. WATTS BAR NUCLEAR PERF0FiMANCE

SYSTEM (tR5LAS) VERSION 2 0 USER'S GUOE. PLANNUREG/CR 5460- A CAUSE OEFENSE APPROACH TO THE UNDER- OfVISION OF ENGINEERING TECHNOLOGY (POST 890827)

STANDING AND ANALYS:S OF COMMON CAUSE FAlLURES. NUREG 1352: ACTON PLANS FOR MOTOR-OPERATED VALVESAND CHECK VALVES

EDO OFFICE OF NUCLEAR REACTOR stEOULATION (POST 4/28/80)TNUREG-1402: CLOSEOUT OF NRC DULLETIN 88 05.NONCONFORM-OFFICE OF NUCLEAR RtACTOR RLGULATION, DIRECTOR (POS ING MATERLALS SUPPLIED BY PIPING SUPPUE S.lNC..AT

870410 FOLSOM,NEW JERSEY.AND WEST JERSEY MANUF ACTURINGNUREG4800 03 6.1 R2: STANDARD REVIEW PLAN FOR THE COMPANY At WILLIAMSTOWN.NEW JERSEYREVIEW OF SAFETY ANALYSIS REPORTS FOR NUCLEAR OtytSON OF SY9TEMS TECHNOLOGY (POST 89082F)

POWER PLANTS LWR EMort Revisen 2 To SRP Sechon NUREG 1417; SAFETY EVALUATON REPORT RELATED TO HY.3.8.1, Plant Deep For i rotection Agavsst Postulated Ppng Failures DROGEN CONTROL OWNERS GROUP ASSESSMENT OF MARK

N DF ~STANDAFID REVIEW PLAN FOR THE REA T R YT DRANCHREVIEW UF UCENSE RENEWAL APPUCATONS FOR NUCLEAR NUREG/CR-3950 V00. FUEL PERFORMANCE ANNUAL REPORTPOWER PLANTS Dra't Rep.or-t For Comment FOR 1988

NUREG 1412 DAFT FC: FUUNDATION FOR THE ADEOUACY.OF O(VtSION OF REACTOR INSPECTON & SAFEGUARDS (POS TTHE UCENSING DASES.A Supplement To The Statement Of Con'870411)sidersbone For The Proposed Rule On Nuclear Pm Piant Ocense NUREG-0040 V13 N04: LICENSFE CONTRACTOR AND VENDOR IN-

0% SPECTON ST ATUS REPORT. Quarterly ReportOctober DecomtorDIVI ION E ACTOR I S S

NUREG-0847 S05 SAFETY EVALUATI REPORT'RELATED TO 1980 (WNte Dook)NUREG4040 V14 N01. UCENSEE CONTRACTOR AND VENDOR IN.THE OPERATON OF WATTS BAR NUCLEAR PLANT, UNITS 1 AND

SPECTON STATUS REPORT. Quanerty Report. January March2 Docket Nos. 50-390 And 50 391.(Tennessee Vetley Autnon iNUREG-0896 SO9 SAFETY EVALUATION REPORT RELA D TO 1980THE OPERATION OF SEABROOK STATION, UNITS 1 AND NUREG 0040 V14 NO2. UCENSEE CONTRACTOR AND VENDOR IN-2. Docket Nos. STN 50 443 And STNM444 (Pubhc Servtce Compe. SPECTON STATUS REPORT' Ouartrty Report.Apr0 June

Of New Ha 1990(WNte Doon)NU EG-1386- Tbtwe L SPECIFICATONS FOR SEADROOK STA.NUREG 0040 V14 NO3 UCENSEE CONTRACTOR AND VENDOR IN-HI

TON, UNIT 1. Appendr "A" To bconso No. NPF-86 bPECTION STATUS REPORT. Quarterty ReportJuly-SeptemberDIVISON O& REACTOR PROJECTS ItVV,V & SPECIAL PROJECTS 1990(WNte Book)

(870411 9012 DIVISON OF UCENSEE PERFORMANCE & QUAUTY EVALUATONNUREG 1390 SAFETY EVALUATION REPORT RELATED TO THE (POST 870411)

RENEWAL OF THE OPERATING UCENSE FOR THE TRIGA NUREG 0600 11.3 ROO STANDARO REVIEW PLAN FOR THETRAINING AND RESEARCH REACTOR AT THE UNIVERSITY OF REVIEW OF SAFETY ANALYSIS REPORTS FOR NUCLEARARIZONA Docket No 50-113 (Unsversdy of Anzonal POWER PLANTS LWR Ecston. Revision 0 To SRP Section 17.3,

NUREG 1403- SAFETY FVALUATION REPORT RELATED TO THE "Ouauty Assuranco Program Desenphon?FULL TERM OPERATING LICENSE FOR ORESf*N NUCLEAR NUREG 1021 R06 OPERATOR UCENSING EXAMINER STAND-POWER STATON. UNIT 2. Docket No 54237 Wommonwealth ARDS.Edison Company) NUHEG 1214 ROS HISTORICAL DATA SUMMARY OF THE SYSTEM-

NUREG-1424 SAFETY EVALUATION REPORT RELATED TO THE ATIC ASSESSMENT OF UCENSEE PERFORMANCE.FULL. TERM OPERATING UCENSE FOR PALISADES NUCLEAR NUREG-1214 A06 HISTOROAL DATA SUMMARY OF THE SYSTEM-PLANT Do(;ket No 54255 (Consumers Power Company) ATO ASSESSMENT OF UCENSEE PERFORMANCE.

b s,em4 4_6.a a,--,,2- ~& -- A A-+ -sM L --e + .mm-s4 -- aaer.m--vman-4-. &-as a- a w m-..a-+a---,aw- w

i

.

.- , . , - -e, . .,. - -..

- .. . .. _ -- . - . ..

NRC Originating Chianization Index (International Agreements)

This index lists those NRC organizations that have published international agreement re.ports. The index is arranged alphabetically by major NRC organizations (e.g., program of -fices) and then t,y subsections of these (e.g., divisions, branches) where appropriate. Eachentry is followed by a NUREG number and title of the report (s). If further information isneeded, refer to the main citation by NUREG number.

EDO. OFFICE OF NUN EAR REQULATORY RESEARCH POST 820405) NUREG/lA4023 V02: ASSESSMENT 0012 JPF1/ MODI VERSION' ^"O 1A 1 TRA PF 1 .T LCULA S OF WN EX RIME S F

N REGIA 40 5/ 2 i ATK)NS OF OECO LOFT NUREG/LA 002 ASSESSMENT OF RELAPS/ MOO 2 COE USINGTEST LP-S841. LOSS OF OFFSITE POWER TRANSIENT OAT' OF KNU #1

N E /iA 00 RELAP5/ MOO 2 CALCULATK)NS OF OECD LOFT

NUREQ/lA4018 RELAPS/ MOO 2 ASSESSMENT.OECO LOFT SMALL 36 05 AGAINST LOFT SMALL DREAK EXPERIMENT L3 7.BREAK EXPERIMENT LP SB-03. NUREG/tA4032- ASSESSMENT OF RELAP5/ MOO 2 CYCLE 36,04

NUREC/lA4019: TRAC.PF1/ MODI POST. TEST CALCULATIONS OF USING LOFT LARGE BREAK EXPERIMENT L2-5.THE OECO LOFT EXPER| MENT LP SB-2. NUREO/IA 0033 ASSESSMENT OF RELAPS/ MOO 2 CYCLE 36.04

NUREG/lA-0021: RELAP5/ MOO 2 CALCULATIONS OF OECO LOFT AGAINST LOFT SMALL BREAK EXPERIMENT L34

NU /lA 2 TRAC PFt! MOO 1 POST. TEST CALCULATIONS OF /$UR ASSES ETS YO 5, MOO 2 CYCLE

.. NU EG IA4023 YO1 A E RAC-PF1/ MOO 1 VER$10N 36,04 BASEO ON PRESSURIZER SAFETY AND REUEF VALVE

14.3 USING SEPARATE EFFECTS CRITICAL FLOW ANO BLOW- TESTS.

DOWN EXPERIMENTS volume 1. Text And Tables.

111

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| NRC Contract Sponsor index (Contractor Reports)

This index lists the NRC organizations that sponsored the contractor reports listed in thiscompilation. It is arranged alphabetically by major NRC organization (e.g., program offi,ce)and then by subsectior s of these (e.g., divisions) where appropriate. The sponsor organiza-tion is followed by the NUREG/CR number and title of the report (s) :)reaared by that organi-zation, if furtner information is needed, refer to the main citation by t1e NUREG/CR number.

EDO OFFICE FOR ANALYSIS & EVALUATION OF OPERATIONAL NUREG/CR 4735 V06 EVALUATON AND COMPILATON OF DOEDATA WASTE PACAAGE TEST DAT A. itannual Report Ad@st 1968 -

OFFICE FOR ANALYSIS & EVALVATON OF OPERATONAL DATA. Di- January 1989RLCTOR

NUREG/CR 5211. UNCERT AINTIES ASSOC 9 TED WITH POdORM-NUREG/C42000 V00N17 LICENSEE EVENT REPORT (LER)ANCE ASSESSMENT OF HIG4 LEVEL RADCACTIVL WAS TE

NU EG/C 00 V09 1 L LN E ENT REPORT (LER) REPOSITORO A Samaw RemCOVPILATON For Month Of Janua 1HO NUREG/CR 5256 COMPONENTS OF AN OVERALL PERFORMANCE

NUREG/CR-2000 V00 N2. LOEN EE EVENT REPORT (LER) ASSESSMENT METHODOLOGY

COMPILATON For Monn Of Fetevan 1990 NUREG/CR 5393 A REVIEW OF 1ECHNIQUES FOR PROPAGATINGNUREG/CR 2000 V00 M. UCENSE E EVENT REPORT (LER) DATA AND PARAME~TER UNCERT AINTIES IN HIGH LEVEL radio.

COMPIL ATON For Month C1 March 1990. ACTIVE W ASTE REPO$tTORY PERFORMANCE ASSESSMENTNUREGIC42000 V09 N4. UCENSEE EVENT REPORf (LER) MODELS

COMPtLATON For Month Of Apnl 1990NUREG/CR 5398. TECHNICAL BASIS FOR REVIEW OF HIGntEVELNUREG/CR 2000 V09 Nt: LICENSEE EVENT REPORT (LER) W ASTE REPOSITORY MODEUNGCOMPILAT ON For Month Of May 1990NVREG/C454tt: EUCITATON & USE OF EXPERT JUDGMENT INNUREG/C42000 YO9 N6 LICENSLE EVENT REPORT (LER)

COMPtLATON For Month Of June 1990. PERFORMANCE ASSESSMENT FOR HIGH40 VEL RADCACitVE^8NUR 20L V 7 UCENS E EVENT REPORT (LER)

RE CAGROUND INFORMATION FOR THE DE-NUREG/CR 2000 V00 NO. UCENSEE EVENT REPORT (LE R) VELOPMENT OF A LOW-LEVEL WASTE PERFORMANCE ASSESS-

COMPILATION For Month Of August 1990 MENT METHODOLOGY Computer Code implementation And As-NUREG/CR 2000 W9 N9 UCENSEE EVENT REPORT (LER) sessrnent

COMPILATON For Mor th of Sogtember 1990 NURLG/C45521. USE OF PERFORMANCE ASSESSMENT IN AS-NUREGICR2NO V09N10- UCLNSEE EVENT REPORT (LER) SESSING COMPUANCE WITH THE CONTAINMENT REQUIRE.

COMPILATON f or Month Of Octooer 1990 MENTS IN 40 CFR PART 191NUREG/C42000 YO9N11: UCENSEE EVENT REPORT (LER) NUREG/CR 5638 TECHN CAL CONSOERATONS FOR EVALUAT-COMPtLATON For Month of November 1991 ING SUBSTANTIALLY COMPLETE CONTAINMENT Of HIG4N /R 67 VO HFCUR ST TENTIAL SEVERE LEVEL WASTE WTTHIN THE W ASTE PACAAGE-

CORE DAMAGE ACCOENTS 19e8 A STATUS REPORT. Mon DIVISON OF LOW 4EVEL WASTE MANAGEMENT & DECOMMISSON.

NUR CR PRECURSORS TO POTENilAL SEVERE NA 5169 Blu2ATON AND TRANSPORT OF UHANIUMCORE DAMAGE ACCOENTS 1968 A ST ATUS REPORT,Appenduies AT URAN:UM MILL T AluNGS OtSPOSAL SITES Apphcation Of AB And C. Chomcal Transport Mode

NUREG/CR 4674 VII: "RECURSORS TO POTENTIAL SEVERE NUREG/CR-5381. ECONOMIC RISK OF CONTAMINATION CLE ANUPCORE DAMAGE ACCOENTS,1969 A STATUS REPORT un COSTS RESULTING FROM LARGE NONREACTOR NUCLEAR MA.Report And Apperox A. TERIAL UCENSEE OPERATIONS

NUREG/CR 4674 V12: PRECURSORS TO POTENTIAL SEVERE NUREG/CR-5517. IMPACTSORC, VERSION 2 0 Progf am User'sCORE DAMAGE ACCOENTS 1969 A STATUS REPORT.Aptendices ManualB Ard C. NUREG/C45532. A PERFORMANCE ASSESSMENT METHODOLO.

GY FOR LOW 4EVEL W ASTE FACluTIESEDO. OFFICE OF INFORMAT'ON RESOURCES MANAGEMENT & ARM NUREG/CR 5547, APPUCATlON OF SURFACE COMPLEAATION

b*" ^ " * * *DI OMPUTER 1 T ELECOMMUN'CATONS SERVICESi p,

N /CR 2 V09 POPULATION DOSE COMWTMENTS DUE TO NUREG/CR 5548 REVIEW OF GEOCHEM CAL PROCESSES ANDRADIOAC11VE RElf%SES FROM NUCLEAR POWER PLANT SITES CODES FOR ASSESSMENT OF RADIONUCLOE MiGRAflON PO-'N 1987. TENTIAL AT COMMERCIAL LLW SITES i

EDC . OFFICE OF NUCLE AR MATERIAL SAFETY & SAFECUARDS EDO OFFIC1 OF NUCLEAR REGULATORY RESEARCH (POST 820405)OtV?SION OF SAFFGUARDS & TRANSPORTATON (POST 870413) OFFICE OF NUCLEAR REGULATORY RESEARCH (POST B60720)

NUREG/C45366 HTAS2; A THREE D!MENSiCNAL TRANSICITT NUREG/CR-2331 V00 N3 SAFETY RESEARCH PROGRAMS SPON.SHIPPING CASW ANALVSIS TOOL. SORED BY OF FICE OF NUCLEAR RE GULATORY

NUREG/C45399 SURVEY OF STATE AND TAIBAL EMERGENCY RESE ARCH Progress heport.Juiv-September 1989RESOSE CAPAMITIES FOR RADIOLOGICAL TRANSPO9f A+ NUREG/CR4331 V00 N4 SAFETY RESEARCH PROGRAMS SPON-TON INCIDENTS SORED BY OFFICE OF NUCLEAR REGULATORYNUREG/C45468 QADS A MULTOIMENSIONAL POINT KERNEL RESEARCH October December 1989

' 'E"V 1AL & MEDICAL NUCLEAR SAFETY (POST WF SYTdM## #NU G 5566 EVALUATION OF HEALTH EFFECTS IN SE.

