certificate of compliance no. 9218 revision 6 march 30,1995

INFORMATION ONLY

CERTIFICATE OF COMPLIANCENO. 9218

REVISION 6

MARCH 30,1995

DISCLAIMER

This report was prepared as an account of work sponsored by an agency of the United StatesGovernment. Neither the United States Government nor any agency thereof, nor any of theiremployees, makes any warranty, express or implied, or assumes any legal liability or responsi-bility for the accuracy, completeness, or usefulness of any information, apparatus, product, orprocess disclosed, or represents that its use would not infringe privately owned rights. Refer-ence herein to any specific commercial product, process, or service by trade name, trademark,manufacturer, or otherwise does not necessarily constitute or imply its endorsement, recom-mendation, or favoring by the United States Government or any agency thereof. The viewsand opinions of authors expressed herein do not necessarily state or reflect those of theUnited States Government or any agency thereof.

TKI? DOCUMENT IS UNLIMITED

DISCLAIMER

Portions of this document may be illegiblein electronic image products. Images areproduced from the best available originaldocument

CERTOCATE OF COMPLIANCE10 OT71 FOR RADIOACTIVE MATERIALS PACKAGES1.1.CERTIFICATE NUMBER

92186. REVISION NUMBER

7&PACKAO& loemncA-noN NUMBER &PAGE NUMBER

1;•. TOTAL NUMBER fAOH

JLL PREAMBLE . . . •

a.- Thta cartHIcate fa istuad to certify that tha packaging and contants described In ttam 5 betaw. meats theappiicanleaafatyatandartasatforthlnTitlaiO.Codaof Federal Regulations. Part 71, "Packaging and Transportation of Radloactiva Material.*" . .

b. This certificate doas not relieve tha consignor from compiianca with any requirement of the regulations of tha U S . Department of Transportation or otharapplicable regulatory agencies, including tha government of any country through or into which tha package will ba trantportod.

3. THIS CERTIFICATE IS ISSUED ON THE BASIS OF A SAFETY ANALYSIS REPORT OF THE PAOOUSEDESIGN OR APPLICATIONa, ISSUED TO 0U«i» « * * * * • » ; • . . 5. x m ^ AHO IDENTIFICATION OF REPORT OR APPLICATION:

Department of EnergyWashington, DC 20585

Nuclear Packaging Inc. applicationdated March 3, 1989, as supplemented.

c. DOCKET NUMBER . 7 1 - 9 2 1 8

4, CONDITIONSThis certificate is conditional upon fulfilling tlw requirements of 10 CFR Part 71 ;aa applicable, and tha conditions specified below.

(a) Packaging " - . . . •

(1) Model No.: TRUPACT-II , '

(2) Description ""; >" / / / ' ' •-. . •

A stainless steel and poiyurethane foam insulated shipping containerdesigned to provide double containment for shipment of contact-handled •transuranic waste. The packaging consists of an unvented, 1/4-inch thickstainless' steel inner containment vessel (ICV), positioned within an outercontainment assembly {OCA) consisting of an unvented 1/4-inch thick stain-less steel outer containment vessel (OCV)i a 10-inch thick layer of poly-urethane foam and a 1/4 to 3/8-inch thick outer stainless steel shell. Thepackage is a right circular cylinder with outside dimensions ofapproximately 94 inches diameter and 122 inches height. The packageweighs not more than 19,250- pounds when loaded with the maximum allowablecontents of 7,265 pounds. . . • t J '

• ' K ~i. ~*\... *'The OCA has a domed lid which is secured to the OCA body with a lockingring. The OCV containment seal is provided by a butyl rubber 0-ring (boreseal). The OCV is equipped with a seal test port and a vent port.

The ICV is a right circular cylinder with domed ends. The outsidedimensions of the ICV are approximately 73 inches diameter and 98 inchesheight. The ICV lid is secured to the ICV body with a locking ring. TheICV containment seal is provided by a butyl rubber 0-ring (bore seal).The ICV is equipped with a seal test port and vent port. Aluminum spacersare placed in the top and bottom domed ends of the ICV during shipping.The cavity available for the contents is a cylinder of approximately 73inches diameter and 75 inches height.

KftCFOMinM CONDITIONS (conttnvd) U * NU(*EAR REQUUTORY COMUIttlC

Page 2 - Certificate No. 9218 - Revision No. 7 - Docket No. 71-9218

5.(a) Packaging (continued) • .

(3) . Drawings* #

The packaging is constructed in accordance with Nuclear Packaging Inc.Drawing No. 2077-500 SNP, Sheets 1 through 11, Rev. K.

• The contents are positioned within .the packaging in accordance withNuclear Packaging Inc. Drawing Nos. 2077-007 SNP, Rev. C, and 2077-008SNP, Sheets 1 and 2, Rev. C. '

(b) Contents

(1) Type and form of teri\ **r

'" *~G (//Dewatered, soTj£p r solidified transuranic an» frcit'ium-contaminatedwastes. Wast^must be packaged in 55-gallon arums, standard waste boxes(SWB), or Uft$. Wastes must.be restricted to prwnJfcLit explosives,corrosives ^ ^ r a d i o a c t i v e phrophorics and pressur^ed containers. Withina drum, t$n*or^5WBjO"adioactive pyrophoricjrfcf not^xceed 1 percent by...„.;~i.* .-j*fc— **—r**~ m u s t n o t exceed/1/getcent by volume.

00 o ^weight ami/Treeorgan i q » S r e 11 mi

(2) Maximurn^Uantity

Conten4rmotcontaine/*^, wf ijpounds per Cfm^(

Maximum rHimberconfiguratityns

» #(11)(111)(iv)(v)(vi)

pFlammable

drum, bin or SWB.

d secondarydrum and 4,000

re authorized packaging

2 SWBs, each SWB contain intone'2 SWBs,2^chJ5WB «ontaajjiflfl4 55-gallon drums,1 ten-drum o r e r p ^ (7B0P), containing 10 55-gallon drums,1 TDOP, containing 1 SWB,1 TDOP, containing 1 bin within an SWB, or

(viii) 1 TDOP, containing 4 55-gallon drums within an SWB.

Fissile material not to exceed 325 grams Pu-239 equivalent with no morethan 200 grams Pu-239 equivalent per 55-gallon drum or 325 grams Pu-239equivalent per SWB. Pu-239 equivalent must be determined in accordancewith Appendix 1.3.7 of the application.

Decay heat not to exceed the values given in Tables 6.1 through 6.3"TRUPACT-II Content Codes", (TRUCON), DOE/WIPP 89-004, Rev. 8.

(c) Transport Index for Criticality Control

Minimum transport index to be shown onlabel for nuclear criticaHty control: 0.4

CONDITIONS (continue!)

Page 4 - Certificate No. 9218 - Revision No. 7 - Docket No. 71-9218

OS. NUCLEAR REGULATORY COMMISSION

REFERENCES . '

Safety Analysis Report for the TRUPACT-II Shipping Package dated March 3, 1989.

Supplements dated: May 26, June 27, June 30, August 3, and August 8, 1989;April 18, July 10, July 25, August 24, and December 20, 1990; April 11, April 29,and June 17 1991; September 24, 1992; April 22, and October 22, 1994.

"TRUPACT-II Content Codes", (TRUCON), DOE/WIPP.89-004, Rev. 8, dated October 1994.

Date:

rbiMm\(j\(j./NUCLEAR REGULATORY COMMISSION

William D. TravfersVmrector.Spent Fuel ProjOffice of

andMaterial Safety

UNITED STATESNUCLEAR REGULATORY COMMISSION

WASHINGTON, D.C. 20855-0001

/* * * * *

APPROVAL RECORD. Model No. TRUPACT-II"PackageCertificate of Compliance No. 9218

Revision No. 7

The Nuclear Regulatory Commission and the Department of Transportation haveadopted new regulations for the safe transport of radioactive material (60 FR50248 and 60 FR 50292). Among other things, the new regulations includeprovisions that affect the shipment of fissile material packages.. Under thenew regulations, the transport index, rather than fissile class, is used tolimit the number of fissile material packages that may be transportedtogether. . • . . . •

The Certificate, of Compliance has been revised to be consistent with the newprovisions for fissile material packages, and to specify the minimum transportindex to be shown on the package label for nuclear criticality control. Thechanges in the certificate are summarized below for .the three fissile classespreviously used:

Fissile Class I - Certificates are being revised to show a minimumtransport index of 0.4, consistent with the accident array size of 250packages specified in the previous regulations. Accordingly, thesepackages may no longer be transported with an unlimited number ofpackages per shipment.

Fissile Class II - The minimum transport index is unchanged.

Fissile Class III - Certificates are being revised to show a minimumtransport index derived in accordance with 10 CFR §71.59 of the newregulations, based upon the maximum number of packages per shipmentspecified in the previous certificate. Because the new regulationsrequire larger array sizes to be considered under normal conditions,some packages previously authorized as Fissile Class III may now belimited to fewer packages per shipment. Packages previously authorizedfor one package per shipment are being assigned a transport indexof 100.

The staff expects that some certificate holders for packages previouslydesignated Fissile Class I and Fissile Class III may choose to submit anapplication, with appropriate information, requesting a lower transport index.

William D. Travers, DirectorSpent Fuel Project OfficeOffice of Nuclear Material Safety

_ and SafeguardsDate

TRUPACT-II SARP (CONDENSED) Revision 14, October 199.4

TRUPACT-II

SAFETY ANALYSIS REPORT

FOR PACKAGING (SARP)

CONDENSED VERSION FOR PAYLOAD

CONTROL, USE, AND MAINTENANCE

Revision 14

October 1994

Prepared by: Westinghouse Electric CorporationWaste Isolation'DivisionCarlsbad, NM 88220

Prepared for U.S. Department of EnergyCarlsbad Area OfficeCarlsbad, NM 88221

TRUPACT-II SARP (CONDENSED) Revision 14, October 1994

TRUPACT-II SARP CONDENSED VERSION FOR

PAYLOAD CONTROL, USE, AND MAINTENANCE

INTRODUCTION

The condensed version of the TRUPACT-II Safety Analysis Report for Packaging (SARP) containsessential material required by TRUPACT-n users, plus additional contents (payload) informationpreviously submitted to the U.S. Nuclear Regulatory Commission.

All or part of the following sections, which are not required by users of the TRUPACT-II, are deletedfrom the condensed version:

• Structural analysis• Thermal analysis• Containment analysis

Criticality analysisShielding analysisHypothetical accident test results.

i-2


TRUPACT-II SARP CONDENSED VERSION FOR

PAYLOAD CONTROL, USE, AND MAINTENANCE

CONTENTS

PAGE

TRUPACT-II CERTIFICATE OF COMPLIANCE

NRC APPROVAL RECORD

1.0 GENERAL INFORMATION 1-1

1.1 Introduction 1-1

1.2 Package Description 1-8

1.2.1 Packaging 1-8

1.2.2 Operational Features 1-19

1.2.3 Contents of Packaging 1-19

1.3 Appendix 1.3.0-1

1.3.1 References . 1.3.1-1

1.3.2 Packaging General Arrangement Drawings 1.3.2-1

1.3.3 Specification for 55 Gallon Drum and Liner 1.3.3-1

1.3.4 Specification for Standard Waste Box and Ten Drum Overpack 1.3.4-1

1.3.5 Carbon Composite and Kevlar Filter Vent Specifications 1.3.5-0

1.3.6 Specification for Closure of Inner Confinement Layers 1.3.6-1

1.3.7 TRUPACT-II Authorized Methods for Payload Control

(TRAMPAC) 1.3.7-0

1.3.8 Payload Assembly Drawings 1.3.8-1

1.3.9 Waste Sampling Programs at DOE Sites 1.3.9-1

1.3.10 Use of TRUPACT-II for Shipment of Tritium-ContaminatedWaste ' 1.3.10-1

2.0 STRUCTURAL EVALUATION

2.10 Appendices

2.10.9 Free Halides in the TRUPACT-II Payload—Source Termand Release Rate Estimates 2.10.9-1

2.10.11 Volatile Organic Compounds (VOC) in the TRUPACT-IIPayload—Source Term and Release Rate Estimates 2.10.11-1

2.10.12 Chemical Compatibility of Waste Forms 2.10.12-0


3.0 THERMAL EVALUATION

3.4.4 . Maximum Internal Pressure 3-43

3.6 Appendices

3.6.4 Shipping Period for TRUPACT-n 3.6.4-1

3.6.5 Biological Activity Assessment 3.6.5-0

3.6.6 Thermal Stability of Payload Materials at Transport Temperatures 3.6.6-0

3.6.7 Effective G Values for TRUPACT-II Waste Types 3.6.7-0

3.6.8 Radiolytic G Values for Waste Materials 3.6.8-0

3.6.9 Gas Release Assessment 3.6.9-0

3.6.10 Gas Release Testing 3.6.10-0

3.6.11 Aspiration of Unvented Payload Containers of CH-TRUWaste 3.6.11-0

3.6.12 Temperature Dependence of Hydrogen Gas Generation andRelease Rates 3.6.12-0

3.6.13 Effect on Decay Heat Limits of Overpacking PayloadContainers in a Ten Drum Overpack 3.6.13-0

7.0 OPERATING PROCEDURES 7-1

7.1 Procedures for Loading the Package 7-1

7.1.1 Loading the Payload Containers 7-1

7.1.2 Loading the TRUPACT-II Shipping Package 7-1

7.2 Procedures for Unloading the Package 7-12

7.3 Preparation of an Empty Package for Transport 7-12


7.4.1 References 7.4.1-1

7.4.2 Assembly Verification Leak Test 7.4.2-1

7.4.3 Payload Control Procedure 7.4.3-1

8.0 ACCEPTANCE TESTS AND MAINTENANCE PROGRAM 8-1

8.1 Acceptance Tests 8-1

8.1.1 Visual Inspection 8-1

8.1.2 Structural and Pressure Tests 8-1

8.1.3 Leakage Tests 8-2

8.1.4 Component Tests 8-9

8.1.5 Tests for Shielding Integrity 8-11

8.1.6 Thermal Acceptance Tests 8-11

ii-2


8.2 Maintenance Program 8-12

8-12

8-12a

8-17

8.2.1 •

8.2.2

8.2.3

8.2.4

8.2.5

8.2.6

Appendix

8.3.1

Structural and Pressure Tests

Leak Tests

Subsystems Maintenance

Valves, Rupture Discs, and Gaskets on the ContainmentVessel

Shielding

Thermal

References

8-26

8-26

8-27


8.3.1-1

9.0 QUALITY ASSURANCE 9-1

9.1 Introduction - 9-1

9.2 Quality Assurance Requirements 9-1

9.2.1 U.S. Nuclear Regulatory Commission 9-1

9.2.2 U.S. Department of Energy 9-1

9.2.3 Transportation to/from WIPP 9-2

9.3 NRC Regulatory Guide 7.10 9-2

9.4 Procurement 9-2

9.5 Design 9-3

9.6 Fabrication, Assembly, and Testing 9-3

9.7 Use 9-3

9.7.1 DOE Shipments to/from WIPP 9-3

9.7.2 Other DOE Shipments: Non-WTPP ' 9-4

9.7.3 Non-DOE Users of TRUPACT-H 9-4

9.8 Maintenance and Repair 9-4

9.9 References 9-5

ii-3


REVISION DATES

REVISION NO. C of C REVISION NO. DATE

0 March 3, 1989

1 May 26, 1989

2 June 27, 1989

3 August 3, 1989

4 . August 8, 1989

0 August 30, 1989

5 April 18, 1990

6 July 10, 1990

7 July 25, 1990

1 September 14, 1990

8 August 24, 1990

9 December 20, 1990

2 April 25, 1991

10 April 29, 1991

11 June 17, 1991

3 August 1, 1991

12 September 24, 1992

4 November 19, 1992

13 April 13, 1994

5 June 9, 1994

14 October 24, 1994

6 March 30, 1995

ii-4

NuPac TRUPACT-II SAR Rev. 12, September 1992

1.0 GENERAL INFORMATION

This section of the TRUPACT-II Contact Handled Transuranic Waste Shipping Package

Safety Analysis Report (SAR) presents a general introduction and description of

the TRUPACT-II Shipping Package. Schematics of the key components making up the

TRUPACT-II Shipping Package are presented as Figures 1.0-1 through 1.0-4.

Figure 1.0-1 presents an exploded view of all TRUPACT-II packaging components.

Figure 1.0-2 presents a detailed view of the closure/seal areas. Representative

payload configurations are presented in Figures 1.0-3, 1.0-4, and 1.0-4a.

Terminology used throughout the report is presented in Table 1.0-1. Drawings

presenting all design details associated, with the packaging are included in

Appendix 1.3.2 herein. Payload details are presented in Appendices 1.3.3

through 1.3.9.

1.1 Introduction

The TRUPACT-II Contact Handled Transuranic Waste Shipping Package, Model:

TRUPACT-II. has been developed by Nuclear Packaging, Inc., as a safe means of

transporting contact-handled transuranic (CH-TRU) materials. The packaging has

been optimally designed to be both rugged and lightweight. Both of these design

goals, although sometimes conflicting, benefit operator and public safety. The

use of rugged, yet deformable, packaging features provides abundant capabilities

to ensure no release of contents, if and when subjected to extreme accident

abuse. A lightweight design allows the transport of a maximum pay load per legal

weight vehicle, thereby reducing the total number of radioactive shipments to an

absolute minimum. To achieve the desired rugged yet lightweight design, a

variety of engineering development tests were included as part of the design

process. Ultimately, three full-scale prototypes of the TRUPACT-II Shipping

Package were subjected to multiple free drop and puncture tests and two full

scale prototypes subjected to thermal (fire) tests to conclusively demonstrate

package performance capabilities.

1-1

NoPac TRUPACT-II SAR Rev. 3, July 1989

L I D rinc CONSIMABLC VENTOYPlCA... i PLACES)

INNCK CONTAINMENTVESSEL LID

UPPER ALUMINUM M0NEYCOM8SPACER ASSEMBLY

INNER CCNTAINMCNTVESSEL BOOT

ANNULUS TOM! RINS(OPTIONAL)

ICMCR ALUMINUM MONCTCOVieSPACCB ASSCM6LT

OCA LIO L I "POINT COVERS(TTHCAL.3 PLACES)

OCA LIFT POINT-LIO ONLT(TlrPICAL. 3 PLACES)

OUTER CONTAINMENTASSEMBLY LID

ICV I I " POINT-LIO OR£»*>TT VESSEL ONLT(TTPICAL. 3 PLACES)

SEE riCURE 1.0-2rcn aOSUIE/SEAL AREADETAILS

PATLOAO. AVAILABLE CAVITT •7 2 - 9 / K OIA % 71 -5 /B LONG(StE riCURE 1.0-3 4 1 . 0 - * )

SEE FICUtE I 0 -2FOR CLOSIXE/SEAL AREADETAILS

OUTER CONTAINMENT

ASSEMBLY BOOT

OUTER CONTAINMENT VESSEL

STIFTCNINC RINC

BOOT riDE CONSUMABLE VENT(TTPICAL. 6 PLACES)

TIEDCKN OOUBLER PLATE(TTPICAL. « PLACES)

TIEDOm LUC(TTPICAL. 4 PLACES)

LIFT POCKETS(TO LIFT LOADEO PACKAGE)

-rofnc u r T POCKETCOVERS(TYPICAL.* PLACES)

Figure 1.0-1

TRUPACT-II Packaging Components

1-2

NnP»c TRUPACT-II SAR Rev. 3 , July 1989

ICV UPPER SEAL FLANGE

UPPER MAIN (CONTAINMENT)O-RING. BUTYL

(I EA. FOR ICV & OCV)

WIPER O-RING

LOWER MAIN (TEST)O-RING, NEOPRENE OR

FLOUROSILICONE(I EA FOR ICV A OCV)

ICV LOWER SEAL FLANGE

ICV LOCKING RING

OCV LID GUIDE PLATE(TYPICAL 6 PLACES)

(OPTIONAL)

OCV LOWER SEAL FLANGE

POLYESTER FOAMANNULUS FOAM RING

(OPTIONAL)

LYTHERM INSULATION(TYPICAL AT FOAM/STEEL INTERFACES)

NOTE: ALL MATERIAL IS STAINLESS STEELUNLESS OTHERWISE SPECIFIED.

POLYURETHANE FOAM (LID)

OCV UPPER SEAL FLANGE

OCV LOCKING RING

MICROLITE INSULATION

INNER THERMAL SHIELD

NEOPRENE WEATHERSEAL BAND (OPTIONAL)

OUTER THERMAL SHIELD

LID STIFFENING ANGLE

LOCKING 2-FLANGE

OCV LOCKING RING LOCKBOLT (TYPICAL 6 PLACES)

BODY STIFFENING ANGLE

CERAMIC FIBER. LOCKINGZ-FLANGE GUIDES

POLYURETHANE FOAM (BODY

Figure 1.0-2TRUPACT-II Closure/Seal Area Details

1-3

NaPme TEDFACT-II SA£ Her. 2. Joae 1589

• 7 2 PLASTIC REINFORCINGPLATES ANO SLIPSHEETS(OPTIONAL) "

PLASTICREINFORCING PLATE(OPTIONAL)

ALIGNkCNTGUIDE TUBE. 3.PLACES(CPTIOMAL)

PLASTIC STRETCH WRAPON UCTAL BANDING (OPTIONAL)(OMITTED FOR CLARITY)

PLASTIC SLIPSHEET ANOREINFORCING PLATE(OPTIONAL)

PLASTIC STRETCH WRAPOR UETAL 8ANDINC (OPTIONAL)(OMITTED FOR CLARITY)

35 GAL ORIV•4 PLCS

PLASTIC SLIPSHEET(OPTIONAL)

PAYLOAO PALLET

LIFT PIN. 3 PLACES

FIGURE 1.0-3

Representative TBUPACT-II 14~Drna Payload Configuration.

1-4

MaP«c THUPACT-II SAR Rev. 1, May 1989

\\

069

3ATCHET/WEBBING ASSEMBLY(OPTIONAL)

HANDLING LUG(TYP 6 PLACES. EACH

-TILTER PORT(2 MIN. EACH S¥B)

^ — STANDARD WASTE BOX(SWB)

FIGURE 1.0-4

Representative TRUPACT-II 2-SWB Payload Configuration

1-5


72" O.D.(MAX)

73" HIGH(LID INSTALLED)

LIFT CLIP(3 MINIMUM)

FILTER PORT(9 MINIMUM)

FIGURE 1.0-4a

Representative TRUPACT-II TDOP Payload Configuration

l-5a

NaPmc TRUPACT-II SAR Rev. 0, February 1989

Table 1.0-1

Terminology and Notation

Model: TRUPACT-ir

Sh.isDi.nz Packaze: The Packaging with i t s radioact ive contents , or

Pay load, as presented for transportation (10 CFR

71.4) . Within this SAR, tae Package is denoted as

the TRDPACT-II Contact-Handled Transnranic Waste

Shipping Package, or equivalently, the TRUPACT-II

Shipping Package, or TRDPACT-II Package.

Packaging; The assembly of components necessary to ensure

compliance with packaging requirements (10 CFR .

71.4) . Within this SAR, the Packaging i s denoted

as the TRTTPACT-II Packaging.

TRUPACT-TI Packaging; The Packaging consisting of an Outer Containment

Assembly, an Inner Containment Vessel and two

aluminum honeycomb spacer assemblies.

Pavload; Contact-Handled Transuranic (CH-TKU) waste contained

within 14, 55-gal lon drums or two Standard Waste

Boxes (SWBs). In this SAR, the payload is considered

to include a l i f t pallet i f Standard Waste Boxes are

not used. Any dunnage used external to the 55-gallon

drums or SWBs is also considered to be part of the

payload.

Standard Waste Box: Specia l ized payload container for use within the

TRUPACT-II Packaging. Two Standard Waste Soxes (one

on top of another) can f i t within the TRUPACT-II

Packaging.

1-6

NnPmo TRUPACT-II SAR Rev. 0, February 1989

TABLE 1.0-1


(continued)

Pavload P a l l e t : A l ightweight p a l l e t with an aluminum honeycomb

core, used for loading and unloading 14, 55-gallon

drums of CH-TRU waste at one time.

Inner The assembly (comprised of a lid and body) provi-

Vessel: ding a secondary level of containment for the

payload. Within each end of the Inner Containment

Vessel (ICV) is an aluminum honeycomb spacer

assembly.

Miimm Honeycomb An assembly which is located within each end of

Spacer Assembly; the ICV to provide:

1. A generous void volume to accommodate payload

gas generation.

2. An energy absorbing barrier between the payload

and the ICV dished heads.

Outer Cnnta-JTunwnt The assembly (comprised of a lid and body)

Assembly: providing a primary level of containment for the

payload. The Outer Containment Assembly (OCA)

completely surrounds the Inner Containment Vessel

and consists of an exterior stainless steel shell,

a relatively thick layer of polyurethane foam and

an inner stainless steel boundary which forms the

Outer Containment Vessel (OCV).

Outer Containment The innermost boundary of the Outer Containment

Vessel: Assembly.

1-7


TABLE 1.0-1


(Continued)

Ten Drum Overpack: A specialized payload container for use within the |

TRUPACT-II packaging. One Standard Waste Box or ten 55- 1

gallon drums can fit inside a.Ten Drum-Overpack (TDOP). |

l-7a

NuPae TKUPACT-II SAR Rev. 3, July 1989

The TRUPACI-II Shipping Package i s designed for truck t ransport . Up to three(3) loaded TRUPACT-II packages can be transported at one time on a singlet r a i l e r . The payload within each TRUPACT-II Shipping Package wi l l e i ther bewithin 55-gallon drums or within Standard Waste Boxes (SWB's). A singleTRDPACT-II Shipping Package can transport 14, 55-gallon drums of CH-TRU wasteor a l te rna te ly , two SWB's. Each SWB is capable of containing up to four, '55-gallon drums of waste or other appropriately prepared waste. The TRUPACT-IIpackaging provides two (2} levels of tes table containment for the 'payloadduring both normal and hypothetical accident conditions, per the requirementsof 10 CFR 71.63(b), as found in Reference 1 .3 .1 .1 .

Authorization is sought for shipment of the TRUPACT-II Shipping Package by

truck as a type B(U), F i s s i l e Class I , package per the def in i t ions delineated

in.10 CFR 71.4, Reference 1 .3 .1 .1 .

1.2 Package Description

This section presents a basic descript ion of the TRUPACT-II Shipping Packageand the contents tha t may be t r a n s p o r t e d . Defining general arrangementdrawings of the Packaging are presented within Appendix 1.3.2. Appendices1.3.3 through 1.3.8 present payload d e t a i l s .

1.2.1 Packaging

1.2.1.1 General Design Description. Containment Boundary and ClosureIdent i f icat ion, Overall Dimensions and Materials of Construction

The TRUPACT-II Shipping Package i s composed of an Outer Containment- Assembly(OCA) which provides a primary containment boundary and acts as an environmen-ta l ba r r ie r , an Inner Containment Vessel (ICV) which provides a secondarycontainment boundary, and two aluminum honeycomb spacer assemblies, one withineach dished head of the ICV. A si l icone wear pad i s u t i l i z ed at the interfacebetween the bottom exterior of the ICV and the bottom in te r io r of the OCA. Anoptional polyseter foam rubber ring (annulus foam ring) may be used in theannul us between the ICV and OCA j u s t below the

1-8

HuP*c TRUPACT-II SAR Rev. 10, April 1991

OCA seal flanges to keep debris from becoming trapped between the ICV and OCA.

Inside the packaging, the payload will be within 55-gallon drums or within

Standard. Waste Boxes. The Outer Containment Assembly, the Inner Containment

Vessel and the aluminum honeycomb spacer assemblies are more fully described in

the following subsections. The payload containers are specificed in Appendices

1.3.3 and 1.3.4. The overall arrangement of the TRUPACT-II Shipping Package and

the design details are presented in the Appendix 1.3.2 drawings.

1.2.1.1.1 Outer Containment Assembly-

The Outer Containment Assembly (OCA) consists of a lid and body, each of which

is composed primarily of an inner stainless steel boundary (containment

boundary), a relatively thick layer of polyurethane foam and an external

stainless steel shell. When the lid is installed on the body, the overall

dimensions of the OCA consist of a basic external diameter of 94-3/8 inches and

height of 121-1/2 inches. The internal cavity provided by the OCA has a minimum

diameter of 73-5/8 inches, a maximum diameter of 76-13/16 inches and a maximum

overall length (at the package centerline) of 100 inches.

The containment boundary provided by the OCA consists of the inner stainless

steel vessel formed by a mating lid and body, plus the uppermost of two (2) main

0-rings enclosed between them. The upper main (containment) O-ring is butyl

material with a 0.400 inch (nominal) cross-section. The lower main (test) 0-ring

may either be neoprene or ethylene propylene with a 0.375 inch (nonrLal) cross-

section. The purpose of the lower main (test) 0-ring is to allow for

establishing a vacuum on the exterior side of the upper main (containment) 0-ring

for' helium and pressure rise -leakage rate testing. A vent port feature in the

body is the only containment boundary penetration. A single stiffening ring

extending radially out from the containment shell is included in the design.

The Outer Containment Assembly lid is secured to the body via a locking ring

assembly located at the outer diameter of the lid and body seal flanges. The

closure / seal design is illustrated in Figure 1.0-5. The lower end of the

locking ring possesses 18 tabs which mate with a corresponding set of 18 tabs on

the body seal flange. To install the lid, the locking ring tabs are aligned

between the body seal flange tabs, the lid and body seal flanges are brought

together, and the locking ring is rotated to the locked position. In order to

rotate the locking ring, a locking z-flange extends radially outward

1-9

NaPac TEDPACT-II SAR Rev. 1. May 1989

LOCKING RING

SEAL FLANCE

:OOr SEAL FLANGE

9)ASSEMBLEO AND LOCKEO CONFIGURATION.

INSTALL W I N O-HINGS IN BCOY SEAL FLANGE

(8)POSITION LOCKING RING CIRCLWERENTIALLYON LID SEAL FLANGE.

©INSTALL LIO SEAL FLAHCE ANO LOCXINC RING

ONTO BODY SEAL FLANGE.

(T)ROTATE LOCKING RING TO ENCAGE TABS.

-BOOr SEAL FLANGE TAB(TYPICAL IS PLACES)

FIGURE 1.0-5

OCV Closure/Seal Design

1-10

NnPac TRUPACT-II SAR Rev. 3, July 1989

to the exterior of the package. Six (6), 1/2 inch diameter socket head cap

screws are used at the exterior surface of the OCA body to secure the locking

z-flange and attached locking ring in the locked position.

Completely surrounding the outer containment boundary is a relatively thick

.layer of insulating and energy absorbing polyurethane foam and an exterior

stainless steel shell varying in thickness between 1/4 and 3/8 inches. A 1/4

inch thick layer of high temperature insulating material (Lytherm ceramic

fiber paper) is typically included at foam to steel interfaces. The specified

combination of exterior shell,, polyurethane foam and insulating Lytherm

ceramic fiber paper is sufficient to protect the containment boundary from the

consequences of all specified normal and accident conditions, especially

normal and accident condition free drops, accident condition puncture, and

accident condition thermal (fire) events. Inner and outer thermal shields are

included at the lid-to-body interface to minimize the flow of hot gasses into

and around the vicini ty of the seal flanges in a hypothetical accident thermal

event.

During transport, an optional 18 inch wide, 3/16 inch thick, neoprene band may

be used as a weather/dust seal to cover the lid-to-body interface. Other

significant OCA features discussed in subsequent sections include lid l i f t

pockets and straps, fork l i f t pockets, tiedown hardware, polyurethane foam

cavity fire-consumable vents, l id insta l la t ion guide plates, and vent and seal

test ports.

The Outer Containment Assembly is fabricated primarily of Type 304 stainless

steel and medium density, closed cell polyurethane foam. Other materials used

in the OCA include butyl and ethylene propylene or neoprene for 0-rings,

neoprene for the lid-to-body weather/dust seal, silicone for the ICV-to-OCV

wear pad, and polyester foam rubber for the annul us foam ring. ABS plast ic

is used for the polyurethane foam cavity, fire-consumable vents. The OCA lid

l i f t pockets, vent port access tube and a portion of the seal test port access

tube are made from fiberglass. Brass is used for the vent and seal tes t port

plugs and high alloy stainless steel is used for the locking ring joint pins.

Insulating materials in the form of Lytherm ceramic fiber paper at foam/steel

interfaces and microlite for the inner thermal shield, a variety of stainless

steel fasteners, and a variety of lubricants and adhesives are also employed

as specified in the Appendix 1.3.2 drawings.

1-11

NnP»c TRDPACT-II SAR Rev. 1. Mty 1989

1.2.1.1.2 Inner Containment Vessel and Aluminum Honeycomb Spacer Assemblies

The Inner Containment Vessel (ICV) consists of an upper stainless steel l idand a lower stainless steel body. When the l id is installed on the body, theovera l l enveloping dimensions of the ICV consis t of a maxioun externaldiameter of 76-5/16 inches, a minimum external diameter of 73-1/8 inches, andan overall external length of 99 inches. The internal cavity provided by theICV has a minimum diameter of 72-7/16 inches, a maximum diameter of 73-7/8inches, and a maximum overall length (at the package centerline) of 98-1/2inches.

Fitt ing within the dished heads, at each end of the ICV, are aluminum honey-comb spacer assemblies. Each spacer assembly includes a 1/2 inch deep pocketwhich may be nsed in the future to honse a catalyst mixture. The lower spacerassembly also includes a 3 inch diameter hole at the package centerline which

• serves as an inspection port to check for water accumulation in th«~ lower ICVhead. With the spacer assemblies in place, the available payload cavitylength becomes 74-5/8 inches.

Similar to the OCA containment boundary, the containment boundary provided bythe ICV consists of a stainless steel vessel formed by a mating l id and body,plus the uppermost of two (2) main O-rings enclosed between then. The uppermain (containment) O-ring is butyl material with a 0.400 inch (nominal) cross-section. The lower main (test) O-ring may either be neoprene or ethylene pro-pylene with a 0.375 inch (nominal) cross-sect ion. The purpose of the lowermain (test) O-ring is to allow for establishing a vacuum on the exterior sideof the upper main (containment) O-ring for helium and pressure rise leakagerate testing. To protect the O-rings from debris which may be associated withsome paylo.ads, a silicone debris shield is incorporated at the uppermost in-terface between the body and l id seal flanges (see Drawing Sheet .7, Appendix1.3.2) . Further protection is provided by a wiper O-ring which is held inplace between the ICV upper ( l id) seal flange l ip and the ICV lower (body)seal flange. To ensure that the helium leakage rate test tracer gas reachesthe cavity above the upper main (containment) O-ring, a helium f i l l port is

•. integral'to the ICV vent port configuration (see Drawing Sheet 4, Section J-J,Appendix 1 .3 .2) . Three (3) polyethylene f i l t er s are placed in the body (lowerseal flange, just above the upper main O-ring to allow for pressure equaliza-tion across the sil icone debris shield during l id installation and removal. Avent port feature in the body is the only containment boundary penetration.

1-12

NnPac TRUPACT-II SAR Rev. 1. May 1989

The Inner Containment Vessel l id i s secured to the body via a locking ring

l o c a t e d at the onter diameter of the l i d and body seal f l a n g e s . The

closure/seal design concept is identical to that employed on the OCV (see

Figure 1 .0 -5 ) . The lower end of the locking ring possesses 18 tabs which mate

with a corresponding set of 18 tabs on the body (lower) seal flange. To

i n s t a l l - t h e l i d , the locking ring tabs are aligned between the body seal

flange tabs, the l id and body seal flanges are brought together and the

.locking ring i s rotated to the locked pos i t ion . Three (3) , 1/2 inch diameter

socket head cap screws thread, into the ICV body seal flange, and are u t i l i z e d

to secure the locking ring in the locked pos i t ion . Other s ignif icant ICV

features discussed in subsequent sections include l i f t pockets, vent and seal

t e s t ports , and l id instal lat ion guide p la tes .

The Inner Containment Vessel i s fabricated primarily of Type 304 s ta in le s s

s t e e l . Other materials used in the ICV include butyl, ethylene propylene,

neoprene, buna-N, flourosilicone or flourocarbon for a l l O-rings, s i l i cone for

the seal debris shield, polyethylene for the ICV seal debris shield vents,

brass for the vent and seal t e s t port plugs, and high alloy s ta in less s tee l

for the locking ring joint pins. Aluminua i s used in the fora of screws,

sheet and honeycomb for the ICV spacer assemblies. A variety of s ta in le s s

stee l fasteners and a variety of lubricants and adhesives are employed as

specif ied in the Appendix 1.3.2 drawings.

1 .2 .1 .2 Gross Weight

Gross shipping weight of a TRUPACT-II Shipping Package i s approximately

19,250 pounds. A summary of overall component weights, detailed in

Table 2 .2-1 of Section 2.2, i s tabulated below:

Component

OCA LidOCA Body

ICV Lid (w/spacer)ICV Body (w/spacer)

Pay load (maxinnm)Total

Weight ( lbs)

3,5205,845

8951,725

7.26519,250

1-13

NnPae TRUPACT-II SAR Rev. 0, February 1989

1.2.1.3 Neutron Moderation and Absorption

The TRUPACT-II Shipping Package does not require specific design features to

provide neutron moderation and absorption for criticality control. Fissile

materials in the payload are limited to an amount which ensures safely

subcritical packages for normal and accident conditions. The f iss i le material

limit in the payload of a single TRUPACT-II Package is based on an. optimally

moderated and reflected sphere of f i ss i le material. The structural materials

in the packaging are sufficient to maintain interactive effects between the

spheres of f i s s i l e material in an inf in i te array of damaged TRUPACT-II

Shipping Packages at an acceptable level. Further discussion of neutron

moderation and absorption is provided in Section 6.0.

1.2.1.4 Receptacles. Valves. Testing, and Sampling Ports

The Inner and Outer Containment Vessels each have a seal test port and a vent

port (see Drawing Sheet 4, Appendix 1.3.2). For each vessel, a seal test port

provides access to the volume between the two (2) 0-ring seals which exist

between the lid and body (upper and lower, respectively) seal flanges. These

seal test ports are used to demonstrate the leaktightness of the seals and to

verify proper assembly of the packaging prior to shipment. The vent port is

used at the loading end for ease of lid installation and as required by helium

leak check procedures.

To install a l id , the vent port is opened and the lid placed on the body to

initiate compression of the 0-rings. However, in order that the locking ring

can be freely rotated to the locked position, the 0-ring seals must be more

fully compressed. This is accomplished by using the vent port to pull a

partial vacuum within the containment vessel cavity thus pulling the lid onto

the body. A negative pressure on the order of 1 to 2 psig will allow the

locking ring to be freely rotated. At the receiving end of shipment, this

same vent port is used to relieve any vacuum or. pressure buildup which may

have occurred during shipment.

1-14

NoPac TRTJPACT-II SAR Rev. 0, February 1989

Access ports which pass through the polyurethane foam wall of the OCA are

provided to access both the seal t e s t port plug and the vent port plug. The

access ports are capped off a t the OCA exter ior surface with 1-1/2 inch pipe

plugs (NPT) within 3 inch diameter couplings. Reinforcing doubler p la tes are

also included on the inner surface of the OCA exter ior shell adjacent to the

couplings. Polyurethane foam cyl inders , ident ical in composition to the foam

used in the basic OCA s t ructure , attach to the pipe plugs and f i t within the

access holes to provide a level of thermal protection from the hypothetical

accident thermal event. The vent port access hole i s l ined with non-metallic

f iberglass and a f iberglass l ink i s included in the seal t e s t port access hole

l ining to achieve heat t ransfer performance compatible with that provided by

the polyurethane foam. When the OCA l id is removed, the ICV vent and t e s t

port plugs are readi ly accessible.

To access the OCV seal t e s t port plug and the ICV seal t e s t and vent port

plugs, localized cutouts are provided in the corresponding vessel locking

r ings . Since ICV l id i n s t a l l a t i o n procedures (as discussed above) require the

locking ring to be rotated while the vent port i s being used to pu l l a s l ight

vacuum in the vessel , an elongated cutout in the locking ring i s required at

the ICV vent port location. Smaller cutouts are provided in the ICV and OCV

locking rings at the seal t e s t port locations since these por ts are only used

with the locking r ings in the locked pos i t ion . The OCV vent port feature i s

located such that i t does not require a cutout in the OCV locking r ing.

Appendix 1.3.2 presents detailed drawings of the t e s t and vent port features

and the associated local cutouts in the locking r ings . There are no recep-

tac les or valves used on th i s package.

1.2.1.5 Heat Dissipation

The package design capacity is 40 thermal watts maximum. The TRUPACT-II

Shipping Package diss ipates th is r e l a t i ve ly low internal heat load en t i r e ly by

passive heat t ransfer . No special devices or features are needed or u t i l i zed

to enhance the normal dissipat ion of heat . Features are included in the

design to enhance thermal performance in the hypothetical accident thermal

event . These include the use of a h igh tempera ture i n s u l a t i n g ma te r i a l

1-15

NnPac TRDPACT-II SAR Rev. 0, February 1989

(Lytherm ceramic f iber paper) a t polyurethane foam-to-steel interfaces and the

presence of an inner and outer thermal shield a t the OCA lid-to-body in te r -

face. A more detai led discussion of the package thermal charac te r i s t i cs is

provided in Section 3.0.

112.1.6 Coolants

There are no coolants utilized within the TRUPACT-II Shipping Package.

1.2.1.7 Protrnsions

The only significant protrusions on the package are those associated with the

lifting and tie down features. For the OCA lid. a pair of l ift straps and a

guide pocket exist at three (3) equally spaced locations around the top of the

lid (on a 56 inch diameter). These lift features protrude above of the OCA

dished exterior head a maximum of 4-1/2 inches, but are radially located such

that they remain below the elevation of the top center line of the package and

do not affect overall package height. The guide pockets are made of fiber-

glass rather than stainless steel and are designed so that they will break

away in lid-end impacts. The only significant external protrusions from the

OCA body are the tie down features at the bottom end of the package. For

tiedown of the package to the trailer, four (4) sets of doubler plates and

tiedown lugs are used at locations corresponding with the main beams of the

trailer. These tiedown protrusions extend a maximum of 2-3/32 inches radially

from the exterior shell of the OCA body. The only internal protrusions into

the OCA cavity are the six (6) guide plates (3/16 inch thick) which are used

as an aid to lid installation. These internal protrusions are non-structural

in nature and of no consequence regarding performance of the package.

For the ICV lid, the only external protrusion from the basic structure is the

locking ring itself. This ring extends radially approximately 1 inch from the

skirt of the dished head. With a 3-7/8 inch axial length directly backed/sup-

ported by the Outer Containment Assembly (1/4 inch radial clearance between

locking ring OD and Outer Vessel ID), this external protrusion from the ICV is

of l i t t l e consequence for the package. The only significant internal protru-

1-16

NoPac TEUPACT-II SAR Rev. 1. May 1989

sions for the ICV lid are the three (3) lift pockets which penetrate the

dished head. These pockets are evenly spaced on a 56 inch diameter and extend

into the ICV cavity a maximum of 4-1/2 inches from the inner surface of the

lid. These protrusions are of little consequence as they are protected by the

surrounding alumintn honeycomb spacer assembly. There are no significant

internal or external protrusions associated with the ICV body.

1.2.1.8 Lifting and Tiedown Devices

Lifting features are included to lift either vessel or their component parts.

The three (3) sets of lift pins, lift straps and associated doubler plates

used in the OCA lid are sized to lift the lid of the OCA only (including

overcoming any resistance to lid removal associated with the presence of the

O-rings). They are not intended to lift a loaded package or empty OCA. Under

excessive load, failure will occur in the vicinity of the lift pin locations,

above the exterior surface of the OCA dished head. A loaded package or any

portion thereof can be lifted via the pair of fork lift pockets which exist at

the base of the OCA. These pockets are sized to accommodate forks 8 to 10

inches wide and up to 4 inches thick. An overhead crane can also be used to

lift the loaded package but will require accessing the fork lift pockets.

Lifting of the ICV is via the three lift pockets which extend into the lid

dished head. These lift pockets with their associated lift pins and the

adjacent doubler plates are sized so that the lid itself (including overcoming

any resistance to lid removal associated with the presence of the O-rings), or

an empty ICV can be lifted. A loaded ICV must be fully supported by the OCA

body and lifted via the OCA fork lift pockets. The ICV lift pins are locally

reduced in diameter so that under excessive load, the lift pins will fail in

shear prior to compromising the ICV containment boundary. OCA and ICV lift

points are appropriately labeled to limit their use to the intended manner.

The OCA fork lift pockets are also appropriately labeled to prevent their use

as tiedown devices.

1-17

NaPmc TRUPACT-II SAR Rev. 0, February 1989

As discussed in Section 1.2.1.7, the t ie downs consist of four (4) sets of

double r plates and t ie down lugs which correspond in location with the main

beams of the trai ler . At each tiedown location, one doubler i s used on the

outside surface of the OCA side wall and one on the inside surface of the OCA

lower flanged head. Internal gusset plates (one at each tiedown location) are

also used between the inside of the OCA exterior shell and the doubler in the

lower head to s t i f fen the tiedown areas. The doubler plates are sized to

adequately distribute the regulatory-defined tiedown loads (10 g's longitu-

dinal, 5 g's lateral and 2 g's vert ical , applied simultaneously) out into the

1/4 inch thick OCA exterior shell. Each tiedown lug is welded directly to

the adjacent side doubler p l a t e . In an excess ive load condit ion, these

tiedown lug welds are sized to shear from the adjacent doubler plate. A more

detailed discussion of l i f t ing and tiedown features is provided in Section

2.5.

1.2.1.9 Pressure Relief System

There are no pressure rel ief systems included in the TRUPACT-II Shipping

Package design which r e l i e v e pressure within the ICV or OCV containment

cavit ies . Fire-consunable vents in the form of ABS plast ic pipe plugs are

employed on the exterior surface of the OCA. These plugs, are included to

release any off-gasses generated by charring polyurethane foam in the hypothe-

tical accident thermal event. In a f i re , these plugs will melt out, thus

relieving any pressure generated by the foam as i t chars. Three (3) consum-

able plugs are used on the OCA l id and six (6) on the OCA body. For optimum

performance, they are located uniformly around the circumference of the

package and in the vic ini ty of the center of mass of the foam.

1.2.1.10 Shielding

Due to the nature of the payload, the packaging itself is not required to, and

does not, specifically provide any neutron or gamma shielding.

1-18

NuPac TROPACT-II SAR Rev. 12, September 1992

1;2.2 Operational Features

The TRUPACT-II Shipping Package is not considered to be operationally complex.

All operational' features are readily apparent from an inspection of the General

Arrangement drawings provided in Appendix 1.3.2 and the previous discussions

presented in Section 1.2.1. Detailed operational procedures are delineated in

Section 7.0.

1.2.3 Contents of Packaging

The TRUPACT-II Shipping Package is designed to transport contact handled

transuranic (CH-TRU) materials for the U.S. Department of Energy (DOE). CH-TRU

payload materials transported in the TRUPACT-II Shipping Package must meet the

restrictions set forth in this report. The following sections describe the

allowable payload contents.

1.2.3.1 Overview

CH-TRU materials are characterized by having very small amounts of transuranic

radioactivity contaminating a wide variety of materials. The material consists

of plastic, metal, glass, paper, salts, absorbents, oxides, filters, filter

media, cloth, sludges,, and other items.

All CH-TRU materials are packaged in a payload container that is either a

55-gallon drum, a Standard Waste Box (SWB), or a ten-drum overpack (TDOP). At

the present time, the use of the TDOP is limited to overpacking either ten 55-

gallon drums or one SWB. A 14-drum payload assembly of 55-gallon drums in the

TRUPACT-II Shipping Package is shown in Figure 1.0-3. Starting from the bottom,

the payload consists of a payload pallet, a slip sheet, a 7-pack of drums

surrounded by stretch wrap or metal banding, a reinforcing plate, another slip

sheet, another stretch wrapped or metal banded 7-pack of drums, and a second

reinforcing plate on top. Three (3) guide tubes are installed through holes in

the slip sheets and reinforcing plates to prevent rotation of the top layer of

drums relative to the bottom layer. These reusable guide tubes also provide

1-19


access to the lift attachments on the payload pallet. The slip sheets, stretch

wrap or metal bonding, reinforcing plates and guide tubes are optional components

to assist in handling the drum payload assembly. The pallet is a reusable,

3-inch thick aluminum honeycomb sandwich assembly as shown in Appendix 1.3.8.

The optional slip sheets are polyethylene plastic, with tabs slightly larger in

radius than the 7-pack of drums. Centering spacers are molded into'each slip

sheet to position the drums. The optional reinforcement plates are the same size

and material as the slip sheets, but without the centering spacers.

The optional stretch wrap material is thin prestretched, polyethylene plastic

film. The 7-pack of drums are wrapped many times to pull the drums together for

ease of handling. Metal bands are also an option for use in preparing a 7-pack

of drums for ease of handling.

The SWB payload container is designed so that two (2) SWBs will fit within the

TRUPACT-II Inner Containment Vessel (ICV) cavity, stacked one atop the other.

A SWB is nominally 37 inches high by 72 inches in diameter with two flat sides

as shown in Figure 1.0-4:

The TDOP payload container is designed so that one (1) TDOP will fit within the

TRUPACT-II ICV cavity. A TDOP is nominally 74 inches high by 71 inches in

diameter, as shown in Figure 1.0-4a.

One or more carbon composite filters are installed into the filter vents of each

drum, SWB, and TDOP, to ensure free diffusion of gases through the payload con- |

tainer lid or wall. In addition, any rigid liners in the drums are punctured or

vented to ensure diffusion of gases into the annulus between the payload

container and the liner.

The CH—TRU material may be enclosed in plastic bags or metal cans prior to

placement in a payload container. The bags and cans confine the radionuclides

during handling operations at the generator or storage site. Multiple layers of

confinement are sometimes used. All layers of confinement from the innermost bag

or can release any generated gases to outside of the payload container.

Knowledge of the number of confinement layers and the configuration of the layers

(i.e., minimum number of large bags or metal containers as the inner-most layers

of confinement) is required to assign the CH-TRU material into a

1-20

NuPac TRDPACT-II SAR Rev. 1, May 1989

paylpad shipping category (see Section 1.2.3.2) for t ransport in TRDPACT-II

Shipping Package.

Radio isotopes of aay element are permissible in the payload for the TRDPACT-II

Shipping Package. Typical CH-TRTJ material consis ts of waste contaminated with

transnranic elements ( i . e . , elements with atomic umbers greater than 92) from

DOE defense a c t i v i t i e s . The presence of these transuranic radionnclides also

resu l t from the production of special isotopes such as heat source material or

neutron generators. Trace quant i t ies of f i s s ion products and decay chain

daughters may also be present.

The c r i t i c a l i t y evaluation in Section 6.0 considers the r a t i o of the umber of

hydrogen atoms to the number of atoms of f i s s i l e mater ia l . The worst case

ra t io is used for the payloads based on compacted polyethylene sheets and

water with various r a t i o s of Pu-239 to demonstrate that the package is subcri-

t i ca l in a l l cases.

1.2.3.2 Pavload Classif icat ion

The wide v a r i e t y of CH-TRU ma te r i a l has been subdivided based on common

charac te r i s t i c s . The material i s c lass i f ied into groupings called 'payload

shipping categories ' which were developed specif ica l ly for the TRDPACT-II

Shipping Package. The primary difference between the categories is their

potential for gas generation and internal bagging configuration. The thermal

wattage allowed in each payload shipping category is r e s t r i c t e d such that the

hydrogen generated during transport r e su l t s in a concentration of less than

five volume percent in any layer of confinement in the payload container.

The broadest divis ion of CH-TRD materials i s into two groupings; the analy-

t i ca l and t e s t categories. The analytical categories are for CH-TRD materials

for which' an analytical prediction can demonstrate compliance with the hydro-

gen concentration l imit during t ransport . The t e s t categories are for CH-TRD

materials that require a tes t for gas release from a payload container prior

to t ransport . Both analytical and t e s t categories require knowledge of the*

physical and chemical form of the material, the type of payload container and

f i l t e r , the number of layers of confinement, the type of closure of each layer

1-21

NnPae TBUPACT-II SAR Rev. 4, August 1989

and the decay energy of the radionuclides present in the material . Thesefactors determine the gas generation and release ra tes within the payloadcontainers and are the bas is for c lass i f i ca t ion of CH-TEH materials into pay-load shipping categories.

The shipping period i s a lso considered in precluding po ten t i a l ly flammable gasconcentrations. The shipping period s t a r t s when the TROPACT-II Shipping Pack-age is sealed after loading and continues un t i l i t i s vented prior to un-loading. The TRDPACT-II Shipping Package safety analyses consider a maximum60 day shipping period as discussed in Appendix 3 .6 .4 . The safety analysesfor increased pressure to the maximum normal operating pressure consider a oneyear time period as discussed in Section 3 .4 .4 .

1.2.3.2.1 Analysis and Test of Payloads

The analyt ical payload shipping categories include well characterized CH-TRUmaterials with a known potent ia l for production of gases. Each of the analy-t i ca l categories has a decay heat , or thermal wattage l imi t . The decay heatl imit i s set such that the amount of radioactive decay energy deposited in theCH-TRD material and surrounding packaging wil l produce a concentration ofhydrogen gas less than five volume percent (5%) in the innermost layer of con-finement at the end of the maximum 60 day shipping period.

The analyt ical prediction considers the waste type ( i . e . , the physical andchemical form) for the CH-TRU materials in each analyt ical category. Eachwaste material type has an effective G value, or the amount of gas moleculesproduced per unit energy (per 100 eV) emitted by radioactive decay. Theanalysis uses the material with the highest effective 6 value (worst case) forthe calculations of maximum decay heat for each category and also assumes thatthe worst case material i s 100% of the waste in a payload container. Theanalysis also considers the buildup and re lease of the hydrogen gas from eachlayer of .confinement into the payload container and ICV of the TRDPACT-IIShipping Package during t ranspor t .

Materials which cannot be demonstrated safe by analysis must be tested for gasgeneration and release from each payload container prior to transport in aTRUPACT-II Shipping Package. The t e s t categories include payload containerswith CH-TRU material that exceed the decay heat limit imposed on the analy-

1-22

NnPac TRUPACT-II SAR Rev. 1, May 1989

tical. categories, or materials with, an unknown effective 6 value. The test

plan to demonstrate acceptably safe gas accumulations in a TRTJPACT-II Shipping

Package during transport is provided as Attachment 2.0 in Appendix 1.3.7.

1.2.3.2.2 Waste Type

Payloads for the TRUPACT-II Shipping Package are subdivided into four (4)

waste types based on physical and chemical form as shown in Table 1.2.3.2-1.

A complete l i s t ing of the chemicals/materials (> 1 weight %) allowed in each

waste type is included in Appendix 3.6.7. These waste types combine with the

subdivisions for analysis and test to form a matrix encompassing al l pay load

shipping categories for CH-TRU materials. Table 1.2.3.2-2 presents the waste

types and the analytical and test divisions to provide an overview of pay load

classification.

1.2.3.2.3 Waste Material Type

The next subdivision separates the four waste types into waste material types.

By dividing the waste type further, an effective 6 value can be assigned to

specif ic CH-TRU waste materials within each of the waste types. Table

1.2.3.2-3 presents the waste material types within each of the waste types.

The effective G value for a waste material type i s based on the maximum G

value from any material found in that particular waste material type (in con-

centrations greater than 1 percent by weight). Effective G values are dis-

cussed in more detail in Section 3.4.4 and Appendix 3 .6 .7 .

1-23

NuPac TRUPACT-II SAR Rev. 1, May 1589

TABLE 1.2.3.2-1

Summary of Payload Waste Types

Waste Type Description and Examples

Solidified Aqueous or Homogeneous Inorganic

Solids

(< 1% organics - not including packaging)

- absorbed, adsorbed or solidified

inorganic liquid

- soi ls , solidified part icipates, or sludges

formed from precipitates

- concreted inorganic part iculate waste

I I Solid Inorganics

- glass, metal, crucibles

- other solid inorganics

I I I Solid Organics

- plast ics (e .g . , polyethylene, PVC)

- cellulose (e .g . , paper, cloth, wood)

- cemented organic solids

- other solid organics

IV Solidified Organics

- cemented or immobilized organic liquids

and solids

1-24

NnPac TRDPACT-II SAR Rev. 1, Hay 1989

TABLE 1.2.3.2-2

Analytical and Test Divisions of CH-TRU Waste Types

Waste

Type Analysis Test

Analysis of Test of

sol idif ied aqueous or sol idif ied aqueous or

homogeneous inorganic solids homogeneous inorganic solids

II Analysis of

solid inorganics

Test of

solid inorganics

III Analysis of

solid organics

Test of

solid organics

IV Not currently

addressed

Test of

solidified

1-25

j TRUPACT-II SAR Rev. 14, October 1994

TABLE 1.2.3.2-3

CH-TRU Haste Material Types

WasteWaste MaterialType Type Typical Material Description

I.I Absorbed, adsorbed, or solidified inorganicliquid

1.2 Soils, solidified participates, or sludgesformed from precipitation

1.3 Concreted inorganic particulate waste

II II.1 Solid inorganic materials in plastic bags

II II.2 Solid inorganic materials in metal cans

III III.l Solid organic materials

IV IV. 1 Solidified organics

1-26


1.2.3.2.4 Pavload Containers

As discussed previously, only three types of payload containers are allowed for |

transport of materials in the TRUPACT-II Shipping Package. One is a 55-gallon

drum, specified in Appendix 1.3.3. The second is the Standard Waste Box (SHB), j

specified in Appendix 1.3.4.- The SWB is specifically designed and tested for

transportation in TRUPACT-II. The SWB is also designed as an overpack to hold

up to four (4), 55-gallon drums, or one experimental bin which fits in the SWB.

The bin is of a rectangular configuration, fitted with at least two kevlar

filters. The third is the Ten-Drum Overpack (TDOP), also specified in Appendix j

1.3.4. The TDOP is designed as an overpack to hold up to ten (10), 55-gallon j

drums, or one (1) SWB, or one (1) experimental bin overpacked in an SWB. 1

The notation used to designate the configuration of the payload containers when

specifying a payload shipping category is summarized in Table 1.2.3.2-4. As

shown in Appendix 3.6.13, allowable decay heat limits of payload containers are

not decreased when overpacked in a TDOP. This is because the TDOP is vented with j

a minimum of nine filters and there are less payload containers. Thus, new j

shipping categories for payload containers overpacked in a TDOP are not required. |

TABLE 1.2.3.2-4

Notation for Payload Container Configurations

Notation Description

A Drums with materials in additional

layers of confinement [such as rigid

liner(s), bag(s), and can(s)].

B Overpacks of drums placed in an SWB.

C SWB with material in additional layers

of confinement [such as bag(s), and can(s)].

D Overpack of an experimental bin in an SWB.

1-27

NnPac T2DPACT-II SAIL 2ev. 2, June 1989

The notation A, B, C or D i s used to designate the payload container in analy-

t ical payload categories as shown in Table 1 .2 .3 .2-5 . The notation 'T' i s

added to the end of the analytical category designation to identify a test

pay.load shipping category.

TABLE 1.2.3.2-5

Waste

Types

I

II

III

ANALYTICAL

Drams

IA

IIA

IIIA

PAILOAD SHIPPING

Overpacks

of Drums

IB

I IB

I I IB

CATEGORIES

STBs

IC

IIC

me

Overpacks

of Bins

ID

IID

IIID .

1.2.3.2.5 Layers of Confinement

CH-T&n materials are-usually placed in a payioad container within multiple

layers of plastic and/or metal cans that act as layers of confinement for

radionuclides during waste handling operations. These layers of confinement

are not included in the transport safety analysis for shielding or cri t i -

cal ity. CH-TBU materials are assumed to breach the layers of confinement and

also the payload containers under hypothetical accident conditions of

transport.

The payload safety analysis considers these layers of confinement as barriers

that impede, but do not preclude, the release of gases from inside the layers

of confinement to the outside of the payload container. Tests have been per-

formed to quantify the rate of release of hydrogen gas from the inside to the

outside of plastic bags using the 'twist and tape' method of closure. The

hydrogen gas release rates are sufficient to allow the release of hydrogen gas

from the layers of confinement.

1-28


The payload safety analysis presented herein predicts a hydrogen gas genera-

tion rate. A conservative approach to each factor i s used to calculate gas

generation and ensure less-than-flammable gas concentrations during transport

of CH-TRU material in the TRUPACT-II Shipping Package. l i e predicted rate is

usually much greater than the actual gas generation rate in a particular pay-

load container.

The analytical approach considers each layer of confinement in the calculation

for release of hydrogen and corresponding hydrogen concentration during trans-

port. For added margin of safety, the radioactivity in any shipping category

is assumed to be in only one innermost bag. Payload shipping categories

demonstrated safe by testing also consider the umber of layers of confinement

in the acceptance criteria.

When the number of layers of confinement i s included in the matrix for

classification of CH-TRU materials into TRUPACT-II payload shipping cate-

gories, the following notation i s used (Table 1 .2 .3 .2-6) :

TABLE 1.2.3.2-6

Notation for Layers of Confinement in CH-TRU Payload Containers

Notation Description

0 No closed bags around waste

1 Up to a maximum of 1 closed bag around waste

2 Up to a maximum of 2 closed layers of bags around waste




- 6 Up to a maximum of 6 closed layers of bags around waste

H Metal container(s) as the innermost layer of confinement

1-29

NuPac TRUPACT-II SAR Rev. 9, December 1990

| As described in Appendicies 3.6.9 and 3.6.10, the layers of confinement in the

| drum payload containers are of two types - drum liner bags, and inner bags. The

| release rates for these two types of bags are different (Appendix 3.6.9). For

| waste types II and III, the minimum number of liner bags in the confinement

| layers is indicated by using a lower case alpha trailer along with the notation

| for the total number of bags. The following designations identify the minimum

| number of liner bags used to package waste in drums:

I| • No alpha trailer - minimum of one drum liner bag.

I| • Alpha trailer "a" - minimum of two drua liner bags.

I| For example, the notation II.1A2 indicates waste material type II.1 packaged in

| a drum with two bags, at least one of which is a liner bag. The notation II.lA2a

| indicates waste material type II. 1 packaged in a drum with two bags, both of

| which are liner bags. Section 3.4.4.4 of the SAR and the TRUCON document contain

| tables that provide information of the total number and types of bags in

| different payload shipping categories.

l-29a

NoPae TEUPACT-II SAR Rev. 0, February 1989

1.2.3.2.6 Payload Shipping Categories

Not a l l of the potent ia l payload shipping categories shown in the tables are

needed for transport of CH-TRU mater ia ls . Categories in the tab les which, are

shaded include a combination of waste type, payload container, and layers of

confinement that are not current ly addressed or needed to prepare CH-TRU

materials for t ranspor t .

The types of CH-TRU materials which meet the payload shipping categories r e -

quirements for TRUPACT-II are shown in Table 1.2.3.2-7 for the analytical

categories and in Table 1.2.3.2-8 for the t e s t ca tegor ies . Only those blocks

identif ied with the notat ion for a shipping category are current ly needed to

classify CH-TRU materials as payloads for the TRUPACT-II Shipping Package.

1.2.3.3 Payload Controls and Restr ic t ions

1.2.3.3.1 Overview

Each payload for t ransport in the TRUPACT-II Shipping Package has parameters

which are controlled to ensure safe t ransport . The charac te r i s t i c s of the CH-

TRU materials must be determined and controlled to comply with the r e s t r i c -

tions set forth below. The controls and the allowable methods for compliance

are provided in the document fTRUPACT-II Authorized Methods for Payload

Control (TRAMPAC)' in Appendix 1.3.7. The following sections address each

payload parameter to be controlled and/or r e s t r i c t e d .

1-30

Table 1.2.3.2-7TRUPACT-II ANALYTICAL PAYLOAD SHIPPING CATEGORIES

WasteType

I

II

III

WasteMaterial

Type

I.I1.21.3III11.2lll.l

Analytical

ADrums

0

1.1 AO

I.2AO

I.3A0

II.1A0

III.IAO

1

I.1A1

I.2AI

I.3AI

II.IA1

III.1AI

2

I.1A2

I.2A2

I.3A2

II.IA2

III.IA3

3

1.1 A3

I.2A3

I.3A3

II.1A3

lll.l A3

4-

I.2A4I.3A4II.IA4

1II.1A4

5

II.1A5

III.IA5

6

1I.IA6

III.1A6

M

II.2AM

BOvcrpackof Drums

•

. *•**

CStandard Waste Box

0

I.1C0I.2C0

I.3CO

II.ICO

III. ICO

1

II.ICI

III.1C1

2

II.IC2-

III.IC2

3

II.1C3

III.IC3

4

-_

I1.IC4

III.IC4

5 6

-

M

II.2CM

DOvcrpack

of Bins2

N ^ \

II.ID2

III.ID2

cS3HH

tn

Ul

Table 1.2.3.2-8TRUPACT-II TEST PAYLOAD SHIPPING CATEGORIES

Waste

Type

I

II

IIIIV

WasteMaterial

Type

I.I

1.2

1.3

II. 1

II. 1

IV.1

0

I.IAOT

I.2A0T

I.3A0T

II.IAOT

1I1.IA0T

•

l

I.IAIT

I.2AIT

I.3AIT

II.IAIT

III.1A1T

IV. 1 AIT

2

1.1 A2T

1.2A2T

I.3A2T

1I.IA2TIH.1A2T

IV.1A2T

Test

A

Drums

3

I.1A3T

1.2A3T

I.3A3T

II.IA3T

III.IA3T

IV.1A3T

4

I.2A4T

I.3A4T

II.IA4T

III.IA4T

5

II. 1 AST

lll.l AST

6

II.IA6T

III.IA6T

M

BOvcrpackof Drums

*•

*

*

»

•

onftoXT(D

vo

* Same notations as the categories for A- Drums, but with a B for overpacking of drums in an SWB.%%;;£ : Shaded areas indicate future potential payload shipping categories.


1.2.3.3.2 Physical Form

The physical form of the TRUPACT-II payload is restricted to solid or solidified

material. Liquid waste shall be prohibited in the payload containers except for

residual amounts in well-drained containers. The total volume of residual liquid

in a payload container shall be less than" one volume percent of the payload

container. Sharp or heavy objects shall be blocked, braced or suitably packaged

as necessary to preclude damage to the payload container. Sealed containers

shall be prohibited from being included as a part of the waste except for

containers that are four liters or less in size. Pressurized containers shall

not be allowed in the waste. The methods of determination and control for the

physical form requirements are described in Section 4.0 of TRAMPAC.

1.2.3.3.3 Chemical Properties

The chemical properties of the waste are determined by the chemical constituents

allowed in a given waste type. The classification of the CH-TRU payload

materials into waste types and waste material types is provided in

Sections 1.2.3.2.2 and 1.2.3.2.3. All materials for a given shipment are

restricted to those listed in the waste material type tables (5.1 to 5.6) of

TRAMPAC. The chemical constituents are restricted so as to ensure safe transport

conditions. Waste types that could be reactive during transport shall be

prohibited from the payload. This restriction specifically applies to three

types of chemical constituents:

• Explosives

Non-radioactive pyrophorics

Corrosives

The methods of determination and control for compliance with these requirements

are described in Section 5.0 of TRAMPAC.

The classification of the payload materials into waste material types is based

on their gas generation potential which is quantified by the effective G value

(see Appendix 3.6.7). In order to ensure that the effective 6 value for the

1-32

NnPmc TRUPACT-II SAB. ' Rev. 2. June 1989

waste material type i s not exceeded, the chemicals and materials within a

given vaste material type are further restr icted. The restrictions apply to

a l l materials that are present in the waste in amounts greater thaa 1 weight

percent. The t o t a l amount of trace mater ia l s /chemicals in the waste i s

restricted to l ess than 5 weight percent in a payload container. Chemical

constituents that can be present within each waste material type in concen-

trations greater than one percent are l i s t ed in Tables 4 - 8 in Appendix 3.6.7

of the SAIL The total concentration of potential ly flammable volat i le organic

compounds shall be limited to 500 ppm in the headspace of a payload container.

The methods of determination and control for compliance with these require-

ments are described in Section 5.0 of THAMPAC. -----

1.2.3.3.4 Chemical Compatibility

Chemical compatibility of the waste within i t s e l f and with the packaging en-

sures that chemical processes do not occur that might pose a threat to safe

transport of the payload in the T2DPACT-II package. The chemical compati-

b i l i t y shall be ensured for the following four conditions:

Chemical compatibility of the waste form within each individual

payload container.

Chemical compatibility between contents of payload containers during

hypothetical accident conditions.

Chemical c o m p a t i b i l i t y of the was te forms w i t h the

TRUPACT-II Inner Containment Vessel (ICV).

•' ^Chemical compatibility of the waste forms with the TEUPACT-II 0-ring

seals.

The methods of determination and control for compliance with these require-

ments are described in Section 6.0 of THAMPAC.

1-33


1.2.3.-3.5 Gas Distribution and Pressure Buildup

Gas concentrations and pressures during transport of TRUPACT-II payloads are

restricted to the following limits:

The gases generated in the payload shall be controlled to prevent the

occurrence of potentially flammable concentrations of hydrogen (<5

volume percent) within the payload confinement layers and the void

volume of the ICV cavity.

The gases generated in the payload and released into the ICV cavity

shall be controlled to maintain the pressure within the TRUPACT-II ICV

cavity below the acceptable design pressure of 50 psig.



1.2.3.3.6 Pavload Container and Contents Configuration

The type of payload container and the contents configuration in each individual

payload container are restricted as follows:

The payload container shall be either a 55-gallon drum, a Standard j

Waste Box (SWB), or a Ten-Drum Overpack (TDOP). The acceptable spe- |

cifications for each container allowed in a TRUPACT-II payload are

provided in Appendices 1.3.3 and 1.3.4 of the SAR.

Filter vent(s) shall be installed in all payload containers and in any

overpacked payload containers. Appendix 1.3.5 of the SAR specifies the

hydrogen diffusion and flow requirements for those filters. The drums

must have a minimum of one filter, the SWB must have at least two

filters, and the TDOP must have a minimum of nine filters. Bins

overpacked in SWBs must have at least two filters. Only the SWB model

* filter shall be installed in the SWB and in the TDOP. Either the SWB

or the bin model filter may be installed in the bins overpacked in

SWBs. Either the drum model or the SWB model filter may be installed

in the drum.