OOOYAH FUELS CORPORATON WORKERS FROM ACCOENTAL PROGRAMMATIC PERFORMANCE IND4CATORS ASSOCIATEDEXPOSURE TO URANIUM HEXAFLUORCE WITH MAINTENANCE AT NUCLEAR POWER PLANTS Main Report

NUREG/C45574 DETERMiNATON OF THE CHEMICAL FORM OF NUREG/CR-5436 V02 THE DEVELOPMENT AND EVALUATION OFTRTTIUM IN SELF4UMWOUS SIGNS. PROGRAMVATO PERFORMANCE INDICATORS ASSOCIATED

DIVISON OF HIGH-LEVFL WASTE MANAGEM7NT (POST 8704t3) WITH MAINTENANCE AT NUCLEAR POWER PLANTS AppendcesNUREG/CR 1667; FLSK METHOOOLOGY FOR GEOLOGIC DISPOS- NUREG/C45475- MODEL FEASIDIUTY STUDY OF RADIOACTIVE

AL OF RADtOACTIVE W ASTE. Scenano Sem procedure PATHWAYS FROM ATMOSPHERE TO SURFACE WATER

113

_ . .. .

. .. - ____ - ___________ - _____ ______ _- __- ____ _ - - _ . . - _ - - . .-- .--- --

114 NRC Contract Sponsor index

Olvl3 TON OF ENGINEERING (POST B70413) NURE G /CR43 td V03 U'E ASSESSMENT PROCEDURES FORNUREG/C43146 V00 GEOPHYSICAL INVESilGATONS OF THE MAJOR LWR COMPONENTS Cast Statnissa Steel Components

WESTERN OHIO INDLANA REGION Annual ReportOctober 1960 - NUREG/CR$369 THE SEISMIC CATEGORY I STRUCTURES PRO.September 1989 GRAM RESULTS FOR FY 1987.

NUREG/CR-3444 V07; THE IMPACT OF LWR DECONTAMINATIONS NUREG/CH-6385: INITIAL ASSESSMENT OF THE MECHANISMSON SOLIDIFICATION. WASTE DISPOSAL AND ASSOCIATED 00 AND S GNIFICANCE OF LOW TEMPERATURE EMDRITTLEMENTCUPATIONAL EXPOSURE OF CAST STAINLESS ST!ELS IN LWR SYSTEMS

NUREG/CR-3873. EFf ECT OF WELDING CONDf7DNS ON TRANS' NUREG/CR 6386 BASIS FOR $NUDBER AGING RESE ARCH NU-FORMATION AND PROPERflES OF HEAT.AFFECTED ZONES ON CLEAR PLANT AGING RESEARCH PROGRAM

NUREG/CR4404 V01: AUXILIARY FEEDWATER SYS1EM AGINGN G 4219 Y 2: HEAVY SECTON STEEL TECHNOLOGY

NUREG/CR 5405. ANALYCIS OF SHELL RUPTURE F AILURE DUENUF E / 4 9 V08 R EEA NA DE) RE- TO HYPOTHETICAL ELEVATED TEMPERATURE PRESSURIZA-

LIADILITY FOR INSEfWICE INSPECTION OF LIGHT WATER TION OF THE SEQUOY AH UNIT 1 STEEL CONT AINMENT DUILD-RE ACTORS Semaannual ReportOctoter 1981. March 1988ING-

NUREG/CR-4469 V09- NONDESTRUCilVE EXAMINATION (NDE) RE- NUREG/CR4409. NFUTRON EXPOSURE PARAMETERS FOR THELIABILITY FOR INSERVICE INSPECTION . 0F LIGHT WATER MET ALLURGtCAL TEST SPECIMENS IN THE SWTH HEAVY SEC-RE ACTORS Sernannual ReportAprlbSeptember 1984NUREG/CR4469 V;0: NONDESTRUCTIVE EAAMlvilON (NDE) RE. TION STEEL (RRADIATION SERIES

LIABILITY FOR LNSERVICE INSPECTION OF LIGHT WATER NUREG/CR-6419- AGING ASSESSMENT OF INS 1RUMENT AIR SYS-REACTORS Semiannuai ReportOctober 1988 March 1989 TEMS IN NUCLEAR POWER PLANTS.

NUREG/CR 4564 V00: SCANS (SHIPPING CASK ANALYSIS NUREG/CR.6435' ENVIRONMENTAL EFFECTS ON CORROSION IN

SYSTEMM MICROCOMPUTER BASED ANALYSIS SYSTEM FOR THE TUFF REPOSITORY.SHIPPING CASK DESIGN REVIEW. Volume 6. Theory Menvai Bock, NUREGrCR-5448' AGIN3 EV ALVATON OF CLASS 18. BATTERIES.

SEISMIC TESTINGknqof Cncular Cyhnancat ShetisNURLG/CR4554 VOL SCANS (SritPPING CASK ANALYSIS NUREG/C4544 DiTERMINATON OF THE NEUTRON AND

SYSTEM) A MICROCOMPUTER BASED ANALYSIS SYSTEM FOR GAMMA FLUX DISTRIBUTION IN THE PRESSURE VESSEL ANDSHIPPING CASK DESIGN REVIEW.Votume 7: Theory Manual Punc. CAVITY OF A BOILILNG WATER REACTORture Of Shippeng Casks NUREG/CR 5450- HIGH TEMPERATURE CRACK ARREST TESTS

NUREG/CR-4659 Vol SEISMIC FRAGILITY OF NUCLEAR POWEft USING 162-MM-THICK btiN WiDC PLATES OF LOW UPPER SHELFPLANT COMPONENTS (PHASE 11) Switchgear, 4C Panels (NSSS) DASE MATERIAL; TESTS WP.2.2 AND WP 2 6

And Relavs NUREG/CR-5451: CRACK ARREST BEHAVIOR IN SEN WIDENUREG/C44667 V07; ENVIRONMENTALLY ASSISTED CRACKING AATES OF LOW-UPPER SHELF BASE METAL TESTED UNDER

IN LIGHT WATER REACTOPS. Semsamuel Report.Apni-September NONISOTHERMAL CONDITONS WP 2 SERIES1988 NUREG/CR-5461: AGING OF CABLES, CONNECTIONS, AND ELEC-

NUREG/C44687 VOS: FNVIRONMENT ALLY AS$1STED CRACKING TRICAL PENETRAT.ON AMEMBLIES USED IN NUCLEAR POWERIN LIGHT WATER REACTORS. Sermannual ReportOctober 1968 PLANTSMarch 1989 yys1EG/CR4463 EFFECTS OF MINERALOGY ON EDRPTION OF

NUREG/CR 4731 V02. RESIDUAL LIFE ASSESSMENT OF MAJOR STRONilVM AND CESIUM ONTO CALICO HILLS TUFF.NUREG/CR44f3. INCLUSON OF UNSTABLE DUCTILE TCARING

N E/ 44 VO LO E bRTLE ENT OF CAST AND EXTFtAPCLATED CRACK ARREST TOUGHNESS DATA INDUPLEX STAINLESS STEELS IN LWR SYSTEMS Sermannual PWR VESSEL INTEGRITY ASSESSMENT,

NUREG/CR44 r6: POSTTEST ANALYDS OF A 1.6-SCALE REIN-NUR C4 4V 2L G RM EMBRITTLEMENT OF CAST r ORCED CONCHETE REACTOR CONT AINMENT BUILDING

DUPLEX STAINLESS STEELS IN LWR SYSTEMS Sermannual NUREG/CR447L IMPROVED EDDY CURRENT INSPECTION FORSTEAM GENERATOR TUBING Progress Report For January 1985

NUR C 7 ADtAN SEISMIC AGREEMENT, Annual Tc December 1987,Report- 1987 1988 NUREG/CR4482 LABORA10RY ANALYSIS OF FI,UID FLOW AND

NUREG/C44753 V04: CANADIAN SEISMIC AGREEMENT. Annual SOLL'TE TRANSPORT THROUGH A VARIADLY SATURATEDReport 1988 1989NUREG/CR4816: PR.EDB. POWER REACTOR EMBRITTLEMENT FRACTURE EMBEDDED IN POROUS TUFF.

NUREG/CR4464 PH BENSORS BASED ON IR:DIUM OXCE.DATA BASE VERSION 1 Prooram DescriphortNUREG/CR-4882. QUALIFICATION PROCESS FOR ULTRASONIC NUREG/CR4487; STATIC LOAD CYCLE TESTING OF A LOW.

TESTING IN NUCLE AR INSERVtCE INSPECTON APPLICATIONS. ASPECT 41ATO FOU41NCH WALL,TRu TYPE STRUCTURE TNG-

NUREG/CR-4908 ULTRASONIC INSPECTION RELLABILITY FOR IN- S 4 (1,0.0 561TERGRANULAR STRESS CORROSON CRACKS A Round Robin NUREG/CR4490 V01: REGULATORY INSTRUMENT REV'EW. MAN.Study Of The Effects Of Personnel, Procedures. Equipment, /nd AGEMENT OF AGING OF LWR MAJOR SAFETY RELATED COM-Crack Charactenshca PONENl'S.

NUREG/C44918 VD4. CONTROL OF WATER INFILTRATON INTO NUhEG/CR449 h SHIPPLNGPORT STATION AGING EVALUATONNEAR SURFACE LLW DISPOSAL UNITS,Progresa Report On Field NUPEG/CR4492: INVE"TKlATONS OF IRRADIATION-ANNEAL-Esoentnants Al A Hurmd Regon Site,Bettsville. Maryland. REIRRADIATION L'.AR) PROPERTIES TRENDS OF RPV

NUREG/CR 5001: EFFECTS OF MANUFACTURING VARIABLES ON WELDS. Phase 2 Final RWPERFORMANCE OF HIGH LEVEL WASTE LOW CARBON STEEL NUREG/C45401 inh.UENCE OF FLUENCE RATE ON RADIATON-

NU E / 51 7: STEAM GENERATOR TUBE INTEGRITY PFO. " "E "GRAM / STEAM GENERATOR GROUP PROJECT. Final Protect Sum-

NUREG/CH W CORRRATON OF IRRADIATON4NEEDNU G $229 V02. TMI 2 EPICOR-il RESIN / LINER INVESTIGA- TRANSITION TEMPERATURE INCREASES FROM C(V) AND K(JC)/

TION. LOW LEVEL WASTE DATA BASE DEVELOPMENT PRO-NU / - PI IMINARY STRUCTURAL EVALUATION OF

NUREGI 229 V EP 1 IP /L ER INVESTIGATON TROJAN RCL SUMECT TO POSTULATED RPV SUPPORT Fall.I LOW LEVEL WASTE DATABASE DEVELOPMENT PROGRAM FOq

NUR G/CR45tJ1; RESULTS FROM THE NUCLEAR PLANT AGINGNU G/C 5 8V2 , ALABAMA REGIOPtAL SEISMO-

RESEARCH PhCGRAM THEM USE IN INSPECTION ACTIVITIEEGEORGbt, July 1086 June 1987'SEISMO. HUREG/CR4510 EVALUATONS OF CORE MELT FREQUENCY EF.GRAPHIC NETWORK. Annual R

LABAMA REGONALNUREG/CR-5258 V03: FECTS DUC TO COMPONENT AGING AND MAIPITENANCE.GRAPHIC NETWORK. Annual Report July 1987 June 1968.NUREG/C45258 V04: GEORGIA / ALABAMA REO ONAL SEISMO. NUREG/CR4513: IvtRADIATION EFFECTS ON STRENGTH AND

TOUGHNESS OF THREE WIRE SERIES ARC STAINLESS STEELGRAPHIC NETWORK. Final Report, August 1965 - October 1990NUREG/CR-5280 V01: AGE-RELATED DEGRADATION OF WES- WELO OVERL AY CLAODING.

TINGHOUSE 400 VOLT CIRCulT BREAKERS Agng Assessment NUREG/CR 6515 1.lGHT WA'ER PEACTOR PRESSURE ISOt.ATIONAnd Recommendahons For Imoroving Breaker Reaabo ty. VALVE PERFORMANCE TESTING.

NUREG/CR 5280 V02; AGE RhLATED DEGRADATION OF WES- NUREG/CR4519 v01: AGING OF CONTROL AND SERVICE airTINGHOUSE 480-VOLT CIRCUIT BREAKERS Mechanical Cycling Of COMPRESSORS AND DRYERS USED IN NUCLEAR POWERA DS416 Breaker. Test Results. PLANTS.

1

NRC Ctntract Sp:ns:r Indca 116

NUREG/CR 5523 DEVELOPMENT OF AN INFILTRATON EVALUA- NUREG/CR-3668 MINET CODE DOCUMENTATONTON METOOOLOGY FOR LOW-LEVEL WASTE SHAM.OW LAND NUREG/CR414 R01 Pl. HEALTH EFFECTS MODELS FOR NUCLE.DURIAL SITES AR POWER PLANT ACCIDENT CONSCOUENCE ANALYSIS Low

NUREG/CR 5524 vot: TMLt VESSEL INVESTIGATION PROJECT lei Ra$stion Par 11 Introduction, integration And Summary(YlP) METALLURGICAL PROGRAM Progresa Report, January Sep. NURE G/CR-4704 V03 RELATIVE DIOLOGICAL EFFECTIVENESStomter i pse (RDE) OF FISSION NEUTRONS AND GAMMA RAYS AT OCCUPA.

NUREG/CR 5524 V02: TMI 2 VESSEL INVESTIGATION PROJECT TIONAL EXPOSURE LEVELS Studies On The Gross And Weroscon-(V6P) MET ALLURGICAL PROGRAM Propees Report. October 1989 ic Pethology Observed At Death Of Mice Exposed To no EqualJune 1990. Once Weekly Doses of Flesson.~

NUREG/CR 5530 ANALYSIS OF H D. ROBINSON PWR VESSEL NUREG/CR 5489 BIOLOGICAL CHARACTERIZATON OF RADbFLUENCE FOR CYCLE 10 UTILIZING PARTIAL LENGTH SHIELD ATON E APOSURE AND COSE ESiliJATES FOR INHALED URANI.ASSEMDLIE S UM MILLING EFFLUENTS

NUREGICR4533 STATIC LOAD CYCLE TESTING OF A VERY LOW- NUREG/CR 5514- MODELING AND PERFORMANCE OF THEASPECT RATIO SIX INCH WALL TRG-TYPE STRUCTURE TRG4-6 MHTGR RE ACTOR CAVITY COMING SYSTEM(027,050) NUREG/CR 6516 CAUSES OF F AILING THE DRAFT ANSI STAND-

NUREG/CR 5542 MODELS FOR ESTIMATION OF SERVICE LIFE OF ARD N13 30 RADODtOASSAY PERFORMANCE CRITERlON FORCONCRETE DARRIERS IN LOW 4EVEL RADtOACTIVE WASTE MINIMUM DETECT ABLE AMOUNT.DISPOSAL NUREG/CR5540. PERFORMANCE TESTING OF EXTREMITT

NUREG/CR 5552: AN , OVERVIEW OF THE LOW UPPER SHELF DOSIMETERS. STUDY 2.TOUGHNESS SAFETY MARGIN ISSUE- NUREG/CR4631. CONTRIDUTON OF MATERNAL RADlJJVCLIDE

NUREG/CR 5553 COMPLff ER PROGRAMS FOR EDDY. CURRENT DURDENS TO PRENATAL RADIATON DOSE $ interirnDEFECT STUDIES Recommendeuons For CommentNUREG/CR 5554. RECOMMENDATONS FOR THE dHALLOW. NUREG/CR 5635. CELLULAR AND MOLECULAR RESE ARCH TOCRACK FRACTURE TOUGHNESS TESTING TALK WITHIN THE REDUCE UNCERTAINTIES IN ESilMATES OF HEALTH EFFECTSHS$1 PROGRAM.

NUREG!CR4560. AGING OF NUCLEAR PLANT RES*TANCE TEM- FROM LOW. LEVEL RADIATION A Feasstulity StudyDIYlSON OF SAFETY ISSUE RESOLUTION (POST 880717)

NUR G 53W. WWWACT AMWS M REGRAN %NU EG/ A L / MPACT ASSESSMENT Os IMPlNGE. T F R N OF GENERIC ISSUE C 6 MSiv LEAK-MENT LOADS AND PIPE.TO PIPE IMPACT DAMAGEmmed Meth.

NUREG/CR 5528 AN ASSESSMENT Or DWR MARK la CONTAIN.NU R 558 PREDtCTION OF CHECK VALVE PERFORMANCEfg OMS, AND ENDAL MAAND DEGRADATION IN NUCLEAR POWER PLANT SYSTEMS .

gWEAR AND IMPACT TESTS. Final Report, September 1988 April

NUREG/CR 5556 REVIEW OF CURRENT LITERATURE RELATED'NUR G/CR 5584. RESULTS OF CRACK ARREST TESTS ON TWO

NURE 556 R DRY C TAINMENT ISSUE CHARACTER.tRRADIATED HIGH COPPER WELDSNUREG/CR-5588 V01: CARES (COMPUTER ANALYSIS FOR RAPID 12A TION

EVALUATION OF STRUCTURES) VE1SION 1.0 SeismacNUREGICR 5575, OUANTITATIVE ANALYSIS OF POTENTIAL PER-

Modu 6e Theorehcal Manual FORMANCE IMPROVEMENTS FOR THE DRY PWR CONTAIN.NUREG/CR 5586 V02: CARES (COMPUTER ANALYSIS FOR RAPID MENT.

EVALUATION OF STRUCTURES) VERSION 10.Soiarme NUREG/CR 5588 MITIGATION OF DIRECT CONTAINMENT HEAT.Module User's Manual ING AND HYDROGEN COMBUSTION EVENTS IN ICE CONDENS-

NUREG/CR 5588 V03. CARES (COMPUTER ANALYSIS FOR RAPID ER PLANTS Analyses With The CONTAIN C4xle And NUREG 1150

V UA ON OF STRUCTURES) VERSION LO Setsmic PAA gg

NUREG/CH-5591 Vnt N1: HEAVY.SECTION CTEEL IRRADLATON MENT PERFORMANCE ISSUESPROGRAM Sermannual Progress Report For October 1989. March NUREG/CH-5602- SIMPLIFIED CONTAINMENT EVENT TREE ANALY.1990 SIS FOR THE SEQUOYAH ICE CONDENSER CONT AINMENT.

NUREG/CR 5504. RADtATION DEGRADATION IN EPICOR il CN EX, NUREG/CR 5601 PRESSURE DEPENDENT FRAGILITIES FORCHANGE RESINS PIPING COMPONENTS Pi6ot Study On Davis Desse Nuclear Power

NUREG/CR 5596: UNSATURATED FRACTURED ROCK CHARAC. StabortTERl2ATION METHODS AND DATA SETS AT THE APACHE LEAP NUREG/CR4659 CONTROL ROOM HAafiADILITY SYSTEMTUFF SITE, REVIEW MODELS.

NUREG/CR 5500 DYNAMIC TESTING OF A CIRCULAR FOUNDA. OlVi$lON OF SYSTEMS RESEARCH (POST 880717)TION AND ANALYSES OF SOIL / STRUCTURE INTERACTION NUREG/CR 4550 VUt R1: ANALYSIS OF CORE DAMAGE FREQUEN-

NUREG/CR 5607. FLOW AND TRANSPORT AT THE LAS CRUCES CY: INTERNAL EVENTS METPOOOLOGY.TRENCH SITE.Expertrnents 1 And 2 NUREG/CR 4550 V3 RIP 1: ANALYSIS OF CORE DAMAGE

NUREG/CR 5613. PALEOLlQUEFACTION FEATURES ALONG THE FREQUENCY:SURRY, UNIT 1. INTERNAL EVENTSATLANTIC SEADOARD. NUREG/CR 4550 V3 RIP 2 ANALYSIS OF CORE DAMAGE FRE-

NUREG/CR 56t5. LOW LEVEL RADIOACTIVE WASTE DISPOSAL OUENCY: SURRY. UNIT 1,1NTERNAL EVENTS APPENDICES.FACILTTY CLOSURE Part | Long-Term Envronmental Coretione Af- NUREG/CR 4550 V3R1P3. ANALYSIS OF CORE DAMAGE FRE.tecting Low Level Waste Disposal Sete Performence Part II. Periorm- QUENCY: SURRY POWER STATION.UN" 1 EXTERNAL EVENTSance Monitonno To Support Regulatory Doctasons. NUREG/CR 4550 V4 RIP 3 ANALYSIS OF CORE DAMAGE FRE.

NUREG/CR 562L ALTERNATE MOOAL COMalNATON METHOOS OUENCY: PEACH 00TTOM. UNIT 2 EXTERNAL EVENTS.IN RESPONSE SPECTRUM ANALYSIS NUREG/CR4550 V5RIPI: ANALYSIS OF CORE DAMAGE FRE.

NUREG/CR 5629 MICROEARTHOUAKES IN KANSAS ANO NE- QUENCY: SEQUOYAH UNIT 1 INTERNAL EVENTS.BRASKA 19771969 Final Report NUREG/CR 4550 V5 RIP 2. ANALYSIS OF CORE DAMAGE FRE.

NUREG/CR 5644: CONSEQUENCE EVALUATON OF RADIATON OUENCY: SEQUOYAH. UNIT 1,1NTERNAL EVENTS APPENDICESEMORITTLEMENT OF TROJAN REACTCH PRESSURE VESSEL NUREG/CR4550 V7 RO1: ANALYSIS OF CORE DAMAGE FREQUEN-SUPPORTS CY. ZION. UNIT 1, INTERNAL EVENTS

DIVISION OF REGULATORY APPLICATONS (POST 870413) NUREG/CR4551 V2R1PI: EVALUATON OF SEVERE ACCIDENTNUREG/C.R-06/2 ADD 04. TECHNOLOGY, SAFETY AND COSTS OF RISKS: QUANTIFICATON OF MAJOR INPUT PARAMETERS. Expert

DECOMMISSIONING A REFERENCE BOILING WATER REACTOR Opinion Elicitaton On in-Vessel issuesPOWER STATONCompannon Of Two Decommessioning Cost Este NUREG/CR 4551 V2 RIP 7. EVALUATION Or SEVERE ACCIDENTmates Developed For The Same Commercial Nuclear Reactor Power RISKS QUANTIFICATION OF MAJOR INPUTStatiott PARAMETERS MACCS input

NUREG/CR-2P' . AD001: TECHNOLOGY, SAFETY AND COSTS OF NUREGICR4551 V381P1. EVALUATION OF SEVERE ACCIDENTDECOMM.wONING REFERENCE LIGHT WATER REACTORS RISKS SURRY UNIT 1 Main Report.FOLLOWING POSTULATED ACCIDENTS. Re Evaluation Of The NUREG/CR4551 V3 RIP 2, EVALUATON OF SEVERE ACCIDENTChanup Cost For The Boiling Water Reactor (DWR) Scenario 3 AccF RISKb SURRY UNIT t. Appendices.dent From NUhEGICA 2601. NUREG/CR4551 V4RIPt. EVALUATION OF SEVERE ACCIDENT

NUREG/CH 3469 V0i OCCUPATIONAL DOSE REDUCTON AT NU- RISKS PEACH 00TTOM. UNIT 2. Main ReportCLEAR POWER PLANTS ANNOTATED DIBLIOGRAPHY OF SE. NUREG/CR-4551 V4RIPt EVALUATION OF SEVERE ACCIDENTLECTED READINGS IN RAD!ATION PROTECTION AND ALARA. RISKS. PEACH BOTTOM UNIT 2, Appendices

|!1

116 N'.C C ntract Spons;r Index

NUREG/C44551 V5R1P1: EVALUATON OF SEVERE ACCIDENT NUREO/CR 5437: ORGANI2ATION AND SAFETY IN NUCLEARRISKS SEOUOY AH. UNIT 1 Main Repart POWER PLANTS.

NUREO/C.R-4551 V541P2. EVALUATON OF SEVERE ACCIDENT NUREG/C45438. BASO CONSOERATIONS IN PREDICTINGRISKS- SEQUOY AH, UNIT 1. Agordces. ERROR PROBABILITIES IN HUMAN TASK PERFORMANCE.

NUREG/CR-4551 V6 RIP 1: EVALUATON OF SEVERE ACCIDENT NUREG/CR-5439 HUMAN FACTORS ISSUES ASSOCIATED WITHRISKS GRAND GULF, UNIT 1. Main R ADVANCED INSTRUMENTATON AND CONTROLS TECHNOL-

NUREO/C44551 V6RtP2. EVALUAT .OF SEVERE ACCIDENT OGIES IN NUCLEAR PLANTS.RISKS ORAND OULF. UNIT 1. Appendices NUREG/CR-5447: DEPRESSURIZAflON AS AN ACCIDENT MAN-

NUREG/C44624 YO6 RADIONUCLIDE RELEASE CALCULATONS AGEMENT STRA1EGY TO MINiui2E THE CONSEOVENCES OFFOR SELECTED SEVERE ACCOENT SCENARIOS.Supolemental DIRECT CONTAINMENT HEATING

NUREO/CR-5480 A CAUSE DEFENSE APPROACH TO THE UNDER-NU E CR 639 V01 R1: NUCLEAR COMPUTERlZED LIBRARY

FOR ASSESSING REACTOR RELIABlUTY (NUCLARA). Summary NUREO/ $472 A SK BA D E EW INS U T AIRSYSTEMS AT NUCLEAR POWER PLANTS.

NU f 639 V4P1R2: NUCLEAR COMPUTERIZED LIBRARY NUREG/CR$474. ASSESSMENT OF CANDOATE ACCOENT MAN-FOR ASSESSING REACTOR RELIABluTY (NUCLARA) Unvs

NUF C 3 4 R2- NUC RC IZED UBRARY NUREG/C A VATION OF THE REUABluTY AND USE-FULNESS OF EXTERNAL INITIATOR PRA METHODOLOGIES.FOR ASSESSING REACTOR RELIABILITY (NUCLARR) Users NUREG/C45480 DATA SUMMARY REPORT FOR FISSON PROO.Quede.Part 2' Gude To Opershone

NUREG/CR4639 V4P3R2: NUCLEAR COMPUTERIZED UBRARY UCT RELEASE TEST VI-3

FOR ASSESSING REACTOR REUABluTY (NUCLARALUsks hUREQ/C45513 Vol: ACCOENT MANAGEMENT INFORMATONOusde Peq 3: NUCLARR System Description. NEEDS. Volume 1. Methodoiogy Development And Application To A

NURFG/CR 4639 V5P1R3. NUCLEAR COMPUTER 12ED LIBRARY Pressurtzed Wster Reactor (PWR) With A large, Dry Containment.

FOR ASSE SSING REACTOR RELIABILITY (NUCLARA). Data NUREG/CR 5513 V02: ACCIDENT MANAGEMENT INFORMATIONManual Part 1 SummaN Descrtphon, NEEDS Voeume 2 Appendecos.

NUREO/CR 4639 V5P2A3: NUCLEAR COMPUTERIZED LIBRARY NUREG/CR-5545: VICTORIA: A MECHANISTIC MODEL OF RADO-FOR ASSESSING REACTOR REUA81UTY (NUCLARR).Deta NUCUDE BEHAVIOR IN THE REACTOR COOLANT SYSTEMManual.Part 2- Human Error Probatwirty (HEP) Data UNDER SEVERE ACCOENT CONDITIONS.

NUREG/CR-e639 V5P3R3. NUCLEAN COMPUTERIZED LIBRARY NUREO/CR 5557, RELAPS THERMAL HYDRAUUC ANALYSIS OFFOR ASSESSING REACTOR RELIABlVTY (NUCLARA).Deta THE SNUPPS PRESSUR! ZED WATER REACOR.Manual.Part 3 Hardware Component Failure Data (HCFDL NUREG/C45568 V01: INDUSTRY BASED PERFORMANCE INDICA-

NUREG/C44868 DAMAGED FUEL EXPERtMENT DF 1.Aesults And TORS FOR NUCLEAR POWER PLANTS Phase 1 Report June 1989

AnaYses . February 1990.NUREG/CR-4671: THE OF 4 FUEL DAMAGE EXPERIMENT IN ACRR NUREO/C45572: AN EVALUATON OF THE EFFECTS OF LOCAL

WITH A BWR CONTROL BLADE ANO CHANNEL BOX. CONTROL STATON DESIGN CONFIGURATONS ON HJMANNUREG/CR.4691 V01: MELCOR ACCOENT CONSEQUENCE CODE PERFORMANCE AND NUCLEAR POWER PLANT RISK.

SYSTEM (MACCS) Volume 1: Usvs Gude NUREO/CR-5573 BORON FLUSHING DURING A BWR ANTICIPAT.NUREG/CR-4891 V02. MELCOR ACCIDENT CONSEQUENCE CODE ED TRANSIENT W1THOUT SCRAM.

$500 SSESSMENT OF THE COMBUSTION MODEL INNU[EONR CR 69 V C OL SEQUENCE CODE

ENT L F$ESU TS E ETE NUREO/CR-5597 IN-VESSEL ZlRCALOY OXOATON/ HYDROGEN-NURE 479 P GENERATION BEHAVIOR DURING SEVERE ACCOENTS

INTERACTONS US'NG MOLTEN $ TEEL WITH ZlRCONtVM NUREO/CR 5649 V01: COMMIX 1C: A THREE DIMENSIONAL TRAN-NUREGrCR-4840- PROCEDURES FOR THE EXTERNAL EVENT SIENT SINGLE-PHASE COMPUTER PROGRAM FOR THERMAL.CORE DAMAGE FREQUENCY ANALYSES FOR NUREG 1150

NUREO/C45111: INTEGRATED REUADluTY AND RISK ANALYSIS HYDRAULIC ANALYSIS OF SINGLECOMPONENT AND MULTI-

SYSTEM (IRRAS) VER$10N 2 0 USER'S GUIDE. COMPONENT ENGINEFR:NG SYSTEMS Ecuations And Numancs.NUREO/C45213 V01: THE COGNITIVE ENVIRONMENT SIMULA. NJREGICR-5649 V02: COMMIX 1C A THREE DIMENSIONAL TRAN-

TION AS A VDOL FOR MODEUNO HUMAN PERFORMANCE AND SIENT SINGLE PHASE COMPUTER PROGRAM FOR THERMAL.REllABldTY.Executw Summa HYDRAUUC ANALYSIS OF SINGLE COMPONENT AND MULTI-

NUREGICR 5213 V02- THE C NITIVE ENVIRONMENT SIMULA- COMPONENT ENGINEERING SYSTEMS User's Gunie And Manual.TION AS A TOOL FOR MODEUNG HUMAN PERFORMANCE AND NUREO/CR-5653: RECRITICAUTY IN A BWR FOLLOWING A COREREUABILITY. Main Report DAMAGE EVENT.

NUREG/C45253. PARTITON: A PROGRAM FOR DEFINING THE DIVISION OF REGULATORY APPUCATONS (860720 870413)SOURCE TERM / CONSEQUENCE ANALYSIS INTERFACE IN THE NUREO/CR-5512 DAF FC: RESIDUAL RADIOACTIVE CONTAMINA-NUREG 1150 PROOABluSTIC RISK ASSESSMENTS. User's Guide. TON FROM DECOMMISSIONING. Techrucal Basis For Translaung

NUREG/C45254 BLAS IN PEAK CLAD TEMPERATURE PREDIC- Contanunahon Levels To Annual Doso Drsft Repor1 For CJmmentTONS DUE TO UNCERTAINTIES IN MODEUNG OF ECC BYPASSAND OtSSOLVED NON-COeOENSABLE GAS PHENOMENA. EDO . OFFICE OF NUCLEAR RE ACTOR REOULATION (POST 4/28/90)

NUREG/CR-5262. PRAMIS- PROBA8|dTY RISK ASSESSMENT DIVISION OF OPERATIONAL EVENTS ASSESSMENT (POST 870411)MODEL INTEGRATON SYSTEM User's Ouede NUREG/C44525. CLOSEOUT OF IE BULLETIN 84 03. REFUELING

NUREG/CR 5273 V04. SCDAP/RELAPS/ MOD 2 CODE CAVITY WATER SEALMANUAL. VOLUME 4.MATPRO . A UBRARY OF MATERIALS NUREG/C44861: CLOSEOUT OF IE BULLETIN 85-03 MOTO40P-PROPERTIES FOR L GHT WATERREACTOR ACCIDENT ANALY- ERATED VALVE COMMON MODE FAl(URES DURING PLANTSIS TRANSIENTS DUE TO IMPROPER SWMCH SETTINGS.