1-34


Sites adding filters to existing waste containers shall ensure that there

is equilibration after venting of any gases that may have accumulated

in the closed container prior to transport by aspirating the payload

containers by one of three approved options (Section 8.0 of Appendix

1.3.7).

A rigid drum liner, if present, shall be punctured (0.3 inch or larger

hole) or have an equivalent filtered vent installed.

The maximum number of layers of confinement for a payload container shall

be known.

Bags shall be closed with a twist and tape or fold and tape closure.

The acceptable specifications for this procedure and the bag material

are provided in Appendix 1.3.6.

Metal cans may be used as internal confinement providing that the

restrictions in Appendix 1.3.6 are met.



1.2.3.3.7 Isotopjc Inventory and Fissile Content

There are two limits for TRUPACT-II payload compliance which require a knowledge

of the specific isotopic composition and radionuclide quantity. They are:

Pu-239 fissile gram equivalent quantity (FGE).

Decay heat.

A payload container is acceptable for transport only if Pu-239 FGE plus two times

the error is below 200 grams for a drum, or 325 grams for a Standard Waste Box.

The limit on Pu-239 FGE plus error for the TRUPACT-II payload is 325 grams.



1-35


1.2.3.3.8 " Decay Heat

There are two limits for decay heat: 1) the total decay heat from the radio-

active decay of the radioisotopes within an individual waste container and 2)

the total decay heat from all payload containers in a TRUPACT-II. A payload

container in a given shipping category is qualified for transport only if the

measured decay heat plus error is less than or equal to the limits for that

shipping category. The decay heat limits for payload containers in each shipping

category are presented in Table 1.2.3.3-1 for the analytical categories and in

Table- 1.2.3.3-2 for the test categories. The total decay heat limits per

TRUPACT-II for each shipping category are listed in Table 1.2.3.3-3. As shown |

in Appendix 3.6.13, no new decay heat limits or shipping categories are needed |

for containers overpacked in a TDOP. J



1.2.3.3.9 Weight and Center of Gravity

The weight of each individual payload container, payload assembly, and loaded j

TRUPACT-II shall conform with the following limits: |

• 1,000 pounds per drum (1,450 pounds per drum overpacked in an SWB)

• 4,000 pounds per SWB

7,265 pounds per payload assembly of 14 drums including.pallet, guide |

tubes, slip sheets, and reinforcing plates j

7,265 pounds per payload assembly of two SWBs or one TDOP

19,250 pounds per loaded TRUPACT-II

The total weight of the top seven drums or SWB of the payload assembly must be

less than or equal to the total weight of the bottom seven drums or SWB. The j

total weight of the top five drums in a TDOP must be less than or equal to the |

total weight of the bottom five drums. |



1-36

TRUPACT-II SAR Rev. 13. April 1994

TABLE 1.2.3.3-1

ANALYTICAL SHIPPING CATEGORY WATTAGE LIMIT PER DRUM(Watts/drum)

Wait*

Matt Type

1.11.21.3

n.i

n.2

m.i

A • Drum

AO

O.2O6O

0.25360.82410.2251

0.1126

A1

0.1797

0.22120.71890.1924

''','

0.0962

A2a

-

0.1680

/ ' ' '0.0840

A2

0.15940.1962

0.63750.0869

. ' , ',

0.0434

A3

0.0466

0.05730.1863

0.0561

0.0280

A4

0.0418

0.13590.0414

'?% ; ,

0.0207

A5

0.0328

0.0164

A6

0.0272

0.0136

AM

40.0000

ANALYTICAL SHIPPING CATEGORY WATTAGE UMITPER OVERPACKED DRUM

(Watts/drum)

WasteMatl Type

1.11.21.3

n.i

n.2ra.i

BO

0.1457

0.1793

0.58270.1711

0.0856

B1

0.1320

0.1625

0.52810.1516

0.0758

B2a

j

0.1360

0.0680

B • Overpacked Drums

B2

0.1207

0.1486

0.48280.0774

0.0387

B3

0.0426

0.0524

0.17030.0520

0.0260

B4

0.03910.12720.0392

0.0196

B5

0.0314-

0.0157

B6

0.0262

0.0131

BM

40.0000• •

ANALYTICAL SHIPPING CATEGORY WATTAGE UMiT PER SWB(Watts/SWB)

Waste

Mat) Type

1.1

1.213

n.i

n.2m.i '

C • Standard Waste Box

CO

0.9132

1.1240

3.65281.0206

'""', 'i*.0.5103

C1

-

0.7029'/'"!'' ''

0.3515

C2

" " •

/ H :

0.5361,;'/£*-'•

0.2680

C3

0.1222* ' " '- '

0.0611

C4

;

0.0690

0.0345

C5

v

', ', '

'' 'S ,

-

C6

s

•r '

' ' ,

CM

s

40.0000

;| Shaded areas indicate payload shipping categories currently not addressed.

1-37

TRUPACT-II SAR Rev. 14, October 1994

TABLE 1.2.3.3-1 (Continued)

ANALYTICAL SHIPPING CATEGORY WATTAGE LIMIT PER OVERPACK BIN(Watts/Bin)

Waste

Matl Type

1.1

I.2I.3

11.1

II.2111.1

D • Overpacked Bin

DO

>

D1 02

-

0.4271

0.2135

03 04

-

D5 D6

• •

DM

...... ...

Shaded areas indicate payioad shipping categories currently not addressed.

1-37a


TABLE 1.2.3.3-2

TEST SHIPPING CATEGORY WATTAGE LIMIT PER DRUM*(Watts/drum)

Waste

Mat) Type

I.I1.21.3

n.in.2m.inu

A - Drum

AOT

10

10

10

20

20

A1T

10

10

10

20

20

7

A2aT

20

,,

20

-

A2T

10

10

10

20

20

7

A3T

10

10

10

20

20

7

A4T

10

10

20

20

ACT

20

20

A6T

20

20

AMT

TEST SHIPPING CATEGORY WATTAGE LIMIT*PER OVERPACKED DRUM

(Watts/drum)

Waste

Matl Type

I.I

1.2

1.3

n.in.2m.iIV.l

B - Overpacked Drums

BOT

10

10

10

20

20

B1T

10

10

10

20

20

7

B2aT

20

20

B2T

10

10

10

20

20

7

B3T

10

10

10

20

20

7

B4T

10

10

20

20

B5T

20

20

B6T

20

20

BMT

-

', •' Shaded areas indicate payload shipping categories currently not addressed.

Alto the limit for the total TRUPACT-II payload.

1-38

TRUPACT-II SAR Rev. 13, April 1994

TABLE 1.2.3.3-3

ANALYTICAL SHIPPING CATEGORY WATTAGE LIMIT PER TRUPACT-II(Watts/TRUPACT-ll)

Wast*Mat) Type

I.I1.21.3n.in.2m.i

AO

2.88403.550411.53743.1514

1.5764

A1

2.51583.096810.06462.6936

1.3468

A2a

-

f f '•

* ;

2.3520

1.1760

•

A2

2.23162.74688.92501.2166

0.6076

A- DrumA3

0.65240.80222.60820.7854

0.3920

A4

10.58521.90260.5796

0.2898

A5

" -

0.4592s

0.2296

A6

0,3808

0.1904

AM

40.0000

WasteMat) Type

I.I

1.2Un.in.2m.i

B • Overpacked DrumsBO

1.16561.43444.66161.3688-

0.6848

B1

1.05601.30004.22481.2128

0.6064

B2a

1.0880f ;

0.5440

B2

0.96561.1888

•3.86240.6192

0.3096

B3

0.34080.41921.36240.4160

0.2080

B4

0.31281.01760.3136

-

0.1568

B5

0.2512

0.1256

B6

0.2096

0.1048

BM

-

N :

40.0000

Wast*Mati Type

1.11.2Un.in.2m.i

CO

1.82642.24807.30562.0412"', ' ,

1.0206

C1

1.4058_, f / f f

0.7030

C-

C2

1.0722- -,

0.5360

Standard Waste Box

C3

',

0.2444

0.1222

C4

:

:

0.1380

0.0690

C5 C6 CM

-

40.0000

\ Shaded areas indicate payload shipping categories not currently addressed.

1-39

TRUPACT-II SAR Rev. 14. October 1994 ;


ANALYTICAL SHIPPING CATEGORY WATTAGE LIMIT PER TRUPACT-O(Watts/TRUPACT-II)

Waste

Matl Type

1.1

I.2

I.3

11.1

II.2

111.1

D - Overpacked Bin

DO

f

-

D1

•

02

0.8542

0.4270

03 \

• -

D4 D5 06 DM

. • . -•••

Shaded areas indicate payload shipping categories currently not addressed.

1-39a


.1.2.3.3.10 Radiation Dose Rates

The rad ia t ion level at the surface of aad two meters from any unshielded pay-

load container shall not exceed 200 mrem/hr and 10 mrem/hr respect ively. The

rad ia t ion dose rate res t r i c t ions to comply with. 10 CFR 71.47 for the TRUPACT-

I I package and contents are discussed in Section 12.0 of the TRAMP AC.

1.2.3.3.11 Paylbad Assembly Rest r ic t ions

The following res t r ic t ions are for assembly of a pay load:

The shipping category s h a l l be c l e a r l y marked on e&ch payload

container.

* All containers forming a payload within each TRUPACT-II sha l l belong

to the same shipping category.

* . Payload containers qual i f ied for transport in the analyt ical and

te s t categories cannot be t ransported in the same shipment.

The transportation parameters l i s t e d in Tables 13.1 and. 13.2 shall

be completed in accordance to the procedures in Section 13.3 of

Appendix 1.3.7 of the SAR for each payload container.

The transportation parameters l i s t e d in Table 13.3 shal l be com-

pleted in accordance to the procedures in Section 13.3 of Appendix

1.3.7 of the SAR for each TRUPACT-II shipment.

The methods of determination and control for compliance with these r equ i re -

ments are described in Section 13.0 of TRAMPAC.

1-40

NoPac TRDPACr-II SAR Rev. 3, July 1989

1.2.3.3.12 Test Category Criteria

1.2.3.3.12.1 Introduction

Section 1.2.3.2.1 defines the classification of payload containers into two

group s:

Containers that can be qualified for transport by analysis comprise

the analytical categories. These can be shown to meet the trans-

port requirements of TRUPACT-II using bounding values for gas gen-

eration and gas release values that provide a margin of safety.

Containers that need to be tested for gas generation and release

under normal transport conditions in order to qualify for transport

comprise the test categories.

The containers must meet a l l other restrictions listed above. The detailed

procedure for testing a payload container in a test category is provided in

Attachment 2.0 of Appendix 1.3.7. The purpose of this section is to define the

criteria which need to be satisfied in order to qualify a payload container

for transport under the test category.

A payload container can be placed in a t e s t category under one of two

conditions:

The decay heat loading of the waste in a payload container exceeds

the limit set for the shipping category (e.g., a drum of solidified

inorganics with two bag layers [I.2A2] with a decay heat greater

than 0.1962 watts, the limit tabulated in Table 1.2.3.3-1 of Section

1.2.3.3.8). Payload containers in Waste Material Types I . I , 1.2,

1.3, I I . 1 , and I I I . l belong in this class.

A content code that does not have a characterized bounding 6 value.

Payload containers in Waste Type IV belong to this category.

The test cr i ter ia for these two cases are discussed separately below.

1-41

NoPae TRUPACT-II SAR Rev. 1, May 1989

1.2.3.3.12.2 Cri ter ia for Shipment of Waste Types

I. I I or I I I in a Test Category

A' payload container can be qualif ied for shipment only if i t can be demonstra-

ted (e i ther by analysis or tes t ing) that the concentration of hydrogen is

maintained below the 5"J l imit in a l l confinement l ayers . For a payload con-

ta iner in this tes t category, th i s requires a knowledge of the gas generation

and re lease ra tes in the container under the t e s t conditions (see Attachment

2.0 of Appendix 1.3.7).

In addit ion, the concentration of flammable v o l a t i l e organics in the headspace

of the payload container is limited to less than or equal to 500 ppm as in the

case of an analytical category.

After steady s ta te conditions are achieved under the t e s t conditions (Attach-

ment 2.0 of Appendix 1.3.7 describes the analyses to be performed during the

tes t condit ions) , the gas generation r a t e from the payload container and the

composition of the gases being generated wi l l remain, constant.

The hydrogen generation ra te under these conditions shal l be less than the

l imit for each category in Table 3 .4 .4 .4-1 of Section 3 .4 .4 .4 . The methodolo-

gy for arr iving at these l imi ts i s also presented in Section 3 .4 .4 .4 .

In summary, the t e s t c r i t e r i a for payload containers in t h i s group are :

1. Measure the hydrogen generation r a t e under steady s ta te conditions.

2. Compare this ra te to the maximum allowed generation ra te for the

shipping category of the container l i s t e d in Table 3.4.4.4-1 of

- Section 3.4.4.4.

3 . The container qual i f ies for t ransport if the maximum allowed genera-

tion rate is not exceeded.

1-42

NuPac TRUPACT-II SAR Rev. 4, August 1989

1.2.3.3.12.3 Criteria for Shipment of Tfaste Type IV

Waste Type IV (Sol idif ied Organics) does not have a quantified bounding Gvalue unlike the other three waste types (Appendix 3 . 6 . 7 ) . After steady-stateconditions are achieved under the test conditions (Attachment 2.0 of Appendix1.3.7 describes the analyses to be performed during the t e s t conditions), thegas generation and release rates from a pay load container and the compositionof the gases being generated wi l l remain constant. The following criteriashall be used to qualify a payload container in these test categories for

transport:i

1. The steady state gas generation rate shall not exceed the limitspecified in Table 3.4.4.3-5 of Section 3.4.4.3. This limit isnecessary in order to ensure that the design pressure of 50 psig isnot exceeded. Derivation of this is also presented in Section3.4.4.3.

2. The concentrations of potentially flammable volatile organics in theheadspace of the container shall be less than or equal to 500 ppm.

3. The steady state hydrogen generation rate shall not exceed the limitspecified in Table 3.4.4.4-2 of Section 3.4.4.4. This limit isnecessary to ensure that the hydrogen concentration in the innermostconfinement layer is less than or equal to 5% at steady state-. Themethodology for arriving at the limit is also discussed in Section3.4.4.4.

If the limits on total pressure, hydrogen gas generation, and the flammableorganics in headspace are met, a payload container in a test category quali-fies for transport.

1-43

MoPac TRDPACT-II SAR *ev. 1, May 1989

1.2.3.4 • Implementation of Restrictions

rThe restrict ions in Section 1.2.3.3 for preparation and characterization of

CH-TRU-materials for transport in the TRDPACT-II Shipping Package shall be

implemented through controls nsing the c lass i f icat ion system called payload

shipping categories described in Section 1 .2 .3 .2 . The methods for determining

and controlling each restrict ion shall be as described in TRAMPAC, Appendix

1.3.7. TRAMPAC describes how each DOE s i t e can determine or measure each

restricted parameter as well as the factors which influence the value ( e . g . ,

analytical methods and error bars).

The restrict ions applicable to each payload shipping category shall also be

correlated to the current system for describing wastes at DOE s i tes . The

docnnent t i t l ed , 'TRDPACT-II Content Codes', (TRUCON), Reference 1 .3 .1 .2 ,

shall be a correlation of DOE site waste identif ication codes with the payload

shipping categories for the TRDPACT-II Package. TRDCON shall provide a des-

cription of each payload related restr ict ion required for each content code at

each DOE s i t e . The description in TRDCON shall be binding on how the CH-TRD

waste i s generated and prepared for transport. TRAMPAC shall govern the-

me thods for the preparation of the CH-TRU waste. TRDCON shall identify the

specific aethods applicable to each content code.

1-44

NuPac THDPACT-II SAR Rev. 0, February 1989

1.3 Appendix

1.3.1 References

1.3.2 Packaging General Arrangement Drawings

1.3.3 Specification for Drums and Liners *

1.3.4 Specification for Standard Waste Boxes ^

1.3.5 Specification for Vents \

1.3.6 Specification for Bags and Bag Closures

1.3.7 TRDPACT-II Methods for Payload Control (TRAMPAC)

1.3.8 Payload Assembly Drawings

1.3.9 Waste Sampling Programs a t DOE sites

1.3.0-1

NaPac TRUPACT-II SAR Hev. 0, February 1989

APPENDIX 1 .3 .1

REFERENCES

1.3 .1-1

HuPac TRUPACT-II SAR Rev. 9, December 1990

1.3.1 References

1.3.1.1 Title 10, Code of Federal Regtilations, Part 71 (10 CFR 71),

Packaging and Transportation of Radioactive Materials. August 24,

1983

1.3.1.2 U.S. DOE, 'TRUPACT-II Content Codes (TRUCON),' Rev. 5, April 1991.

1.3.1-2

NnPae TRUPACT-II SAR Rev. 0, February 1989

APPENDIX 1.3.2

PACKAGING GENERAL ARRANGEMENT DRAWINGS

1.3.2-1.

NoPtc TRUPACT-II SAR Rev. 3, July 1989

1.3.2 Packaging General Arrangement Prayings

This appendix provides the General Arrangement Drawings for the TKDPACI-II

Packaging. The design i s completely depicted on the eleven (11) following

drawing sheets making up drawing number 2077-500SNP. An overall arrangement

drawing showing the Inner Containment Vessel (ICV) within the Outer Contain-

ment Assembly (OCA), and f i tup of the aluminum honeycomb spacer assemblies

within the ICV dished heads, i s presented on Drawing Sheet 2. Sheets 1, and 3

through 11 present a l l the other per t inent design d e t a i l s .

1.3.2-2

DANCE WITH THE FOLLOWING :5EMBLY LOCKING RING LOCK BOLTSLBS (LUBRICATED [J5>).SSEL LOCKING RING LOCK BOLTSLBS (LUBRICATED [>5>).

UGS SHALL BE INSTALLED USING

MADE IN ACCORDANCE WITH ASUETION NB, ARTICLE NB-4230, OCACCORDANCE WITH ASME CODE SECTIONIE NF-4230,

HT SHELL FABRICATIONS SHALL COMPLYME CODE, SECTION III, DIVISION I.LAG NOTE 19.

:ES, EXCEPT FOR AN 8 INCH SQUAREIEL LOCATION), AND OUTER THERMALZ-FLANGE, SHALL BE SAND BLASTEDI WITH SSPC-SP-6.

NOT SHOWN, BUT WILL BE UTILIZEDOVE PER G/N 6, 47 AND INSPECTED

1 SHELL MATERIALS SHALL BE FULLNSPECTED PER NOTES 7,8 4 10.

075 THK) ASTM A240 TYPE 304: FABRICATED AS WELDED ASSEMBLIESIOM ONE PIECE. UPPER Z-FLANGE MAY,'.) SPUN PARTS JOINED WITH ONE (I)r WELD, WELDS (IF ANY) SHALL BEL 8. FOR SPUN OPTION, CORNERSTHERWISE SHOWN.

W LIFTING AND HANDLING THE OCAILEO WITH THE FOLLOWING WARNING:2 INCH LETTERING USING A.OR: BLACK.

» LIFTING AND HANDLING THE ICV!LY ONLY. EACH LOCATION SHALL BE'LID OR EMPTY CONTAINER LIFT ONLY'USING A STANDARD INDUSTRIAL

IFT ING AND HANDLING THE COMPLETEriEDOWN.

HIGH QUALITY EPOXY ADHESIVE.

.ESS PARTS USING HIGH QUALITY

i THK. LYDALL NO. 1535-LK. ADHEREDICONE ADHESIVE, DOW CORNING NO.

IVE TO ICV BODY AND ASSEMBLEDDNTROLLED. POSITIONS SHOWNEPRESENTATIVE ONLY.

AL SHIELD ARE LOCALLY CUT OUT TOG.

IN 20 PLACESLESS STEELC. ORIALLY SPACED WITH

REVISION HISTORY

REV DESCRIPTION

SEE DC*

[4j>WEAR PAD INCLUDES SILI CONE-BASED PRESSURE SENSITIVE ADHESIVE BACKING FOR" ATTACHMENT TO INSIDE SURFACE OF OCV LOWEB 01 SHED HEAD.

•AXIAL DIMENSIONS SHALL BE COfTROLLED SUCH THAT WHEN ASSEMBLED WITH LOCKINGRING IN LOCKED POSITION. MAXIMUM AXIAL FREE PLAY BETWEEN UPPER AND LOWERSEAL FLANGES SHALL BE NO GREATER THAN 0.S53 INCHES.

•MATERIAL: BUTYL PER RAINER RLBBEP RR0403-50.OR BUNA-N PER MIL-F 3065 GR.SO,OR FLUOROCARBON PER ASTM D2000 UHK 607. ZI(50 TO 55 SHORE A)OR FLU0R0S1LIC0NE FER MIL-R 25958.

R ^ > MATERIAL: NEOPRENE PER ASTM C2000 BC 715,OR ETHYLENE PROPYLENE PER ASTM D2000 BA 712.

45. ASME HEADS SHALL BE CONSTRUCTED TO SECTION VIII OF THE ASME CODE.ALL CONSTRUCTION WELDING OF THE HEADS SHALL BE 100% RADIOGRAPHICEXAMINED USING THE EXAMINATION TECHNIQUE AND ACCEPTANCE CRITERIA OFSECTION III OF THE CODE (NB 5000). DOCUMENTATION OF RADIOGRAPHICEXAMINATION SHALL BE IN ACCORDANCE WITH SECTION VIII (UW-51 (o)( I ))OF THE CODE.

APPROXIMATE LOCATION OF ADHESIVE BACKED LABELS.

WELDS FOR THE ICV AND OCV SHELLS SHALL CONFORM TO ASME CODE, SECTION 111.DIVISION I, SUBSECTION NB. AFTICLE N8-4400. MAXIMUM WELD REINFORCEMENT FORTHE ICV AND OCV SHELLS SHALL BE 3/32 INCH IN ACCORDANCE WITH ASME CODE.SECTION III, DIVISION I. SUBSECTION NB. ARTICLE NS-4426. SUBARTICLE NB-4426.1.WELDS FOR THE OCA (EXTERNAL) SHELL SHALL CONFORM TO ASME CODE. SECTION 111.DIVISION I, SUBSECTION NF. ARTICLE NF-MO0. AND SHALL BE SMOOTH. THAT IS.HAVE A MAXIMUM REINFORCEMENT OF 1/32 INCH AND HAVE A TAPERED TRANSITION TOTHE BASE MATERIAL SURFACE.

48: REPAIR OF BASE MATERIAL

FOR THE ICV AND OCV COMPONENTS AND OCA INTERNAL SURFACES ONLY. REPAIR OF BASEMATERIAL SHALL BE IN COMPLIANCE WITH ASUE CODE. SECTION III, DIVISION I.SUBSECTION NB, ARTICLE NB-253S AND NB-2S39, OR NB-4I3I. MAXIMUM WELDREINFORCEMENT SHALL BE +3/32 INCH IN COMPLIANCE WITH ASME CODE. SECTION 111.DIVISION I, SUBSECTION NB. ARTICLE NB-4426. SUBARTICLE NB-4426.1.

FOR THE OCA EXTERNAL SURFACES. REPAIR OF BASE MATERIAL SHALL BE IN COMPLIANCEWITH ASME CODE, SECTION III. DIVISION I. SUBSECTION NF-4I3I OR NF-2510 ANDASTM A-240. ALTERNATIVELY. REPAIRS MAY BE PERFORMED IN COMPLIANCE WITH NS-2538AND NB-2539. OR NB-4I3I. MAXIMUM WELD REINFORCEMENT SHALL BE +1/32 INCH.

REMOVAL OF EXCESS WELD REINFORCEMENT FROM BASE MATERIAL REPAIR WELDS.'TEMPORARY ATTACHMENT WELDS. ETC.. SHALL BE UNIFORMLY BLENDED, THAT IS. SHALLHAVE A MAXIMUM WELD REINFORCEMENT AS STATED ABOVE AND HAVE TAPERED TRANSITIONTO THE BASE MATERIAL SURFACE.

DOCUMENTATION OF BASE MATERI/L REPAIRS SHALL BE IN COMPLIANCE WITHARTICLE NB-4132.

•OUTER THERMAL SHIELD HAS A 3/» INCH X 10-1/2 INCH RELIEF TO PROVIDE CLEARANCEFOR VENT PORT TOOLING IN THE '.OCKED OR UNLOCKED POSITION.

WHERE SECTIONS OF THE AMERICAN SOCIETY OP MECHANICAL ENGINNEERS BOILER ANDPRESSURE VESSEL CODE (ASME CODE) ARE REFERENCED, THE CODE EDITION ANDADDENDA WHICH ARE APPLICABLE ARE 1986 EDITION. 1987 ADDENDA. FOR OTHERREFERENCED CODES AND STANDARDS. THE CURRENT REVISION AT THE TIME OFFABRICATION OF THE TEST UNITS SHALL APPLY (1987). REVISIONS AND/OR ADDENDAFOR ALL COOES AND STANDARDS L.VTER THAN THESE DATES MAY BE USED.

•MIRROR IMAGE OF SAWCUT AND P U S RELATIVE TO TABS IS AN OPTION.

•OPTION: 2.2 INCHES.

•LOCATE THE SIDE DOUBLER PLATE SO THAT THE TIEDOWN LUG LANDS BETWEEN THECENTERLINES OF THE ADJACENT 1-1/2 INCH DIAMETER HOLES. IF .ANY PORTION OFTHE LUG OR LUG WELD OVERLAPS \ HOLE. THE HOLE SHALL BE'PLUG WELDED PRIORTO WELDING THE LUG TO THE D0U3LER. POSITIONING OF .J-fEDOWN LUG AND 1/4 INCHTHICK INTERNAL GUSSET PLATE MJST BE MAINTAINED PER SECTION T-T, SHEET .11.

B

H A THIN COAT OFIGS AND COVERSH THE FOLLOWING:

TO 6-B FT-LBS.-10 FT-LBS,13-16 FT-LBS.-13 FT:-LBS.

1DING I/B X 20 '

I CHARACTERS(INT OR

ITEM OTY NEXT ASSY

[APPDS.A.PORTERAPPOn I <W»NNACKAPPCQ. SCHMOKERAPPCH.WJNSCHAPPIW.fl. RICHARDSlENGFL.E.ULBRICHTOA G . E . H I L LICHECKH. LEVITTDRAWN WYAW

l-?4-89

2-23-892-23-892-23-S9

2-2J-89t-a-tt

UNLESS OTHERWISE SPECIFIEDTOLERANCES.FRACTIONS ± K/AANGLES ± N/A

DIMENSIONS ARE M INCHES3 PLACE DECIMALS ± N/A2 PLACE DECIMALS ± N/A1 PLACE DECIMAL ±M/A

NUOJEWRSY5TOB

TRUPACT-II

PACKAGING

SCALE: NONE |WT. N / A

REV-

DWG ISIZE

SHEET I OF I I

2077-500SNP

1

B

NOTES. UNLESS OTHERWISE SPECIFIED:

1. INTERPRET DRAWING PER ANSI Y-14.5.

2. THREADS PER ASA Bl.I I960 EDITION.

[ i > IDENTIFICATION: PACKAGE SHALL BE IDENTIFIED ON THE OUTER CONTAINMENT ASSEMBLYLID AND BODY WITH STAINLESS STEEL NAMEPLATES SEAL WELDED ALL AROUND INACCORDANCE WITH THE REQUIREMENTS OF IOCFR 71.85 (c).'TYPE B" SHALL BE STENCILEDNEAR THE NAUEPLATE IN 1/2 INCH MINIMUM HIGH CHARACTERS USING STANDARD INDUSTRIALENAMEL PAINT OR MARKING INK. COLOR: BLACK.

[?>> POLYURETHANE FOAM SHALL HAVE A NOMINAL DENSITY OF B-l/4 LBS/CU FT.INSTALLATION TECHNIQUES. ACCEPTANCE TESTS AND ACCEPTABLE DEVIATIONS IN PROPERTIESARE'SUMMARIZED IN SECTION 8.1.4.1 OF THE TRUPACT-II SAFETY ANALYSIS REPORT.

5. PRIOR TO ASSEMBLY. ALL COMPONENTS SHALL BE CLEANED OF CUTTING OILS. MARKINGDYES. WELD FLUX. SPATTER. SCALE. GRIME AND ALL OTHER FORE IN MATERIALS.FINISHED ASSEMBLY AND ALL INTERIOR SURFACES SHALL BE CLEANED. AND VISUALLYOR WIPE TEST INSPECTED IN ACCORDANCE WITH ASTM-A380.

6. -ALL WELDING PROCEDURES AND PERSONNEL (EXCEPT AS NOTED) SHALL BE QUALIFIEDIN ACCORDANCE WITH ASME CODE. SECTION IX. WELD PROCEDURESAND WELDER QUALIFICATIONS SHALL BE AVAILABLE FOR AUDIT OR REVIEW..

7. ALL WELDS (EXCEPT AS NOTED) SHALL BE VISUALLY EXAMINED IN ACCORDANCE WITHAWS 01.1. SECTION 8.IS.I. VISUAL WELD INSPECTORS SHALL BE QUALIFIED PER AWS Dl.l.

B. ALL WELDS (EXCEPT AS NOTED) ON THE ICV AND OCV (CONTAINMENT BOUNDRY) SHALL BELIQUID PENETRANT INSPECTED ON FINAL PASS IN ACCORDANCE WITH ASME CODE. SECTION III.DIVISION I. SUBSECTION NB. ARTICLE NB-SOQO AND SECTION V. ARTICLE 6.ALL WELDS (EXCEPT AS NOTED) ON THE OCA OUTER SHELL SHALL BE LIQUIDPENETRANT INSPECTED ON FINAL PASS IN ACCORDANCE WITH ASME CODE. SECTION III.DIVISION I. SUBSECTION NF. ARTICLE NF-5000.

P|>- INDICATED WELDS SHALL BE LIQUID PENETRANT INSPECTED ON ROOT AND FINAL PASSESU""^ IF A MULTIPASS WELD AND ON THE COMPLETED WELD IF A SINGLE PASS WELD IN ACCORDANCE

WITH ASME CODE. SECTION III, DIVISION I. SUBSECTION NB, ARTICLE NB-5000 ANDSECTION V. ARTICLE 6.

I7cf> INDICATED WELDS SHALL BE RADIOGRAPH INSPECTED IN ACCORDANCE WITH ASMECODE SECTION III. DIVISION I. SUBSECTION NB. ARTICLE NB-5000 AND SECTION V.ARTICLE 2 FOR THE ICV AND OCV (CONTAINMENT BOUNDARY) WELDS AND RADIOGRAPHINSPECTED IN ACCORDANCE WITH SUBSECTION NF. ARTICLE NF-5000 FOR THE OCAOUTER SHELL WELDS.

[n>- MATERIAL: ASTM-A240. TYPE 304 STAINLESS STEEL (ROLLED AND WELDED PLATE).

^ ^ OPT: ASTM-AI82. GRD F304 (FORGED BILLET)

OPT: ASTM-A35I. GRD CF8A (CENTRIFUGAL CASTING)

MATERIAL SHALL BE ULTRASONIC OR RADIOGRAPHIC TEST INSPECTED IN ACCORDANCE WITHASME CODE. SECTION III, DIVISION I. SUBSECTION NB. ARTICLE NB-2500 AND SECTIONV. ARTICLE S OR ARTICLE 2 RESPECTIVELY. ROLLED AND WELDED PLATES SHALL BE FULLPENETRATION WELDED AND RADIOGRAPHIC TEST INSPECTED IN ACCORDANCE WITH ASME CODESECTION III. DIVISION I, SUBSECTION NB, ARTICLE NB-5000 AND SECTION V, ARTICLE 2.

12. MAXIMUM NORMAL OPERATING PRESSURE IS 50 PSIG. INNER AND OUTER VESSEL CONTAINMENTBOUNDARIES SHALL BE SUBJECTED TO AN INTERNAL TEST PRESSURE EQUAL TOA MINIMUM OF I50X OF THE MAXIMUM NORMAL OPERATING PRESSURE PER IOCFR 7l.85(b).

13. INNER AND OUTER VESSEL CONTAINMENT BOUNDARIES SHALL BE LEAK TESTEDTO DEMONSTRATE A LEAKAGE RATE NOT TO EXCEED I X IO~7 STANDARD CUBICCENTIMETERS PER SECOND PER ANSI N14.5-1987.

14. OCA AND ICV LID LIFTING FEATURES SHALL BE LOAD TESTED TO I50S OF THEIRMAXIMUM WORKING LOAD. MAXIMUM WORKING LOAD FOR EACH CCA LID LIFTPOINT IS 2.500 POUNDS AND FOR EACH ICV LID LIFT POINT IS 1.667 POUNDS.

[ > > PRIOR TO ASSEMBLY. COAT EACH O-RING WITH APPROXIMATELY I TABLESPOON OF y^^ DOW CORNING HIGH VACUUM GREASE. SEAL FLANGES MAY ALSO AS AN OPTION BE

COATED WITH A THIN COAT OF DOW CORNING HIGH VACUUM GREASE.

Il6> PRIOR TO ASSEMBLY. THREADS SHALL BE COATED WITH A HIGH QUALITY1 NICKEL BEARING LUBRICANT.

COAT THREADS WITH A HIGH QUALITY THREAD LOCKING COMPOUND PRIOR TO INSTALLATION.

BUTYL MATERIAL PER RR0405-70. RAINIER RUBBER CO.. SEATTLE. WA.

MATERIAL IS ASTM-A240, TYPE 304 STAINLESS STEEL. TOLERANCES FOR AS-ROLLED SHELLMATERIAL ARE IN ACCORDANCE WITH THE TOLERANCES GIVEN IN ASTM-A480. TABLEA I. 17. THICKNESS OF AS-ROLLED PLATE MATERIAL FOR HEADS MAY BE 1/32 INCH GREATERTHAN ALLOWED BY ASTM-A240/A480 TO ALLOW FOR THINNING DURING THE FORMINGPROCESS. THE MINIMUM THICKNESS FOR ALL 1/4 INCH NOMINAL MATERIAL IS 0.240 INCH;THE MINIMUM THICKNESS FOR 3/16 INCH NOMINAL MATERIAL IS 0.178 INCH; THE MINIMUM"HICKNESS FOR 3/8 INCH NOMINAL MATERIAL IS 0.365 INCH.

TAMPER INDICATING SEALS SHALL BE INSTALLED AT ONE (I) OCA LOCK BOLT LOCATIONAND THE OCA VENT PORT ACCESS PLUG AS SHOWN.