NUREG/CR-5316: met.T PROGRESSION. OXIDATION, AND NATU- NUREG/CR 5286: CLOSEOUT OF IE BULLETIN 79-17. PIPE CRACKSRAL CONVECTON IN A SEVERELY DAMAGED REACTOR CORE, IN ST AGNANT BORATED WATER SYSTEMS AT FWR PLANTS.

NUREGICR-5368: REACTIVITY ACCOENTS.A Reassessment Of The NUREO/C45289 CLOSEOUT OF IE bOLLMIN 79 23. POTENTIAL" "^ "

NU E C 7 DEMONSTRATION EXPERIMENT OF STEAM- R S MRREM 5295 MEN & IE MpCE Bam M

NU / 76 L N V I T OF POTENTIAL FAlltiRE OF MULTIPt.E ECCS PUMPS DUE TOSINGLE FAILURE OF AIROPERATED VALVE IN MINIMUM FLOWNL G R 9 VO LTI CDP INTEORAL SYSTEM TEST

N EG 5 5 V 0- T IN AL SYSTEM TEST NUhE 29 C EOUT OF IE BULLETIN 8345 ASME NUCLE.AA CODE PUMPS AND SPARE PARTS MANUFACTUREC BY THE(MIST): FINAL REPORT. ret AP5/ MOD 2 MIST Analysis Compart. HAYWARD TYLER PUMP COM, ANY.

sons.NUREG/CR-5305 V11: MULTILOOP INTEGRAL SYSTEM TEST NUREG/CR-E298. CLOSEOUT OF IE BULLETIN 85-01: STEAM BIND-

ING OF AUXIUARY FEEDWATER PUMPS.(MIST)-FINAL REPORT MIST Phase IV Tests.

NUREG/CR 5395 V11 AD. MULTILOOP INTEGRAL SYSTEM TEST NUREO/C45302: CLOSEOtJT OF IE BULLETIN 8010: CONTAMINA-

(MIST)-FINAL REPORT. MIST Phase IV Tests. TION OF NONRADIOACTIVE SYSTEM AND RESULTING POTEN-NUREG/CR-5424: EUCITING AND ANALYZING EXPERT TIAL FOR UNMONITORED. UNCONTROLLED RELEASE OF RA-,

i JUDGEMENT A Prachcal Gu6de. OlOACTIVITY TO ENVIRONMENT.

!

!

.- - - .

NRC Contract Sponsor Index 117

NUREO/CR 5306. CLOSEOUT OF IE BULLETIN 79-18 AUDIDILITY NUREO/CR-5622 ANALYSIS OF REACTOR TRIPS ORIGINATING INPROBLEMS ENCOUNTERED ON EVACUATON OF PERSONNEL DALANCF OF PLANT SYSTEMSFROM NIGH NOISE AREAS NU54EO/CR-5640. OVERVIEW AND COMPARISON OF U S. COM-

NUREG/CR 5307: CLOSEOUT OF IE DULLETIN 8042, INADEOUATE MERCIAL NUCLEAR POWER PLANTS Nuclear Pounr Planl SystemOVALITY ASSURANCE FOR NUCLE AR SUPPUED EOutPMENT, y,g

NUREO/CR-5308 CLOSEOUT OF IE DULLETIN 8015: POSSIBLt;OlvtSON OF ENGINEt. RING & SYSTEMS TECHNOLOGY (870411LOSS OF EMERGENCY NOTIFICATON SYSTEM (ENS) WilH g

OIVI. Or E I R TECHNOLOGY CST 890827) NUREG/CR 3950 V06: FUEL PERFORMANCE ANNUAL REPORTNUREGICR 5475 MODEL FEASlBluTY S UOY OF RADtOACTIVE FORI M

PATHWAYS FROM ATMOSPHERE TO SURFACE W ATER, DIVISION OF RADIATON PROTECTION & EMERGENCY PREPARED-NUREG/CR 5479 CURRENT APPLICATONS OF VIBRATION MONI- NESS (POST 870411)

TORING AND NEUTRON NOtSE ANALYSIS Detecten And Ana'ysis NUREO/CR 5527: R!SK SENSITIVITY TO HUMAN ERROR IN THEOf Structural Degradahon Of Reactor vessel Internals From Oper- LASALLE PRAstonal Aoing NUREG/CR 5616. AUXILLARY FEEDWATER SYSTEM RISK BASED

NURE G/CR-55 76. SURVEY OF BORC ACID CORROSON OF INSPECTION GUIDE FOR THE DIABLO CANYON UNIT 1 NUCLE-CARBON STEEL COMPONENTS tN NUCLEAR PLANTS. AR POWER PLANT

NUREG/CR4617: AUxlLIARY FEEDWATER SYSTEM RISK DASEDR / R $3 M Y FN UAEC E COOLING IN-STRUMENTATON FOR UNITED STATES NUCLEAR POWER INSPECTON OUlDE FOR THE J M. FARLEY NUCLEAR POWER

PLANT.PLANTSNUREO/CR-5421; LAPOR USER'S OutDE NUREO/CR 5637: OENERC RISK INSIGHTS FOR WESilNOHOUSENUREG/CR-5605' LAPUR BENCHMARA AGAINST IN PHASE AND AND COMBUSTON ENGINEERING PRESSURIZED WA1ER REAC.

OUT,OF. PHASE STABILITY TESTS TORS.

paa.. s. -h-_.,a -- - u +,s. _ w-.h 4 d.. a*en s 4- ..ah-- ,.L_d-,a.. mm,a._ .,&*. J .g m..,.4a 6 .-ha p -. _ . - .As. a.24hJ .W A +..ma ,

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lIi

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I

.

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m ._ . . _ . _ _ .- _ . . _ -. __ _ . . . _ . ._ .

Contractor index

LThis index lists, in alphabetical order, the contractors that prepared the NUREG/CR reportslisted in this compilation. Listed below each contractor.are the NUREG/CR numbers and '

titles of their reports, if'further information is needed, refer to the. rnain citation by theNUREG/CR nurnber.

Att IMPELL CORP. (FORMEPLY IMPELL CORP.) NUREG/CR4551 V5R1P1: EVALUATON Or SEVERE ACCIDENTNUREG/CR 303- PRESSURE DEPENDENT FRAGIUTIES FOR PIPING RISKS. SEQUOY AH, UNIT 1 Masn Report

COMPONENTS. Pilot Study On Dayts Bevse Nuclear Power Statiort NUREG/CR-4551 V5A tP2: EVALUATON OF SEVERE ACCIDENTRISKS SEQUOYAH, UNIT 1. Appendices

AGRICULTURE. DEPT. OFNUREG/CR 4551 V6 RIP 1: EVALUATON OF SEVERE ACCIDENTNUREG/CR 54F5: MODEL FEAslettfiY STUDY OF RADsOACT!VE RISKS. GRANO GULF, UNIT 1 Main Report.

PATHWAYS FROM ATMQSPHERE TO SURFACE WATER. NUREG/CR-4551 V681P2: EVALUATON OF SEVERE ACCIDENTANALYS48 & MEASUREMENT SERYlCES CORP. - RISKS- GHAND GULF. UNIT 1, Appereces

NUREG/CR-5253: PARTITION A PROGRAM FOR DEFINING THENUREG/CR 5560: AGING OF NUCLEAR PLANT RESISTANCE TEM-PERATURE DETECTORS- SOURCE TERM / CONSEQUENCE ANALYS13 INTERFACE IN THE

NUREG-1150 PROBABluSTC RISK ASSESSMENTS. User's Guide.AROONNE NATIONAL LABORATORY

NUREG/CP-0112 V01: PROCEEDINGS OF THE THIRD INTERNATON- A A '

LADORAT'ORY ANALYblS OF FLUID FLOW AND08" AI

AL ATOMO ENERGY AGENCY SPECIALISTS' MEETING ON SUB. NUREG'/CR 5482:- -

CRITICAL CRACK GHOWTH.Operung Session And Techr*:41 Session SOLUTE TRANSPORT THROUGH A VARIABLY SATURATED FRAC-- 1.He4d At Moscow. USSR,Ma 14 17 1990 TURE EMBEDDED IN POROUS TUFF.

NUREQ/CP-0112 V02: PROCkEDINdS OF THE THIRD INTERNATION, NUREG/CR 5596: UNSATURATED FRACTURED ROCK CHARACTER.AL ATOMIC ENERGY AGENCY SPECIAUSTS' MEETING ON SUB. (2ATON METHODS AND DATA SETS AT THE APACHE LEAP TUFFCRITICAL CRACK GROWTH Techr* al Sesssons is, ill, And IV And - SITE.Recommendations And Conclusions Sessaon V. Held Al NUREG/CR-5007: FLOvV AND TRANSPORi AT THE LAS CRUCES

' Moscow. USSR,May 14 17.1990. TRENCH SITE Expenments 1 And 2NUREG/CR4667 VU7: ENVIRONMENTALLY ASSISTED CRACKING IN

LIGHT WATER REACTORS Semaannual Report. April-September 1968. BABCOCK & WILCOX CO.NUREG/CR4667 V08. ENVIRONMENTALLY ASSISTED GRACKING IN NUREG/CR 5395 V02: MULT! LOOP INTEGRAL SYSTEM TEST (MiSit -UGHT WATER REACTOR $. Sorniennual Report,0ctober 1968. March FINAL REPORITost Group 30.Mappan0 Tests,

1989. NUREG/CR 5395 V10: MULilLOOP INTEGRAL SYSTEM TEST (MIST)- NUREG/CR4704 V03: RELATIVE BIOLOGICAL EFFECTIVENESS (RDE) FINAL REPORT. RELAPS/ MOD 2 MIST AneWe Compartoons,

OF FISSON NEUTRONS AND GAMMA RAYS AT OCCUPATIONAL NUREG/CR-5305 V11: MULTILOOP INTfGRAL _ SYSTEM TESTEXPOSURE LEVELS Studies On The Gross And Microscopic Patholo. (MIST) FINAL REPORT. MIST Phase IV Testagy Observed At Death Of bice Exposed To 60 Equal Once Weeuy NUREG/CF.5395 V11 AD MULTILOOP INTEGRAL SYSTEM TESTDoses Of Fusiort... (MIST). FINAL REPORT. MIST Phase IV Tests,

NUREG/CR4744 V03 N1: LONG TERM EMBRITTLEMENT OF CASTDUPLEX STAINLESS - STEELS IN LWR SYSTEMS. Semiannual BATTELLE MEMORIAL INSTTTUTEReport. October 1987 a March 1968 NUREG/CR-5653: RECRITICAUTY IN A DWR FOLLOWING A CORENUREG/CR+4744 V03 N2, LONG-TERM EMBRITTLEMENT OF CAST DAMAGE EVENT.DUPLEX STAINLESS STEELS IN LWR SYSTEMS.SerrmannualReoort. April September 1968. BATIELLE MEMORIAL INSTITUTE. COLUMSUS LADORATORIES

NUREG/CR 5229 V02: TML2 EPICOR41 RE$1N/UNER l*7STIGATON. NUREG/CP 0109- PROCEEDINGS OF THE SEMINAR ON LEAK-LOW LEVEL WASTE DATA BASE DEVELOPMENT - :iAM FOR BEFORE BREAK.Further Developments in Regulatory Policies AndFISCAL YEAR 1989 Annua! Report Supporting Research.

NUREQ/CR 5385: INITIAL ASSESSMENT OF THE MECHANISMS AND NUREG/CR-4624 V06: RADIONUCUDE HELEASE CALCULATONSSIGNIFICANCE OF LOW TEMPERATURE EMBRITTLEMENT OF FOR SELECTED SEVEDE ACCIDENT SCENARIOS.Supp6emental CesCAST STAINLESS STEELS IN LWR SYSTEMS. culabons.

NUREG/CR-5524 V01: TMI 2 VESSEL INVESTIGATION PROJECT (VIP)METALLURGICAL PROGRAM. Progress Report, January-September BATTELLE MEMORIAL INSTITUTE, PACIFIC NORTHWESTM89. LAeORAtoRy

~ NREG/CR-5524 V02: TMI-2 VESSEL INVESTIGATON P60 JECT (VIP) NUREG/CR4672 ADD 04. TECHNOLOGY, SAFETY AND COSTS OFMETALLURGICAL PROGRAM Progress Report,0ctober 1989 JuneDECOMMISSIONING A REFERENCE BOtVNG WATER REACTOR-

:N G/CR-5599: DYNAMIC TESTING OF A CIRCULAR FOUNDATkJN POWER STATION Compenson Of Two Decommiassoning Coat Esth- AND ANALYSES OF SOIL / STRUCTURE INTERACTION. mates Dwetoped 6 De Same Commercial Nuclear Ream PowerNUREG/CR 5649 VOI: COMM1X 1C: A THREE DIMENSIONAL TRAN. Statiort

SIENT SINGLE-PHASE COMPUTER PROGRAM FOR THERMAL HY. NUREG/CR 2601 ADOO1: TECHNOLOGY. SAFETY AND COSTS OF DE-DRAUUC ANALYSIS OF SINGLE-COMPONENT AND MULTICOV. COMMISSONiNG REFERENCE UGHT WATER REACTORS FOL.PONENT ENGINEERING SYSTEMS Equatw.e And Numence LOWING POSTULATED ACCIDENTS. Re Evaluation Of The Cloenup

NUREG/CR 5649 Vo2. COMMIX 10: A THREE.DiMENA60NAL TRAN. Cose For The Boiling Water Reactor (BWR) Sceneno 3 Accident FiumSIENT SINGLE PHASE COMPUTER PROGRAM FOR THERMAL HY. NUREG/CA-2601.DRAUUC ANALYSIS OF blNGLE COMPONENT AND MULTICOM- NUREG/CR.2850 VW POPULATION DOSE COMMITMENTS DUE TO

- PONENT ENGINEERING SYSTEMS. User's Guido And Manual. RADOACTIVE RELEASES FROM NUCLEAR POWER PLANT SITES,

.

IN 1987.ARI2ONA STATE UNIV TEMPL A2 NUREG/CR-3950 V06: FVEL PERFORMANCE ANNUAL REPORT FOR

NUREG/CR4551- V2 RIP 7; EVALUATON OF SEVERE ACCIDENT 1988RISKS: QUANTIFICATION OF MAJOR INPUT PARAMETERS MACCS NUREQ/CR4469 V08 NONDESTRUCTIVE EXAMINATON (NDE) REU-Input. ABlWTY FOR INSERVICE INSPECTION OF UGHT WATER

G4UREG/CR4551 V4 RIP 1: EVALUATION OF SEVERE ACCIDENT REACTOR 9 Semiannual Report. October 1987 March 1968RISKS: PEACH BOTTOM,UNtT 2. Main Report NUREG/CR4469 V09- NONDESTRUCTIVE EXAMINATON (NDE) REU.