"FASTENERS SHALL BE INSTALLED IN ACCO!

a. TORQUE OUTER CONTAINMENT AS

(I/2-I3UNC-2A) TO 28-32 FT-

b. TORQUE INNER CONTAINMENT Vt

(I/2-I3UNC-2A) TO 28-32 FT-

OCA SEAL TEST AND VENT PORT ACCESS PIA TORQUE OF 35-45 FT-LBS (LUBRICATED

ALL CONTAINMENT SHELL JOINTS SHALL B!CODE. SECTION III. DIVISION I. SUBSE(OUTER SHELL JOINTS SHALL BE MADE IN /III. DIVISION I. SUBSECTION NF, tRTIf

24. ALL CYLINDRICAL AND CONICAL CONTAINMfWITH THE TOLERANCE REQUIREMENTS OF AiSUBSECTION NE. ARTICLE NE-4220. \ND I

25. ALL EXPOSED EXTERNAL OCA STEEL SURFA(AREA ON EACH SIDE OF THE PACKAGE (LA(SHIELD WHICH ATTACHES TO THE LOCKINGWITH A FINE SILICA SAND IN ACCORDANCJ

26. THE FOLLOWING LONGITUDINAL WELDS AREAND SHALL BE FULL PENETRATION 'V GR<PER NOTES 7, 8, & 10:

a. OCA EXTERNAL SHELLSb. OCV SHELLSc. ICV SHELLS

ANY ADDITIONAL WELDS REQUIRED TO JOIIPENETRATION WELDS PER G/N 6. 47 WO I

ALL Z-FLANGES ARE MADE FROM 14 G\. (,STAINLESS STEEL AND MAY OPTIONALLY B|USING CYLINDERS AND DISKS. OR SPUN F|AS AN OPTION, BE FABRICATED AS TIIO (iCIRCUMFERENTIAL FULL-PENETRATICN BUT1PER G/N 6 AND INSPECTED PER NOTES 7 IARE SPUN WITH I INCH RADIUS UNLESS 0'

!5|> INDICATED RECEPTACLES ARE PROVIDED FCLID ONLY. EACH LOCATION SHALL BE LAB("LID LIFT ONLY*. VIA STENCILING MlTHSTANDARD INDUSTRIAL ENAMEL PAINT. C01

|3§> INDICATED RECEPTACLES ARE PROVIDED F(LID OR EMPTY INNER CONTAINMENT ASSEMLABELED WITH THE FOLLOWING WARN I IK::VIA STENCILING WITH 2 INCH LETTEIIINGENAMEL PAINT, COLOR: BLACK.

31. FORK LIFT POCKETS ARE PROVIDED FOR LiASSEMBLY AND ARE NOT TO BE USED FOR )

BOND FOAM TO ACCESS PLUG UTILIZIN3 A

•BOND FIBERGLASS TUBE TO MATING STAIN!RTV SILICONE ADHESIVE.

LYTHERM CERAMIC FIBER PAPER. 1/4 I NCITO OCA FOAM CAVITY WALL WITH RTV SIL732 OR NO. 737.

'ANGULAR ORIENTATION OF ICV LID RELATICV WITHIN OCA IS NOT SPECIFICALLY OfARE FOR REFERENCE PURPOSES AND ARE R(

•MICROLITE INSULATION AND INNER THERMPROVIDE ACCESS TO SEAL TEST PORT PLO

OPTIONAL FABRICATION:ATTACHMENT OF ANGLE: MAY BE RIVETEDEQUALLY SPACED WITH 300 SERIES STAII>#1/8 COMMERCIAL POP RIVETS ON #82 B.RESISTANCE SPOT WELDED 20 PLACES EQU•3/16 SPOTWELDS ON • 82 B.C.

COAT PLUG AND COVER SEAL O-RINGS WITDOW CORNING HIGH VACUUM GREASE. PLliSHALL BE INSTALLED IN ACCORDANCE WIT

a. TORQUE SEAL TEST PORT PLUGSb. TORQUE VENT PORT PLUGS TO 8<c. TORQUE VENT PORT COVERS TOd. TORQUE VENT PORT PLUG 10 10

MATING SEAL FLANGE LUG HAS CORRCSPONTAPER ON LEADING EDGE.

STENCIL AS SHOWN USING 1/2 INCH HIGhWITH A STANDARD INDUSTRIAL ENAMCI. PAMARKING INK: COLOR: BLACK.

8

8

OCV SEALTEST PORTLOCATION

OCA LOCK BOLT(6 PLCS EQ.SP.)

(SH9)

TAMPER INDICATING SEAL

NAMEPLATES

FOAM FILL PORT - TOP

WEATHER SEAL BAND (NOT

OCA LIFT POCKET E § >(3 PLCS) ^(SH5)

FIRE CONSUMABLE VENTTOP (3 PLC

TYP

FIRE CONSUMABLE^ VENlLOWER SIDE (6 PLCS E(SH 5) |

TIE-DOWN LUG(4 PLCS)

ICV LID ASSE»CLYfe>

1/4 THK pi

DETAIL M;(«>II

3/8 THK X

B

121—1/2

- 7 / 8 CLEARANCE

UPPER SPACER ASSEV61.Y(SH 6)OCA LID ASSEMBLY

WEATHER SEAL BANDSILICONE WEAR PAD(1/8 THK X 36 O.D.

X 3 I.D.) fj

DETAIL B ;3/8 THK X 12 UIN. LG IT

D E T A I L ' U— « 72-5/8 ID——(ICV)

* 73-5/8 ID—»(OCV)

74-5/8

OCA BODY ASSEMBLY

(OCV CAVITY HT) DETAIL P«J,MLOWER SPACER ASSEMBLY

(SH 6)

FIRE CONSUMABLE VENTLOWER SIDE (6 PLCS) ICV BODY ASSEMBLY

—.46

DETAIL D<DETAIL Li

FORK POCKET(2 PLACES)

TIE-DOWN LUG(4 PLACES)(SH 5)

DETAIL BB(SH 5) A-TRUPACT-1 I PACKAGING

SCALE: 1/16

8

-3 -

E OCX

REVISION HSTORY

OESCHPTON CHECK PEL

SHOWN FOR C L A R I T Y )

D

/FOAM FILL PORTS)

XJ.SP.)

! 26-1/4 UIN. LG

103-3/4

64

52

|SH3)

1SH3)

—11—1/4 NCf.

DETAIL V

MICROLITE INSULATION5 WIDE X 1-1/4 THK

X 261 LG(2 THICK UNCOMPRESSED)

INNER THERMAL SHIELDI6GA (.060 THK) X 3/4 X 2

ANNULUS FOAM RING2 X 2

ESTERFOAM UIL-P-26SI4-C200(OPTIONAL)

ICV CONTAINMENT WALL

DETAIL C

(SH 3)

OCV CONTAINMENT WALL

DETAIL U(at)

OCA LID OUTER SHELL .

UPPER Z-FLANGE g g >WEATHER SEAL BAND (SH 3)

(OPTIONAL)

LOCKING Z-FLANGE fe>

LOWER Z-FLANGE E § >

OUTER THERMAL SHIELD14 GA (.075 THK) X 6-l/B

APPROX. 1/2 GAP

DETAIL E(SH 3)

OCA BODY OUTER SHELL

—APPROX. 1/2 GAP

DETAIL B ASCALE: 3/8

(LOCK BOLT NOT SHOWS) IN TRUE POSITION)

fTEM art NEXT ASSY

N.J.SWANNACK

APPOS. A. PORTERAPPqi.L.SWANNACKAmp.sCHMOKERAPWH.WUNSCHAPPOi.R .RICHARDSENM g.ULBRICHT

G.E.H1LLCH6CXH.LEVITTDRAWN amw

' - • > * - * * \ „ , ,

UNLESS OTHERWISE SPEORED DMENSONS ARE IN MCHESTOLERANCES: S PLACE OECMALS ± V AFRACTIONS* * / A 2 PLACE DECIMALS ± IVAANGLES ± K/A 1 PLACE DEOMAL ± I V A _

w. 5Y51-EM5

TRUPACT-II

PACKAGING

B

SCALE: NOTED WT. M / A

REV:

DWG DWQNO.

SHEET2 O f I I

2077-500SNP

1

WEATHER SEAL BANO. NEOPRENE3/16 THK X 18 WIOEMIL-R-6855CLASS II, GRADE 50-70 (OPTIONAL)

INSERT, INTERNAL

REVISION HISTORY

BEV DESCWnON

;EE DCNCHECK

Vht*

I/2-I3UNC-2B, P/N: KN8I3J

THREAD.TRIDAIR, P/N. ..(6 PLCS, EQ SP)

r-SLOT. 1-3/8 (AXIALLY)X 7/86 PLCS EQ.SP. THRU

I LOCKING Z-FLANGE AND OUTERL THERMAL SHIELD/I6

>(OPTIONAL) • «93-3/B —•-

/-THERMOSEAL ADHESIVE/ OR DOW CORNING RTV' SILICONE ADHESIVE' NO. 732 OR 737

T7«T\OCA LOCK BOLT WELDMENT6 PLACES EQ.SP. AS SHOWN(REF. SH 9 FOR DETAIL)

•TAMPER INDICATING SEAL 20

CERAMIC FIBERINDUSTRIAL TEXTILE,

WOVEN TAPE.HYTEXFIBERGLASS CARRIERI' WIDE X A/R THICK

38 PLCS"EQ. SPACED,

7/32 (2 PL)

LOCK BOLTf3 EQ.SP. 0 120'

DETAIL ARSCALE: 1-1/2

ICV SEAL TEST PORTLOCATION

ICV VENT PORTLOCATION

I)

ITION)ICV UPPER

SEAL FLANGE

DEBRIS SHIELD

ICV LOWER'SEAL FLANGE

ICV LOCKING RING

FROM LOWER SEAL FLANGEUPPER SURFACE

ICV LOCK BOLT WELDMENT(REF SH 9 FOR DETAIL)

INSERT. INTERNAL THREADI/2-I3UNC-2BTRIDAIR, P/N KN8I3J

fl7>-(0PTI0NAL)

}CV SHELL I3/16 THKI

I (SHI)

SECTION F-F(ICV LOCK BOLT 3 EQUALLY SPACED)

SCALE: 1/2

-OCV BODYSHELL

3/16 TKK

12UIN

X»YI SHELLfHK

8 MINMAX

-ICV LIFT POCKET(3 PLCS EQ SP)

VIEW A-A ICV L IDSCALE: r / 16

(OCA NOT SHOWN FOR CLARITY)

(SH2)

3/6 THK X 1-1/2WIOE RING. ASTMA276 OR ASTMA479. TYPE 304STAINLESS STEEL,

O.D.

DETAIL PSCALE: 1/2

LOCATIONICV UPPERICV LOWEROCV UPPEROCV LOWEROCA UPPEROCA LOWER

7

'441/4'/*l/*l/4l/4

O.D.74-3/873-1/877-5/1674-1/894-3/894-3/8

C.R.74-3/873-1/877-5/167<-l/894-3/8F-JkT

H15-5/8 MIN15-3/8 MIN15-7/8 MINI5-I/B MIN16-7/8 MIN1-3/8 MIN

K.R.8-1/28-1/28-1/2

8-1/a'6-3/83/4

F3/8 MIN3/8 MIN3/6 MIN3/4 MIN3/8 MIN3/6 MIN

MATERIAL SPECIFICATIONSASTM-A240.TYPE 304 ST.STL.ASTM-A240.TYPE 304 ST.STL.ASTM-A240.TYPE 304 ST.STL.ASTM-A240.TYPE 304 ST.STL.ASTM-^A24fl.TYPE 304 ST.STL.ASTM-A240.TYPE 304 ST.STL.

:A BODYITER SHELL'4 THK 64

FROM BOTTOMOF PACKAGEt>

- N'2I Z-FLANGE.NOT SHOWN

Y . }

ITEM OTY NEXT ASSY

N.J.SWANNACK -24-ea

AITOS.A.PORTER tffcSLAPPCD.L.SWANNACKAPPOn.SCHMOKER

WCH.WUNSCHAPPaj.R.RICHAROS6NQB F.utBRICHT

°* C.E.HILLCHECKH.LEVITT

nut•23-88

I-O-U

UNLESS OTHERWISE SPECKEDTOLERANCES:FRACTIONS * tl/AANGLES ± V A

0 M E N 9 0 N S ARE M INCHES3 PLACE DECMALS ±*/k2 PLACE OECMALS ±N/A1 PLACE DECIMAL ±K/A

ASME FLANGED AND DISHED HEADS Il5^>SCALE: NONE l^*^ *

mineSYSTEMS

TRUPACT-I I

PACKAGING

SCALE: NOTEDREV:

SEE

SHEETS O f I I

2077-500SNP

1

D'

B

8

nJ>BRACKET. I2GA.(.IO5 THK)X 1-1/2 WIDE

6 PLCS EQ. SP.

I/4-20UNC X 3/4 FLAT HO.ALUM. SCR.5/16 FLAT WASHER, AS REQ'D, U-TYPEFASTENER. I/4-20UNC. 6 PLCS EQ.SP.

1/8 1/2-69/32 NOM — 1 f—

LOWER SPACER ASSEMBLY(REF SH 6 FOR DETAILS)

3/4 MAX 8 x (. A S T U_ A 2 7 8

OR ASTM-A479. TYPE 304STAINLESS STEELSTAINLESS STEEL(6 PCS. EQ SP)

ANGLE, 2 X 2 X 1 / 4ASTM-A276, OR A479TYPE 304 STAINLESS

OCV LOWER HEAD(SEE TABLE FOR DETAILS)

I 1-1/4 TO q INSIDE OISHED HEADI RADIUS

ICV LOWER HEAD(SEE TABLE FOR DETAILS)

ANGLE. I X I X 1/8.ASTM-A276, OR A479TYPE 304 STAINLESS STEEL

LOCKING Z-FLANGE

DETAIL

1/4 1/2-6

DETAIL ESCALE: 1/2

(LOCK BOLT NOT SHOWN IN TRUE P.

DETAIL DSCALE: 1/2

OUTER THERMAL SHIELD OCA LID OUTER SHELL

« 3/424 EO.SP.(THRU OUTERTHERMALSHIELD ONLY)

B

# I". 6 PLCS EQ. SP.(DRAIN HOLE THRU OUTER

RMAL SHIELD ONLY)#3/4TYP

OCV LOCKING RINGOPERATING HANDLEKEY SLOTS(3 SETS, EQ. SP.)

OCA UPPERHEAD(SEE TABLEFOR DETAILS)

VIEW AS-AS^LOCKING Z-FLANGE

(WEATHER SEAL OMITTED FOR CLARITY)SCALE: 1/2

1-3/8 MIN2" MAX

OCA BODY OUTER SHELL1/4 THK

W\. vC VvV*.Vi vi. vi v o k > \

OCV SHELL(CONICAL TRANS.O ^ 1/4 THK

ICV SHELL1/4 THK

DETAILSCALE: 1/2

OCA LIDOUTER SHELL3/8 THK

26-1/4MIN

103-3/4FROM BOTTOMOF PACKAGE

OCA LOWER HEAD(SEC TABLE FOR DETAILS)

DETAIL L <».*)SCALE: 1/2

8

DETAIL M (««SCALE: 1/2

X LOCK ING Z-FLANGEAND WEATHER SEAL NOT SHOWN

FOR CLARITY.)

DETAJSCALE:

(LOCKBOIT, LOCK!AND WEATHER SEt

FOR CLAI1

OCA LID ASSY.

FOAM PLUG#1-13/32 X 4-1/2 LG

REVISION HBTORVOESCMTKN

E DCHCH6P* na.

-VENT PORT FITTING(REF SH 9 FOR DETAI . )

SEAL TEST PORT ACCESS PLUG1-1/2 NPT PIPE SI2ETYPE 304, STAINLESS STEEL

SEAL TEST PORT COUPLING(REF SH 9 FOR DETAIL)

TUBE, # 1-5/8 X .06 WALLX I* LG., FIBERGLASS |J

TUBING, #1-1/2 X 20 GA.(.030) WALL, ASTM A2I3,TYPE 304 STAINLESS STEEL

— SEAL TEST- PORTDOUBLER PLATE

(SH2)

fllTY)

VENT PORT PLUG(REF SH 9 FOR DETAIL)

FOAM PLUG. # 1-13/32 X 6-1/2 LG.

VENT PORTCOUPLING (OUTBOARD)(REF SH 9 FOR DETAIL)

VENT P0RTli5ACCESS PLUG [2

(REF SH 9 FOR DETAIL)

> VENT PORTDOUBLER PLATE

VENT PORT COUPLING (INBOARD)(REF SH 9 FOR DETAIL)

OCA BOOY ASSY.

PORT COVER(REF SH 9 FOR DETAIL)

TUBE, # 1-5/8 X .06 WALL THK X 7 LGFIBERGLASS

1/2-13UNC-2A X 1/2 LGHEX HEAD BOLT. TYPE 300SERIES STAINLESS STEEL

# 3/32 THRU

TAMPER INDICATING SEAL

IEW AL-ALSCALE; 1/4

#3-7/16

SECTION H-H (SH*2)(OCV VENT PORT)

SCALE: 1/2(WEATHEf. SEAL OMITTED FOR CLARITY)

R 5-13/16

I 1VIEW AT-AT

3/8 THK(SEAL TEST PORT DOUBLER PI.ATE)

(SEAL TEST PORT FITTINGS OMITTED FOR CLARITY)SCALE: 1/8

R 5-13/16

s VIEW AN-AN3/8 THK ••

(VENT PORT OOUBLER PLATE)(VENT PORT FITTINGS OMITTED FOR CLARITY)

SCALE:»l/8

OCA LIDOUTER SHELL

• OCA OUTERTHERMAL SHIELD

OCA BOOYOUTER SHELL

QTY

N.J.SWANNACKWPOW.HENKELAfPOS. A .PORTERAPPCQ.L.SWANNACKAfPOD.SCmOKERAFFCH.VHJNSCHAPPOI.R.RICHARDS -:ENGR..E.ULBRICHT '-,OA G . E . H I L LCHECXH.LEVITTDRAWN WKlUt

UNLESS OTHERWISE SPEOF1E0TOLBUNCES:FcnofsFRcosAHOIES±

a/AX/A

OMBCIONS ARE M MCHE53 PLACE DECMA1SIVA2PLACEDECMALSSK/AIPLACEOEOUAL 1H/A

i n CNlgOUBTO

srsmntsTRUPACT-II

PACKAGING

SCALE: NOTED WT. N / A

REV:DWQSEE

SHE6T4DWQ NO.

2077-500SNP

B

8

D

B

O-RING HOLDER6 GA(.OSO) THX X 1-1/2OPTION:

SEE DETAIL AF SH 7.

JRIVE SCREW PAN HEAD»l/8 X 3/8. I 14 PLCS18-8 STAINLESS STEELOPTION:

SEE DETAIL AF SH 7

O-RING.«68 I.D.(±2X)X #.375±.OIO

ICV UPPERSEAL FLANGE

ICV LOCKING RING

O-WING. 75-5/8 1.0.[1|{ #.400

O-RING. 7 4 - 1 / 4 1 . 0 .[ { j #.375

FROM UPPER SEALFLANGE LOWER SURFACE

FROM LOWER SEALFLANGE UPPER SURFACE

i 8 g > SEAL TEST PORT PLUG(REF SH 9 FOR DETAIL)

SEAL TEST PORT INSERT(REF SH 9 FOR DETAIL)

INNER VENT PORT PLUGREF SH 10 FOR DETAIL)

VENT PORT INSERT(REF SH 10 FOR DETAIL)

-VENT PORT COVER h o i(REF SH 10 FOR D E T A I L ) ^

OUTER VENT PORT PLUG E >(REF SH 10 FOR DETAIL)!---5

SECTION J-J<*H3)(ICV VENT PORT)SCALE: FULL

ICV UPPERSEAL FLANGE

//-FlICV LOCKING RING

FROM LOWER SEALFLANGE UPPER SURFACE

O-RING. 71-1/2 I.D. (1 2%) X #.4001.010

O-RING. 71-3/16 I.D. (± 2X) X #.3751.010

SECTION G-((OCV SEAL TEST PORT}

SCALE: 1/2 :(WEATHER SEAL OMITTED FOR 3

SEAL TEST PORT PLUG &8g(REF SH 9 FOR DETAIL)

SEAL TEST PORT INSERT(REF SH 9 FOR DETAIL)

EAL l\

ICV LOWERSEAL FLANGE

SECTION AK-AK(ICV SEAL TEST PORT)

SCALE: FULL

VIEW AV-AV(OCA STENCILING) [4O~~>

SCALE: 1/4 U - ^(WEATHER SEAL OMITTED FOR CLARITY)

8

3 '

R 1-1/22 PLCS

3 SIDES

2 (2 PLCS)

3 SIDES |<T

REVtSOflttSTOflY

BEV OESCWnON

K !EE OCN

TIE-OOWN. LUG(SEE DETAIL THIS SHEET)

SIDE DOUBLER PLATE H Q ^X 24 X 3 /B THK L - ^

« 1 - 1 / 2 , 30 HOLESTHRU SIDE DOUBLER ONLY

•OCA BODYOUTER SHELL

—GUSSET. 1/4 THK

3/8 ( \ N

VIEW R -SCALE: 1/8

TYPICAL 4 PLACES\Z AS SHOWN. 2 OPPOSITE)

•3 /4 X 3 /4 . ASTW-A276OR ASTU-A479. TYPE 304

STAINLESS STEEL(2 REQ'D. 4 PLCS)

-INSERT. INTERNAL THREADI/4-20UNC-2BTRIDAIR. P/N: KN42OJ(2 REQ'D, 4 PLCS)

(OPTIONAL)

PAN HEAD SCREW [Tg ,.I/4-20UNC X 1/2 l-"""18-8 STAINLESS STEEL1/4 FLAT WASHER2 REQ'D. 4 PLCS

§>

1/2 —II—DETAIL BB

SCALE: 1/4(TYPICAL 4 PLCS. 2 AS SHOWN, 2 OPOSITE)

14 GA (.075 THK)OR 16 GA (.060 THK)

STAINLESS S1EELSECTION BC-BC

SCALE: 1/2/(FOAM AND LYTHERM REMOVED FOR CLARITY)

. , . . fl.460

•21/32

4-3/4

I X 4-3/4 LO'a, TYPE 304NLESS STEEL

SECTION AC-ACSCALE: 1/2

R 9/32—/

B

I — 1/4

TIE-DOWN LUGSCALE: 1/2

W- 2-7/8 r~* '

OR ASTM A479

SCALE: 1/4

LC,CKWASHER

ITEM OTY NEXT ASSY

HFNKFI.A PORTFR

APPDn f cwlMMinfAPPPnAPPOH.WIN5CH

R.RICHARDSF IBHRICHTF HI1L

CH6CKH.IFVITTORAVm WHIM I-O-M

UNLESS OTHERWISE SPECIFIED 0MENS1ONS ARE M MCHESTOLERANCES: 3 PLACE DEOUALS ± V AFRACTION$± K/A 2PLACEDEOUALS±|0kANGLES ± 3>A 1 PLACE OECIMAL ±W/A

FVIOFICNUOJOTR.

SYSTEMS

TRUPACT-II

PACKAGING

SCALE: NOTEDREV: If

S8E

WT M/ASHEET5

2077-500SNP

1

8

WELD FLANGE. 1-1/2 NPTASTM AI82 OR A276. TYPE 304

STAINLESS STEEL

UAKE WELD AFTERFOAM INSTALLATION / | |

PIPE PLUG. FLUSH1-1/2 PIPE SIZEA8S PLASTIC

OCA UPPER HEAD

SECTION Z-Z(»«TYP 3 PLCSSCALE: 1/4

SECTION K-K(tt)IDENTICAL TO SECTION Z-Z WITHOUT FLANGE. PIPE PLUG. AND » 2-3/8 HOLE.

WELO FLANGE. 1-1/2 NPTASTM A182 OR A276.TYPE 304STAINLESS STEEL

PIPE PLUG. FLUSH1-1/2 PIPE SIZEABS PLASTIC

FILL IN FLUSH W/ TOP v /OF BOTTOM DOUBLER PLT / I V

* 2-3/8 i::-i-

VSECTION S-S

A PLI

TYP 6 PLCSSCALE: 1/4

B

• 13/16-4 PLCS EQ SPACEDAS SHOWN ON A

«4 B.C.

SECT I ON AJ-AJ (SH IDSCALE: 1/4(4 PLCS)

DOUBLER PLATE, 3/8 THK X 8 O.D.

4' PIPE.SCH 80 •ASTM A376 OR A312. TYPE 304STAINLESS STEEL

PLT, 1/4 THK X 4-1/2 DIA.

SCALE: 1/4(FOAM AND LYTHERM NOT SHOWN FOR CLARITY)

COVER: STAINLESS STEEL.ALUMINUM OR PLASTIC

RD. TUBING. 4-3/4 O.D. x 4 1.0.RYERTEX FIBERGLASS - GRADE C

RD.BAR, * 7ASTM A

ST

f2 PLCS

./4T\

SECTION AB-AB (SH 3)TYP 3 PLCSSCALE: 1/4

1/4 THK X 2 WIDE PLT2 REQ'D EACH LOCATIONASTM A479 A276.TYPE 304. OR [T^,

- H H*- 2-1/16

TTaTT

FAG4-3/4

/ UPPER 120' ONLYN EACH END OF LIFT PIN

1

SECTION AD-AD (SH 2)TYP 3 PLCSSCALE: 1/4

SCALE: 1/4/LID LIFT POCKET COVER \\NOT SHOWN FOR CLARITY/

V

RD.BAR,#7/8 X 4 LIASTM A479, TYPE 3STAINLESS STEEL

HEX. HD. CAP SCREW,I/4-20UNC-2A x 5/8 L(OR I/4-28UNF-2A x 5/WITH 1/4 I.D. STAR ISTAINLESS STEEL2 REQ'D EACH LOCATIC

8

>EE PCX

BONO HONEYCOMB TO ALUMSHEET WITH 1617 A-BFUFANE ADHESIVE

HONEYCOMB003-3.8P

ALUMINUMACG-3/6-

* 3 THRU(ICV LOWER SPACER ONLY)

3' WIOE CUTOUT6 EO.SP. AT 60

>• RECESS FOR CATALYST AS#15 X 11/18 DEEP(FUTURE APPLICATION)(OPTIONAL)

HEVBONttSTOflY

occx

1SZpa.

SLOT1/2 RADIAL X 5/166 EQ.SP. AT 60*UPPER SPACER ONLY

LOCATIONICV UPPERICV LOWER

0.0.72

70-1/4

1.0.0363

B.C.71

68-1/4

H12-1/411-5/16

O.R.7474

SPACER DETA1 L <SH 2)SCALE: NONE

LOCKING RING

/32

ICV LOCKING RING ICV LID

#5/16 THRUCSK #1/2 X 82*6 EQ SP AT 60*LOWER SPACER ONLY(OPTIONAL: SLOT, 1/2 RADIALX 5/16. 6 EQ. SPACES AT 60*)

UNLOCKED LOCKED6-21/32

VIEW X-X (»4,(IN LOCKED POSITION)

SCALE: 1/2OCA OUTER SHELL

i(FOAM NOT SHOWN FOR CLARITY)B

OCA LP*tR HEAD

SECTION AA-AA (SH 2)SCALE: 1/2

33

5"»S

U FILL PORTS/4 THK PLATE'. ON # 78 BCER OF BOTTOMFLANGED HEAD

BEL H .1 .QHkNNACK '-7<-*8APPDuj UENKEL

APPOe A PORIER_

APPOn SCI*!OKEfi_APPOu WUNSCH_

P PirHARDSr 111 BRIGHT

QA

CH6CKU I FVITT

-n-ti

'-H-ti

UNLESS OTHERWISE SPECffEOTOLERANCES:HWCDOHS± (l/A

OMaexms ARE m MCHES3 PLACE OEOUAU ± KM1 PLACE DECIMALS ± */kf PLACEDECtMAL * K / A

ivinncNUOJEnR

5Y5TEM5

TRUPACT-II

PACKAGING

SCAlfc NOTFD WT. M / A

REV:

DWGSUE

SHESTg O F | |

OWQNa

2077-500SNP

8

OCV UPPER HEAD"(SEE TABLE. SH 3 FOR OETAILS)

hJ£>l/4 THK PLTOCV UPPER SEAL FLANGE(REF SH 7 FOR DETAIL)

STAINLESS STEEL COMPATIBLELUBRICANT (OPTIONAL)

>»PAN HEAD SCREW. #IO-24UNC-2A X 1/2 LGOR #IO-32UNF-2A X 1/2 LG.STAINLESS STEEL3 REQUIRED AT EACH OF 6 LOCATIONS(OPTIONAL)

GUIDE PLATE, 7 GA.(3/I6 TKK) X 4.S X 10!>6 PLACES EQUALLY SPACED

(OPTIONAL)

OCV LOWER SEAL FLANGE


\/

#12 X 1/2 DP. RECESS3 EQ.SP. AT 120

(ICV UPPER SPACER ONLY)

#5-1/2 POCKETS3 EQ.SP. AT 120*

(ICV UPPER SPACER ONLY)

3 TYP-I(ICV UPPERSPACER ONLY)

ALUM.SHT.,14 GA(.OSO THK)ASTM B209. 606I-T6

J

OCV LOCKING RING(REF SH 7 FOR DETAIL)

ICV OR Cl

PAN HEAD SCREW.I/4-20UNC-2A x 3/8 LGOR I/4-28UNF-2A X 3/8 LGI8-« STAINLESS STEELTYP 36 PLCSTORQUE: 22-28 IN-LB

DETAILSCALE: 1/2

B

TO C_ INSIDE DISHED HEAD RADIUS

12

—"11-5/8 f—

VI EW W-W <*(ICV OR OCV SEAL TEST PORT

SCALE: 1/2ICV '.I

UPPER SPACER .ASSEMBLY(SEE DETAIL THIS SHEET)

I/4-20UNC X 3/4 PAN HD.ALUM. SCR.5/16 FLAT WASHER, AS REQ'D

U-TYPE FASTENER, 1/4-20 UNC6 PLCS EQ.SP.

> BRACKET, I2GA.(.105 TKK)1-1/2 WIDE. 6 PLCS EQ. SP.

ICV UPPER SEAL FLANGE


ICV UPPER HEADTABLE, SH 3 FOR DETAILS)

ICV LOWER SEAL FLANGE


STAINLESS STEEL COMPATIBLELUBRICANT (OPTIONAL)

DEBRIS SHIELD(REF SH 7 FOR DETAILS)ICV LOCKING RING(REF SH 7 FOR DETAIL)

MAKE WELD AFTERFOAM INSTALLATION

4 EO.PLUS ONE AT Cl|

DETAIL V(SH2)

/\

1/4 THK PLTf

SCALE: 1/2

8

3 '

.95

.9

2.95

REV

REVtSON HSTORY

iEE DCN

R 1/162 PLCS

#80-1/16

» 78-11/16—\

— * 79-9/16

.215

.205

DETAIL BASCALE: 4/1

I/4-2BUNF-2B X 3/8 OP. ORI/4-20UNC-ZB X 3/8 DP.36 PLCS - SEE VIEW AW-AW(SH 8) FOR OETAILED LOCATIONS.

5/32

OCV LOCKING RING(SEE SH 8 FOR PLAN VIEW)

SCALE: FULL

POLYETHYLENE FILTERGENERAL POLYMERICP/N:7I4.2OO-I2A

• 1/8 X 7/16LOCATE 90*. 180* t 270

FROM SEAL TEST PORT.

VI

R 1/82 PLCS

13/32

rr*m w u . I U I runi. —._— . . . ...PRESS "IT AND STAKE BOTH ENOS U L I A I L A U

SCALE: 4/1

API

R .04

DETAIL AZSCALE: 2 / 1

(TYP, 2 PLCS. EACHLOWER SEAI FLANGE)

13/32

— - « .74-7/16 —— # 75-5/16

API- 1/2

(SH8)

ICV LOCKING RING(SEE SH 8 FOR PLAN VIEW)

SCALE: FULL

BREAK CORNERSAPPROX. .005 RAO.

1/32

DETAIL AHSCALE: 2/1

B

R6L N.J.SWAWACK

*"PW.HENKELWOS.A.PORTERAPPQn t SWANNACK

NUQJD1R5Y5TEM5

APPOD.SCHMOKER •2HLAPPCH.WUNSCHAPPOJ.R.RICHAROSENOtL.E.HLBRICHT

G.E.HILL

ITEM OTY NEXT ASSYO«*H.LEVITTDRAWN WTAN

UNLESS OTHERWISE SPECIFIEDTOLERANCES:FRACTIONS* H/AANGLES ± M/A

0MEKSOKS ARE IN MCHES3 PLACE DECMALS ± 1 0 12 PLACE DEOMALS ±H/A1PLACED6CMAL ±K/A

TRUPACT-II

PACKAGING

SCALE: HQTED WT. N / A

REV:

DWG DWQNO.

SHEET7 O F I I

2077-500SNP

1

B

8

# 78-5/8# 77-5/16# 76-13/16

JIO-24UNC-2B X .5 OP.-T. \/S / *3 REQ'D AT EACH OF 6 EO.SP. \ ' /Y /

-# 78.405

DETAIL BA# 79-1/2

OCV UPPER SEAL FLANGESCALE: FULL

— - # 76-7/8

— — # 78-9/16

- — » 78-5 /8 (O.D. OF FLANGE BETWEEN LUGS)—\

— • 79-1/2 •

OCV LOWER SEAL FLAN

• 74-3/8

DETAIL AF(OPTIONAL)

ADHESIVE TAPEDOUBLE-SIDED, 1/2 WIDEADHESIVES RESEARCH #5190

(SEE SH 8 FOR PLAN VIEW)SCALE: FULL

DETAIL AU-\ -,«95_

DEBRIS SHIELDSIL1CONE SPONGE.OPEN CELL1/4 THK X 1/2 WIDECHR INO. #F-12

>-DETAIL BA DETAIL AH* 75-1/4

CV UPPER SEAL FLANGESCALE: FULL

— — #72-1/2 —

R .180-^v

R . I 2 -

-# 73-1/8 —

-# 74-5/16-

k- .050

• — # 74-3/8 (O.D. OF FLANGE BETWEEN LUGS) —

— # 75-1/4

.030-

DETAIL AFSCALE: FULL

(ICV UPPER SEAL FLANGE OPTION)

ICV LOWER SEAL FLANGE(SEE SH 8 FOR PLAN VIEW)

SCALE: FULL

8

"3 '

25•RING LOCKED VENTPORT LOCATION

RING UNLOCKED VENTPORT LOCATION

/LOCATION OPTIONALNROLLED PLATE OPTION ONLY

/ 11/64 X 45*/ CHAUFER/ 36 PLCS.

REVBXJN KSTOAY

BEV OCSCHPIION;EE OCN

occx

mo*

1/4

•LOCKING RING PIN#1/4 X 4-1/2 LG.CON0.IIS0. ASTM AS64TYPE 630-

03/8 THRU

• 1/42 HOLES

MINIMUM THICKNESS SAWCUT2 PLCS

6-47/64 TYP 6-1/4 TYP •

/LOCATION OPTIONAL\ROLLED PLATE OPTION ONLY

VIEW Y-Y(ICV LOCKING RING)

SCALE: 1/2

-LOCKING RING PIN#1/4 X 4-1/2 LG.CONO.IISO. ASTU AS64TYPE 630

•1/42 HOLES

MINIMUM THICKNESS SAWCUT2 PLCS

PLAN VIEW (SH7)« CLARITY)

2-11/3220" I

18 PLCS. 1

-3-5/16 18 PLCS

6-39/64 18 PLCS

B

7-7/64 TYP 6-39/64 TYP-

13/32VIEW AW-AW i(OCV LOCKING RING) '

SCALE: l/j,;a

1/16PLCSKING RING STOP PLATE. 105 THK) [ ? > >X 13/32 l i * - ^

\ AY-AYi 1/2

ITEM QTY NEXT ASSY

R6L N.J.SWANKACK Z-24-89AfPOW.HENKEL l-U-tiAPPDS. A . PORTER*H"O D. L. SWANNACKAPTOQ.SCHMOKER 2-24-89APfOH.WJNSCHAPPOU.R.RICHARDSENGBL.E.ULBRICHTQA G.E .H ILLCHECK H.LEVITT

M.KI

2-24-892-24-89

2-23-892-2J-892-2M92-24-892-2W9

UNLESS OTHEmASESPECFIEDTOLERANCES:FRACTX)NS± */AANQLES± */A

0MEN9ONS ARE M MCHES3 PLACE DECMALS ± V *»PLACEOEOMAU± K *1 PLACE0EOMAL ± I t *

SY5TEM5TRUPACT-II

PACKAGING

SCALE: NOTEO WT.REV:DW3Sd

D

N/ASHEETS OF

0W3K0.