NUREG/CR4551 V4R1P2. EVALUATON OF SEVERE ACCIDENT ABILfTY FOR INSERVICE INSPECTON OF UGNT . WATERRISKS: PEACH BOTTOM, UNIT 2. Appereces. REACTORS Semiannual Report.ApnLSeptember 1988-'

119

--

120 Contractor index ;

NURE G/CR 4469 V10. NONDESTRUCTIVE E AAMINATON (NDE) RELb NUREG/CR 5254 BLAS IN PE AK CLAD TEMPERATURE PREDtCTIONS

A8itfiY FOR INSERVICE INSPECTON OF LIGHT W AT ER DUE TO UNCERT AINTIES IN MODELING OF ECC DYPASS AND DIS-

Rf ACTORS Semiantual Report. October 1968 + March 1909 SOLVED NON-CONDENSABLE GAS PHENOMENA.

NURE G/CR 4667 OU ALIFICATON PROCESS FOR ULTRASONIC NUREG/CR-5280 VDI: AGEJtELATED DEGRADATON OF WESTING-^ " ' * * * " ' " * ' '

N /E 9 ' f C SPEC 6 E lABit O IN. , p , i

TERGRANULAR STRESS CORROSON CRACKS A Round Rotsn NUREG/CR 5260 V02 AGE.RELATED DEGRADATION OF WESTING.Stud Of The Ettoct. Of Personnel, Procedures, Equpmut, And Crack HOUSE 460 VOLT CIRCUti BAE AKERS MechsNeal Cychng Of A DS-

416 BreakerJest Roses?S 17 STEAM GENERATOR TUDE INTEGRITY PROGRAM /NUREG/CR 5368. REACTIVRY ACCCENTRA Reassenament Of TheNU

STEAM GENERATOR GROUP PROJECT Final Pro |ect Summary Desgn-Basis Events99arg NUREG/CR 5419 AGING ASSESSMENT OF INSTRUMENT AIR SYS-

NURLG/CR-5169 MODILIZATION AND TRANSPORT OF URANIUM AT TEMS IN NUCLEAR 70WER PLANTSURANIUM MILL T AILINGS OtSPOSAL SITES Appicebon Of A ChampNUREG/CR4472 A RISK DASED REVIEW OF INSTRUMENT AIR SYS-cal Transport Model.

MUREG/CR-5366 BASIS FOR SNUDDER AGING RESEARCH NUCLE- TEMS AT NUCLEAR POWER PLANTS

AR PLANT AGING RESEARCH PROGRAM NURLG/CR 5474 ASSESSMENT OF CANDIDATE ACCIDENT MAN-NUREG/CR-5397, VALUE lMPACT ANALYSIS OF REGULATORY OP- AGEMENT STRATEGIES.

TONS FOR RESOLUTON OF GENERIC ISSUE C 8 MSIV LEAAAGE NUREG/CR 5507: RESULTS FROM THE NUCLE AR PLANT AGING RE.AND LCS FAlLURE * SE ARCH PROGRAM THEIR USE IN INSPECTION ACTIVITIES

MUREG/CR,5490 V01: REGULATORY INSTRUMENT REVIEW: MAN' NUREG/CR 5527' HISK SENSITlvtTY TO HUMAN ERROR IN THE LA.AGEMENT OF AGING OF LWR MAJOR SAFETY.RELATED COMPO- M PRA

NUREG/CR-5567. PWR DRY CONTAINVENT ISSUE CHARACTER 12A-NU E CR 5491- SHIPPINGPORT ST ATION AGING EVALUATION TONNUREG/CR 5512 DAF FC' RESOUAL RADOACTIVE CONIAMINATION NUREG/CR 5572 AN EVALUATON C? THE EFFECTS OF LOCALFROM DECOMMIS$10NING. Tochtw;a! Bas a For Transtabng Contamp

CONTROL ST ATION DESIGN CONFIGURATONS ON HUMAN PER.nation Levers To Annual Dose Draft Report For CommentMUREG/C45516. CAUSES OF F AILING THE DRAFT ANSI STANDARD FORMANCE AND NUCLEAR "OWER PLANT HISK

NI3 30 RADOOOASSAY PERFORMANCE CRITERION FOR MINI- NUREG/CR 5573 DORON FLUSHING DURING A DWR ANTICIPATED

MUM DETECT ADLE AMOUNT. TRANSIENT WITHOUT SCRAMNUREG/CR-5523 DEVELOPMENT OF AN INFILTRATION EVALUA- NUREG/CR 5574 DETERMINATION OF THE CHEMICAL FORM Or

TON METHODOLOGY FOR LOW. LEVEL WASTE SHALLOW LAND 1pryggy |q gg(p, LUMINOUS SIGNS"" ' " ^ "" " ^" "

NU 0 PERFORMANCE TESTING OF EXTREMITY 8 TEEL COMPONENTS IN NUCLE AR PLANTS.NUREG/CR 5568 V01 CARES (COMPUTER ANALYSIS FOR DAPO

N E C 55 APP CATON OF SURFACE COMPLEXATION EVALUATON OF ST RUCTURES) VERSON 10 SeuimecMODELS FOR RADONUCLOE ADSOFWTON Sensitrvity Anakysm Of Module Theorece' ManualModel l Parameters NVREG/CR 55e6 V02. CARES (COMPUTER ANALYSIS FOR RAPID

NUREG/* 5548 HEVIEW OF GEOCHEMICAL PROCESSES AND EVALUATION OF STRUCTURES) VERSON 1.0. SesameCODES FOR ASSESSMENT OF RADONUCLIDC MIGRATION PO. Mose User's Manual.TENTIAL AT COMMERCIAL LLW SIT S.

MUREG/CR-5566. EVALUATON OF HL(ALTH EFFECTS IN SEOVOYAHNURES/CR-5588 V03 CARES (COMPUTER ANALYSIS FOR RAPID

FUELS CORPORATION WORKER $ FROM ACCIDENTAL EXPOSURE EVALUATON OF STRUCTURES) VERSON t.0 Semic

TO URANIUM HEXAFLUORIDE Module Sampio Prob 6ema

NUREG/CR 5579 VALUE/ IMPACT ASSESSMENT OF JET IMPINGE- NUREGiCRE89 ASSESSMENT Or ICE CONDENSER CONIAINMENTMENT LOADS AND PlPE TO PtPE IMPACT DAMAGE Rowned Meth* PERFORMANCE ISSUES

^WU G CR 6 AUXILIARY FEEDWATER SYSTEM RISK BASED IN- gg kCTR S

SPECTION GUIDE FOR THE DIABLO CANYON UNIT i NUCLEAR NUREG/Cn.5637. GENERIC RISK INSIGHTS FOR WESTINGHOUSEAND COM0USTON ENGINEERING PRESSURt/ED WATER REAC-

NU / AUXILIARY FEEDW ATER SYSTEM RISK DASED IN- TORSSPECTION GulDE FOR THE J M FARLEY NUCLEAR POWERPLANT C ALIFORNIA, UNIV. OF, BERKELE Y, CA

NUREG/CR 5631: CONTRiBUTON OF MATEnNAL RADONUCLlDEDURDENS TO PRENATAL RADIATON DOSES intenm NUREG/CR.4916 V04 CONTROL OF WATER iNFILTRATON INTO

cieu Ex-NEAR SUHF ACE LLW DISPOSAL UNtTS Progress Report OnRecommendationtFor Comment

NUREG/CR-5653 RECRITICALITY IN A DWR FOLLOWING A CORE perimenta At A Homed Region site.DeftsviittMarytern

DAMAGE EVENT. CANADA, GOVT.OF

BROOKHAVEN NATIONAL LABORATORY NUREG/CR-4753 YC3 CANADIAN SEISMIC AGREEMENT AnnualNUREQ/CP 0105 V0t; PROCEEDIN% OF THE SEVEK *EN'H Report. 1987 1988

NUREG/CR 4753 V04 CANADIAN SEISMIC AGREE MENT.ArruetNUR G/C 0 R F N OF SEVENTEkhTH pod 88 6

WATER REACTOR SAFETY INFORMATION MEETINGNUREG!CP 0105 V03 Pf OCEEDINGS OF THE SEVENTEENTH CAN ADIAN COMMERCIAL CORP,

WATER REACTOR RAFETY INFORMATION MFETINGNUREG/CP-0110, PROCEEDINGS OF THL INTERNAT'ONAL WORK. NUREG/CR-4753 V03: CANADIAN SEISMIC AGr1 EMET 4T. Annual

SHOP ON NEW DEVELOPMENTS IN OCCUPATIONAL DOSE CON.Report 1987 1938

TROL AND ALARA IMNEMENTATON AT NUCLEAR POWER NUREGICR 4753 V04. CANADIAM SEISMIC AGREEMENT.AnruelPLANTS AND SiMILAR FACh,lTIES Report 1988-1989

NUREG/C42331 * ;9 N3 SAFETY RESEARCH PROGRAMS SPON-SORED OY OFFICE G NUCLEAR REGULATORY CENTER FOR NUCLEAR WASTE REGULATORY ANALYBES

RESEARCH Progre_ss Report,.h4liemmber 1089. NUREG/CR 5838 TECHNICAL CONSIDERATIONS FOR EVALUATINGNUREG/C42331 Vw N4. SAFETY WSEARCH PROGRAMS GPON- SUBSTANT. ALLY COMPLETE CON T AINME NT OF HIGH-LEVEL

_

SORED BY OFFICE N MUCLEAR REGULATORY WASTE WITHIN THE WASTE F ACKAGE.RESEARCH Octot>er-December 1989

NUREG/C43444 V07: THE IMPACT OF LWR DECONTAMINATIONS COLORADO SCHOOL OF WINES, GOLDEN, COON SOLOlFICATON. WASTE DISPOSAL AND ASSOCIATED OCCU- NUREG/CR-5001: EFFECTS OF MANUFACTURING VAP' ABLES ON

PERFORMANCE OF HIGH4EVEL WASTE LOW CARDON STEELh3 9 VOS OCCUPATIONAL DOSE REDUCTION AT NU_ CONTAINFRSNURE /

CLEAR POWER PLANTS. ANNOTATED BIBLOGRAPHY OF SELECT.^ COLORADO ST ATE UNIV., FORT COLLINS, CO

NU E E U E T ^

NUREG/C44659 V03. SEISMIC FRAGILftY OF NUCLEAR POWER NUREG/CR5635 CELLULAR AND mot ECULAR RESEARCHPLANT COMPONENTS (PHASE il) Setchgear, l&C Panets (NSSS) REDUCE UNCERTAINTIES IN ESilMATLS Or HEALTH EFFECis

FROM LOW LEVEL RADIATION A Feasitulity SWyAnd Reisys

_ _ - _ - _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _

| Contractor Index 121l

COMMUNICATIONS TECHNOLOGY APPLICAtlONS,INC. NUREG/CR 5504, RADIATION DEGRADATON IN EPICOR Il CN Ex.NUREG/CR-5568 YO1 INDUSTRY DASED PERFORMANCE INDICA. CHANGE RESINS

TORS FOR NUCLEAR POWER PLANTS Phase 1 Report Jurse 1989 NUREG/CR 5602 SIMPUFIED CONTAINMENT EVENT TREE ANALY.Factuary 1990. SIS FOR THE SEOOOYAH ICE CONDENSER CONT AINMENT.

NUREG/CR 5603 PRESSURE DEPENDENT FRAGILITIES FOR PIPINGCONCORD ASSOCIATES.,INC. COMPONENTS P4ot Study On Daws Desse Nuc6 ear Power Station.NUREG!CR 5568 V01: INDUSTRY DASED PERFORMANCE INDICA- NUREG/CR 5615 LOW LEVEL RADIOACTIVE W ASTE DISPOSAL FA-

TORS FOR NUCLEAR POWER PLANTS Phose 1 ReNet June 1989 * CIUTY CLOSURE Part t Long Term Enwonmental Con $ tons Aftset.Fettuary 1990. 6ng low Level Weste Disposal Site Periormance Part II. Portormance

CORTEST COLUMBUS, INC. ""O b#P " *D **"*

NUREG/CR-5435 ENVIRONMENTAL ErFECTS ON CORROSION IN El SERVICES, INC.THE TUFF REPOSITORY *

NUREG/CR4550 V3R1P1: ANALYSIS OF CORE DAMAGEE8 ASCO SERVICES, INC. (SUBS OF ENSERCH CORP.) FREQUENCY.SURRY, UNIT taNTERNAL EVENTS

NUREGICA-5613 PALEOLIQUEFACTON FEATURES ALONG THE AT. NUREG/CH-4550 V3A1P2 ANALYSIS OF CORE DAMAGE FREOVEN-LANTIC SEABOARD ^ CY= SURRY, UNIT 1,1NTERNAL EVENTS APPEND 4CES

NUREG/CR4550 V5AtP1: ANALYSIS OF CORE DAMAGE FREQUEN-EG&G IDAHO,INC. (SUBS OF EGaG,INC.) CY: SEOVOYAH. UNIT 1,1NTERNAL EVENTS

NUREG/CP4111: PROCEEDINGS OF THE SYMPOSIUM ON INSERV. NUREGICA ab50 V5 RIP 2 ANALYSIS OF CORE DAMAGE FREQUEN-ICE TEST!NG OF PUMPS AND VALVES Hs j Al The Hyatt RogeriC'y CY: SEQUOYAH. UNIT 1. INTERNAL EVENTS APPEND 4CES

NU CR 5 7 01 AL S F CORE DAMAGE FREOVEN. ENERG" TECHNOLOGY ENGINEERING CENTERCY: ZION. UNIT 1, INTERNAL EVENTS NUREGiCR-5515 UGHT WATER REACTOR PRESSURE ISOLATION

NUREG/CR4839 V01 Rt: NUCLEAR COMPUTERIZED UORARY FOR VALVE PERFORMANCE TESTINGASSESSING REACTOR REUADIUTY (NUCLARR) Summary Desenp.

NUREG/CR-4639 V4P1R2. NUC' EAR COMPtJTERt2ED LIBRARY FOR NUREG/CR-5597. IN-VESSEL ZlRCALOY OxtDA TION / HYDROGEN-ASSESSING REACTOM RELL AITY (NUCLARR) Users Ques Part 1: GENERATON BEHAVIOR DURING SEVERE ACCIDENTSOve< view Of NUCLARA Data Retneval

NUREG/CR4639 V4P2R2 NUCLEAR COMPUTER: ZED Ll0RARY FOR E OE, INC-

ASSESSING REACTOR REUABluTY (NUCLARR) User's Guide Part 2: NUREG/CR4550 V341P3 ANALYSIS OF CORE DAMAGE FREQUEN-Gude To Operations. CY. SURRY POWER ST ATON. UNIT 1 EXTERNAL EVENTS.

NUREG/CR 4639 V4P342: NUCLEAR COMPUTERIZED LIBRARY FOR NUREG/CR4550 V4RtP3 ANALYSIS OF CORE DAMAGE FREQUEN-ASSESSING REACTOR REUAbiUTY (NUCLARR).U5Vs GuHe Pa't 3 CY: PEACH DOTTOM. UNIT 2 EXTERNAL EVENTS

NUR G 48 V5P R3 VCLEAR COMPUTERIZED UCRARY FOR ERC ENVIRONMENT AL & ENERGY SERVICES, INC.ASSESSM REACIOR REllADluTY (NUCLANR). Data Varmi.Part i NUREGICR-4550 V01 R1: ANALYSIS OF CORE OAMAGE FREQUEN-Summa 7 Deserptm CY: INTERNAL EVENTS METHODOLOGY.