2077-500SNP

8

B

- LOCK BOLTLOCATION VENT PORT LOCATION

/LOCATION OPTIONAL\ ROLLED PLATE OPTION ONLY

SHARP CORNER(STOP PLATE LOCATION)

11/64 X 45" CHAMFER35 PLCS. £ OF JOINT

SEAL TEST PORTLOCATION

l—3-5/32 18 PLCS

ICV LOWER SEAL FLANGE PLAN VIEWSCALE: I/8

(SH 7)

SEAL TEST PORT LOCATION

CV LOCKING RING PLAN(UPPER FLANGE REMOVED FOR CLARITI

SCALE: 1/8

/LOCATION OPTIONAL\ROLLED PLATE OPTION ONLY

SHARP CORNER(STOP PLATE LOCATION)

( O F JOINT

11/64 X 45*CHAMFER36 PLCS.

SEAL TEST PORT LOCATION

6ll/l618 PLCS.

.3-11/3218 PLCS.

OCV LOCKING RING(UPPER FLANGE REMOVED

SCALE: 1/

OCV LOWER SEAL FLANGE PLAN VIEW(SH7)SCALE: I/B

13/32

• 3/4-v2 PLCS.X

-3/8 J ^LC

i : \

5CKV! itn)|^UNLOCK\•^M—1,

2 plfci. VIEW AP-AP (SH7)(ICV LOCKING RING OPERATING HANDLE KEYSLOTS)

(4 PLCS)SCALE: 1/2 f ^ ^

LOCKING RING STOP PLATE12 GA (.105 THK) fT>-1-5/16 X 13/32 liS-*

SECTION AX-AXSCALE: 1/2

L12 GA1-5/1

SECTKSCA

— 7/328 PLCS.

ION AM-AMS C A L E : l / 2

8

I-9/I6-ISUNEF-2A

I/2-20UNF-2BPER SAE J5I4

CHAM I/IS X 45*

CHAM.1/8 X 45*

REVEJON KSTORY

REV OESCSVUON

SEE OCNCHECK! ne.

I-3/I0-I2UN-2BPER SAE J5I4

9/I6-I8UNF-2BPER SAE JSI4

DETAIL DETAIL

1-1/2 NPT

[ST PORT INSERT OCV VENT PORT FITTING OCV SEAL TEST PORT COUPLINGSTAINLESS STEEL

ION)ASTM A479. TYPE 304 STAINLESS STEEL

(IN SECTION)

ASTM A276 OR ASTU A479. TYPE 304 STAINLESS STEEL(IN SECTION)

\ \ \ \III

•ifn2 PLCS

HEX

#3/32 THRU-

SOC.HO. CAP SCREWI/2-J3UNC-2A X I*

ia-8 STAINLESS STEEL

T11/162 PLCS 5/32-J

LSMLS TUBING.5/8 O.D. X 18 GA (.048)TYPE 304 STAINLESS STEEL

TACK(NOTES 8.7AND 8 NOTAPPLICABLE)

OCA

—13/32,

DETAILLOCK BOLT WELDMENT

SCALE: 2/1

1-1/2 NPT

1-1/2 NPT

DETAILVENT PORT ACCESS PLUGTYPE 304 STAINLESS STEEL (MOOIFIEO STO. PLUG)

(IN SECTION)

SULS TUBING3/4 0.0. X II GA (.120)-TYPE 3Q4 STAINLESS STEEL B

SOC.HO. CAP SCREWI/2-I3UNC-2A X I*

18-3 STAINLESS STEEL

(NOTES 6.7 \AND 8 NOT 3 P L /APPLICABLE) TACK

; •• DETAILCV LOCK BOLT WELDMENT

SCALE: 2/1

(OUTBOARD)NLESS STEEL

rTEM OTY NEXT ASSY

H .1 ^WIKMAPK ; -

APPOn I

F in BRirHT

°* n F mi iCHECXM IFVITTDRAWN u. movum

UNLESS OTHERWISE SPEOREOTOLERANCES:FTUCT)ONS± «/AANGLES ± K/A

OMEN9ONS ARE IN MCHES3 PLACE DECIMALS ± H / A2 PLACEDEOMALS±S>At PLACE DEOMAL ± K>A

5Y5TEM5

TRUPACT-II

PACKAGING

SCALE: NQTEDREV:DWGSIZE

D

M/ASHEET9 OF | |

2077-500SNP

1

8 7

B

I—HI— 1/16

3 / 4 T - I 6 U N F - 2 APER SAE J5I4'

I/2-20UNF-2BPER SAE J5I4

CHAM 1/16 X 45'

15"

OPTION I DETAILOCV & ICV SEAL TEST PORT INSERT

ASTM A479, TYPE 304 STAINLESS STEEL(IN SECTION)

13/32

HANDLING O-RINGAS-568-OI1

OPTION 'iOCV & ICV SEAL '

ASTU A479. TYPE(IN SE

•9/I6-I8UNF-2APER SAE JSI4

.SEAL O-filfAS-568-906

DETAILOCV VENT PORT PLUG

ASTM BI6. ALLOY 360 BRASS. 1/2 HARD TEMPER

I -9/16-18UNEF-2B-

#2-3/8

1-7/8 —-f-1-3/16 -

—(11/16

/.HANDLING O-RINGAS-568-OU

•7/8

1-3/16-12UN-2APER SAE JSI4

DETAILOCV VENT PORT COVER

ASTM BI6. ALLOY 360 BRASS. 1/2 HARD TEMPER(IN SECTION)

• 1-5/8 #2

DETAILOCV VENT PORT COUPLING (INBOARD)

ASTM A479, TYPE 304 STAINLESS STEEL( IN SECTION)

SEAL O-RING*" AS-568-905

— 17/642 PLCS

I/2-20UNF-2APER SAE J5I4

-5/8

2-3/8 •

\

v/,

y. I21"

L1

l—i

#5/16 X 82' CSK

OCV SEAL TEST PORT PLUGASTM BI6. ALLOY 360 BRASS. 1/2 HARD TEMPER

DETAILOCV VENT PORT COUPLING!

ASTM A276 OR ASTM A479, TYPE 304 ST.|(IN SECTION)

8

8

7/8-I4UNF-2BPER SAE J5U

#1-13/32

I-9/I6-IBUH-2A

SEAL O-RING> AS-56B-906

B.

9/I6-I8UNF-2APER SAE J5I4

9/l6-l8UNr-2BPER SAE J5U

DETAIL "1CV VENT PORT INSERTASTM A479. TYPE 304 STAINLESS STEEL

(IN SECTION)

—1 —1/4 2 PLCS

#5/16 X 82* CSK

RI/16 MAX.4 PLCS

DETAILICV INNER VENT PORT PLUG

ASTM BIO. ALLOY 360 BRASS, 1/2 HARD TEMPER(IN SECTION)

8

REVtSON HSTORYICHECKl REL

E PCH

GASKET1/16 THK

I-3/8-I2UN-2A

#1-1/4

• I-II/I6

- { 3/8 J - D

-R 1/164 PLCS

#7/16 X 82* CSK

- J 7/16 I -

DETAILICV VENT PORT COVER

ASTM BIO. ALLOY 3E0 BRASS. 1/2 HARD TEMPER(IN SECTION)

^ ^ SEAL O-RINGIB> AS-S68-9I0

7/8-I4UNF-2APER SAE J5I4

— 3/0. 2 PLCS

B

#7/16 X 82* CSK

RI/16 UKX.4 PLCS

-A 7/16 J-

DETAILICV OUTER VENT PORT PLUG

ASTU BIO. ALLOY 360 BRASS. 1/2 HARD TEMPER(IN SECTION)

SYSTEMSAPPDg jAPPDc » PORTER^APPDl c ULBR1CH1B O A i p RfCHARDSOA j n r F R I T HCHECKu I F V I T T

(TSI QTY NBCTASSY DRAWN PL aUIVAMUNLESS OTHERWISE SPECKS)TOLERANCES:FRACTIONS ± n/A ,AN0LES± 5>A

OMENSK)NS ARE N MCHE51 PLACE OECNALS ± a/A2 PLACE OEOMALS ± Zl1 PLACE 06OMAL ±5/A

TRUPACT-II

PACKAGING

SCALE- g / | WT.

OWO DW3N0.

D

SHEETIQ O F | |

2077-500SNP

1

OEVISXW HISTORY

iCE DCN

OCCX

# I*. 18 HOLESTHRU BOTTOM OOUBLERONLY

GUSSET. 1/4 THK [lf>

D0U8LER PLATE

IB PLCS

SECTION T-T. OPTION 2<«»)SCALE: 1/4

(TYPICAL 4 PLACES. 2 AS SHOWN, 2 OPPOSITE)FOAM ANO LYTHERM REMOVED FOR CLARITY

BOTTOM TRIPLER PLATEI" THKfJ>>

S SIDES

ITEM OTY

SECTION BE-BESCALE: 1/4

TYPICAL * PLCS(FOAM ANO LYTHERM REMOVED FOR CLARITY)

NEXT ASSY

APPOg iAPPGh i cufiuji

F 111 RPirUTBWfli p oirmongOA r> cCHECXM I F V I T T

DRAVWw t-l-UNLESS OTHERVHSE SPEOFIB)TO10UNCES:FRACTIONS± - / .AMQtB* S>i

DSieOOKS ARE M WCHES3 PLACE 0EOMA15 ± | i / AJ PLACE DEOMALS ± K J1PLACEDEOMA1. ±j}>I

MUHEffR5Y5TEM5

TRUPACT-II

PACKAGING

SCALE: un-rcn WE M / 1

REV:DWGSIZE

SHEETn ' O F n

2077-500SNP

1

B

b

R 46-5/8

R 46-3/16

4 PLCS

t I*. 18 HOLESTHRU BOTTOM DOUBLERONLY

GUSSET. 1/4 THK

BOTTOM DOUBLER PLATE1/4 THK 1^,.

18 PLCS

• 7 V

SECT I ON T - T , OPT I ON 1 <*«>SCALE: 1/4

(TYPICAL 4 PLACES. 2 AS SHOWN. 2 OPPOSITE)FOAM ANO LYTHERM REMOVED FOR CLARITY

B

BOTTOM TRIPLER PLATE1/2 THK [

5 SIDES

8

SECTION BD-BDSCALE: 1/4

TYPICAL 4 PLCS(FOAM ANO LYTHERM REMOVED FOR CLARITY)

NnP»c TEUPACT-II SAR Rev. 0, February 1989

APPENDIX 1.3.3

SPECIFICATION FOR 55 GALLON DRUM AND LINER

1.3.3-1


1.3.3 Specif i cat ion for 55-Gallon Drum and Liner

The CH-TRU material is contained in 55-gallon drums. The typical materials of

construction are shown in Table 1 .3 .3 -1 . The nominal drum dimensions are

depicted in Figure 1.3.3-1.

The drum's l id can have one of tiro possible configurations. One l id configur-

ation is a standard l id with, no bungs. The other l id configuration has a 3/4

inch Re ike bung f i t t ing . Both require a minimum of one carbon composite

f i l t e r as specified in Appendix 1.3.5. A gasket i s required for closure. The

gasket material i s either tubular Styrene-Butadiene, or Styrene Butadiene

foam, or equivalent.

A rigid polyethylene liner may be used inside the drums. If a l id i s used

with the liner* the l id must contain a 0.3 inch minimum diameter hole or a

f i l t e r equivalent to the hole for hydrogen release.

Table 1.3.3-2 identif ies material content forms authorized for transport in a

55-gallon drum. I

1.3.3-2


TABLE 1.3.3-1

55-Gallon Drum Materials of Construction

Location Material

body and heads

closure

15 gauge s tee l ,18 gauge steel ,3/8 inch minimum convextop and bottom head

12 gauge bolted ring,5/8 inch diameter bolt and nut

gasket - Type IType II

roll ing hoops

Tubular Styrene-Butadiene or equivalentDewey, or Almy Styrene-ButadieneFoam, or equivalent

3-rolled or swedged types, onewithin 3 inches of the top curl

TABLE 1.3.3-2Material Content Forms Authorized for Shipment in 55-Gallon Drums

MaterialForm Number Material Description

1

2

solids - any particle size

solids - large particle size only

(i.e., sand, concrete,

debris, etc.)

solids - objects with no significant

dispersible or removable

contamination

1.3.3-3


Steel Orum (55 gallon)

33 1/4 in. UsableInside Height

221/2 in.1.0.

Bolt Ring (12 gauge)

Boh: (5/8 in.)

Head and Gasket

Roiling Hoop(3 required)

Bodv and Head Sheet

FIGURE 1.3.3-1

Nominal 55-Galloa Drum Dimensions

1.3.3-4


APPENDIX 1.3.4

SPECIFICATIONS FOR STANDARD WASTE BOX AND

TEN DRUM OVERPACK

1.3.4-1


1.-3.4.1 Specification for Standard Waste Box (SWB1 J

The Standard Waste Box (SWB) is a metal box designed to efficiently use the ICV

cavity of the TRUPACT-II Shipping Package. The SWB is available in two styles

of closure: 1) closed with a neoprene gasket and forty-two (42) screws, and 2)

closed with a 1/8-inch fillet weld. Table 1.3.4-1 specifies the nominal

dimensions, and Table 1.3.4-2 the weight of each SWB type. The nominal SWB

dimensions are depicted in Figure 1.3.4-1.

There are four (4) filter ports available in a SWB. Bach SWB requires a minimum

of two (2) carbon composite filters as specified in Appendix 1.3.5. Any ports

that do not contain filters are plugged during transport. The SWB materials of

construction are listed in Table 1.3.4-3.

Table 1.3.4-4 shows material content forms authorized for transport in an SWB.

TABLE 1.3.4-1

SWB Overall Dimensions

Internal External

Dimensions Dimensions

(Inches) (Inches)

height " 36.7 37.0

width 51.9 54.25

length 68.7 71.0

1.3.4-2

NoPac TRUPACT-II SAR Rev. 1 , May 1989

SWB

Style

1

2

TABLE 1.3.4-2SWB Weiglits

Weight (lbs)

Empty Gross

640

630

4,000

4,000

TABLE 1.3.4-3SWB Materials of Construction

Location Material

Sides, top, ends,and bottom

Lift attachments

Upper perimetertube assembly

Offset tubes

Lid perimeterreinforcement

Gasket(Style 1 only)

42 screws(Style 1 only)

4 f i l t e r ports

ASTM A-569, low carbon steel, 10 gauge

ASTM A-36, commercial quality structural gradecarbon steel plate, 1/4 in x 1-1/2 in

ASTM A-513, commercial quality grade carbonsteel tube, 1-1/2 in x 2 in x 11 gauge

ASTM A-513, carbon steel tubing,•1 in x 1 in x 11 gauge

ASTM A-36, carbon steel plate, 1/2 in x 1-1/2 in

ASTM D1056-67, EDPM closed-cell neoprene orequivalent, 1/2 in thick x 1-1/2 in wide

MS24667, 1/2-13 DNC, alloy steel,flat head, socket cap screws

ASTM A-53, 3/4 NPT pipe coupling, carbon steel

1.3.4-3

NnPac TRUPACT-II SAR Rev. 2, June 1989

TABLE 1.3.4-4

Material Content Forms (Non-Radiological Characteristics) Authorized

For Transport In A Standard Waste Box

Material

Form Number Material Description

1 Solids - any particle size

2 Solids - large particle size only ( i . e . , sand,

concrete, debris, e tc . )

3 Solids - objects with, no significant dispersible

or removable contamination

4 Large buliy dense objects with sharp and obtrusive

members or components with dispersible Form 1 and 2

( i . e . , steel plate, e lectr ic motors, steel pipe,

concrete blocks, etc . )

5 Four (4), 55-galTon drums in any arrangement not to

exceed 1,450 pounds per drum

6 One Bin per Standard Waste Box

1.3.4-4

NnP«c TEDPACr-II SAR Rev. 1. May 1S89

BODY PANELS(TOP. BOTTOM,SIDES. ENDS)

71* OH.(OUTSIDE OF POSITIONING TUBES!

SCREW

FILTER PORTS

LIFT ATTACHMENT

5L ML' O.D.(OVER LIFT ATTJ

GASKETUPPER PERIMETER TUBE ASSY.

OFFSET TUBESLID PERIMETER REINFORCEMENT

FIGURE 1.3.4-1

Nominal SffB Dimensions

1.3.4-5


j The Ten Drum Overpack (TDOP) is a metal container, similar to the SWB, designed

| to efficiently use the ICV cavity of the TRUPACT-II Shipping Package. The TDOP

j is a welded-steel, right circular cylinder, approximately 74 inches high and 71

| 'inches in diameter. The maximum loaded weight of a TDOP is 7,265 pounds. A

| bolted lid on one end is removable; sealing is accomplished by clamping a

j neoprene gasket between the lid and the body. There are ten filter ports located

! near the top of the TDOP. Each TDOP requires a minimum of nine (9) carbon

| composite- filters, as specified in Appendix 1.3.5. The TDOP materials of

j construction are listed in Table 1.3.4-5. TDOP material content forms are

| listed in Table 1.3.4-6. A schematic of the TDOP is shown in Figure 1.3.4-2.

1.3.4-6

HuPac TRUPACT-II SAR Rev. 12, September 1992

TABLE 1.3.4-5

TDOP Materials of Construction

Location

Sides, top and bottom

Lift attachments

Tubing

Gasket

Fasteners

Filter ports

Material

Steel

Steel

Steel mechanical tubing

Polymer

Steel screws

Steel

TABLE 1.3.4-6

TDOP Material Content Forms (Non—Radiological) Authorized for Transport

Form Number

1

2

Material Description

Ten, or less, 55-gallon drums, as described in

Appendix 1.3.3.

One Standard Waste Box (SWB), as described in

Appendix 1.3.4.

1.3.4-7


73M HIGH(LID INSTALLED)

72" O.D.(MAX)

SCREW

LID

GASKET

BODY

FILTERPORT

OFFSETTUBES

FIGURE 1.3.4-2

Nominal TDOP Dimensions

1.3.4-8

NtiP«c TRUPACT-II SAR Rev. 9. December 1990

APPENDIX 1.3.5

CARBON COMPOSITE AND KEVLAR FILTER VENT SPECIFICATIONS I


APPENDIX 1.3.5

CARBON COMPOSITE FILTER VENT SPECIFICATIONS

1.0 INTRODUCTION

Two minimum vent specifications are included for carbon composite filters.

2.0 SPECIFICATION FOR DRUM FILTER VENT

Each drum to be transported in TRUPACT-II will be installed with one or more

carbon composite filters. The filter media shall be made of a porous

carbon/carbon composite. The minimum capacity of the filter shall be 200 ml/min

at one inch of water gauge pressure drop across the filter using air or one liter

per minute at one psi gauge pressure drop across the filter using air. A minimum

hydrogen diffusivity of 1.90E-6 mole/sec/mole fraction at room temperature (25°C)

is specified per filter. This hydrogen diffusivity value has been specified as

it is the minimum measured diffusivity value obtained in testing twelve

individual filters. Appendix 3.6.9 of the SAR lists the individual filter

diffusivity measurements. A 100Z verification of the flow capacity shall be made

on the filters. Each filter unit shall exhibit filtering efficiencies of >99.9X

with 0.3 to 0.5-micron particles of dioctyl phthalate (DOP) smoke. The following

information should be legibly engraved on the lid top of each filter.

Supplier's name

Lot number or a unique, serial number

Additional requirements (shipping and handling, for example) and quality control

shall be administered by site-specific quality assurance programs.

1.3.5-1

HuPae TRUPACT-II SAR Rev. 9, December 1990

3.0 SPECIFICATION FOR SWB FILTER VENT

Each Standard Waste Box to be transported in TRUPACT-II will be installed with

two or more carbon composite filters. The minimum capacity of the filter shall

be 200 ml/min at one inch of water gauge pressure drop across the filter using

air. A minimum hydrogen diffusivity of 3.70E-6 mole/sec/mole fraction at room

temperature (25°C) is specified per filter. This hydrogen diffusivity value has

been specified as it is the minimum measured diffusivity value obtained in

testing six individual filters. Appendix 3. 6. 9 of the SAR lists the individual

filter diffusivity measurements. A100Z verification of the flow capacity shall

be made on the filters. Each filter unit shall exhibit filtering efficiencies

of >99.9Z with 0.3 to 0.5-micron particles of Di-Octyl Pthalate smoke. The

following information should be legibly engraved on each filter:

Supplier' s name

Unique serial number

Additional requirements (shipping and handling, for example) and quality control

shall be administered by site specific quality assurance programs.

4.0 SPECIFICATION FOR BIN FILTER VENT

Each bin overpacked in a SWB will be equipped with two or more Kevlar or carbon

composite filters to facilitate the release of hydrogen or any other gases

generated in the bin. The minimum flow and hydrogen diffusion requirements for

these filters are the same as those for the SWB filters listed in Section 3. 0.

Appendix 3.6.9 of the SAR lists the individual filter diffusivity measurements

obtained from testing four of these filters. All of these measurements are

considerably higher than the minimum requirements for the hydrogen diffusivity

values. Since all the bins are overpacked in standard waste boxes, no filtering

efficiency requirements are made for the Kevlar filters in the bins.

The following information should be legibly engraved on each filter:

Supplier' s name

Unique serial number

Additional requirements shipping and handling, for example and quality control

shall be administered by site specific quality assurance programs.

1.3.5-2

NuPac TRDPACT-II SAR Rev. 12, September 1992

5.0 SPECIFICATION FOR TDOP FILTER VENT j

i

Each TDOP used -bo overpack drums or SWBs will be installed with a minimum of nine |

carbon composite filters. The specifications for these filters are identical to j

those for an SWB filter vent as described in Section 3.0. !

1.3.5-3

NnPac TRUPACT-II SAR Rev. 0, February 1989

APPENDIX 1.3.6

SPECIFICATION FOR CLOSURE OF INNER CONFINEMENT LAYERS

1.3.6-1

NnPac THUPACT-II SAR Rev. 2 , June 1989

APPENDIX 1 . 3 . 6

SPECIFICATION FOR CLOSTJRE OF INNER CONFINEMENT LASERS

For the payload of-TRDPACT-II, a confinement layer i s def ined as f o l l o w s :

Any p l a s t i c bag containing waste w i th the c losure method as described

below. Since the only approved methods of c losure are the ones out l ined

below, bags that are not c losed or those without waste w i t h i n do not

cons t i tu te layers of confinement. Punctured bags or l i n e r s , bags open at I

the end, or p i e c e s of p l a s t i c sheet ing wrapped around waste for handling

are not considered as l a y e r s of confinement.

Waste material type I I . 2 i n metal cans does not generate any flammable gas, as

described in Appendix 3.6.7, and hence needs t o meet no s p e c i f i c requirements

of c losure . Metal cans wi th ro l l - seam c losures cannot be used for waste type I

and I I I because the cans are a i r - t i g h t . R e s t r i c t i o n s on the physical form of

the waste out l ined in Appendix 1 .3 .7 preclude the presence of other sealed

containers greater than one g a l l o n in s i z e .

Drum l i n e r bags sha l l be made of mater ia l s belonging t o the c l a s s of po ly -

ethylene (PE) or polyvinyl chloride (PVC) wi th a nominal th ickness between 5 -

15 mi l s and having a surface area of a t l e a s t 1 .6 m . (This area i s equal t o '

that of a r i g i d drum l i n e r - therefore any bag l a r g e r i n s i z e than the drum

liner will meet this specification.)

The only allowable methods of closure for plastic bags used for waste confine-

ment are the following:

Twist and tape closure

Fold and tape closure

1.3.6-2

NuPac TRUPACT-II SAR • R e v« °» Febraary 1989

7/hen the method of closure is twist and tape* the waste bag that is ready to

be closed should be twisted off at the end and then taped tightly with plastic

tape. Site-specific health and safety procedures shall govern the precautions

to be taken by the operators. No supplemental sealing devices such as clamps

or heat sealing shall be used. The twisted portion of the bag that is taped

should generally have a length of six inches; however, procedures for twist

and tape can be site specific. The fold and tape procedure is applicable but

not restricted to bags used in the Standard Waste Boxes (SWB) for which

twisting the-top end is not practicable.

1.3.6-3

NuPac TRUPACT-II SAR R e V - 3 t J u l y 1 9 8 9

APPENDIX 1.3.7

TRUPACT-II AUTHORIZED METHODS FOR PAYLOAD CONTROL

(TRAMPAC1


TABLE OF CONTENTS

SECTION PAGE

1.0 SUMMARY . 1

1.1 References 3

2.0 INTRODUCTION 4

2.1 Waste Acceptance Criteria Certification Committee 5

2.2 Purpose 6

2.3 Payload Parameters 7

2.4 References 7

3.0 PAYLOAD SHIPPING CATEGORIES AND WASTE CLASSIFICATION 8

3.1 Introduction 8

3.2 References 8

4.0 PHYSICAL FORM 9

4.1 Methods of Determination and Control 9

4.1.1 Visual Examination of the Waste 10

4.1.2 RTR Verification of the Physical Waste Form 10

4.1.3 Records and Data Base Information 11

4.1.4 Sampling Programs 11

4.2 References 12

1.3.7-i

NuPac TRUPACT-II SAR Rev. 2, June. 1989

TABLE OF CONTENTS

SECTION PAGE

5.0 CHEMICAL PROPERTIES 13

5.1 Shipping Category Restrictions 14


5.2.1 Control of Explosive Materials 15

5.2.2 Control of Pyrophoric Materials 16

5.2.3 Control of Corrosive Materials 16

5.2.4 Control of Chemical Composition of the Waste 17

5.2.5 Control of Flammable Volatile Organic Compounds

in Payload Containers 31

5.2.6 Sampling and Chemical Analysis of Stored Waste 32

5.3 References 32

6.0 CHEMICAL COMPATIBILITY 33

6.1 References 34

7.0 GAS DISTRIBUTION AND PRESSURE BUILDUP 35

8.0 PAYLOAD CONTAINER AND CONTENTS CONFIGURATION 36

8.1 Specifications for Waste Packaging Parameters 36

8.1.1 Specifications for Payload Containers 36

8.1.2 Specification for Filter Vents 37

8.1.3 Venting and Aspiration Requirements 37

8.1.4 Requirement for Rigid Liners 38

8.1.5 Specification for Inner Layers of ConfinementAround Waste 38

1.3.7-ii

NuPac TRUPACT-II SAR . Rev. 1, May 1989

• ' TABLE OF CONTENTS

SECTION ' PAGE


8.2.1 Methods of Determination and Control for

Payload Containers. 39

8.2.2 Methods of Determination and Control forFilter Vents 39

8.2.3 Methods of Determination and Control forRigid Liner 40

8.2.4 Method of Determination and Control for InnerConfinement Layers 40

8.3 References 40

9.0 ISOTOPIC INVENTORY AND FISSILE CONTENT 41

9.1 Isotopic Composition 42

9.2 Methods of Determination and Control of Isotopic Composition 42

9.2.1 Product and Process Analysis by Mass Spectrometry 42

9.2.2 Gamma Ray Pulse Height Analysis 44

9.3 Quantity of Radionuclides " 44

9.4 Methods of Determination and Control of Radionuclide

Quantity 45

9.4.1 Pu-239 Fissile Gram Equivalent of IndividualRadionuclides 46

9.4.2 Pu-239 Fissile Gram Equivalent of IndividualPayload Containers 46

9.4.3 Pu-239 Fissile Gram Equivalent of the TotalTRUPACT-II Payload 47

9.5 References 47

1.3.7-iii

NuPac TRUPACT-II SAR • Rev. 1, May 1989

TABLE OF CONTENTS

SECTION PAGE

10.0 DECAY HEAT 48


10.1.1 Decay Heat of Individual Radionuclides 48

10.1.2 Decay Heat of Individual Payload Containers 48

10.1.3 Decay Heat of the Total TRUPACT-II Payload 48

10.2 References 49

11.0 WEIGHT AND CENTER OF GRAVITY 52


11.1.1 Weighing of Individual Payload Containers 52

11.1.2 Calculation of the Total Weight of the TRUPACT-IIPayload 53

11.1.3 Determination of the Center of Gravity of the

Loaded TRUPACT-II Package 53

11.2 References 54

12.0 RADIATION DOSE RATES 55

13.0 PAYLOAD ASSEMBLY CRITERIA 56

13.1 Payload Assembly Restrictions 56

13.2 Flowcharts for Load Management 57

13.2.1 Assignment of Shipping Category 57

13.2.2 .Payload Selection 63

13.2.3 TRUPACT-II Transport Criteria 63

13.3 Procedure for Certifying Authorized Payloads for TRUPACT-II 6613.3.1 Procedure for Certifying Individual Payload 66

Containers for Transport in the TRUPACT-II

1.3.7-iv

TRUPACT-II SAR Rev. 13, April 1994 {

TABLE OF CONTENTS

SECTION PAGE

13.3.2 Procedure for Certifying Individual Payload

Containers for Transport in TRUPACT-II 71

13.3.3 Procedure for Assembly of a TRUPACT-II Payload 72

13.4 Dunnage 75

13.5 References 75

14.0 QUALITY ASSURANCE 76 {

14.1 References 79

1.3.7-v

I TRUPACT-II SAR Rev. 13, April 1994

i

ATTACHMENTS

1.0 DESCRIPTION OF REAL-TIME RADIOGRAPHY

2.0 GAS GENERATION TEST PLAN TO QUALIFY TEST CATEGORY WASTE FOR SHIPMENT

IN THE TRUPACT-II

3.0 ASSAY METHODS

1.3.7-vi

NuPac TRUPACT-II SAR Rev. 2, June 1989

LIST OF TABLES

5.1 Materials in Solidified Aqueous or Homogeneous InorganicWastes, Waste Material Type I.I 18

5.2 Materials in Solidified Aqueous or Homogeneous InorganicWastes, Waste Material Type 1.2 . 2 0

5.3 Materials in Solidified Aqueous or Homogeneous InorganicWastes, Waste Material Type 1.3 22

5.4 Materials in Solid Inorganic Wastes, Waste Material Type

II.1 and II.2 23

5.5 Materials in Solid Organic Wastes, Waste Material Type III.l 26

5.6 Materials in Solidified Organic Wastes, Waste Material Type IV • 30

10.1 Pu-239 Fissile Gram Equivalent, Decay Heat, and Specific

Activity of Many Radionuclides 5013.1 Payload Container Transportation Certification Document

(PCTCD) - Analytical Payload Shipping Category 58

13.2 Payload Container Transportation Certification Document(PCTCD) - Test Payload Shipping Category 59

13.3 Payload Assembly Transportation Certification Document (PATCD) 60

1.3.7-vii


LIST OF FIGURES

13.1 Assignment of Shipping Categories 62

13.2 Payload Selection 64

13.3 TRUPACT-II Shipping Criteria 65

14.1 TRUPACT-II Payload Compliance Program 77

1.3.7-viii

NuPac TRUPACT-II SAR Rev. 1. Mav 1989

LIST OF ACRONYMS

ANS American Nuclear Society

ANSI American National Standards Institute

AI Absorption index •

ANL-E Argonne National Laboratory-East

ASTM American Society for Testing of Materials

CFR Code of Federal Regulations

CH DOE Chicago Operations Office

7H-TRU Contact-handled transuranic

JRT Cathode ray cube

DOE Department of Energy

DOE/AL DOE Albuquerque Operations Office

DOE/HQ DOE Headquarters

DOT Department of Transportation

EEG Environmental Evaluation Group

EPA Environmental Protection Agency

FG Fuel grade

FGE Fissile gram equivalent

G G value for radiolysis

HPGe High-purity germanium

HS Heat source

ICV Inner containment vessel

ID DOE Idaho Operations Office

IDC Item Description Code

INEL Idaho National Engineering Laboratory

LANL Los Alamos National Laboratory

LLD Lower limit of detection

LLNL Lawrence Livermore National Laboratory

MI Moderator index

MIL-STD Military Standard

1.3.7-ix


LIST OF ACRONYMS (CONTINUED)

MRL Mound Research Laboratory

MS . Mass spectrometry

N'BS National Bureau of Standards

NCR Nonconformance report

NDA Nondestructive assay

NTDE Nondestructive examination

NTDT Nondestructive testing

NEUT PAN system operating program

NRC Nuclear Regulatory Commission

NTS Nevada Test Site

NV DOE Nevada Operations Office

OCV Outer containment vessel

OR DOE Oak Ridge Operations Office

ORNL Oak Ridge National Laboratories

PAN Passive/active neutron assay

PNCC Passive neutron coincidence counting (assays)

PNL Pacific Northwest Laboratory

PQC Procurement quality control

QA Quality assurance

QC Quality control

QE&C Quality Engineering and Control

R&D Research and development

RFP Rocky Flats Plant

RG Reactor Grade Plutonium

RL DOE/Richland Operations Office

RTR Real-time radiography (fluoroscopy)

SAR ' Safety Analysis Report

SF DOE San Francisco Operations Office

SNT Society for Nondestructive Testing

1.3.7-x


LIST OF ACRONYMS (CONCLUDED)

SGS Segmented gamma scan

SOP Standard Operating Procedure

SOE Statistics Quality Engineering

SR Savannah River Operations Office

SRP Savannah River Plant

SWB Standard Waste Box

SWEPP Stored Waste Examination Pilot Plant

TRAMPAC TRUPACT-II Authorized Methods for Payload Control

TRUPACT-II Transuranic Package Transporter-II

TRUCON TRUPACT-II Content Codes (document)

TRU Transuranic

VOC Volatile organic compounds

WAC Waste Acceptance Criteria

WACCC Waste Acceptance Criteria Certification Committee

WC Waste certification

WF Waste form

WG Weapons grade (plutonium)

WHC Westinghouse Hanford Company

WIPP Waste Isolation Pilot Plant

WIS Waste Information System

WPO DOE/WIPP Project Office

1.3.7-xi


1.0 SUMMARY

The TRUPACT-II Authorized Methods for Pavload Control (TRAMPAC) is the document

that provides acceptable methods required for preparation and characterization

of payloads for transport in Ir.ansuranic Package Transporter-II (TRUPACT-II).

The methods outlined in this document are binding for all sites that transport

contact-handled transuranic (CH-TRU) waste in a TRUPACT-II shipping package.

The quality assurance (QA) programs required to be followed by the sites are also

provided in this document. Each parameter required to prepare waste for

transport is addressed individually in the chapters in this text. Every payload

from each site must meet the requirements for payload control by the methods

described in this document. Where more than one method is acceptable as

indicated in this document, a U.S. Department of Energy (DOE) site needs to

implement only one. The method(s) used however must also be in accordance with

what is documented in the TRUPACT-II Content Codes (TRUCON) document (Ref.

1.1.1).

All of the parameters described below are controlled in order to ensure safe

transport of CH-TRU waste in TRUPACT-II. These parameters are grouped as

follows:

Restrictions on the physical and chemical form of the CH-TRU waste.

Restrictions on chemicals to ensure chemical compatibility between all

constituents in a given TRUPACT-II (including the parts of the package

that might be affected by the waste).

* Restrictions on the maximum pressure in the package during a sixty-day

transport period.

" Restrictions on the amount of potentially flammable gases that might

be present or generated in the payload during a sixty-day transport

period.

1.3.7-1


• Restrictions on the layers of confinement (e.g., plastic bagging) for

CH-TRU materials in payload containers.

Restrictions on the fissile material content for individual payload

containers and the total package.

Restrictions on the decay heat for individual payload containers and

the total package.

Restrictions on the weight for individual payload containers and the

loaded TRUPACT-II package.

Restrictions on the center of gravity for the payload assembly to be

transported in TRUPACT-II.

Restrictions on the dose rate for the individual payload containers,

the total package, and the three loaded packages on a trailer.

The remainder of this document describes how the U.S. DOE sites will prepare

payloads to meet these restrictions. The methods for determining or measuring

each restricted parameter, as well as the factors influencing the parameter

values (analytical methods and error bars, for example) are provided in following

sections.

A complementary document for TRAMPAC is the TRUCON document. TRUCON provides

a description of the payload parameters required for each content code (the type

of CH-TRU materials in a payload container) at the different sites. TRUCON is

a compilation of content codes from all the generator and storage sites with a

description of how the CH-TRU materials are generated and packaged. TRUCON

correlates each content code with the applicable TRUPACT-II payload shipping

category. TRUCON is referenced, as appropriate, in this document. TRAMPAC is

1.3.7-2


the document governing the methods for the preparation of CH-TRU materials for

transport in TRUPACT-II. TRDCON identifies the specific methods applicable to

each content code.

1.1 References

1.1.1 U.S. DOE, "TRUPACT-II Content Codes (TRUCON)," Rev. 8, October 1994, |DOE/WIPP 89-004.

1.3.7-3

NuPac TROPACT-II SAR Rev. 12, September 1992

2.0 INTRODUCTION

The allowable contents of a TRUPACT-II package are described in Section 1.2.3 of

the Safety Analysis Report (SAR) for TROPACT-II. This Appendix provides the

methods for ensuring that CH-TRU waste to be transported in a TRUPACT-II package

is prepared in compliance with the various restrictions limits for the parameters

identified in Section 1.2.3 of the SAR. Waste is defined in this document to

include CH-TRU materials that can be transported between sites. Each method that

shall be used for evaluating each payload parameter is described herein, as are

the controls imposed on the use of these methods. Only certified and categorized

payload containers will be overpacked in the ten-drum overpack (TDOP).

The methods described in this Appendix include all allowable alternatives for

ensuring compliance with the TRUPACT-II payload requirements. Each U.S. DOE TRU

waste generating or interim storage site selects and implements a single

allowable method, or a combination of such methods for evaluation of each

parameter, to ensure that the characteristics of its waste for each specific

shipment are acceptable. Each individual site shall document the methods used

for compliance in a site-specific set of procedures for payload control.

TRU waste from the generator sites is classified as newly generated or

retrievably stored waste, depending on the DOE criteria in effect at the time of

generation. Newly generated waste is defined as waste generated to meet the

Waste Isolation Pilot Plant (WIPP) Waste Acceptance Criteria (WAC) even though

some payload containers may be in interim storage. All waste generated prior to

WAC certification is considered to be retrievably stored waste. Retrievably

stored waste may need additional verification of parameters (e.g., nondestructive

examination or a sampling program) prior to being authorized for transport. For

parameters not governed by the WAC and required for transport, both newly

generated, as well as retrievably stored waste, will need verification of

parameters prior to transport in TRUPACT-II. Many of these requirements are in

place at the sites.

1.3.7-4


For purposes of DOE-site-applied controls, the WAC requires a site certification

official to be responsible for verifying that all waste packages prepared for

shipment to WIPP do indeed meet all those specified criteria. For purposes of

TRUPACT-II payload control, a similar position is established: transportation

certification official. The transportation certification official is responsible

for all payload assembly, payload records, and ultimate assurance that all

parameters are met before the TRUPACT-II may be released for transport. At some

sites, one person may fulfill both functions, but at others, the two positions

are distinct and separate. In this document, transportation certification

official is the person identified who approves the payload.

2.1 Waste Acceptance Criteria Certification Committee

The WIPP WAC were issued to provide limits on many aspects of the TRU waste to

guard the safety of the operations and facilities of the WIPP both now and for

the very long term time period (disposal), and are parallel to the payload

parameters for transport. The method for enforcing compliance with the WAC is

described in detail in the DOE WIPP Project Office Standard Operating Procedure

(SOP) 9.4, "Waste Acceptance Criteria Certification Committee (WACCC),"

(Ref. 2.4.1). The WACCC is assigned the responsibility for providing

verification of documents pertaining to the certification and QA of waste

handling activities, including review, comment, and resolution of concerns or

issues at all DOE sites preparing to transport TRU materials to WIPP. Authority

for this task comes from DOE Order 5820.2A, "Radioactive Waste Management," (Ref.

2.4.2) which names the Albuquerque Operations Office as the Lead Field Office

for TRU Waste Management.

The existing WACCC functions include compliance verification audits at all ten

DOE sites handling TRU waste (generation and interim storage). These

verification audits are conducted periodically at each site to evaluate specific

areas of WAC compliance with all of the criteria. Not only are documents

reviewed during these audits, but the operators are interviewed on a personal,

1.3.7-5


job-function basis relative Co meeting all of the applicable criteria. The

audit team has the authority to give or withhold waste certification

authorization at each site based on objective findings.

The WACCC will also audit each site for compliance with the TRUPACT-II payload

parameters prior to each site's first shipment and. periodically thereafter,

'.vhere specific technical ability is required (e.g. , chemical compatibility,

isotopic inventory and assay), technical experts are included in the audit team

for an in-depth audit of operations, as well as programs.

2.2 Purpose

The purposes of this document are to:

Describe the acceptable methods which shall be used to prepare and

characterize the CH-TRU materials (payload) prior to transport in a

TRUPACT-II package, and

Describe the quality controls (QC) and quality assurance (QA) programs

which shall be applied to the methods mentioned above.

Section 2.3 lists the payload parameters that shall be determined for each

payload. Section 3.0 briefly describes the relationship between payload

parameters and the classification of CH-TRU materials into TRUPACT-II payload

shipping categories. Sections 4.0 through 13.0 discuss each payload parameter

and the allowable method(s) for demonstrating compliance with the TRUPACT-II

payload requirements and the controls that are required for acceptable

implementation of these method(s). Section 14.0 discusses the QA program for

ensuring compliance with the requirements. Section 15.0 discusses the training

program and how it will be audited.

1.3.7-6


2.3 Pavload Parameters

The payload parameters addressed in this document include:

1. Physical form

2. Chemical properties

3. Chemical compatibility

4. Gas distribution and pressure buildup

5. Payload container and contents configuration

6. Isotopic inventory and fissile content

7. Decay heat

8. Weight and center of gravity

9.- Radiation dose rate

The restrictions for each of these parameters are summarized in Section 1.2.3

of the SAR.

2.4 References

2.4.1 DOE WIPP Project Office, SOP 9.4, "Waste Acceptance CriteriaCertification Committee (WACCC)," December 7, 1988.

2.4.2 DOE Order 5820.2A, "Radioactive Waste Management," September 26, 1988.

1.3.7-7

i TRUPACT-II SAR Rev. 14, October 1994

3.0 PAYLOAD SHIPPING CATEGORIES AND WASTE CLASSIFICATION

3.1 Introduction

The basis for the classification of different content codes at the sites into

payload shipping categories is defined in Section 1.2.3.2 of the SAR. The

shipping categories place restrictions on the parameters that are discussed in

subsequent sections. The correlation of the different content codes into the

shipping categories is provided for each of the content codes in the TRUCON

document (Ref. 3.2.1). The required controls on the parameters restricted by the

shipping categories are discussed under appropriate sections in this document.

3.2 References

| 3.2.1 U.S. DOE, "TRUPACT-II Content Codes (TRUCON)," Rev. 8, October 1994,DOE/WIPP 89-004.

1.3.7-8


4.0 PHYSICAL FORM

The physical form of the CH-TRU waste comprising the TRUPACT-II payload shall be

restricted to solid or solidified material. Liquid waste is prohibited in the

payload containers [drums or Standard Waste Boxes (SWBs)], except for residual

amounts in well-drained containers. The total volume of residual liquid in a

payload container shall be less than 1 volume percent of the payload container.

Sharp or heavy objects shall be blocked, braced or suitably packaged as necessary

to provide puncture protection equivalent to Type A packaging requirements.

Sealed containers are prohibited from being included as a part of the waste,

except for containers that are four liters or less in size. Containers greater

than four liters in size may be present in the waste only if there is verifiable

evidence that they are not sealed (e.g., visible absence of cap or presence of

a puncture in the container). Pressurized containers shall not be allowed in the

waste. Waste generation and storage sites' procedures define allowable methods

to ensure that the physical form requirements for the waste are complied with for

all waste to be transported in a TRUPACT-II package.

4.1 Methods of Determination and Control

The physical waste form in each payload container shall be identified.

Prohibited physical waste forms shall be excluded from payload containers. For

newly generated waste, this shall be accomplished by either visual examination

or real-time radiography (RTR) examination, or a combination of both. A second

and independent verification of the physical waste form shall be performed prior

to transport for no less than ten percent of the payload containers transported

from each site per year. To qualify retrievably stored waste for transport in

TRUPACT-II, a combination of existing records and data base information, and

verification using RTR and/or a waste sampling program, shall be used.

Acceptable methods are described in detail below. Site-specific quality

assurance (QA) programs shall ensure compliance with the physical waste form

requirement.

1.3.7-9

MuPac TRUPACT-II SAR Rev. 12, September 1992

4.1.1 Visual Examination of the Waste

The operator in a waste generating area shall visually examine and verify the

physical form of the waste prior to its placement in the payload container. The

operating procedures for each specific generating site shall specify the types

of physical waste that can be packaged together. Only solid or solidified waste

forms are acceptable for transport in TRUPACT-II. The operator shall inspect for

and remove from the waste all prohibited waste forms (e.g., free liquids greater !

than 1% volume of the payload container, sealed containers greater than four '

liters in size, and pressurized containers). j

Independent verification shall occur either visually prior to closure of the

payload container or by nondestructive examination (e.g., RTR) after the payload

container is closed.

When the verification occurs prior to closing the payload container, a second

operator (or QA inspector), other than the operator who filled the payload

container, shall inspect the waste and verify that the physical waste form is in

compliance with the transport requirements. This second operator shall document

this verification by affixing signature, initials, or stamp to the payload

container data sheet.

4.1.2 RTR Verification of the Physical Waste Form

RTR shall be utilized to nondestructively confirm the physical waste form

description and the absence of prohibited waste forms when the verification

occurs after the payload container is closed. Attachment 1.0 of this Appendix

describes typical RTR procedures. RTR examination shall confirm compliance with

the restrictions on free liquids, pressurized containers, and sealed containers.

A drum rejected due to noncompliance shall be suitably marked and segregated.

Site-specific QA and QC procedures ensure that the RTR operators are properly

trained and qualified.

1.3.7-10


4.1.3 Records and Data Base Information

Retrievably stored waste shall be qualified for transport based on information

from the data records available at the sites. Sampling programs and/or RTR

examination shall be used to confirm and supplement the information from existing

records. By using a combination of these three methods (records, RTR and

sampling programs), rhe sites shall ensure the proper evaluation of the

transportation parameters. The specific combination of methods is provided in

the TRUCON document for each content code.

4.1.4 Sampling Programs

A sampling program shall be required for qualification of retrievably stored

waste for transport in TRUPACT-II (see Appendix 1.3.9 of SAR). The sampling

program should be designed to address all the transportation parameters that need

verification. An example of an existing WAC certification program that would

qualify waste for transport (for certain payload parameters) exists at Idaho

National Engineering Laboratory (INEL).

Results from INEL sampling programs for retrievably stored waste from the initial

Transuranic (TRU) Waste Sampling Program of 181 drums (Ref. 4.2.1), and from the

FY-1986 (Ref. 4.2.2) and FY-1987 (Ref. 4.2.3) Stored Waste Examination Pilot

Plant (SWEPP) Certified Waste Sampling Programs have identified only three drums

out of a population of 228 drums (1.3Z) that were rejected under the WIPP WAC

after examination by RTR. The nonconformances were due to the presence of free

liquids. The WAC parameters that are verified in the sampling programs for WIPP

certification are: free liquids (only small residual amounts), pressurized

containers., pyrophorics, corrosives, and immobilization of particulates.

The INEL sampling program for FY-1988 has identified the need to sample 1 out

of every 97 drums (95% confidence limits) from an expected drum population of

1.3.7-11

NuPac TRUPACT-II SAR Rev. 1, Mav 1989

2900. This sampling frequency (1.03%) is based on past sampling programs, which

will increase or decrease each year depending upon the number and type of

nonconformances.

. 2 References

4.2.1 Clements, T. L.. Kudera, D. E., "TRU Waste Sampling Program: Volume I-- Waste Characterization," September 1985, EGG-WM-6503.

4.2.2 Arnold. P. >!. . "EG&G Drum Sampling Program Results FY 1986," October1986. RFP 4250.

4.2.3 Watson. L. E. . "EG&G Sampling Program Results," December 1987, RFP 4251.

1.3.7-12


5.0 CHEMICAL PROPERTIES

The chemical properties of the waste are determined by the chemical constituents

allowed in a given waste type (e.g., solidified aqueous or homogeneous inorganic

solids is Waste Type I). These constituents are restricted so that all the

payload containers are safe for handling and transport (see Section 1.2.3.3 of

che SAR).

Chemical constituents in a payload shall not be in a form that could be reactive

during -transport. Specifically, three types of chemical constituents are

prohibited from a TRUPACT-II payload.

One prohibited type is explosive material. An explosive is defined as:

Any chemical compound, mixture, or device, the primary or commonpurpose of which is to function by explosion (i.e., withsubstantial instantaneous release of gas and heat). (Ref. 5.3.1)

Examples of explosives are ammunition, dynamite, black powder, detonators,

nitroglycerine, urea nitrate, and picric acid.

A second type of prohibited material is pyrophorics. A pyrophoric is defined

as:

A flammable solid which, under transport conditions, might causefires through friction or retained heat, or, which can be ignitedreadily, and when ignited, burns vigorously and persistently soas to create a serious transportation hazard. Included in thepyrophoric definition are spontaneously combustible materials,water reactive materials, and oxidizers. (Ref. 5.3.2 and 5.3.3)

Pyrophoric. radioactive materials shall be present only in a small residual

amounts (<1 weight percent) in payload containers. Examples of pyrophoric

radionuclides are metallic plutonium and americium. Transuranic metals are

highly reactive and must be handled in a nitrogen atmosphere to prevent rapid

surface oxidation. Therefore they are oxidized to a nonreactive form prior to

placement in a payload container. The total quantity of fissile radionuclides

1.3.7-13


is also controlled by criticality safety limits. Nonradioactive pyrophorics

(e.g, organic peroxides, sodium metal, chlorates, etc.) shall be reacted (or

oxidized) and rendered nonreactive prior to placement in the payload container.

A third prohibited macerial is corrosives. Corrosives are defined as:

Aqueous materials which have a pH less than 2 or more than 12.5.(Ref. 5.3.4)

Acids and bases which are potentially corrosive shall be neutralized prior to

being a part of the waste, and rendered noncorrosive. The physical form of

the waste, and waste generating procedures at the sites ensure that the waste

is in a nonreactive form.

A fourth material that is restricted is the total amount of potentially

flammable organics which can occur in the headspace of a payload container.

Total concentration of potentially flammable organics shall be limited to 500

ppm in the headspace of a payload' container.

5.1 Shipping Cateeorv Restrictions

All the content codes from DOE sites are grouped into waste types (e.g., solid

inorganics are Waste Type II) and further divided into waste material types

based on their gas generation potential which is quantified by the effective G

value (see Appendix 3.6.7 of the SAR). In order to conform to these limits, the

chemicals and materials within a given waste material type are further

restricted. These restrictions apply to all materials that are present in the

waste in amounts greater than 1 weight percent.

Chemical constituents that can be present within each waste material type [i.e.,

the chemicals with flammable G values less than or equal to the bounding

flammable G values] are listed in Tables 4-8 in Appendix 3.6.7 of the SAR for

1.3.7-14


all waste types. At the present time, an effective G value cannot be assigned

co waste type IV. This waste type has been assigned to the test category. It

can be qualified for shipment only by testing each individual container. When

sufficient data have been accumulated on a population of payload containers, the

content code can be qualified for routine transport. The test procedures to be

followed, and the controls on the test procedures are discussed in Attachment

2.0 of this document.


The chemical composition of the waste shall be identified to ensure exclusion

of prohibited waste forms. A process flow analysis of the waste stream will

provide primary verification of conformance. Applicable procurement and

inventory controls shall supplement this analysis. Waste generation procedures

at the sites., described in the TRUCON document for each content code, prohibit

the presence of corrosives, explosives and nonradioactive pyrophorics in TRU

waste. Site-specific QA procedures validate compliance with respect to the

requirements.

5.2.1 Control of Explosive Materials

All waste generating sites administratively control the procurement,

distribution, use and disposal of explosives. Most sites have lists of

restricted materials which include explosives. Use and disposal of explosive

materials is closely controlled and monitored, as described in site-specific

administrative, operating and QA procedures.

Typically,, the TRU waste generating and storage sites do not allow explosives

in the same facility as TRU waste. Additionally, waste generating processes

shall be assessed for safety hazards such as potential explosion hazards and

potential inadvertent production of explosive materials. If potential explosive

hazards are identified, then operating and QA procedures shall be written to

control the hazard. The controls in place for individual content codes to

1.3.7-15


ensure the absence of explosive, materials in TRU waste are detailed in the

TRUCON document.

5.2.2 Control of Pvrophoric Materials

Nonradioactive pyrophoric materials are subject to the same controls as

explosives (e.g., procurement controls and safety assessments). In general,

pyrophoric materials are not permitted in TRU process areas. The quantity of

pyrophoric materials that does enter any process is strictly limited and

controlled by site safety considerations. Administrative, operational, and QA

procedures shall implement these controls. Operating procedures shall require

chat the pyrophoric material be rendered chemically safe by processing prior to

being placed into a payload container (e.g., oxidation at high temperature in

the presence of oxygen or immobilized in chemically safe materials), or the

pyrophoric material shall be segregated from the waste form and excluded from

the payload container.

The controls in place for individual content codes ensure the absence of

nonradioactive pyrophoric materials and are detailed in the TRUCON document.

5.2.3 Control of Corrosive Materials

Corrosive materials shall either be excluded from the payload container or

processed to passivate, or neutralize the corrosive material. If a corrosive

material is identified as a potential waste constituent, the process-specific

operating procedures describe the specific actions that are required for

ensuring compliance with the corrosive material prohibition. Sampling programs

(Ref. 5.3.5) for pH of inorganic sludges have shown that the sludges

consistently meet the limitation on corrosives.

The controls in place for individual content codes ensure the absence of

corrosive materials in TRU waste and are detailed in the TRUCON document.

1.3.7-16

TRUPACT-II SAR Rev. 14, October 1994 !

5.2.4 Control of Chemical Composition of the Waste

A process flow analysis shall be performed at the generator sites for all waste

streams that comprise the content codes as described in TRUCON. A process flow

analysis is an inventory of all the components of the process that generate a

particular waste stream. Controls of process technology at each location

generating a specific waste stream, in conjunction with the flow analysis,

characterize the chemical constituents of that particular waste stream. These

controls include procurement records and inventories for the chemical inputs into

each process.

The present classification of content codes into the Waste Material Types I.I,

1.2, 1.3, II.1, II.2, III.l, or IV. 1 has been made using the chemical lists

supplied by each DOE site. All materials and chemicals that have been identified

as potentially occurring in the waste at DOE sites are listed in Tables 5.1-5.6

for each waste material type. All constituents occurring in quantities greater

than 1 weight percent in each waste material type appear in the tables of allowed

materials (Tables 4-8, Appendix 3.6.7 of the SAR). The assignment of any content

code to a shipping category will also be conservative with respect to G values.

For example, if an inorganic solid waste material type (II.l or II.2) at a site

contains materials (e.g., solid organics excluding packaging) that do not comply

with the materials listed in Table 7 (Appendix 3.6.7 of the SAR), it shall be

assigned to Waste Material Type III.l (which has twice the bounding G value).

Materials and chemicals which could occur in trace quantities (<1 weight percent)

in the waste are listed by reactive group or individually in Tables 5.1—5.6.

Total quantity of the trace chemicals/materials (materials that occur in the

waste in quantities less than one weight percent) in any payload container is

restricted to less than five weight percent..

Any proposed change in process technology at a generator site for a given content

code shall be evaluated for compliance with the chemical lists of Tables 4-8

(Appendix 3.6.7 of the SAR). This change should be evaluated and approved

1.3.7-17

Nupac TRUPACT-II SAR Rev. 2, Jur.eJur.e, -11

Table 5.1

Materials in Solidified Aqueous or Homogeneous Inorganic SoliisWaste Material Type -1.1

MATERIALS AND CHEMICALS >1%

ALUMINUM CHLORIDEAQUASET/PETROSETASHCEMENT (Hydrated)ENVIROSTONEHYDROCHLORIC ACIDNITRIC ACIDOTHER NITRATE SALTSOXALATE SALTSPOTASSIUM HYDROXIDESODIUM NITRATEVERMICULITE

MATERIALS AND CHEMICALS <1%

ACIDS, MINERAL, NON-OXIDIZINGACIDS, MINERAL, OXIDIZINGACIDS, ORGANICALCOHOLS AND GLYCOLSAMINES, ALIPHATIC AND AROMATICCAUSTICSFLUORIDES, INORGANICHALOGENATED ORGANICSHYDROCARBON, ALIPHATIC, SATURATED'KETONESMETALS AND METAL COMPOUNDS, TOXICMETALS, ALKALI AND ALKALINE EARTH, ELEMENTAL AND ALLOYSMETALS, OTHER ELEMENTAL AND ALLOYS AS SHEETS, RODS, MOLDINGS, DROPS,NITRO COMPOUNDSWATER AMD MIXTURES CONTAINING WATERCELLULOSEEMULSiriERSFIREBRICKGLASS, LABWAREGRITHYDROGEN PEROXIDEINSULATIONMOLDS AND CRUCIBLES, CERAMICMOLDS AND CRUCIBLES, GRAPHITE

1.3.7-18

Nupac TRUPACT-II SAR Rev. 2, Jur.e, 1553

Table 5.1(Continued)

Materials in Solidified Aqueous or Homogeneous Inorganic SolidsWaste Material Type I.1

MATERIALS AND CHEMICALS <1%(CONTINUED)

OILPOLYETHYLENE (Packaging Material)POLYPROPYLENE (Ful-Flo Filters)POLYVINYL CHLORIDE (Packaging Material)RESINSRUBBER GLOVES, LEADEDSALT (Calcium Fluoride and Calcium Chloride)SANDSLAGSODIUM SILICATESOOTSURFACTANTSSYNTHETIC RUBBERWOOD

1.3.7-19 _

KupacTRUPACT-EISAR * " ' Z' J u n e I 9 3 9

Table 5 .2

Materials in. S o l i d i f i e d Aqueous or Homogeneous Ir.organic Sol ids*«*sce Macerial "me 1.2

MATERIALS AND CHEMICALS > U

ASHCALCIUM CARBONATECALCIUM CHLORIDECALCIUM SILICATE (V«ctr glass • Ma silicact)CARBONCEMENT (Hydraced}CLAY (BENTONITE)DIATOMITErEHRIC HYDROXIDEFLORCOIRON HYDROXIDELOU CARBON STEELPERLITEPOLYETHYLENE (Packaging Maccrial)POLYVINYL CHLORIDE (Packaging Material)PORTLAND CEMENT (Hydraced)SANDSLUDGE (Fixed in macrix)SODIUM CHLORIDESOILTHORIUMVERMICULITE

MATERIALS AND CHEMICALS <12

ACIDS. MINERAL. HON-OXIDIZINGACIDS. MINERAL. OXIDIZINGACIDS. ORGANICALCOHOLS AND GLYCOLSCAUSTICSFLUORIDES. INORGANICHALOGENATZD ORCANICSHYDROCARBON. ALIPHATIC. SATURATEDHYDROCARBONS. AROMATICKETONESMETALS AND METAL COMPOUNDS, TOXICMETALS. ALKALI AND ALKALINE EARTH. ELEMENTAL AND ALLOYSMETALS. OTHER ELEMENTAL AND ALLOYS AS SHEETS. RODS. MOLDINGS. DROPS. ETC.METALS, OTHER ELEMENTAL AND ALLOYS IN THE FORM OF POWDERS. VAPORS. OR SPONGESORGANOPHOSFHATES. PHOSPHOTHIOATES AND PHOSPHODITHIOATES

1.3.7-20

Nupac TRUPACT-II SAR • ?-ev. 2. June L9S9


Materials in Solidified Aqueous or Homogeneous Inorganic Solids-*asce Material Type 1.2

MATERIALS AND CHEMICALS <IX(CONTINUED)

VATER AND MIXTURES CONTAINING WATERALUMINUM HYDROXIDEAMMONIUM NITRATECARBON. SPENT. ACTIVATEDCELLULOSEFLOCCULATING AGENT (POLYSLECTROLYTE)GREASEGRITHYDROGEN PEROXIDEOILOIL-0R1PAPERPHOSPHOROUSPOLYBUTADIENEPOLYPROPYLENEPOLYSTYRENERESINSRUBBER GLOVESSALTSODIUM NITRATESPENT DETERGENTSSURFACTANTS'-OOD

1.3.7-21

Nuoac TRUPACT-II SAR Rev. Z, j u n e 1989

Table 5 . 3

Materials in Solidified Aqueous or Homogeneous Inorganic Solies'-'asce Material Type 1.3

.MATERIALS AND CHEMICALS >LX

CLAY (BENTONITE)CONCRETE (C«m«nc«d Sludges)FIREBRICKGRITLOU CARBON STEELPOLYETHYLENE (Packaging Material)POLYVINYL CHLORIDE (Packaging Material)PORTLAND CEMENT (Hydraced)SANDSLAG -SODIUM CHLORIDESOOT

MATERIALS AND CHEMICALS <1X

ALCOHOLS AND GLYCOLSFLUORIDES. INORGANICHALOGENATED ORGANICSHYDROCARBONS. AROMATICMETALS AND METAL COMPOUNDS. TOXICMETALS. OTHER ELEMENTAL AND ALLOYS AS SHEETS. RODS. MOLDINGS. DROPS. ETC.WATER AND MIXTURES CONTAINING WATERALUMINUM NITRATE NANOKYDRATESODIUM NITSATE

1.3.7-22

Nupac TRUPACT-tl ;AR Rev. 2. June 1989

Table 5 .4 |

Materials in S o l i d InorganicsVasce Waceriai Types I I . 1 and II -2

MATERIALS AND CHEMICALS >LS

ALUMINUM3ARIUM SULFATS5E3.YLLIUMCADMIUMCALCIUM CHLORIDECALCIUM FLUORIDECALCIUM OXIDECARSON. SPENT. ACTIVATEDCSLITSCESIUM CHLORIDECLAY i'3ENTONITZ^OGNCRETECOPPERCRUCIBLES. CERAMIC {Silicact-based)FIREBRICKGLASS. LABVAREGLASS. RASCHIG RINGS 'GRAPHITEINSULATIONIRONIRON TIN (ALLOY)LEADLOV CARBON STEELMAGNESIUM CHLORIDEMETAL CANS (for sale)MOLDS AND CRUCIBLES. CERAMICMOLDS AND CRUCIBLES, GRAPHITEOIL-DRIPLATINUMPOLYETHYLENE (Packaging Mactrial)POLYVINYL CHLORIDE (Packaging Hactrial)POTASSIUM CHLORIDESALT (Fus«d chloride)SANDSODA ASHSODIUM CHLORIDESOILSTAINLESS STEELTANTALUMTUNGSTEN7ERMICULITEZINC MAGNESIUM (ALLOY)

1.3.7-23

TRUPACT-II SAR Rev. 2. June 1939

Table 5.4.(Continued)

Materials in Solid InorganicsUasce Material Types II.1 ano II.2

MATERIALS AND CHEMICALS

ACIDS. MINERAL. .'.'ON-OXIDIZINGACIDS, MINERAL. OXIDIZINGACIDS. ORGANICALCOHOLS AND GLYCOLSAZO COMPOUNDS. OIAZO COMPOUNDS. AND HYDRAZINESCAUSTICSETHERSFLUORIDES. INORGANICHALOCENATED ORGANICSHYDROCARBON. ALIPHATIC. SATURATEDHYDROCARBONS. AROMATICKETONESMETALS AND METAL COMPOUNDS. TOXICMETALS, ALKALI AND ALKALINE EARTH. ELEMENTAL AND ALLOYSMETALS. OTHER ELEMENTAL AND ALLOYS AS SHEETS. RODS. MOLDINGS. DROPS. ETC.METALS. OTHER ELEMENTAL AND ALLOYS IN THE FORK OF POWDERS. VAPORS. OR SPONGESORGANOPHOSPHATES. PHOSPHOTHIOATES AND PHOSPHODITHIOATESPEROXIDES AND HYDROPEROXIDES. ORGANICPOLYMERIZABLE COMPOUNDSWATER AND MIXTURES CONTAINING WATERACRYLIC PAINTALUMINA/SILICA BLANKETALUMINUM CHLORIDE |ALUMINUM NITRATEALUMINUM NITRATE NANOHYDRATEAMMONIUM PERCHLORATE IASHBAKELITEBENELEXBH-38, COMPLETING AGENTBORATED WATER (Cryscallized)BROMINEEDTAFERROUS SULFAMATEFLUORINERTFOAMING INSURANCE. COMPLETING AGENTGREASE-GRITHYDROGEN PEROXIDEHYDROXYL AMINE NITRATEHYDROXYIAMINEMAGNAFLUX. COMPLEXING AGENT

1.3.7-24

Nupac TF.UPACT-II SAB. Rev. 2. June L3S9

Table 5 .4(Concir.ued)

Macerials in Solid InorganicsUasce Material Types Il.l'and II.2

MATERIALS AJiD CHEMICALS <IS(CONTISUED)

NAPHTHAOILPAPERPLEXICLASPOLYPROPYLENEPOLYSTYRENEPOLYURETHANEPORTLAND CEMENT (Hydracaa)POTASSIUM PERMANGANATE?VC SOLVENT CEMENTRESINSRUBBER GLOVESSLAGSODIUM BOROHYDRIDESODIUM NITRATESODIUM NITRITESOOTSYNTHETIC RUBBERVAXESWOOD

1.3.7-25

Nupac TRUPACT-II SAR Rev. 2, June, 1989

. . Table 5.5

Materials in Solid Organicswaste Material Type III.l


ALARAALUMINUMASBESTOSASHASPHALTBAKELITEBARIUM SULFATEBENELEXCADMIUMCARBON STEELCARBON, SPENT, ACTIVATEDCELITECELLULOSECLAY (BENTONITE)CONCRETECOPPERDIATOMACEOUS EARTHDIATOMITEEMULSIFIERS (Sodium Lauryl Sulfate)ENVIROSTONEFIBERGLASSFIREBRICKFLORCOGLASS, LABWAREGLASS, RASCHIG RINGSGRAPHITEGREASEGRITHEPA FILTERSINSULATIONION EXCHANGE RESIN (Dowex)IRONIRON HYDROXIDELEADLEADED GLASSLEXANLOW CARBON STEELMOLDS AND CRUCIBLES, CERAMICMOLDS AND CRUCIBLES, GRAPHITEOILOIL-DRIOILS (C6 TO C20)

1.3.7-26



Materials in Solid OrganicsWaste Material Type III.l

MATERIALS AND CHEMICALS >1%(CONTINUED)

OTHER FILTERSPAPERPLATINUM-PLENUM PREFILTERS (FIBERGLASS)PLEXIGLASPOLYETHYLENEPOLYMETHYL METHACRYLATEPOLYPROPYLENEPOLYSTYRENEPOLYURETHANEPOLYVINYL CHLORIDEPORTLAND CEMENT (Hydrated)RAGS/CLOTH

RESINS (Anion and Cation)RUBBER GLOVESRUBBER GLOVES, LEADEDSANDSLAGSLUDGESODA ASHSODIUM CHLORIDESODIUM NITRATESOILSOOTSTAINLESS STEELSTEELSURFACTANTS (Nonphosphated Anionic Detergent)SYNTHETIC RUBBERTANTALUM1 TEFLONTRIBUTYL PHOSPHATETUNGSTENVERMICULITBWAXESWOOD


ACIDS, MINERAL, NON-OXIDIZING

1.3.7-27

Nupac TROTACT-II SAR Rev. 2 , June, 198 9


Materials in Solid Organics• ' Waste Material Type III.l


ACIDS, MINERAL, OXIDIZINGACIDS, ORGANICALCOHOLS AND GLYCOLSALDEHYDESAMIDESAMINES,. ALIPHATIC AND AROMATICAZO COMPOUNDS, DIAZO COMPOUNDS, AND HYDRAZINES

CAUSTICSESTERSETHERSFLUORIDES, INORGANICHALOGENATED ORGANICSHYDROCARBON, ALIPHATIC, SATURATEDHYDROCARBONS, AROMATICISOCYANATESKETONESMETALS AND METAL COMPOUNDS, TOXICMETALS, ALKALI AND ALKALINE EARTH, ELEMENTAL AND ALLOYSMETALS, OTHER ELEMENTAL AND ALLOYS AS SHEETS, RODS, MOLDINGS, DROPS, ETC.METALS, OTHER ELEMENTAL AND ALLOYS IN THE FORM OF POWDERS, VAPORS, OR SPONGESNITRIDESNITRO COMPOUNDSORGANOPHOSPHATES, PHOSPHOTHIOATES AND PHOSPHODITHIOATESPEROXIDES AND HYDROPEROXIDES, ORGANICPOLYMERIZABLE COMPOUNDSWATER AND MIXTURES CONTAINING WATERACRYLIC PAINTALUMINA/SILICA BLANKETALUMINUM CHLORIDEALUMINUM HYDROXIDE IALUMINUM NITRATEALUMINUM NITRATE NANOHYDRATE iAMMONIUM PERCHLORATE IBATTERIES (Lead-acid, dry)BH-38, COMPLEXING AGENTBORATED WATER (Crystallized)BROMINECALCIUM CHLORIDE |CEMENTCORKCOTTONDEODERIZED MINERAL SPIRITS

1.3.7-28



Materials in Solid OrganicsWaste Material Type III.l


EDTAFERROUS SULFAMATEFLOCCULATING AGENT {POLYELECTROLYTE)FLUORINERTFOAMING INSURANCE, COMPLEXING AGENTFUL-FLO FILTERS'(POLYPROPYLENE)HYDROGEN PEROXIDEHYDROXYL AMINE NITRATELEATHERMAGNAFLUX, COMPLEXING AGENTN-PARAFFIN HYDROCARBONS (NPH)NAPHTHANITRATESOTHER NITRATE SALTSOXALATE SALTSPHENOLIC RESINSPOLYBUTADIENEPOTASSIUM PERMANGANATEPVC SOLVENT CEMENTSALT (Calcium Fluoride and Calcium Chloride)SODIUM BOROHYDRIDESODIUM NITRITESPENT DETERGENTSTURCO 4320, COMPLEXING AGENTVACUUM GREASE

1.3.7-29

TROPACT-II SAR Rev. 14, October 1994

Table 5.6

Materials in Solidified OrganicsWaste Material Type IV.1* •


LIQUIDS IN WASTE ARE IMMOBILIZED OR FIXED IN WASTE MATRIX AND/OR ADDITIVES.