NUREG/CR-4639 v5P2R3 NUCLEAR COMPUYERCf D LaDR ARY FOR NUREG/CR-5381. ECONOMtC AlSK OF CONTAMINATON CLEANUPASSESSING REACTOR REUABillTY (NUCLARh)Ceta ManuaLPart 2. COSTS RESULTING FROM LARGE NONREACTOR NUCLEAR MATE.Human Error Protaab,lity (HEP

NUREG/CR4639 V5P3R3 NW(Data. A1AL UCENSEE OPERATONSLEAP COMPUTER: ZED UDRARY FOR

ASSESSING REACTOR HELIABluTY (NUCLARR).Dets Manual Part 3 ERCE, INC,Hardware Com. ponent Fa4ure Data (HCFD) NUREG/CR4550 V4 RIP 3. ANALYSIS OF CORE DAMAGE FREQUEN-

NUREG/CR-4731 V02: RESIDUAL UFE ASSESSMENT OF MAJOR CY. PEACH DOTTOM,0 NIT 2 EXTERNAL EVENTSUGHT WATER REACTOR COMPONENTS OVERVIEW.

NUREG/CR 5111: INTEGRATED REUABILITY AND RISK ANALYSIS FTA ASSOCIATESSYSTEM (IRRAS) VERSION 2.0 USER'S GUIDE. NUREG/CR 5644 CONSEQUENCE EVALUATON OF RADiATON EM-NUREG/CR-5161: NUCLEAR PLANT AGING RESE ARCH THE 1E BFUTTLEMENT OF TROJAN REACTOR PRESSURE VESSEL SUP-POWER SYSTEM

PORTS'NUREb!CR 5229 V02' TMI 2 EPICOR-Il RES!N/UNER INVESTIGATION

LOW LEVEL WASTE DATA BASE DEVELOPMENT PROGRAM FOR FUTURE RESOURCES ASSOCIATES,lNC,FISCAL YEAR 1989. Annual Report

NUREG/CR 5229 V03 EP1COR il RESIN /UNER INVESTIG ATION' LOW- NUREG/CR 5477. AN EVALUATION OF THE REUADILITY AND USE-

LEVEL WASTE DATABASE DEVELOPMENT PROGRAM FOR FISCAL FULNESS OF EXTERNAL INITIATOR PRA METHOOOLOGIESYE AR 1990. Annual Report GEORGE MASON UNIV FAIRFAX, .?.NUREG/CR 5273 V04 SCOAP/RELAP5/ MOD 2 CODEMANUAL, VOLUME 4 MATPRO . A UBAART OF MATERIALS PROP- NUREG/CR 5430 BASIC CONSIDERATIONS IN PHEDICTING ERROR

ERTIES FOR UGHT WATER REACTOR ACCOENT ANALYSIS PROOADIUTIES IN HUMAN T ASK PEHFORMANCE.

NUREGICR-5314 V03: LIFE ASSESSMENT PROCEDURES FOR GEORGIA INSTITUTE OF TECHNOLOGY, ATLANTA, GA

VYR R A/ A SEMNURE 57 Y ASS t At 10 OF THEGAAPHIC NETWORK. Annual Report, July 1986. June 1987.

NU E / R 4 E ESSURIZATION AS AN ACCCENT MANAGE NUREG/CR 5258 V03 GEORGIA / ALABAMA REGONAL SEISMO-^

MENT STRATEGY TO MIN'VIZE THE CON 3EOUENCES OF DIRECT NUREG/ 2 G A MA R I AL SEISMO-NU / 5 A i EVALUATION OF CLASS 1E DATTERtES CRAPH'C NETWORK Final Report, August 1985 Octohw 1990

NU G/CR 513 01: ACCIDENT MANAGEMENT iNFORMATONNEEDS VWume 1 Methodology Devehpmoat And Appbcation To A NURE41392 LEAKAriE 09 AN IRRADeATOR SOURCE THE JUNE

#8M ^Pressurned Water Amtvr iPWR) With A Ladr a Dry ContainmentNUREG/CR-5513 V02. AC0DElif MANA EklE NT INF ORM ATION

NUREG 5 A"N S ENT Or DWR MARK 11 CONTAINMENT N REG CR 4551 V2 RIP 7 EVALUATION OF SEVEHE ACCIDENTCHALLEN IES FARURE MODES, AND POTENTIAL IMPROVEMENTS RISKS OUANtFICATION Or MAJOR INPUT PARAMFTERS MACCSIN PERSORMANCE Input

NUREGICR 5542: MODELS FOR ESTIMATON OF SERVICE UFE OF NUREG/CR-5211: UNCERT AINTIES ASSOC!ATED WITH F'ERFORM.CONCRETE BARRIERS IN LOW LEVEL RAD OACTIVE WASTE OtS. ANCE ASSERSMENT OF HIGH-LEVEL RADOACTIVE WASTEPOSAL. REPOSITOR:ES A Summary Report.

NUREG/CR-5556. REVIEW OF CURRENT UTERATURE RELATED TO NUREG/CR 5381: ECONOMIC RISK OF CONTAMINATION CLEANUPGENERIC SAFETY tSSUE 15 COSTS RESULTING FROM LARGE NONREACTOR NUCLEAR MATE-

NUREGICR-5557. RELAPS THERMAL HYDRAUUC ANALYSIS OF THE RIAL UCENSEE OPERATIONSSNUPPS PRESSURIZED WATER REACTOR NUREGICA 5521 USE OF PERFOR,JANCE ASSESSMENT IN AS-

NUREG/CR 5575 OUANTITATIVE ANALYSIS OF POTEN11Au PE R- SESSING COMPUANCE WITH THE CONTAINMENT REQUIRE-FORMANCE IMPROVEMENTS FOR THE ORY PWR CONTAlNMENT. MENTS IN 40 CFR PART i91

_.. . ._ . . . .

..-

. _ _ _ _ _ _ _ _ - . _ . _ _ . _ . _ _ _ . _ _ __.. _ _ - .

,

122 Contractor index

HARVARD SCHOOL OF PUBLIC HEALTH, SOSTON. MACRITICAL CRACK OROWTH.lochnical Seasons 16, lit, And IV And

NUREG/C44214 RO1 Pl. HEALTH EFFECTS MODELS FOR NUCLEAR Recommendations And Conclusions Session V Held AlMoscow. USSR.May 14 17, 1990

POWER PLANT ACCIDENT CONSEQUENCE ANALYSIS. Low LET NUREG/C45492. INVESTOATONS OF lHRADIATON-ANNEAL.REl4..Raoiatiordart Lintroduction, integration And Summary.RADtATION (IAR) PROPER 1|ES TRENDS OF RPV VdLDSPhase 2

HAW All. UNIV. OF, HILO, HI Final Report

NUREG/CR 54 t t: ELICITATON & USE OF EXPERT JUDGMENT IN NUREG/CR-5493. INFLUENCE OF FLUENCE RATE ON RADIATON-IN-PERFORMANCE ASSESSMENT FOR HIGH LEVEL RADIOACTIVE DUCEO MECHANICAL PROPERTY CHANGES IN REACTOR PRES-WASTE REPOSITORIES. SURE VESSEL STEFLS Final Report On Exp6 oratory Emperrnents

NUREGICR-5494 CORRELATON OF IRRADIATION INDUCED TRAN-

$h M tRATURE INCREASES FROM C(V) AND K(JC)/K(IC)REG C S3 LY TATE AND TRIBAL EMERGENCY RE.SPONSE CAPABiUTIES FOR RADCLOGICAL TRANSPORTATtONINCIDENTS- MICHIGAN, UNIV, OF, ANN ARBOR, MI

NUREG/C43145 V08 QEOPHYSOAL INVESTIGATIONS -Or THEINHALAtlON TOXICOLOGY RESEARCH INS 71TUTE WESTERN OHIOINDtANA REGION Annual ReportOctober 1988 -

NUREG/CR 5489. BIOLOGOAL CHAMCTER12ATION OF RADIATON Sepe 081 1

EXPOSURE AND DOSE ESTIMATES FOR INHALED URANIUM MILL- |ING EFFLUENTS- MINNESOT A. UNIV. OF, WINNEAPOUS, MNNUREG/CR 543h ORGAN 12ATON AND LM ETY IN NUCLtAR POWER

JSF ASSOCIATES, INC. . PLANTSNUREG/C454ea A CAUSE DEFENSE APPROACH TO THE UNDER,STANDING AND ANALYSl$ OF COMMON CAUSE FAILURES' MfTRE CORP.

NUREGrCP 0108: PUBLtC WORKSHOP ON NUCLEAR POWER PMNT iKALSI ENGINEERING, INC,

UCENSE RENEWALNUREG/CR-5583. PREDsCTION OF CHECK VALVE PERFORMANCE

AND DEGRADATION IN NUCLEAR NWER PLANT SYSTEMS NATIONAL INSTITUTE OF ST ANDARDS A TECHNOLOGY (FORMERLYWEAR AND IMPACT TESTS.Fsnal ReportSepter9er 1988 April 1990 NATIONAL SUREAU OF

NUREG!C44735 V06. EVALVATON AND COMPILATION OF DOEKANSAS, UNIV. OF. LAWRENCE, KSNUREQ/CR 5629. MICROEARTHOUAKES IN KANSAS AND NEBRAS

WASTE PACKAGE TEST DATA. Bennual Report August 1988. Janu-

KA 19771969 Final Report - ary 1969NUREG/CR-5450 HCH TEMPERATURE CRACK ARREST TESTS

LAKE ENGINEERING,INC. USING 152-MM THICK SEN W1DE PLATES OF LOW UPPER-SHELFNUREG/C45386. BASIS FOR SNUBBER AGING RESEARCH. NVCLE* BASE MATERIAL: TESTS WP 2.2 AND WP.2 6

AR PLANT AGING RESEARCH PROGRAM. NUREG/CR 6484. PH SENSORS BASED ON IROtVM OxlOE.

LAWRENCE UVERMORE NATIONAL LABORATORY NEW MEXICO STATE UNIV, LAS CRUCES, NM

NUREG/CR 4554 V06: SCANS (SHIPPING CASK ANALYSIS SYSTEM) A NUREG/CR460h FLOW AND TRANSPORT AT THE LAS CRUCESMICROCOMPtJTER BASED ANALYSIS SYSTEM FOR SHIPPtNG TRENCH SITE.Expenments 1 And 2.C ASK DESIGN MVIEW, Volume 6. Theory Manual 8vedng Of Orcu-lar CWndncal Shons NEW MEXICO, UNIV. OF, ALSUOUEROVE, NM

NUREG/CR4554 VOL SCANS (SHLPPING CASK ANALYSIS SYSTEM) NUREG/CR 5361 THE SEISMIC CATEGORY l STRUCTURES PRO-' A MICROCOMPUTER BASED ANALYSIS SYSTEM FOR SHIPPING GRAM RESUL,TS FOR FY 198LCASK DESIGN REVIEW. Volume 7. Theory Manual Puncture Of She NUREG/CR 648h STATIC LOAD CYCLE TESTING OF A LOW. ASPECT-

^ ^NU G $500: PREUMINARY STRUCTURAL EVALUATION OF 0 56)

TRCUAN RCt. SUBJECT TO POSTULATED RPV SUPPORT FAILURE. hAEG/CR4533: STATIC LOAD CYCLE TESTING OF A VERY LOW-NUREG/CR-5644 CONSEQUENCE EVALUATION OF RADIATION EM- ASPECT. RATIO SIX INCH WALL TRG-TYPE STRUCTURE TRG-6-6

BRITTLEMENT OF TROJAN REACTOR PRESSURE VESSEL SUP- - (0.2?,0.501PORTS.

NUS CORP,LOS ALAMOS NATIONAL LA80RATORY NUREGICR4460: A CAUSE DEFENSE APPROACH TO THE UNDER-

.NUREG/CR-5369: THE seismic CATEGORY l STRUCTURES PRO- STANDING AND ANALYSIS OF COMMON CAUSE FAlLURESGRAM RESULTS FOR FY 1967.

NURE /CR 54 E IT AND ANALYZING EXPERT R M W M R N R W AYNUREG/CR 2000 V08N12- UCENSEE EVENT REPORT (1.ER)NUREG/CR 548h ST ATIC LOAD CYCLE TESTING OF A LOW. ASPECT, COMPILATON For Monm O Decembec 1960.

RATIO FOURINCH WALLTRG TYPE STRUCTURE TRG4-4 NUREG/CR 2000 YO9 N1: UCENSEE EVENT REPORT (LER)- (1.0.0.56) COMPILATON For Month Of January 1990,

NUREG/CR 5533: STATIC LOAD CYCLE TESTING OF A VERY LOW. NUREG/C42000 V00 N2- UCENSEE EVENT REPORT (LER)ASPECT RATO SIX tNCH WALL TRG YYPE STRUCTURE TRG-6-4 COMPILATION for Month Of February 1990(0.27,0.50p' NUREG/C42000 V09 N3: UCENSEE EVENT REPOR| (LER)

COMPILATION.For Month Of March 1990.~

LOUISIANA STATE UNIV, BATON ROUGE, LANUREQ/C45530: ANALYSIS OF H B. ROBINSON PWR VESSEL

NUREG/C42000 V00 N4 - UCENSEE EVENT REPORT (LER)COMPILATON For Month Of Apnl 1990.

FLUENCE FOR CYCLE to UTIU21NG PART!AL LENGTH SHIELD AS. NUREG/CR-2000 V09 N5: UCENSEE EVENT REPORT (LER)SEMBUES. COMPtLATON For Month Of May 1990

NUREG/C42000 V09 N6: UCENSEE EVENT REPOHT. (LER)MANUFACTURING SCIENCES CORP,NUREG/C45001: EFFFCTS OF MANUFACTURING VARIABLES ON COMPILATON For Month Of June 1990

NUREQ/CR 2000 V09 NL UCENSEE EVENT REPORT (LER)PERFORMANCE OF HIGH LEVEL WASTE LOW CARBON STEEL COMPILATON For Month Of July 1990.CONTAINERS - NUREG/C42000 V09 N8: UCENSEE EVENT REPORT (LER)

COMPILATION For Monm Of August 1990.CARYLANO, UNIV. OF, COLLEGE P ARK, MO

NUREG/CR 4918 V04. CONTROL OF WATER INFILTRATION INTO NUREG/CR-2000 V00 N9 LICENSEE EVENT REPORT (LER)NEAR SURFACE LLW DISPOSAL UNITS Progress Report On Field Ex. COMPILATION For Monm Of September %90

NUREG/CR 2000 V09N10 UCENSEE EVENT REPORT (LER)penments At A Hunwd Region Site.Bettsydle,Marytarwi COMPILATION For Monm Of October 1990

CATERIALS ENGINEERING ASSOCIATES,lNC. NUREG/C42000 V09N11: UCENSEE EVENT REPORT (LER)NUREG/CP-0112 V01: PROCEEDINGS OF THE THIRD INTERNATON- COMPILATON For Monm Of November 1900.-

AL ATOMIC ENERGY AGENCY SPECIAUSTS' MEETING ON SUB- NUREG/CR 3873: EFFECT OF WELDING CONDITONS ON TRANS-CRITICAL CRACK GROWTHOperung Session And Techrucal Sessnon FORMATION AND PROPERTIES OF HEAT AFFECTED 70NES ON

LWR VESSEL STEELSl. Held Al Moscow, USSR.May 14 17 1990NURFG/CP 0112 V02 PROCEEDfNdS OF THE THIRD INTERNATON-

NUREG/CR 4219 V06 N2; HEAVY SECTON STEEL TECHNOLOGY

AL ATOMIC ENERGY AGENCY SPECIAUSTS' MEETING ON SUB-PROGRAM. Semiannual Progress Report For Apnt-September 1909.

- , - - + e- - m a - r--- w=- % * .y 3 yr y y

_ _ _ _ __ __ _ . _ .- - _ - - - . _ . __ _ _ ._

Contractor inder 123

NUREGIC44671 THE DF-4 FUEL DAMAGE EXPERIMENT IN ACAR NURIG/CR 5213 V02 THE COGNITIVE ENVIRONMENT $1MUL Af TONWITH A BWR CONTROL BLADE AND CHANNEL 101AS A TOOL FOR MODEUNG HUMAN PE RFORM ANCE ANDNUREGICR-4674 VQ9 PRECURSORS TO POTLNTIAL SEVERE CORE REUABluTY Main Report

DAMAGE ACCOENTF 1968 A STATUS REPORT Mem Report And Ap-per e A

P ARAMETE R, INC.NUREG/CR-4674 V10. PRECURSORS TO POTENTIAL SEVERE CORE

NUREG/044525 CLOSEOUT Of IE IMLETIN 84-03 RlFUELINGDAMAGE ACODENTS 1968 A ST ATUS REPORT Apperdies B AndC CAVITY W ATER SE AL

NUREG/C44614 V11: PRECURSORS TO POTENTtAL SEVERE CORE NURE G/CR-4661 CLOSLOUT OF 10 DULLE TIN 85?J MOf 040PE4DAMAGE ACCIDENTS 1989 A STATUS REPORT Main Report And Ap- ATED VALVE COMMON MOJC F AILURES DURING PL ANT TRAN.

SIENTS DUE TO IMPROPER SWITCH SET 11NGSNU / 44674 V12 PRECURSORS TO POTENitAL SEVERE CORE NUREG/CR 5286 CLOSEOUT OF IE HULLETIN 79-17. PIPE CRACKS !N

DAMAGE ACCIDENTS 1989 A STATUS REPORT. Appendices D And gh$NA CLO8 RATLD R SYSTEM AT R LA

CNURE G /CR-4616. PREDB. POWER REACTOR E MOR!TTLEMENT FAILURE OF EMERGENCY DIESEL GENERATOR FIELD EXCITER

DAT A BASE.VERSON 1 Progam Desenptiors TRANSFORMERNUREG/CR4229 V02 TMi-2 EPICOR-si PiSIN/UNER INVESTIGATON NUREG/C45295 CLOSEOUT or IE COMPUANCE BULLETIN M 03

LOW. LEVEL WASTE DATA hASE DEVELOPMENT PROGRAM FOR POTENTIAL F AILURE OF MULTIPLE 6CCS PUMPS DUE TO (UNGLEFISCAL YEAR 129 Annual ReportNUREG/C45366. HTAS2 A THREE DiMENSIO*lAL TRANSIENT SHIP- FAILURE OF Al4 OPERATED VALVE IN MINIMUM FLOW RECIRCU-

LATON LINE.PING CASK ANALYSIS TOOL

NURE G/CR-5374 SUMMARY OF INADEOUATE CORE COOUNG IN- NUREG/CR-5297 CLOSEOUT OF iE DULLETIN 83-05 ASME NUCLE ARCODE PUMPS AND SPARE PARTS MANUf ACTURED BY THE HAY.STRUMENTATION FOR UNITED STATES NUCLEAR POWER WARO TYLE R PUMP COMPANY

NU G/ R-5404 V01: AUXIUARY FEEDWATER SYSTEM AGING ARY TE $ UMPSNR /CR 5400 NEUTRON EXPOSURE PARAMETERS FOR THE REG /CW2 GOSEOUT W $ WM CO CONRM

METALLURGICAL TEST SPECIMENS IN THE SIXTH HEAVY SEC- TION OF NONRAD40 ACTIVE SYSTEM AND RESULTING POTENTIALTON STEEL IRRADIATON SERIES FOR UNMONfTORED. UNCONTROLLED RELEASE OF RADIOA0fiv.

NUREG'CR-5421 LAPUR USER'S GUIDE ITY TO ENVIRONMENT.NUREG/C45439 HUMAN FACTORS ISSUES ASSOCIATED WITH AD, NUREG/CR 5306 CLOSEOUT GF IE BULLETIN 7918 AUDlHILITY

VANCED INSTRUMENTATON AND CONTROLS TECHNOLOGtES IN PROOLEMS ENCOUNTERED ON EVACUATON Of PERSONNELNUCLEAR PLANTS FROM HIGH NOtFI AREASNUREG/CR 5449 DETERMINATION OF THE NEUTRON AND GAMMA NUREG/CR 5307: CLOSEOUT OF IE DULLETIN BO-02 INADEOUATE

FLUX DISTRIDUTION IN THE PRESSURE VESSEL AND CAVITY OF QUALITY ASSURANCE FOR NUCLE AR SUPPLIED E QUIPMENTA BOILILNG W ATER RE ACTORNUREG/CR5300 CLOSEOUT OF IE BULLETIN 8015 POSSrDLENUREG/CFM450: HIGH-TEMPERATURE CRACKARREST TESTS

LOSS 'V EMERGENCY NOTIFICATION SYSTEM (ENS) WITH LOSSUSING 152 MWTHICA SEN WlDE PLATES OF LOW UPPER SHELF OF Oh;.TE POWERBASE MATERIAUTESTS WP-2 2 AND WPJ 6.

NUREG/CR 5451: CRACK ARREST BEHAVOR IN SEN WIDE PLATES PITTSOURQH. UNIV. 0F. PITTSBURGH, P AOF LOW-UPPER, SHELF BASE MET AL TESTED UNDER NON1SOTH-

NUREGICR 5213 V01 THE COGNITIVE ENVIRONMENT SlMULATONERMAL CONDITIONS WP-2 SER!ESAS A TOOL FOR MODELING HUMAN PERFORMANCE ANDNUREG/CR 5463 EFFECTS OF MINERALOGY ON SORPTION OF

STRONTIUM AND CESIUM ONTO CALICO HILLS TUFF. REttABILITY Executive Samrhary

NUREG/CR 5468- OADS A MULTIOIMENS10NAL POINT KERNEL NUREG/CR 5213 V02 THE COGNITIVE ENVIRONMENT SIMULATIONAS A TOOL FOR MODEUNG HUMAN PERFORM ANCE ANDNU /CR 54 LUSON OF UNSTABLE DUCTILE TEARING AND REllADIUTY. Main Report

EXTRAPOLATED CRACK-ARREST TOUGHNES$ DATA IN PWRSANDIA NATIONAL LADORATORIES

NU kF$47 P OVE Y CURRENT INSPECTON FOR NUREG/C41667. RISK METHODOLOGY FOR GEOLOGIC DISPOSALS AM GENERATOR TUDING. Progress Report For January 1985 T

hFE MDILSNU E CR 42 4 F 0 P HEA A NUCLEARNUREG/CR5479' CURRENT APPUCATIONS OF VIBRATION MONI. POWER PLANT ACCIDENT CONSEQUENCE ANALYSIS tow LET

TORING AND NEUTRON NOISE ANALYSIS Detection Anti Analysis Of Rathatkin. Par 1 Iintroduction. Integration And SummaryStructural Degradation Of Reactor Vesset internare from Operatsonaj NUREG/CR4550 V01 R1, ANALYSIS OF CORE DAMAGE FREQUEN.A CY: INTERNAL EVENTS METHOOOLOGY.NU /CR-5480: DATA SUMMARY REDORT FOR FISSION PRv00CT NUREG/CR-4550 V3R t PI- ANALYS6S OF CORE DAMAGERELEASE TEST Vt-3 FREOVENCY.SURRY. UNIT 1. INTERNAL EVENTS

NUREG/CR5511: IRRADIATON EFFECTS ON STRENGTH AND NUREG/CR-4550 V3 RIP 2: ANALYSIS OF CORE DAMAGE FREQUERTOUGHNESS OF THREE%lRE SERIES-ARC STAINLESS STEEL CY: SURRY. UNIT 1. INTERNAL EVENTS APPENDICESWELD OVERLAY CLADOING

NUREG/CR 4550 V3 RIP 3 ANALYSIS OF CORE DAMAGE FREQUEN.NUREG/CR-5514 MODELING AND PERFORMANCE OF THE MHTGR CY SURRY POWER STATON. UNIT I EXTERNAL EVENTSRE ACTOR CAVITY COOUNG SYSTEMNUHEG/CR5519 V01 AGING OF CONTROt. AND SERVICE AIR COM- NUREG/CR 4550 V4 RIP 3. ANALYSIS OF CORE DAMAGE FRECUEN-

PRESSOAS AND DRYERS USED IN NUCLEAR POWER PLANTS CYi PEACH BOTTOM. UNIT 2 EXTERNAL EVENTSNUREG/CR4550 V5RIPt, ANALYSIS OF CORE DAMAGE FREQUEN-NUREG/CR-5530: ANALYSIS OF H.0 ROBINSON PWR VESSEL CY: SEQUOYAKUNIT 1. INTERNAL EVENTSFLUENCE FOR CYCLE 10 UTlu21NG PARTIAL LENGTH SHIELD AS-

SEMBUES NUREG/CR4550 V5 RIP 2 ANALYSIS OF CORE DAMAGE FREQUEN.CY:

NURE G/CR5552 AN OVERVIEW Or THE LOW UPPER SHELF SEQUOYAKUNf11. INTERNAL EVENTS APPENDICESNUREG/CR4551 V2R1P1: EVALUATION OF SEVERE ACCIDENT

NUR /C 5 53 C P AMS FOR EDDY. CURRENT RISKS QUANTIFICATION OF MAJOR INPUT PARAMETERS ExpartOpenson Elecitation On in Vessel lasues

NURE A 5554 ECOMMENDATONS FOR THE SHALLOW-CRACK NUREG/CR45b1 V2R t P7- EVALUATION OF SEVERE ACCIDENTFRACTURE TOUGHNESS TESTING TASK WITHtN THE HSST PRO- RISKS OUANTIFICATION OF MAJOR INPUT PARAMETERS MACCSGRAM I"Ddr

NUREG/CR5584 RESULTS OF CRACK. ARREST TESTS ON TWO IR. NUREG/CR 4551 V3RIPt: EVALUATION OF SEVERE ACCIDENTRAD > ATED HtGH-COPPER WELDS RISKS SURRY UNIT 1 Main Report

NUREG/CR 5591 V01 N1- HEAVY SECTION STEEL 1RRADIATON NbREG/CR 4551 V3RtP2. EVALUATION OF SEVERE ACCIDENTPROGRAM bemiannual Progrou Report For October 1980 March AfSKS SURRY UNIT t Appendices1990

NUREG/CR4551 V4RtPt: EV ALUA TION OF SEVERE ACCIDENTNUREG /CR5605 LAPUR BENCHMARK AGAINST IN. PHASE AND RISKS PEACH DOTTOM. UNIT 2. Main Report

OUT OF PHASE STABluTY TESTS NUREG/CR 4551 V4 RIP 2. EVALUA TION OF SEVERE ACCOENTOHIO STATE UNIV, COLUMBUS. OH HISKS PEACH DOTTOM. UNIT 2. Appendices

NUREG/CR 4551 V5RIPI EVALUATION OF SEVERE ACCIDENTNUREG/CR 5213 V01: THE COGNiilVE ENVIRONMENT SIMut.ATION RISKS SEQUOY AH.UNii 1 Main RetortAS A TOOL FOR MODEUNG HUMAN PERFORMANCE AND NUREG/CR4551 V5 RIP 2 EVALU A TION OF SEVERE ACCIDE NTREUA81UTY ExecutNe Summary RISKS SEQUOYAH. UNIT I Appendicos

124 Contractor index

NUREG/CR 4551 V6R1P1: EVALUATON OF SEVERE ACCIDENT SCIENCE APPLICATIONS INTERNATIONAL CORP.tFORMERLYSCIENCE APPUCATiONS,

R!SKS ORAND GULF. UNIT 1 Main Report.NUREG/CR 4551 V6R1P2: EVALUATON OF SEVERE ACCOENT

NUREG-0713 Vn9 OCCUPATONAL RADIATION EXPOSURE AT COM-MERCIAL NUCLEAR POWER REACTORS AND OTHER FACILITIESRISKS GRAND GULF. UNIT 1. Appenctices

NUREQ/CR4668. DAMAGED FUEL EXPERIMENT OF 1.Results And1967 Twentem Annual Re%rt

NUREG/CH-4550 V01 R1: ANALYSTS OF CORE DAMAGL FREQUEN-Analysee CY INTERNAL EVENTS ME7HODOLOGY,

NUREG/CR-4671: THE OF-4 FUEL DAMAGE EXPERIMENT IN ACAR NUREG/CR 4551 V2R 1P1. EVALVATON OF SEVERE ACCIDENTWITH A BWR CONTROL DLADE AND CHANNEL BOK. RISKS GUANTIFICATION OF MAJOR INPUT PARAMETERS Export

NURE G /CR4601 Vol; MELCOR ACCIDENT CONSEQUENCE CODE Open Ehenahon On in-Vessel testesSYSTEM (MACCStyolume t' User's Guce NUREG/CR-4551 V4RtPl: EVALUATION OF SEVERE ACCIDENT

NUREG/CR-4691 V02: MELCOR ACCOEM CONSEQUENCE CODE RISKS PEACH DOTTOM. UNIT 2 Main ReportSYSTEM (MACCSLVolume 2 Model Description NUREG/CR-4551 V4 rip 2 EV ALUATION OF SEVERE ACCtDENT

NUREG/CR 4621 V03. MELCOR ACCIDEN* CONSEQUENCE CODESYSTEM (MACCSLVolume S Propammer's Ruerence Manual NU /C 51 6 P1 VA U 10 F SEVERE ACCIDEN1

NUREG/CR 4794 EXPERIMLNT AI RESULTS OF CORECONCRETE RISKS GRAND GULF. UNIT 1 Main RN OF SEVERE ACCIDENTINTERACTONS USING MOLTEN STEEL WITH ZlRCONIUM. NUREGICR 4551 YbR1P2. EVALVATNUREG/CR 4840 PROCEDURES FOR THE EXTERNAL EVENT CORE RtSKS GRAND GULF UNIT 1. Appeeces

DAMAGE FREQUENCY ANALYSES FOR NUREG 1150'H PERFORM'NUREG/CR 5253. PARYlTON. A PROGRAM FOR DEFINING THE

UNCERTAINTIES ASSOCIATED WIT SOURCE TERM! CONSEQUENCE ANALYSIS INTERF ACE IN THENUREG/CR 5211:ANCE ASSESSMENT Or HIGhtEVEL RADIOACTIVE WASTE NUREG 1150 PROBABILISTIC RISK ASSESSMEN18 0wr's GukteREPOSITORIES A Summary Report NVREG/CR 6436 V01: THE DEVELOPMENT AND EV ALVATON OF

NUREG/CR 5253 PARTITON A PROGRAM FOR DEFINING THE PROGRAMMATIC PERFORMANCE INDICATORS ASSOCIATED WITH

SOURCE TERM / CONSEQUENCE ANALYSIS INTERFACE IN THEMAINTENANCE AT NUCLEAR POWER PLANTS Main Report

NUREG-1150 PROBA8tuST:C RISK ASSESSMENTS User's GuMe NUREGiCR4436 YO2: THE DEVELOPMENT AND EVALVATON OF

NUREG/CR 5256 COMPONENTS OF AN OVERALL PERFORMANCE PROGRAMMATIC PERFORMANCE INDICATORS ASSOCIATED WITHMAINTENANCE AT NUCLEAR POWER PLANTS Appeeces

ASGESSMENT METHOOOLOGY-NUREG/CR 5262: PRAMIS PROBABluTY NSK ASSESSMENT MODEL NUREG/CR 5472. A RISK BASED REVIEW OF INSTRUMENT AIR SYS-

TEMS AT NUCLEAR POWER PLANTSINTEGRATION SYSTEM User's Gukte

NUREG/CR 5316 MELT PROGRESSON,0KOATION. AND NATURAL NUREG/CR M10: EVALuATONS OF CORE MELT FREQUENCY EF-FECTS DUE TO COMPONENT AOHG AND MAINTENANCE.