1.1.1-TRICHLOROETHANE1.1.2-TRICHLORO-l.2.2-TRIFLUOROETHANEAQUEOUS SOLUTIONS AND MIXTURES (Fixed in matrix)CALCIUM SILICATECARBON TETRACHLORIDECHLOROFORMCONCRETECONWED PADSENVIROSTONE (CaSO4)MAGNESIA CEMENT (Hydrated)METHYLENE CHLORIDEN-PARAFFIN HYDROCARBONS (NPH)NON-IONIC DETERGENTOIL (Absorbed)OIL-DRIORGANIC ACIDSPOLYETHYLENE (Packaging Material)POLYETHYLENE GLYCOLPOLYVINYL CHLORIDE (Packaging Material)PORTLAND CEMENT (Hydrated)POTASSIUM SULFATESLUDGETRIBUTYL PHOSPHATETRICHLOROETHYLENETRIMETHYLBENZENETRIOCTYL PHOSPHINE OXIDEXYLENE


ACIDS, ORGANICALCOHOLS AND GLYCOLSHALOGENATED ORGANICSHYDROCARBONS, AROMATICKETONESMETALS AND METAL COMPOUNDS, TOXICORGANOPHOSPHATES, PHOSPHOTHIOATES AND PHOSPHODITHIOATESWATER AND MIXTURES CONTAINING WATER1.10-PHENANTHROLINEALPHA-HYDROXYQUINOLINECHELATING AGENTSEDTASODIUM ACETATESODIUM CITRATEVERMICULITE

* Can be shipped only as a test category.

1.3.7-30


by the WACCC for compliance with existing waste material type restrictions. All

changes in the chemical characteristics of the waste shall be recorded, and the

date of the new process, description of the process, and list of new chemicals

submitted to the WACCC. The WACCC can allow transport of the content code under

the old payload shipping category if none of the restrictions are violated as

a result of the change. If the WACCC decides that the old shipping category is

no longer valid, the NRC shall be notified of the change. Once the change is

approved by NRC, the TRUCON is revised and an amendment to the C of C issued.

5.2.5 Control of Flammable Volatile Organic Compounds in Payload Containers

Total concentration of potentially flammable volatile organic compounds shall

be limited to 500 ppm in the headspace of a payload container.

Controls described in this section for generation processes ensure compliance

with the chemical lists. These lists shall be the basis for evaluating the

presence of flammable VOCs in a particular content code. Content codes which do

not identify any of the flammable VOCs in the chemical lists do not have to

implement additional controls to meet this requirement.

For content codes that identify flammable VOCs as part of the waste, the

following options exist to comply with the above transportation requirement:

Specify, from waste generation procedures, what the maximum amount

of flammable VOCs in the waste can be if all the potentially

• flammable VOCs vaporized into the headspace of the drum. If this

is less than 500 ppm, the content code meets the above limit. A

nargin of safety is provided in this assessment, because all of

the potentially flammable VOCs in the waste would not vaporize in

a drum because of the immobilization in cemented wastes or

adsorption of these compounds on waste materials. Verification for

this should be from process records and random sampling.

1.3.7-31


• . • If an upper limit cannot be established on the amount of flammable

VOCs in a content code or if the limit exceeds 500 ppm, a sampling

program needs to be implemented to verify compliance with the

requirements.

For retrievably stored waste, headspace sampling for potentially

flammable VOCs shall be an added parameter for waste sampling

programs. Newly generated waste sites shall meet compliance for

content codes by establishment of sampling program for waste streams

and/or payload containers, by content codes, at the 95% confidence

limits.

In summary, the limit on flammable VOCs will be met either by means of

process controls, or by suitable sampling programs.

5.2.6 Sampling and Chemical Analysis of Stored Waste

Documented administrative controls and records of process technology, in addition

to supporting data from a sampling program, shall be used to characterize stored

waste. A more detailed description of the sampling program can be found in

Section 4.1.4 of this Appendix and in Appendix 1.3.9 of the SAR.

5.3 References

5.3.1 49 CFR 173.50, "An Explosive"

5.3.2 49 CFR 173.150, "Flammable Solid; definition"

5.3.3 49 CFR 173.151, "Oxidizer; definition"

5.3.4 40 CFR 261.22(a)(1), "Characteristics of Corrosivity"

5.3.5 U.S. DOE, "TRUPACT-II Content Codes (TRUCON)," Rev. 8, October 1994,DOE/WIPP 89-004.

1.3.7-32


6.0 CHEMICAL COMPATIBILITY

Chemical compatibility of the waste within itself and with the packaging shall

ensure that chemical processes would not occur that might pose a threat to safe

transport of the payload in the TRUPACT-II package. The chemical compatibility

shall be ensured for the following four conditions:

Chemical compatibility of the waste form within each individual

payload container.

Chemical compatibility between contents of payload containers during

hypothetical accident conditions.

Chemical compatibility of the waste forms with the TRUPACT-II Inner

Containment Vessel (ICV).

Chemical compatibility of the waste forms with the TRUPACT-II 0-ring

seals.

The basis for evaluating chemical compatibility shall be the Environmental

Protection Agency (EPA) document "A Method for Determining the Compatibility of

Hazardous Wastes" (EPA-600/2-80-076; Ref. 6.1.1). This method provides a

systematic means of analyzing the chemical compatibility for specific

combinations'of chemical compounds and materials. Any incompatibilities between

the payload and the package shall be evaluated separately if not covered by the

EPA method (Ref. 6.1.1). As described in Appendix 2.10.12 of the SAR, the EPA

method classifies individual chemical compounds into chemical groups and

identifies the potential adverse reactions resulting from incompatible

combination's of the groups.

Any component present within a waste material type is evaluated for chemical

compatibility (Tables 5.1 to 5.6). Only compatible waste content codes are

considered for transport and included in the TRUCON document (Ref. 6.1.2). The

restrictions imposed on the chemical constituents of the content codes ensure

1.3.7-33


compliance with the compatibility requirement. As noted earlier in Section 5.0,

the sites shall not transport waste generated by a new process or an existing

process that has changed without prior WACCC approval. If the WACCC decides that

the old payload shipping category is no longer valid, the NRC shall be notified

of the change. Once the change is approved by NRC, the TRUCON is revised and an

amendment to the C of C issued.

6.1 References

6.1.1 Hatayama, H. K., Chen, J. J., de Vera, E. R., Stephens, R. D.,Storm, D. L., 1980, "A Method for Determining the Compatibility ofHazardous Wastes," EPA-600/2-80-076, EPA, Cincinnati, Ohio, 181 pp.

! 6.1.2 U.S. DOE, "TRUPACT-II Content Codes (TRUCON)," Rev. 8, October 1994,DOE/WIPP 89-004.

1.3.7-34


7.0 GAS DISTRIBUTION AND PRESSURE BUILDUP

Gas concentrations and pressures during transport of CH-TRU wastes in a

TRUPACT-II payload shall be restricted to the following limits:

" The gases generated in the payload shall be controlled to prevent the

occurrence of potentially flammable concentrations of gases within the

payload confinement layers and the void volume of the ICV cavity.

• The gases generated in the payload and released into the ICV cavity

shall be controlled to maintain the pressure within the TRUPACT-II ICV

cavity below the acceptable design pressure of 50 psig.

Gas concentrations and pressure shall be controlled by:

• Restricting the materials that shall be present within each payload

shipping category.

' Limiting the number of internal layers of confinement within each

payload container.

• Limiting the decay heat within each payload container.

Chemical properties are discussed in Section 5.0. The payload container type

and configuration of the contents is discussed in Section 8.0. Decay heat is

discussed in Section 10.0.

1.3.7-35


,8.0 PAYLOAD CONTAINER AND CONTENTS CONFIGURATION

The type of payload container and the layers of confinement of the contents in

each individual payload container shall be controlled as follows:

• The payload container shall be either a drum or TRUPACT-II Standard

Waste Box (SWB) or a Ten-Drum Overpack (TDOP). |

Filtered vent(s) shall be installed in all payload containers. Filters

shall also be installed in bins and drums overpacked in SWBs, and drums |

and SWBs overpacked in a TDOP. Filter vents for drums must meet the j

minimum specifications in Section 2.0 of Appendix 1.3.5 of the SAR. j

All filters installed in an SWB must meet the specifications in Section

3.0 of Appendix 1.3.5 of the SAR. All filters installed in bins

overpacked in SWBs must meet the specifications in Section 4.0 of

Appendix 1.3.5 of the SAR. All filters installed in TDOPs must meet j

the specifications of Section 5.0 of Appendix 1.3.5 of the SAR. \

A rigid drum liner, if present, shall be punctured or have a filtered

vent.

The number of layers of confinement for the waste shall be known.

Bags shall be closed with a twist and tape or fold and tape closure.

8.1 Specifications for Waste Packaging Parameters

8.1.1 Specifications for Pavload Containers

The payload containers shall be either 55-gallon drums or SWBs or TDOPs. The

acceptable specifications for each container and contents that shall be allowed

in a TRUPACT-II payload are provided in Appendices 1.3.3 and 1.3.4 of the SAR.

In addition to meeting the SAR specifications at the time of procurement, the

integrity of the payload containers shall be inspected prior to transport. Drums

which appear by visual inspection to be corroding, shall be overpacked in

1.3.7-36


an SWB if wall thickness is less than what. is allowable per container

specification. Site-specific handling and operating procedures shall ensure

proper implementation of these requirements.

8.1.2 Specification for Filter Vents

Each payload container to be transported in TRUPACT-II shall have one or more

filter vents. Appendix 1.3.5 of the SAR specifies the flow and hydrogen

diffusion requirements for those filters. The minimum number of filter vents

shall be one for a drum, two for an SWB, two for a bin overpacked in an SWB, and

nine for a TDOP. All filters installed in an SWB must meet the specifications

in Section 3.0 of Appendix 1.3.5 of the SAR. All filters installed in a bin

shall meet the specifications in Section 4.0 of Appendix 1.3.5 of the SAR. All

filters installed in a TDOP must meet the specifications in Section 5.0 of

Appendix 1.3.5 of the SAR.

8.1.3 Venting and Aspiration Requirements

Sites adding filters to unvented payload containers of waste shall aspirate the

payload containers for a sufficient period of time to ensure that there is

equilibration of any potentially flammable gases that may have accumulated in the

closed containers prior to transport. The procedure to be followed for

aspiration and determination of aspiration time are presented in Appendix 3.6.11.

Three options are provided in this appendix, any one of which can be implemented

by the storage sites:

• Option 1 - Aspiration Time Based on Date of Drum Closure. This option

determines aspiration time based on the closure date of the payload

container and the content code. This method does not require headspace

gases to be sampled.

Option 2 - Headspace Gas Sampling at the Time of Venting. This option

' determines aspiration time based on the measured concentration of

hydrogen in the headspace of the drum (between the drum lid and the

rigid liner) at the time of venting.

1.3.7-37


• Option 3 - Headspace Gas Sampling During Aspiration. This option

utilizes the measured headspace concentration of hydrogen two or more

weeks after venting to determine aspiration time.

8.1 ..4 Requirement for Rigid Liners

The rigid liner, if present, in a payload container shall be punctured

(>0.3 inch diameter hole) or filtered before the container is transported in

TRUPACT-II (see Appendix 1.3.3 of SAR).

8.1.5 Specification for Inner Layers of Confinement Around Waste

The inner layers of confinement around the waste materials in the payload

containers shall be plastic bags and/or metal cans that meet the specifications

outlined in Appendix 1.3.6 of the SAR. A twist and tape closure or a fold and

tape closure shall be the only allowable method of closure for a bag. For waste

within a given content code, the maximum number of layers of bags is specified

in the TRUCON document (Ref. 8.3.1).


The payload container and content configuration requirements are met as a part

of the waste generation processes at the sites. The methods of control for each

content code are described in the TRUCON document.

The allowable methods for controlling and verifying the payload container and

waste packaging requirements shall consist of:

" Procurement controls

" Visual inspection

• RTR

* Records and database information

* Sampling programs

1.3.7-38

NuPacTRUPACT-II SAR Rev. 1, May 1989

8.2.1 Methods of Determination and Control for Pavload Containers

Procurement controls shall ensure compliance with specifications for purchase

of payload containers. Site-specific QA requirements shall be used to ensure

implementation of these requirements. Site QA personnel review and approve

procurement specifications and purchase orders for the payload containers. The

procurement specifications describe the design, manufacturing, and QA

requirements. Site quality control inspectors shall perform receipt inspection

of the payload containers upon delivery from the manufacturer or supplier.

Nonconforming payload containers shall be identified, segregated, and

dispositioned in accordance with the site waste certification and QA plans.

The operator that initiates the filling of an empty payload container shall

inspect the payload container prior to filling it with waste. This inspection

includes the physical condition of the payload container for signs of physical

damage such as bulges, dents or deterioration. The operating procedures for

each waste packaging area should specify the acceptable type and configuration

of payload container and any documentation requirements.

Visual inspections shall be used for retrievably stored waste to ensure

compliance with the requirements prior to transport. Nonconforming drums shall

be either repackaged or overpacked in an SWB.

8.2.2 Methods of Determination and Control for Filter Vents

Procurement controls shall ensure compliance with the specifications for each

filter vent. Written procedures at the sites shall require conformance with the

specifications from the manufacturer. Site-specific QA procedures shall ensure

compliance with these requirements. Visual inspection shall be used to ensure

compliance for the number and type of filters on each payload container.

1.3.7-39

I TRUPACT-II SAR ' Rev. 14, October 1994

. 8.2.3 Methods of Determination and Control for Rigid Liner

The requirements on the rigid liner shall be met by procurement controls and the

site QA procedures. Puncturing or filtering of the lid of a liner for newly

generated waste shall be controlled administratively (i.e., buying only punctured

liners), or by visual examination of liner prior to closure. For retrievably

stored waste, RTR, sampling programs, or existing records shall be used to verify

that the liner meets the requirement.

8.2.4 Method of Determination and Control for Inner Confinement Layers

The individual filling a newly generated payload container shall verify that the

method of closure for each bag is by the twist and tape or fold and tape methods.

The waste generation procedures shall specify the maximum number of plastic bag

layers for each content code. For retrievably stored waste, the maximum number

of bags is known from the waste management techniques in use at the time the

waste was packaged. This is confirmed as part of the sampling program.

8.3 References

j 8.3.1 U.S. DOE, "TRUPACT-II Content Codes (TRUCON)," Rev. 8, October 1994,DOE/WIPP 89-004.

1.3.7-40


' -9.0 ISOTOPIC INVENTORY AND FISSILE CONTENT

The isotopic inventory for each payload container shall provide both the isotopic

composition of the radioactive material and the total quantity plus error of all

radioactive material, both fissile and nonfissile TRU radionuclides and nonTRU

radionuclides. The plutonium-239 fissile gram equivalents (FGE), and identity

and quantity of individual radionuclides or mixtures is recorded in the database

for individual payload containers and summarized in the data sheet of the total

TRUPACT-II payload.

There are two limits for TRUPACT-II payload compliance which require a knowledge

of the specific isotopic composition and radionuclide quantity. They are:

Pu-239 fissile gram equivalent quantity

Decay heat

Decay heat is discussed in Section 10.0 of this document.

The three primary activities that generate TRU waste at DOE sites are:

Production of plutonium for weapons and heat source applications,

including associated research and development activities

Production of special isotopes for research purposes

Examination of special reactor fuels

A detailed knowledge of the radioisotopic composition and quantity is an

operational prerequisite for ensuring product material quality for each of these

activities.

1.3.7-41


9.1 Isotopic Composition

The isotopic composition of the waste is determined from measurements taken on

the product material during the processing at each site. The processing

organizations transmit the isotopic composition information to the site waste

certification organization. Therefore, the isotopic composition of the waste

need not be determined by direct analysis or measurement of the waste unless

process information is not available.

Process areas (at each site) usually only handle product materials of specific

isotopic composition [e.g., weapons -grade (WG) Pu or heat-source (HS) Pu] .

Therefore, the isotopic composition in the waste from specific process areas

remains constant since product isotopic composition is closely controlled to

meet production isotopic specification requirements.

Certain process areas may handle product materials of varying isotopic

composition (e.g., varying ratios of Am-241, Cm-244, and Cf-252). In these

cases, the isotopic composition in the waste is determined by direct measurement,

analysis of the waste or from existing records.

9.2 Methods of Determination and Control of Isotopic Composition

There are two allowable methods for determining isotopic composition. Depending

on the mixture of radionuclides present in the waste, one or both of the methods

may be required. Plutonium isotope composition is determined by mass

spectrometry. Isotopic composition for gamma-emitting radionuclides (Ref. 9.5.1)

is determined by gamma ray pulse height analysis.

9.2.1 Product and Process Analysis by Mass Spectrometrv

The product specifications for TRU materials produced or utilized at DOE

plutonium production facilities (e.g., Savannah River Plant and Hanford) are

closely controlled. Frequent checks and measurements are conducted during

1.3.7-42


production operations for both product quality verification and special nuclear

materials accountability purposes. The site processing organizations are

responsible for transmitting the isotopic composition information to the site

waste operations/certification organization. The three major product material

isotopic compositions are:

1. Weapons - grade (WG) plutonium (primarily Pu-239)

2. Fuel-grade (FG) plutonium (primarily Pu-239)

3. Heat-source (HS) plutonium (primarily Pu-238)

Other product material mixtures are occasionally produced by special request,

and the isotopic compositions of these special mixtures shall be thoroughly

characterized by the production facility.

Mass spectrometry (MS) is a primary method for determining the radioisotopic

composition in product material. The plutonium isotope analyses shall be

performed in accordance with American Society for Testing of Materials (ASTM)

methods (Ref. 9.5.2, 9.5.3, 9.5.4, 9.5.5). These ASTM methods describe the

instrument setup, preparation of calibration standards, and calibration and

operating procedures. DOE conducts a bimonthly analytical sample exchange

program among the plutonium production facilities to crosscheck analysis results

on WG plutonium. Sampling and analyses of feedstock and product materials are

required at various stages in the processes.

Research and development facilities provide support to the plutonium production

facilities and utilize a production facility's product specification data

(determined by MS) when assigning the radioisotopic composition to their waste.

Plutonium is also recovered from scrap material to produce product material.

The recovery operation removes the nonplutonium radionuclides (e.g., Am-241)

from the scrap material. The removed radionuclides are concentrated in the

recovery operation's waste streams, and additional analyses (e.g., gamma ray

pulse height analysis) are performed on the waste streams, to determine their

isotopic composition. The plutonium isotopes in the scrap, product material,

and waste have long half-lives, and the isotopic composition remains unchanged

1.3.7-43


for some tens of years after initial production. Even Pu-241 (half-life - 13.2

years) does not decay rapidly enough to require reassessment of the original

plutonium isotopic composition. Therefore, TRU wastes generated from scrap

recovery operations are assigned the same plutonium isotopic composition as the

product material. The Am-241 content in the waste is determined by gamma ray

pulse height analysis.

9.2.2 Gamma Ray Pulse Height Analysis

Facilities which produce or utilize special (non-plutonium) transuranic

radionuclides have more variability in the isotopic distribution in the waste.

There is less reliance on production records and specifications for determining

isotopic distribution. These facilities use gamma ray pulse height analysis or

MS techniques to determine the isotopic composition of individual payload

containers. Gamma scanning methods are described in detail in Attachment 3.0.

Facilities which examine special reactor fuels have the most detailed and

traceable data regarding the isotopic composition of the waste. The quantity

of waste generated from these activities is very small and highly characterized.

The initial isotopic composition of the fuel, neutron flux, irradiation time,

and cooldown time are measured and documented. The isotopic composition of the

irradiated fuel is calculated based on the data mentioned above, or the isotopic

composition of the irradiated fuel is confirmed by radiochemical analysis. The

isotopic composition of the waste shall be determined by either referencing the

irradiated fuel analysis or by direct measurement of the waste by segmented

gamma scan (SGS) . These assay methods are described in detail in Attachment 3.0.

9.3 Quantity of Radionuclides

The quantity of the radionuclides in each payload container shall be estimated

by either a direct measurement of the individual payload container, summation

of assay results from individual packages in a payload container, or by a direct

measurement on a representative sample of a waste stream (such as solidified

inorganics). An assay refers to one of several radiation measurement techniques

1.3.7-44


that determine the quantity of nuclear material in TRU wastes. Assay instruments

.detect and quantify the primary radiation (alpha, gamma, and/or neutron)

emanating from specific radionuclides, or a secondary radiation emitted from

neutron interrogation techniques. The measured quantity of radiation is then

used to calculate the quantity of other radionuclides and the total quantity of

Pu-239 fissile equivalent grams. That calculation requires knowledge of the

isotopic composition of the waste. Combinations of gamma spectroscopy and

neutron measurements are often needed to calculate the quantity of nonfissile

radionuclides.

9.4 Methods of Determination and Control of Radionuclide Quantity

The five allowed assay methods for identifying and quantifying radionuclides in

TRU waste are:

Passive Gamma (HPGe, Ge, Ge(Li), Nal: transmission-corrected and

noncorrected)

Radiochemical assay (alpha and gamma spectroscopy)

Passive neutron coincidence counting (PNCC)

Passive-active neutron assay (PAN)

Calorimetry

These assay methods are described in Attachment 3.0. Typical errors and

sensitivities of each method, calibration standards, operator training, and

assay procedures are discussed.

General assay requirements that apply to all sites are as follows:

Each site shall select and use the assay method(s) of its choice,

provided the method(s) are identified in this document as allowable

methods and the prescribed controls are implemented.

1.3.7-45

NuPac TRUPACT-II SAR Rev. 2, June" 1989

The site's waste content code descriptions list the specific assay

method(s) and their application^).

Site-specific operating and QA procedures describe the assay method(s)

and the controls imposed on the assay operations. The controls include

performing calibration and background measurements. The calibration

and background measurements must fall within the stated acceptable

ranges before assays are performed.

QA plans and procedures shall include oversight of assay methods and

controls.

Each site shall provide a specialized training program for assay

operators.

9.4.1 Pu-239 Fissile Gram Equivalent of Individual Radionuclides

Pu-239, U-233, and U-235 are considered as equivalent fissile materials. Pu-239

fissile gram equivalent (FGE) for other fissile or fissionable isotopes,

including special actinide elements, is obtained using American National

Standards Institute/American Nuclear Society (ANSI/ANS)-8.15-1981 (Ref. 9.5.6).

Chapter 10 lists the Pu-239 FGE for many isotopes.

9.4.2 Pu-239 Fissile Grflj) Eiyjvalent °^ Individual Pavload Containers

The Pu-239 FGE is calculated from the isotopic inventory data and the Pu-239 FGE

for each radionuclide. A container shall be acceptable for transport only if

the Pu-239 FGE" plus two times the error is below 200 grams for a drum, or 325

grams for a standard waste box (Section 1.2.3 of the SAR).

1.3.7-46


9.4.3 Pu-239 Fissile Gram Equivalent of the Total TRUPACT-II Pavload

Prior to loading the TRUPACT-II, a proposed group of payload containers (e.g.,

14 drums or two standard waste boxes) is selected. The Pu-239 FGE for each

payload container is summed to compute the total measured Pu-239 FGE for the

proposed TRUPACT-II payload. The total Pu-239 FGE error is the square root of

Che sum of the squares of the individual Pu-239 FGE errors. The total shipment

Pu-239 FGE (measured value plus total error) is compared to the TRUPACT-II limit

for Pu-239 FGE (325 grams). If the total proposed payload Pu-239 FGE is less

than 325 grams, then the payload meets the payload compliance limit for Pu-239

FGE. If not,'a different combination of payload containers is selected for Pu-

239 FGE calculations. This process of load management continues until a group

of payload containers is identified that meets the TRUPACT-II Pu-239 FGE limits.

This calculation can either be done by hand or by computer. The calculations

and container selection process shall be reviewed by the site transportation

certification official prior to loading.

9.5 References

9.5.1 ASTM C 1030-84, "Determination of Plutonium Isotopic Composition byGamma-Ray Spectrometry."

9.5.2 ASTM C 696-80, "Methods for Chemical, Mass Spectrometric, andSpectrochemical Analysis of Nuclear-Grade Uranium Dioxide Powders andPellets."

9.5.3 ASTM C 697-86, "Methods for Chemical, Mass Spectrometric, andSpectrochemical Analysis of Nuclear Grade Plutonium Dioxide Powders andPellets."

9.5.4 ASTM C 759-79, "Methods for Chemical Mass Spectrometric, andSpectrochemical, Nuclear, and Radiochemical Analysis of Nuclear-GradePlutonium Nitrate Solutions."

9.5.5 ASTM C 853-82. "Standard Test Methods for Nondestructive Assay ofSpecial Nuclear Materials Contained in Scrap and Waste."

9.5.6 ANSI/ANS-8.15-1981. "Nuclear Criticality Control of Special ActinideElements."

1.3.7-47


10.0 DECAY HEAT

There are two limits for decay heat: 1) the total decay heat from the

radioactive decay of the radioisotopes within an individual payload container

and 2) the total decay heat from all payload containers in a TRUPACT-II. Decay

heat shall be determined by calculations using the isotopic inventory

information for fissile and nonfissile TRU radionuclides and for any nonTRU

radionuclides present in the payload container.


10.1.1 Decay Heat of Individual Radionuclides

The decay heat of each radionuclide shall be calculated. Specific heats for

many radionuclides are shown in Table 10.1 (Ref. 10.2.1 and 10.2.2).

10.1.2 Decay Heat of Individual Pavload Containers

The decay heat of individual payload containers shall be calculated by combining

the isotopic inventory data, that are obtained as described in Section 9.0, and

the calculated decay heat for each radionuclide. The calculated value of the

decay heat for an individual payload container and the decay heat error shall

be recorded in the data package for an individual payload container. A

container in a given payload shipping category is transported in TRUPACT-II only

if the measured decay heat plus error is below the limits for that shipping

category, as given in Section 1.2.3.3 of the SAR.

10.1.3 Decay Heat of the Total TRUPACT-II Pavload

The decay heat for each payload container is summed to compute the total

calculated decay heat for a TRUPACT-II payload. The total decay heat error is

calculated as the square root of the sum of the squares of the individual decay

1.3.7-48

NuPac-TRUPACT-II SAR Rev. 1, May 1989

heat error values. The total shipment decay heat value (calculated value plus

total error) shall be compared to the TRUPACT-II limit for decay heat. If the

total decay heat in a payload is less than the limit for the specific payload

shipping category (Section 1.2.3.3.8 of SAR), then the payload meets the payload

compliance limit for decay heat. This calculation may either be performed by

hand or by computer. The calculations shall be reviewed by the site

transportation certification official prior to transport in a TRUPACT-II package.

10.2 References

10.2.1 Annals of the International Commission on Radiological Protection-38,Volumes 11-13, "Radionuclide Transformations: Energy and Intensity ofEmmissions", Pergamon Press, Oxford (1.983.)

10.2.2 Walker, F. William, Kiravac, Dr. George J., and Rourke, Francis M. , Chartof the Nuclides. 13th Edition, Knolls Atomic Power Laboratories,Schenectady, NY (1983).

1.3.7-49


Table 10.1Pu-239 FISSILE GRAM EQUIVALENT, DECAY HEAT,AND SPECIFIC ACTIVITY OF MANY RADIONUCLIDES

MUCLIDE

HCHaPMnFeCoCoNiCuAsKrRbSrSrYZrZrRuRuAgCdSbIIICsCsBaCeCePraSmEuEuEuTmTaPbPoRaRaRa

31422325455576063647385868990888895

103106110m109125125129131134137133141144147151152154155168182210210223226228

ATOMICNUMBER

16

1115252627272829333637383839404044444748515353535555565858616263636369738284888888

Pu-239FGE

0.00E+000.00E+000.00E+000.00E+000.00E+000.00E+OO0.00E+000.00E+000.00E+000.00E+000.00E+000.00E+000.00E+000.00E+O00.00E+000.00E+000.00E+000.00E+000.00E+000.00E+000.00E+000.00E+000.00E+000.00E+000.00E+000.00E+000.00E+000.00E+000.00E+000.00E+000.00E+000.00E+000.00E+000.00E+000.00E+000.00E+000.00E+000.00E+000.00E+000.00E+000.00E+000.00E+000.00E+00

1.3.7-50

DECAY HEAT

(V/p)

3.28E-011.32E-038.94E+011.19E+033.88E+018.49E-027.29E+001.76E+016.05E-037.21E+031.02E+015.94E-013.71E+021.01E+021.60E-012.24E+024.46E+011.10E+021.05E+022.00E-017.99E+011.68E+003.27E+006.38E+009.34E-084.23E+021.33E+O19.74E-026.82E-014.19E+012.14E+003.44E-013.10E-031.35E+002.39E+003.42E-018.39E+015.60E+011.96E-021.45E+021.83E+O32.88E-022.76E-02

SPECIFICACTIVITY(Ci/e)

9.76E4O34.51E-+O36.32E-KB2.89E+O57.82E+O32.44E+O38.55E4O31.14E+O3

•5.98E+O13.89E4O62.25E4O43.97E4O28.22E4O42.94E4O41.38E-*O21.41E+041.80E4O42.17E4O43.26E4O43.38E+O34.80E4O32.61E+O31.04E-+031.76E+O41.79E-041.25E4O51.31E-JO38.80E4O1

- 2.53E-IO22.88E+O43.22E-tO39.38E4O22.66E4O11.78E4O22.67E4O24.70E4O28.44E4O36.31E4O37.72E4O14.54EHO35.18E4O41.00E+002.76E-H)2


NUCLIDE

Table 10.1Pu-239 FISSILE GRAM EQUIVALENT, DECAY HEAT,AND SPECIFIC ACTIVITY OF MANY RADIONUCLIDES

(CONTINUED)

ATOMICNUMBER

Pu-239FGE

DECAY HEATSPECIFICACTIVITY

AcThThThPaUUUUUUUNpPuPuPuPuPuPuPuAmAmAmCmCmCmCmCmCmCmCmBkBkCfCfCfCfEsEs

227228230232231232233234235236237238237236238239240241242244241242m243242243244245246247248250247249249250251252252254

899090909192929292929292939494949494949495959596969696969696969797989898989999

0.00E+000.00E+000.00E+000.00E+00 •0.00E+000.00E+001.00E+000.00E+001.00E+000.00E+000.00E+000.00E+001.50E-020.00E+001.13E-011.00E+002.25E-022.25E+007.50E-030.00E+001.87E-023.46E+011.29E-020.00E+005.00E+009.00E-021.50E+010.00E+005.00E-010.OOE+000.00E+000.00E+000.OOE+004.50E+010.OOE+009.00E+010.OOE+000.OOE+000.OOE+00

3.68E-022.71E+015.75E-042.68E-091.46E-036.93E-012.84E-041.82E-046.04E-081.78E-061.64E+028.62E-092.09E-051.87E+015.73E-011.95E-037.16E-033.31E-031.17E-045.22E-071.16E-014.32E-036.49E-031.23E+021.90E+002.86E+005.77E-031.02E-022.98E-065.53E-041.59E-013.69E-023.24E-011.54E-014.12E+005.89E-024.06E+014.37E+017.35E+01

7.32E+018.29E+022.04E-021.11E-074.78E-022.16E+019.76E-036.32E-032.19E-066.54E-058.25E+043.40E-077.13E-045.37E+02

. 1.73E+016.29E-022.30E-011.04E+023.97E-031.79E-053.47E+009.83E+002.02E-013.35E+O35.22E+018.18E+O1

- 1.74E-013.11E-019.38E-054.30E-032.10E-011.06E+001.66E+034.14E+001.11E+021.60E+005.44E+021.11E+031.88E+O3

Reference 10.2.1 and 10.2.2

1.3.7-51


11.0 WEIGHT AND CENTER OF GRAVITY

The weight of each individual payload container, payload assembly, and loaded

TRUPACT-II shall be less than the weight restrictions as outlined in Section

1.2.3.3 of the SAR. The weight limits are:

1,000 pounds per drum .(1450 pounds per drum overpacked in an SWB)

4,000 pounds per SWB

7,265 pounds per payload assembly of 14 drums including pallet, guide

tubes, slip sheets and reinforcing plates j

7,265 pounds per payload assembly of two SWBs or one TDOP j

19,250 pounds per loaded TRUPACT-II |

The total weight of the top seven drums or SWB of the payload assembly shall be j

less than or equal to the total weight of the bottom seven drums or SWB. The j

total weight of the top five drums in a TDOP shall be less than or equal to the |

total weight of the bottom five drums. !

The weight of each payload container shall be measured and recorded in the

database for individual containers, along with an estimate of the error in the

weight. The weight and the error of the total TRUPACT-II payload shall be

calculated and reported in the TRUPACT-II payload data sheet (see Section 13.0).

The site transportation certification official shall review the payload data

sheets and approve the weight of each individual container and the total payload.


11.1.1 Weighing of Individual Pavload Containers

Each individual payload container shall be weighed on a calibrated scale after

it is filled and closed. The weight of an individual payload container shall be

less than 1,000 pounds per drum, less than 4,000 pounds per SWB, and less j

1.3.7-52

NuPac TRDPACT-II SAR Rev. 12, September 1992

than 7,265 pounds per TDOP as stated in Section 1.2.3.3.9 of the SAR. The weight

of the payload container shall include the addition of the error from the

measurement. A pay load container that does not comply with the weight limit must

be segregated for repackaging or other corrective action. Site-specific

procedures shall ensure that a container weighing more than the weight limit is

prohibited from the payload.

Trained personnel shall calibrate and maintain the scale and document those

actions in accordance with formal operating and QA procedures. Calibration must

be in accordance with National Bureau of Standards (NBS) Handbook 44,

Ref. 11.2.1. Individuals shall perform the weighing operation in accordance with

operating procedures and document the results. The error should be calculated

as part of the calibration procedure.

11.1.2 Calculation of the Total Weight of the TRDPACT-II Pavload

The total weight of a TRUPACT-II payload shall be less than 7265 pounds for an

entire payload assembly. For fourteen drums, the payload assembly shall consist

of the fourteen actual payload containers, payload pallet, and optional

slipsheets, reinforcing plates, guide tubes and banding material. The payload

assembly for SWBs shall consist of two SWBs and optional nylon strap assemblies

attached to the two SWBs. For a TDOP, the payload assembly shall consist of one j

TDOP. !

The total payload weight shall include the error in all measurements, or if

weighed as an assembly shall include the error in the measurement. The site

transportation certification official shall review and approve the total weight

of the payload assembly. All TRUPACT-II trailer loads must also meet all DOT

weight restrictions.