CONVECllON IN A SEVERELY DAMAGED REACTOR CORE. NUREG/CR 5500 ASSESEMENT OF THE COMDUSTION MODEL INNUREG/CR 5373. A DEMONSTilATON EXPERIMENT OF STEAM. THE HECTR CODE

DRIVEN. HIGH-PRESSURE MELT EJECTON The HIPS-108 Test NUREG/CH 5622. ANALYSIS OF REACTOR TRIPS ORIGINAflNG INNUREG/CR4361: ECONOMIC RISK OF CONTAMINATON CLEANUP

COSTS RESULTI FR ARGE NONREACTOR NUCLEAR MATE. gjgy g 36350F MYL ND MOLECULAR RESEARCH TOCREDUCE UNCERTAINTIES IN ESilMATES OF HEALTH EFFECTS

NUREGICR4393 A REVIEW OF TECHNOUES FOR PROPAGATINGDATA AND PARAMETER UNCERTAINTIES IN HIG+ LEVEL RADO- NUREG/ 5 VERVIE ND AI OF U S. COMMER-

ACTNE WASTE REPOSITORY PERFORMANCE ASSESSMENT CIAL NUCLEAR POWER PLANTS Nuclear Power Ptant System Sour-MODELS.

NUREG/CR 5398 TECHNICAL BASIS FOR REYlEW OF HIG4 LEVEL Nt$F CR4659 CONTROL ROOM HABITA81UTY SYSTEM REVIEWWASTE REPOSITORY MODELING MODELS'

NUREG/CR4405 ANALYSIS OF SHELL RUPTURE FAILURE DUE TOHYPOTHETICAL ELEVATED TEMPERATURE PRESSUR12ATON OF

SOUTHERN CALIFORNIA UNIV. OF, LOS ANGELES, CA

THE SEQUOYAH UNIT 1 STEEL CONT AINMENT DUILDING NUREG/CR 5411: EUCfTATION 4 USE OF EXPERT JUDGMENT IN

NUREG/CR 54 t t: ELICITATON A U"E Or EXPERT JUDGMENT IN PERFORMANCE ASSESSMENT FOR HOSLEVEL RADIOACTIVE

PERFORMANCE ASSESSMENT FOR HlGH-LEVEL RADtOACTWE WASTE REPOSITORIES

WASTE REPOSrTORIES.NUREG/CR 5453 VOS BACKGROUND INFORMATION FOR THE DE-

T AlW AN POWER CO.

VELCPMENT OF A LOW-LEVEL WASTE PERFORMANCE ASSESS-NUREG/CP 0100 PROCEEDINGS OF THE SEMINAR ON LE AK-

DEFORLOREAK Further Dewccments in Regulatory Poloes AndMENT METHODOLOGY.Compu*er Code implementation And Assess.

Supparing Research.mont.

NUREG/CR4460 A CAUSE DEFENSE APPROACH TO THE UNDER- TECHNADYNE ENGINEERING CONSULTANTS,INC.STANDING AND ANALYSIS OF COMMON CAUSE FAILURES NUREG/CR-4551 V5 RIP 1: EVALUATON OF SEVERE ACCIDENT

NUREG/CR4461: AGING OF CABLES, CONNECTONS, AND ELECTR). YA UN 1 amPENETRATION ASSEMBLIES USED IN NUCLEAR POWER g.KSSEg/CR g VAL N OF SEVERE ACCIDENT

RISKS. SEQUOYAH, UNIT 1. ApperdcasNUREG/CR4476. POSTTEST ANALYSIS OF A 16 SCALE REIN.

FORCED CONCRETE REACTOR CONTAINMENT BUILDING- TENNESSEE, UNIV, OF, KNOXVILLE, TNNUREG/CR4517: IMPACTS-BACNERSON 2 0 Program Use's Manual NUREG/CR 3873 EFFECT OF WELDING CONDITONS ON TRANS-NUREG/CR4521: USE OF PERFORMAN'1E ASSESSMENT IN AS- FORMATON AND PROPERilES Or HEAT AFFECTED ZONES ON

SES$1NG COMPUANCE WITH THE CONTAINMENT REQUIRE. LWR VESSEL STEELS'MENTS IN 40 CFR PART 191.

NUREG/CR 5532: A PERFORMANCE ASSESSMENT METHODOLOGY WESTINGHOUSE ELECTRIC CORP.FOR LOW LEVEL WASTE FACIUTIES. NUREQ/CR-5213 VOI: THE COGNITIVE ENVtRONMEM SIMULATON

NUREG/CR4545 VICTORIA: A MECHANISTIC MODEL OF RADIONU- AS A TOOL FOR MODELING HUMAN PERFORMANCE ANDCUDE BEHAVOR IN THE REACTOR COOLANT SYSTEM UNDER RFLIABiUTY ExecutNe Summary

NUREG/CR-5213 V02 THE COGNITIVE ENVIRONMENT SIMULATONSEVERE ACCIDENT CONDITIONS-NUREG/CR4586 MITIGATON OF DIRECT CONTAINMENT HE ATING AS A TOOL FOR MODELING HUMAN PERF ORM ANCE AND

AND HYDROGEN COMBUSTON EVENTS IN ICE CONDENSER REUABlWTY. Main Report

PLANTS Anatyses With The CONTAIN Coce And NUREG-1150 PRAWYLE LABORATOFl!ES

NUREG/CR 5500 ASSESSMENT OF THE COMBUSTON MOOEL INNUREG/CR 5386 DASIS FOR SNUBBER AGING RESEARCH. NUCL.E.Methodology.

AR PLANT AGING RESEARCH PROGRAMTHE HECTR COOE-

. _. _ _ . _ __ _ __ . _ _ _ _ _. _ ._ __ _ _ _ . . . _ _ ___

international Organization index

This index lists, in alphabetical order, the countries and performing organizations that pre-aared the NUREG/!A reports listed in this compilation. Listed below each country and per."orming organization are the NUREG/lA numbers.and titles of their reports. If further infor-mation is needed, refer to the main citation by the NUREG/lA number.

DELQlVM . SWEDENTRACTEBELSWEDiSH NUCLEAR POWER INSPECTORATE'

NUREG/IA4034 ASSESSMENT STUDY OF RELAPS/ MOO 2 CYCLE NUREC.'lA 0033 ASSESSMENT OF RELAPS/ MOD 2 UYCLE 36.0436.04 BASED ON PRESSURIZER SAFETY AND RELIEF VALVE AGAINST LOFT SMALL BREAK EAPERIMENT L34

' SWIT2ERLAND -FRANCgPAUL SCHERRER INSTITUTE

COMMISSION OF ATOMIC ENERGY NUREG!!A 0018. RELAP5/ MOO 2 ASSESSMENT, OECD LOFTNUREG/LA 0023 ASSESSMENT OF TRAC.PF1/ MOO 1 VERSION 14.3 SMALL BREAK EXPERIMENT LP-$8-03.USING SEPARATE EFFECTS CRsTICAL FLOW AND BLOWDCMrNEXPERIMENTS VOLUME 1: TEXT AND TABLES UNITFD KINGDOM

NUREG/lA4023- ASSESSMENT OF TRAC.PF1/ MODI VERSION 14.3 CEN|RAL ELFCTRICITY GENERATING DOAADUSING SEPARATE EFFECTS CRTTICAL FLOW AND BLOWDOWh NUREGAA4012. 4, ? LAPS / MOO 2 CALCULATIONS OF OECD LOrTEXPERIMENTS. VOLUME 2 FIGURES TEST LP SB01.

NUREQ/lA-0013 RELAD$/ MOO 2 CALCULATONS OF OECD LOFTTEST LP-SB43 -

OREA NUCLEAR SAFETY CENTEF. f A 0mNUREG/IA4030 ASSESSMENT OF RELAP6/ MOO 2 COOE UtWG 73 (

UNITED KINODOM ATOMIC ENERGY AUTHORITYLOSS OF OFFSfTE POWER TRANSIENT DATA OF KNU #1 NUREO/lA4011: TRAC.PF1/ MOO 1 POST,1EST CALCULATONS OFPLANT.NUREG/lA4031: ICAP ASSESSMENT OF RELAP6/ MOO 2, CYCLE THE OECO LOFT EXPERIMENT LD SB 1.

36.06 AMINST LOFT SMALL BREAK EXPERIMENT L34. NUREOhA4019: TRACPF1/MOct POST TEST CALCULATONS OFTHE OECD LOFT EXPERIMENT LP.S8 2.NUREO/lA4032: ASSESSMENT OF RELAPS/ MOO 2 CYCLE 36 04

NUREO/tA4022: TRAC-PF1/ MOO 1 POST TEST CALCULATIONS OFUSING LOFT LARGE BREAK EXPERIMENT L2 5.THE OECO LOFT EXPERIMENT LP-SB.3.

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Licensed Facility Index

This index lists the facilities that were the subject of NRC staff or contractor reports. Thefacility names are arranged in alphabetical order. They are preceded by their Docket number

i

Gnd followed by the report number, if further information is needed, refer to the main citationby the NUREG number,

S42e AMn W Voges kc'es Plant, DW 1, Georpe NURE41410 M443 Seetroot hise Sueon, WW 1, P4c Sevce NURE4t3eepoen CoCa eNo.sen v.b445 Conethe Peet Sneem Dects $4seon, UrW 1, NUREG479? $22 64443 Sestrock ktow $ asea WW 1, Pd; Sernce NUREG1425

Tense Uttese DoceCo e New HempetsS 445 Comache Peak liese Deces Stenon, uit I, NWIEG4797 $23 64444 W kctaw weson, UrW L P@c $ ewe IdJREG4696 $09

fense Uueens Doct.4 of New hemfewS 445 Comeri:he Peak $imem Dectt $4seon, UrW 1, NUREG4797 $24 4 444 $setroot kries avun be 2, P@c Semco NURE41425

B445 Peak Docte $4ston, Urd 1, NURE41381 @ 327 - - MiaN WW 1. Tomasone NUREG/W560 V5R1P1' $4445 - Co Decer Steson, DW 1, NURE413eg 54327 ~ Plant, Urd 1. Temessee NUREWCR4550 V5 RIP 2Tome Utsese Elect Veavy Morg

54446 Comece Pese Saeem Decet $leton, W 2, NUREG4797 822 M7 88 pre Mcteer Ple'it, Ure 1, Tomesses NUREG/CR4561 Y5RIPI'

temas Utleen Elect Vetey MalyS 446 Comsche Poen senem Ekte Sheon, WW L NUREG4797 $23 64327 8eppe kiner Pist Uret 1, Temessee NUREG/CM61 V5R1P2Tense Utsese Doce veney Morgbe46 Come@e Peak Stesti Decet Season, UrW 3, NUREG4797 $24 M 8m*ove kdeer Plant, W 1, temeense - MG/CR 644 -Tome Ulease Doc, Yeasy AumorerS3e6 De*8eene Nudeer Poser secon, Ure 1, NUREG/Cn5603 54327 - Sancyeh k1 c Piwt Ur* 1, temese NUREGGMTeento Edson Co Venev AumontyWF75 Dieteo Canyon Mcseer Poma Mart, Dit I, MJREG/CR 5616 M Sepye Nucter Pient, UrW L tenneeees M&me02

Peate Gee & Flecetc Co Veney Aumonty. nr37 Desden kms Pouw SmA WW t, NURE41403 E290 SW Poww Stran W 1, Vepro Elects & . NUREG/CR4550 V3RIPier - Edson Co Poner Ca$4416 Grand GUI Nucteer SaskA UrW 1, useneg4 NUREG/CA4551 VtR1Pt M % Poew sukA Ur* t Wyne Nine & NUREWW550 V3R;P2B416 Gr G Stenon Urd 1, by NUREG/CR4551 WRIP2 M $kes, W t WgneE W 4 mW20 V3RIN

kB M UrW t.Cnome PowerS 261NUREG/C46530 200 Sirty Power StemA Urd t Vrgne Decat & NUREGICR4551 V3R1P1

m_ . ,. _&M _ _ . , M ,

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u!:|f"C b tC.mm.es..m - - s527 =:.m255

Ps|= " Ett a *,," = % % e ' a =!!&"Saaa.t C- Powe, Ca m 4,mm =t --530 v4RinPMedetese Decenc C4 .e. k,es, m . t nmessee mG 4,,05

B377 Pem*i Somom Ascenc Power Steen ud f, MG/C44551 V4 RIP 1 SM Wene kcasar Plant, und 1, Tenneense NURE41232 V04

V uenryPNimassNe Docts Co-

Veney .wtherty54277 Peach Bonom Atonec Power $4sson, Urs 2, NW4EG/CR4551 V4R1P2 54391 wem se kcteer Piant, Urd L Tennsesen NUREG4647 $06PNiedeeNo Esecee CaVenef Auswre.$4443 Sestrook Nuclear Steem, UrW L PWc Sense NUREG4ee6 SM 54295 hon kcteer Powe $4 hon, W 1, NUREG/CR4550 V7 Rol 'Ca of New HempeneCommonweenn Eesco Ca

127

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NRC FORM SM(pag - U.S. NUCLEAR HEQtAATORY eOMMSF,CN t IENII NUMittHNRCM i102, Assigrod by NHO, Adid Vol.320h a202 uw. Rn, and Amt ndum Mim.

BIBUOGRAPHIC DATA SHEET 6'' * - " *"r 3is instrucuan. on in. e.m.) NUllI!G-0301

a urtt ANo suumte Vo1.15, No. 4 -

3. DA f f hlPUHI PUUUSttLP11egulatory and Technical 11eports ( Abstract Index Journal)

yogg ygnAnnual Compilation for 1990 March - 1991

4. FIN C#1 CRANT NVM0ER

6 AvlrivHit46. 3 YPt, OP nLPOH r

lieference

r. eenoo covtoto wum. o....)i

1990

a. n.nsonwN.o..onomzAroN - NAue ANo.nd m.ntsa in m...e. wwm o.m.,. on.c. , n.pn. u 6. ew.., n.gw.wy cww...m anaAcom mna ae ; n contracin, umid. riam. mnon e >

Division of Freedom of Information and Publications ServicesOffice of AdministrationU.S. Nuclear llegulatory CommissionWashington, DC 20555

9. UV4Sosu.N.,O ORG.ANi2ATON * NAME.nd m. ADO 6ESS.io(if NHC, typ. * $.m. .s aboy.'4 it contractor. Nmo. NHC Divlsson, Offc. or H.gnon,4

ANDv. s tw R.ous iory commtnilon, mrs .o

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Same as 8, above.

10. 41WPLLMLNr AHY NOT S

11, ABSTRACT (200 words or I.s.)

This journal includes all formal reports in the NUltliG series prepared by the NitC staff and contractors; proceed-ings of conferences and workshops; as well as international agreement reports. The entries in this compilation areindexed for access by title and abstract, secondary report number, personal author, subject, NP.C orgamzation forstaff and international agreements, contractor, international organization, and licensed facility,

.

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compilation 14. SECURITY Ct. ASS $1CATON- abstract index g,,,,,,,,,

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NRC FO81M 3% (2-693

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Tl!IS DOCUMENT WA8 PRINTED USING RECYCLED PAPER.

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'^ ''NUCLEA's t TORY Mi&SIONj"'wAsswoTow, o.c. sones

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I cnd AbstractsMain Citations ir0s55139s31 1-1AN1Ac14sicv1

g,Ny8-|A{4 0USLIC ATI ONS S VC P,les-POR-NUREGP-?23WASHINGTON De 70555

S3condary ReportNumber Index

Personal Author index

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Subject index

NRC Originating OrganizationInder (Staff Reports)

NRC Originating OrganizationIndex (International Agreements)

NRC Contractor I

SponsorIndex

Contractor index

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inten i Janizationinde- 1

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Licensed FacilityIndex

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NUREG - Nuclear Regulatory Commission

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