11.1.3 Determination of the Center of Gravity of the Loaded TRUPACT-II Package

The center of gravity (e.g.) of a loaded TRUPACT-II shall be determined by

knowing "the weights and locations of the individual payload containers. For

fourteen-drum payload assemblies, the weight of the seven bottom drums shall be

1.3.7-53 !


added together and shown to be greater than or equal to the weight of the seven

drums on top.

For the two SWB pay load, the weight of the top SWB shall be shown to be no

greater than the weight of lower SWB.

11.2 References

11.2.1 NBS Handbook 44 1988, "Specifications, Tolerances, and-Other TechnicalRequirements for Weighing and Measuring Devices," U.S. Department ofCommerce, National Bureau of Standards.

i

1.3.7-54

NuPac.TRUPACT-II SAR Rev. 1, May 1989

12.0 RADIATION DOSE RATES

The external radiation dose rates of individual payload containers and the three

loaded TRUPACT-II payloads to be shipped on a trailer, shall meet 200 mrem/hr

at the surface and 10 mrem/hr at two meters as specified in Section 5.0 of the

SAR. Radiation dose rates for TRUPACT-II must comply with 10 CFR 71.47.

Occasionally, drums of TRU waste that meet the radiation level (surface dose

rate) requirements require ALARA/dose reduction shielding to meet DOE site

requirements. The radiation level at the surface of and two meters from the

unshielded payload container is measured to ensure compliance with the 200

mrem/hr and 10 mrem/hr, respectively. If the measured radiation levels are

below the specified levels, but do not meet the site criteria, shielding may be

added to the drum. DRUMS THAT EXCEED THE 200 mrem/hr SURFACE READING OR 10

mrem/hr AT TWO METERS WITHOUT SHIELDING SHALL NOT BE TRANSPORTED.

1.3.7-55

! TRUPACT-II SAR ' Rev. 14, October 1994

13.0 PAYLOAO ASSEMBLY CRITERIA

This chapter presents an overview and the control procedures that shall be used by

the sites in order to assemble a pay load approved for transport in TRUPACT-II. The

parameters described in previous chapters must be evaluated according to the

constraints in Section 1.2.3 of the SAR for selection of a payload. Flowcharts

showing the steps for load management of payloads are also presented in this

chapter. U.S. DOE sites shall implement these flowchart requirements by the

methods that have been outlined in this document.

13.1 Pavload Assembly Restrictions

Only content codes described in the TRUCON document (Ref. 13.5.1) shall be

transported in TRUPACT-II. The assignment of each of these content codes to a

payload' shipping category is provided in the TRUCON document. The logic for this

classification is presented in Section 1.2.3.2 of the SAR. Together, these

documents (TRUCON, TRAMPAC, and relevant sections of the SAR) present the

foundation, justification and the verification of this classification. The

correlation chart of content codes and shipping categories is shown in Table 5 of

the TRUCON document. The shipping categories impose restrictions and requirements

on the manner in which a payload can be assembled. These are listed below:

• After all the payload parameters have been quantified and verified, the

shipping category shall be clearly marked on the pavload container, to

provide a visual verification that the container is authorized for

shipment.

• All containers forming a pavload within each TRUPACT-II shall belong to

the same shipping category. This precludes the mixing of different Waste

J Material Types I.I, 1.2, 1.3, II.1, II.2, III.l and IV.1, different

payload containers (drums and SWBs), and different internal packaging

configurations (number of bag layers). This requirement, also applies

1.3.7-56


for up to four drums overpacked in an SWB, or up to ten drums overpacked in a |

TDOP, each of which shall belong to the same shipping category. The shipping j

category shall be marked on the SWB and the TDOP, if used. The site |

transportation certification official shall verify that there is no mixing of

shipping categories within a payload.

• Payload containers qualified for transport in the analytical and test

categories cannot be mixed in a TRUPACT-II package.

Transportation parameters of individual payload containers are recorded

in the database or records. An example of this data is shown in

Table 13-1 for the .analytical case and in Table 13-2 for the test

category. A payload container shall be certified for transport only if

all the transportation parameters are in compliance. It shall be the

responsibility of the site transportation certification official to

verify this compliance before authorizing containers for transport. A

step-by-step instruction for completing Tables 13-1 and 13-2 is given

in Section 13.3.1 and 13.3.2.

• The transportation parameters of every TRUPACT-II shipment shall be

recorded in the database. An example of this data sheet is shown in

Table 13-3. A TRUPACT-II shipment shall be authorized only if all the

transportation parameters are in compliance. It shall be the

responsibility of the site transportation certification official to

verify this compliance before authorizing the TRUPACT-II for transport.

A step-by-step instruction for completing Table 13-3 is given in

Section 13.3.3.

13.2 Flowcharts for Load Management

13.2.1 Assignment of Shipping Category

The methodology by which a shipping category is assigned to a content code is

shown in Figure 13-1. Procedural and administrative controls at a waste

1.3.7-57

.NuPac TRUPACT-II SAR Rev. 12, September 1992

TABLE 13-1

PAYLOAD CONTAINER TRANSPORTATION CERTIFICATION DOCUMENT (PCTCD)(ANALYTICAL PAYLOAD SHIPPING CATEGORY)

Container I.D. #: Payload Shipping Category:

Decay Heat Limit forContent Code: __ • Category:

Container Type: WAC Certified:

Drum Liner Punctured/Filtered:

SWB Certification Site:

Filter(s) Model: Correct Filter Installed:

TDOP Filter(s) Model:

Correct Filter(s) installed:

RETRIEVABLY STORED WASTE ONLY:

• Aspiration Method: Option 1 Option 2 Option 3

Period of Time Container Closed Prior to Venting (Option 1 Only)

Hydrogen Concentration in Headspace: (Option 2 or Option 3)

Period of Aspiration: Table:

Payload Container has Vented the Indicated Period of Time

Container Weight + Error

Container Decay Heat + Error

Container Fissile Mass + Two Times the Error

Approved for Shipment

I certify that the above container meets the requirements for shipment in

TRUPACT-II.

TRANSPORTATION CERTIFICATION OFFICIAL

DATE

1.3.7-58


TABLE 13-2

PAYLOAD CONTAINER TRANSPORTATION CERTIFICATION DOCUMENT (PCTCD)(TEST PAYLOAD SHIPPING CATEGORY)

Container I.D. #:

Content Code:

Container Type:

Drum

Bin

Filter(s) Model:

TDOP:

Payload Shipping Category:

Decay Heat Limit for

Category:

WAC Certified:

Liner Punctured/Filtered:

Certification Site:Correct Filter Installed:

Filter(s) Model:

Correct Filter(s) Installed

TEST CRITERIA:

Limit for TotalGas Generation:

Limit for HydrogenGas Generation:

Limit for Flammable VolatileOrganics Concentration:

Measured GasGeneration Rate:

Measured HydrogenGeneration Rate:

Concentration ofFlammable VOCs Present:

Container Weight

Container Decay Heat

Container Fissile Mass

Approved for Shipment

+ Error

+ Error

+ Two Times the Error

I certify that the above container meets the requirements for shipment inTRUPACT-II.


DATE

1.3.7-59

NuPac TRUPACT-II SAR ' Rev. 12, September 1992

TABLE 13-3

PAYLOAP ASSEMBLY TRANSPORTATION CERTIFICATION DOCUMENT (PATCD)

TRUPACT OCA BODY NO.: SHIPMENT NO.:

TRUPACT OCA LID NO.:

PAYLOAD SHIPPING CATEGORY:

DECAY HEAT LIMIT FOR SHIPPING CATEGORY:

PAYLOAD CONTAINER CONFIGURATION: (DRUM, SWB OR OVERPACK [SWB, TDOP]) |

PAYLOAD COMPOSITION

BOTTOM 7 DRUMS, SWB, OR TDOP |

PAYLOAD CONTAINERI.D. NO.*** WEIGHT ERROR FISSILE GRAMS ERROR** DECAY HEAT ERROR

Sub-Total

*Error on total weight can be determined by weighing the entire pay load assembly.

**Two times the error from individual payload containers.

***For seven-drum configuration, use the first seven rows; for ten-drum overpackconfiguration, also use the last three rows.

1.3.7-60


TABLE 13.3 (Continued)-

TOP 7 DRUMS OR SWB

PAYLOAD CONTAINERI.D. NO. WEIGHT ERROR FISSILE GRAMS ERROR** DECAY HEAT ERROR

Subtotal

TOTAL FISSILE QUANTITY (WITH ERROR) OF ALL CONTAINERS:

TOTAL DECAY HEAT (WITH ERROR) OF ALL CONTAINERS:

BOTTOM SEVEN DRUMS OR SWB WEIGHT (WITH ERROR)> TOP SEVEN DRUMS OR SWB WEIGHT (WITH ERROR): _

TOTAL WEIGHT (WITH ERROR) OF PAYLOAD AND PACKAGE:

MAXIMUM DOSE RATE ON THE OUTSIDE OF PACKAGE: AT 2 METERS

DATE OF ICV CLOSURE

APPROVED FOR SHIPMENT

I certify that all of the above containers meet the requirements for shipmentin TRUPACT-II.


DATE

*Error on total weight can be determined by weighing the entire payloadassembly.**Two times the error from individual payload containers.

1.3.7-61


PROCEDURAL CONTROLS

• EAG5IHG CONFIGURATION• TWIST & TAPE CLOSURE• FUNCTL'KED/FILTERED LINER• FILTERED CONTAINER• CHEMICAL COMPOSITION• PHYSICAL / CHEMICAL FORM

ADKZNZSTRATZVZ CONTROLS

NO N0N-RA3I0NUCLIDE FYRCPHOrilCSNO COMPRESSED GASESNO CORROSIVES/EXPLOSIVESNO LIQ3IDS > 1%

CONTEST CCDZ

CLASSIFICATION

to

-

PHYSICAL /CHEMICAL

FORM

VISUAL INSPECTIONt

PAYLOADCONTAINER

BAGGING

CONFIGURATION.

\r

VERIFICATION OFPARAMETERSPRIOR TCSHIPMENT

DETERMINEWASTETYPE

DETERMINEPAYLCADCONTAINER

DETERMINE

SnIPPINGCATEGORY •

SOLZDZFZSDZHORGAKZCS

( 1 . 2 )

55-GALLONDRUM

2 BAGS

(Z.2A2)

Figure 13.1 Assignment of Shipping Categories

1.3.7-62


generator site shall specify for each content code, the' transportation

parameters that have been described in previous chapters. Knowing the content

code of the waste determines its physical and chemical form, and compliance with

the transportation requirements. A visual inspection shall determine the type

of payload container, and the bagging configuration follows from the content

code description. These parameters shall lead to the assignment of a shipping

category to the content code. An example of this correlation between a content

code and a shipping category is shown in Figure 13-1. The TRUCON document is

a comprehensive description of this flowchart for all content codes that are

allowed to be transported from all the DOE sites.

13 .2.2 Pavload Selection

The flowchart of transport requirements for a payload container is shown in

Figure 13-2. The container I.D. shall uniquely identify the payload container.

The content code shall identify a shipping category per TRUCON which is

confirmed if all the limits on the parameters are met. Wherever applicable,

the parameters (weight, fissile material, and the decay heat) shall be checked

against the limits after addition of the appropriate error. If any of the

limits are not met by the container, it shall be rejected from transport,

marked, and segregated. If all requirements are satisfied except for the decay

heat- limit, the container shall be assigned to a test category, and can be

qualified for transport only by the procedure outlined in Attachment 2.0. If

all transport requirements are satisfied, the shipping category shall be

confirmed and labeled on the container.

13.2.3 TRUPACT-II Transport Criteria

The logic for selecting a TRUPACT-II payload is presented in Figure 13.3.

Payload selection shall be made from only those payload containers that have

been approved for shipment. Individual containers shall be selected from the

1.3.7-63

SuPac TRUPACT-II SAR Rev. 1, May 1989

11

Z3TAIM c

CCT"A-\'-= —=-

* >

TR1CriOF!

fr

WEIGHT ,2RUM < 1000 LBSSWB < 4000 LBS

NOREJECT

^YES

FISSILE MATERIALDRUM < 200 GRAMSSWB < 325 GRAMS

NOREJECT

f~YES

DECAY HEAT

(BY SKIPPING CATEGORY)

rNO

ASSIGN TOTEST CATEGORY

\NSPORTATICNVTIFICATIONriCIAL

VES

-

CCRRELAT:

•

PROS?SHIPPING

<

FINAL SI

CATEGOJ

SCTIVECATEGORY

r

IIPPING

Vi

r

AUTHORIZED FOR

TRANSPORT

Figure 13.2 Payload Selection

1.3.7-64


TRANSPORTIONCERTIFICATIONOFFICIAL

11I

— ELECT !•; CRUMS C= 2 S'WBS

yjTKCRIZiO) Cr SAME CATEGCRY

rMEET TCTAL WEIGHT ANDCENTER OF GRAVITYREQUIREMENTS

NO

YES

r

MEET TCTAL FISSILEQUANTITY REQUIREMENTS

\

i.'O

YES

t

LOAD IN TRUPACT-II

1

YES

r

MEET 3OSE RATSREQUIREMENTS

NO—*J

YES

r

TRUPACT-II SHIPMENTAVAILABLE

r

AUTHORIZED FOR TRANSPORT

Figure 13.3 TRUPACT-II Shipping Criteria

1.3.7-65


same shipping category such that the weight and fissile quantity limits on the

total TRUPACT-II payload are met. The containers shall be loaded into the

TRUPACT-II with the heavier seven-pack or SWB placed in the bottom to satisfy

the center of gravity criteria. If the dose rate requirements are met on the

loaded TRUPACT-II, it shall be authorized for shipment by the site

transportation certification official.

13.3 Procedure for Certifying Authorized Pavloads for TRUPACT-II

All authorized payloads must meet the requirements set forth in Section 1.2.3

of the SAR. Data on the parameters for specific payloads is obtained by the

methods outlined in this document in accordance with the specific limits of the

TRUCON document. The following procedures give step by step methods for

evaluating the data against the limits set forth in Section 1.2.3 of the SAR.

13.3.1 Procedure for Certifying Individual Pavload Containers for Transport inthe TRUPACT-II (analytical case)

U.S. DOE waste generating and storage sites shall qualify an individual payload

container for transport in TRUPACT-II by verifying that each container meets the

parameter requirements/limits listed in Table 13.1, Payload Container

Transportation Certification Document (PCTCD) Analytical Case.

The attached form (Table 13.1) may be reformatted for site use. All*parameters

noted on the form must be included in modified versions.

Listed below is an outline of the procedure to follow for qualification of a

payload container for transport (Table 13.1). References in parenthesis are to

chapters in this document (TRAMPAC). The procedure to follow is:

Container I.D.: The identification number is unique to each container

of waste and provides a means for tracking process data records and

1.3.7-66


package history. The container identification number is assigned to the

container prior to placement of waste in a container. The I.D. number

appears on a label affixed to the drum and can be read for visual

verification or for electronic retrieval (i.e., bar codes). Information

necessary for transporting payload containers is entered into the data

package under this I.D. number.

Container Type: This information may be obtained by visual inspection.

The container must be one of the approved types listed in Section 1.2.3,

Table 1.2.3.2-4 of the SAR (Section 8.0).

Container Weight: The loaded weight of each payload container is

obtained from its data package (Section 11.0).

Container Weight + Error: An error (Section 11.0) shall be assigned to

the container weight in accordance to the methods listed in Chapter 8.0

and entered into the data package. This resulting value shall be

compared to those limits listed in the Section 1.2.3.3 of the SAR to

ensure compliance.

Certification Site: This is the location at which transportation

certification takes place. For newly generated waste this will be the

generating site. For retrievably stored waste it may be either the

generating or storage site.

Content Code: This information may be obtained one of two ways: First

method is to acquire the content code from the data package, where the

content code has been preassigned, or

If the content code is not available in the data package but the Item

Description Code (IDC) is listed on the container, the transportation

certification official shall use the correlation tables listed in the

TRUCON document (Ref. 13.5.1) to determine the content code.

1.3.7-67


• If an IDC is not listed in the Correlation Tables of the TRUCON, the

payload container is not eligible for shipment. The generator who

assigns the IDC is responsible for ensuring that the parameters listed

in the TRUCON for that IDC are met (i.e., maximum number of bags, method

of closure, waste form verification, chemical compatibility, etc). The

site transportation certification official shall verify that the proper

IDC is assigned to the content code using the correlation tables in the

TRUCON document.

• Shipping Cateeorv: The site transportation certification official shall

ensure that the proper shipping category is assigned to the payload

container. This assignment is made in the TRUCON document. Each

content code lists the shipping category under which it shall be

shipped. The transportation certification official must verify this

assignment using the corresponding tables in TRUCON. If the content

code is not listed in the TRUCON document it is not eligible for

shipment.

Payload for all containers should not contain greater than 500 ppm total

flammable organics in the headspace of each payload container.

• Decay Heat Limit: When the shipping category is determined, the

allowable decay heat for that category shall be recorded from

Tables 1.2.3.3-1 to 1.2.3.3-3 of Section 1.2.3.3 of the SAR.

• Decay Heat: The decay heat of each payload container shall be

calculated by combining the isotopic inventory data and the calculated

decay heat for each radionuclide present in the waste (Section 10.0).

This information shall be obtained by the site transportation

certification official from the data package.

1.3.7-68

NuPacTRUPACT-II SAR Rev. 1, May 1989

Decay Heat + Error: The decay heat + error shall be obtained

(Section 10.0). by the transportation certification official from the

data package. The transportation certification official shall compare

this total with the limits for the payload container's shipping category

in Section 1.2.3 of the SAR.

Fissile Mass: The Pu-239 fissile gram equivalent (FGE) is calculated

(Section 9.0) by combining the isotopic inventory data and the Pu-239

FGE for each radionuclide present in the waste. This information shall

be obtained by the site transportation certification official from the

container I.D.'s data package.

Fissile Mass + Two Times the Error: An error shall be assigned to the-

fissile mass in accordance with the methods listed in Section 9.0. This

information shall be obtained from the data - package by the site

transportation certification official. The transportation certification

official shall ensure that the fissile mass + two times the error is

less than the transport limits set in Section 1.2.3 of the SAR.

WIPP WAC Certified: This information shall be obtained from the data

package corresponding to the payload container I.D. WIPP WAC

certification, as it applies to this document (TRAMPAC), specifies that

the following criteria have been met:

Free liquids are limited to residual amounts. (Section 4.0)

Non-radioactive pyrophorics are prohibited. (Section 5.0)

Explosives are prohibited. (Section 5.0)

Corrosives are prohibited. (Section 5.0)

Pressurized containers are prohibited. (Section 4.0)

1.3.7-69

NuPac TRUPACT-II SAR Rev. 2, June'1989

Carbon Composite Filter Model Installed: This information is obtained

by visual inspection (Section 8.0). The site transportation

certification official shall ensure that the specifications for carbon

composite filters listed in Appendix 1.3.5 of the SAR are met. The

• filter model number should be checked with the specification in Appendix

1.3.5. of the SAR and recorded on the data sheet. All filters installed

in a SWB must meet the specifications in Section 3.0 of Appendix 1.3.5

of the SAR. All filters installed in bins overpacked in SWBs shall meet

the specifications in Section 4.0 of Appendix 1.3.5 of the SAR. The

second blank under carbon composite filter should be answered with a

"yes" or "no" reply.

Punctured/Filtered Liner: This information shall be obtained from the

data package for the container I.D. (Section 8.0).

Aspiration Time Determination: This part of the table ensures

conformation with the requirements on aspiration time for containers

that have been closed (unvented) for a period of time (Appendix 3.6.11).

The five questions under this section that shall be answered (Section

8.0) are:

The method for determination of the aspiration period needed to

qualify the payload container for transport shall be indicated.

The period of time that a payload container has been unvented in

storage shall be recorded here (Option 1 only).

The concentration of hydrogen measured in the headspace shall be

noted here (Options 2 and 3).

The aspiration time for the option chosen should be noted and the

appropriate table that the value was derived from in the SAR. If

the hydrogen concentration indicates that aspiration is not needed,

a zero should be entered.

1.3.7-70


Indicated here that the payload container has vented the prescribed

amount of time. The answer is "yes", if the task has been

accomplished.

Approved for Transport; The site transportation certification official

shall ensure that all of the requirements for the above transportation

parameters are met as stated in Section 1.2.3 of the SAR. If the

requirements are not met the payload container is rejected (nonconformance

disposition) and not qualified for shipment.'

Transportation Certification Official; The site transportation

certification official shall sign and date this document upon completion.

13.3.2 Procedure for Certifying Individual Pavload Containers for Transport inTRUPACT-II (Test Category)

Payload Containers which have been assigned to the test category must meet

additional criteria. These are listed in Table 13-2.

An outline of the procedure to qualify payload containers which have been assigned

to the test categories follows:

Complete items described in Table 13.1 as defined above.

Date of Test Completion; This should be the date the test is terminated

as outlined in Attachment 2.0 of Appendix 1.3.7.

Test Criteria; The following data are obtained from the test procedure

of each payload container.

Limit for Total Gas Generation; This limit is defined for each shipping

category in Table 3.4. 4.3-5 of the SAR. This limit is arrived at by

1.3.7-71


setting a maximum pressure limit of 50 psig in the TRUPACT-II ICV

cavity.

• Limit for Hydrogen Gas Generation: This limit is defined for each

shipping category in Table 3.4.4.4-2. This limit is arrived at by

limiting the maximum hydrogen concentration to <5X in all parts of the

payload and the package.

• Limit for Potentially Flammable Volatile Organics Concentration: This

limit is set at 500 ppm in the headspace (total flammable organics) for

all payload containers.

13 .3.3 Procedure for Assembly of a TRUPACT-II Payload

Certified payload containers shall be assembled per the instructions given

below. Only two SWBs or 14 drums of a single shipping category can be assembled

into a specific payload. The total TRUPACT-II package limits as given in Section

1.2.3 of the SAR are complied with by evaluating the data from the individual

Payload Container Transportation Certification Documents (PCTCD). The data from

individual payload containers is combined in accordance with the Payload

Assembly Transportation Certification Document (PATCD) per the following

instructions. The attached form (Table 13.2) may be reformatted for site use.

All parameters noted on the form must be included in any site-modified version.

References are to chapters within this document (TRAMPAC).

The procedures for assembling a payload within a TRUPACT-II are as follows:

' TRUPACT-II OCA Body No.: The identification number on the TRUPACT-II

OCA Body shall be recorded.

• Shipment No. : The site transportation certification official shall

record the shipment number of the trailer of TRUPACT-IIs.

1.3.7-72


- TRUPACT-II OCA LID NO. : The identification number on the TRUPACT-II OCA

shall be recorded.

• Pavload Shipping Category (Section 13.1): The site transportation

certification official shall record the shipping category of the payload

to be shipped. All of the payload containers within a TRUPACT-II must

be of the same shipping category and analytically qualified containers

cannot be shipped with containers qualified by test. The transportation

certification official shall ensure this through visual inspection of

the affixed shipping category labels on each payload container or the

respective Payload Container Transportation Certification Documents

(PCTCD).

* Decay Heat Limit for Shipping Category: When the payload shipping

category is assigned, the allowable decay heat limits shall also be

recorded in Section 1.2.3 of the SAR.

' Payload Container Configuration: The site transportation certification

official shall identify and record the type of payload containers being

assembled in the TRUPACT-II (Section 8.0).

" Payload Composition: The site transportation official shall record the

following parameters for the PACTD from individual PCTCDs:

Payload Container I.D. Number

Weight and error

Fissile Gram Equivalent and two times the error

Decay Heat and error

The weights, fissile gram equivalent and decay heats of individual containers

are summed, and the total error for each parameter shall be calculated by

1.3.7-73


utilizing Che. square root of the stun of the squares of the individual errors J

(indicated in Tables 13-1 and 13-2). The error on the total veight can also be |

estimated by weighing the total payload assembly and determining the error.

* Total Fissile Quantity (With Error) of All Containers: The site

transportation certification official shall calculate and record the

total fissile quantity + the error for all the containers comprising a |

shipment (Section 9.0). The resulting total shall not exceed the limits

for fissile quantity for a TRUPACT-II as stated in Section 1.2.3 of the

SAR.

' Total Decay Heat 'With Error) of All Containers: The site

transportation certification official shall calculate and record the

total decay heat + error for all the containers comprising a shipment

(Section 10.0). The resulting total shall not exceed the limits set in

Section 1.2.3 of the SAR for the shipping category.

* Total Weight (With Error> Of Pavload and Package (Section 11.0): The

site transportation certification official shall be responsible for

ensuring that the total weight of the payload and package does not

exceed those limits set in Section 1.2.3 of the SAR. The total error

can be determined by weighing the entire payload assembly. The top

seven drums or SWB shall be verified to weigh no more than the bottom

seven drums or SWB.

• Dose Rate On The' Outside of Package (Section 12.0): The site

transportation certification official shall be responsible for ensuring

that the dose rates measured for the package do not exceed those limits

set in Section 1.2.3 of the SAR.

• Date of ICV Closure: The site transportation certification official |

shall record the date that the ICV is closed on the form. I

1.3.7-74

TRUPACT-II SAR Rev. 14, October 1994 J

•• Transportation Certification Official; The site transportation

certification official shall sign and date this document upon assuring

that the transportation requirements for the TRUPACT-II are met and the

payload is qualified for transport.

13.4 Dunnage

Dunnage is not required in TRUPACT-II shipments when the fourteen-drum or two-SWB

configuration is used. However, a shipper must use dunnage to complete one of

the above configurations if too few payload containers are available that meet

all payload container requirements and transportation requirements. An empty,

55-gallon, metal drum or an empty SWB may be used as dunnage. Dunnage drums may

be assembled into a seven-pack of only dunnage drums, or they may be assembled

into a seven-pack with drums of waste that meet all applicable requirements. In

the latter case, the Dunnage Drum(s) must be labeled with a unique package

identification number like the waste drums because of the WIPP Waste Information

System. All dunnage containers must be labeled "EMPTY" or "DUNNAGE."

13.5 References

13.5.1 U.S. DOE, "TRUPACT-II Content Codes (TRUCON)," Rev. 8, October 1994, |DOE/WIPP 89-004.

1.3.7-75

j ' TRUPACT-II SAR Rev. 13, April 1994

i

| • 14.0 QUALITY ASSURANCE

! This section describes the quality assurance (QA) programs applicable to the

j TRUPACT-II authorized methods for payload compliance (TRAMPAC).

| 14.1 Introduction

i| The TRUPACT-II will be primarily used by the U.S. Department of Energy (DOE) for

| the shipment of contact-handled transuranic (CH-TRU) waste. Typically TRU wastes

| are byproducts from the production of nuclear weapons for the U.S. Department of

! Defense; they are contaminated with small quantities of radioactive elements with

i atomic numbers greater than uranium, hence the name transuranic. CH-TRU waste

! that may be shipped in the TRUPACT-II is described in detail in the TRUPACT-II

| Content Codes (TRUCON) document (Ref. 14.4.1). The TRUPACT-II may be used by the

j DOE for shipments of CH-TRU waste, or other authorized contents, — to the WIPP

{ site, between DOE sites other than WIPP (inter-site), or within site boundaries

| (intra-site). Additionally the TRUPACT-II may be used for non-DOE shipments as

j approved by the NRC. In all cases the shipper is responsible for verifying the

| contents are authorized for shipment; the receiver also has a vested interest in

| the shipper's waste characterization methods and quality assurance program.

14.2 Quality Assurance Requirements for Pavload Compliance

Certification of authorized contents for shipment in TRUPACT-II will be under QA

programs that are equivalent to Subpart H of 10 CFR Part 71 (Ref. 14.4.2). For

payload control some of the 18 criteria of Subpart H, such as Packaging Design

Control, may not be applicable. Each shipper's QA program will address those

elements necessary to assure the allowable payload control methods provide the

level of confidence necessary for both the shipper and the receiver.

1.3.7-76

iTRUPACT-II SAR Rev. 14, October 1994

14i3 Quality Assurance Programs for Pavload Compliance

14.3.1 Shipments to the WIPP

The Waste Acceptance Criteria for the Waste Isolation Pilot Plant (WAC) document

describes payload technical requirements that must be met for shipments to the

WIPP (Ref. 14.4.3). The WAC also includes WIPP Operations and Safety Criteria,

RCRA requirements, and Performance Assessment Criteria. Using the WAC, the DOE

shipper sites write technical and QA program plans that are submitted to the WIPP

Waste Acceptance Certification Committee (WACCC), a standing committee reporting

to the DOE Carlsbad Area Office, for review and approval. Once the plans are

approved by the WACCC, the shipper sites prepare implementing procedures. These

procedures will be periodically audited by the WACCC to assure compliance with

the approved plans.

14.3.2 Shipments not to the WIPP

For shipments not to the WIPP site the WACCC will provide surveillance of the

shipper's QA program for payload compliance to assure the TRUPACT-II is only used

for the shipment of authorized contents. In addition the receiver may approve

and/or audit the shipper's QA program to assure the contents are as authorized.

14.4 REFERENCES

14.4.1 U.S. DOE, "TRUPACT-II Content Codes (TRUCON)," Rev. 8, October 1994, \DOE/WIPP 89-004.

14.4.2 Title 10, U.S. Code of Federal Regulations, Part 71, Subpart H - QualityAssurance, "S 71.101 Quality Assurance Requirements"

14.4.3 U.S. Department of Energy - Carlsbad Area Office, WIPP-DOE-069, "WasteAcceptance Criteria for the Waste Isolation Pilot Plant"

1.3.7-77

j TRUPACT-II SAR Rev. 13, April 1994

PAGES 78 THROUGH 81 ARE DELETED

1.3.7-78

NuPac TRUPACT-II SAR ' Rev. 1, May 1989

ATTACHMENT 1.0

REAL-TIME RADIOGRAPHY PROCEDURES


1.0 DESCRIPTION OF REAL-TIME RADIOGRAPHY

Real-time radiography (RTR) is a nondestructive testing method that allows the

RTR operator to ascertain the physical waste form within a payload container

without opening it. The examination method utilizes X rays to inspect the

payload container and contents and allows the operator to view events in

progress (real time) such as wave motion of free liquids. A typical RTR system

consists of:

1. An X-ray-producing device

2. An imaging system

3. An enclosure for radiation protection

4. A payload container handling system

5. An operator control station

The X-ray-producing device has controls which allow the operator to vary the

voltage, thereby controlling image quality. The voltage can be varied,

typically between 150-400 kV, to provide an optimum degree of penetration

through the waste. For example, high-density material (e.g., solidified liquid)

is usually examined with the X-ray device set on the maximum voltage. This

ensures maximum penetration through the payload container. Low-density material

(e.g., plastics and cellulose) is usually examined at lower voltage settings to

improve contrast and image definition. The imaging system typically utilizes

a fluorescent screen and a low light television camera.

Payload containers are placed in the RTR vault. Waste drums are placed on a

rotating platform. The platform or the X-ray tube and imaging system move up

and down to allow total coverage of the drum. X rays are projected through the

payload container and onto a fluorescent screen/image intensifier. The

resultant image is transferred by a camera to a remotely located television

screen. The operator conducts the examination by viewing the remote television

screen. The operator scans the contents of the payload container during the

examination. Waste boxes cannot be rotated during RTR inspection but are first

1.3.7.A1-1


inspected from one side and then rotated 180 degrees and inspected from the

opposite side. The two-sided inspection is performed to compensate for

magnification factors. Large magnification factors can occur depending upon the

location of an object within a box. Scanning from two sides, 180 degrees apart,

allows a higher degree of accuracy for determining sizes and quantities. The

two scans, from opposite sides, also provide a higher degree of confidence for

detection of objects that may be hidden when scanning from only one side. The

waste payload are inspected for correct physical waste form description, sealed

containers, pressurized containers, and free liquid waste forms.

The RTR operator documents the findings of the RTR examination of each waste

payload by several means listed below:

The results are recorded on an RTR examination form, and this form is

included in the waste payload data package. The examination results

may also be entered into a computerized data collection system.

The examination is recorded on a videotape recorder.

The RTR operator verbally describes the results of the RTR examination

on the audio track of the videotape. The audio voice track on the

videotape is an additional positive feature of RTR.

These videotapes are maintained as a permanent record (i.e., maintained

throughout the life of the WIPP Proj ect). Therefore a videotape is available

and on file for every payload container transported to WIPP which has been

examined by RTR.

The advantage of viewing the examination in real time is that the X-ray device

can be adjusted on the spot to obtain optimum imaging conditions, or the system

can be stopped to focus on one object. RTR works extremely well for detecting

free liquid due to its ability to view events in progress, such as wave motion.

The presence of free liquids is verified by jogging the container or handling

1.3.7.A1-2


system (stopping and starting the container rotation) and then watching for the

resulting wave motion. Free liquids in pressurized containers are easily

detected, thereby assessing two parameters, liquids and pressurized containers.

Items that may otherwise go undetected, due to being shielded from the X rays

by another object, are often found because the operator is watching the

inspection in real time while rotating or moving the payload container.

Interpretation of results and disposition of the inspected payload containers

are also accomplished at the time of inspection rather than waiting for X-ray

film to be processed.

Operator training and experience are the most important control factor in

ensuring the quality of RTR interpretation and inspection. Operator training,

qualification and certification are performed in accordance with Society for

Nondestructive Testing (SNT)-TCIA (Ref. 2.1). SNT-TC1A is a nationally

recognized guideline and is used by employers to train, qualify, and certify

employees to perform specific nondestructive tests.

Recertification of operators is based upon evidence of continued satisfactory

performance and is performed at least every two years. Unsatisfactory operator

performance is cause for decertification. Retraining is required before an

operator is again certified to interpret and disposition payload containers.

A training drum containing a variety of different container sizes, and holding

various amounts of liquid, is periodically examined by each operator, as

prescribed in the site waste certification and QA procedures. - The test

videotape is then reviewed by supervision to ensure that the operator's

interpretations remain consistent and accurate. The test tapes are also used

for monitoring the imaging system characteristics and identifying other shapes

or matrices.

1.3.7.A1-3


QA oversight functions are performed by independent individuals who review

videotape, of examined payload containers. The frequency and number of payload

containers included in these reviews is determined in accordance with Military

Standard (MIL-STD)-105D, "Sampling Procedures and Tables for Inspection by

Attributes," (Ref. 2.2).

The RTR has several inherent limitations. X rays with a high enough energy

level to penetrate high-density waste forms or shielded containers present an

image with such a large latitude that low-density materials (i.e., liquids) will

be indiscernible. Therefore, high-density waste forms or shielded payload

containers must have the physical waste form verified by other methods (e.g.,

visual examination during packaging) or be rejected.

RTR inspection is a semi-quantitative examination that can identify and verify

the payload container's physical contents. The RTR cannot determine the

chemical composition of the waste.

2.0 REFERENCES

2.1 SNT-TC-1A, "Recommended Practice No. SNT-TC-1A, Personnel Qualification andCertification in Nondestructive Testing", August 1984.

2.2 MIL-STD-105D, "Military Standard, Sampling Procedures and Tables forInspection by Attributes", April 29, 1963.

1.3.7.A1-4

I TRUPACT-II SAR Rev. 14, October 1994

ATTACHMENT 2.0

GAS GENERATION TEST PLAN TO QUALIFY TEST CATEGORY

WASTE FOR SHIPMENT IN THE TRUPACT-II

TRUPACT-II SAR Rev. 13, April 1994 I

TABLE OF CONTENTS

Page

1.0 Introduction 1

1..1 Background 1

1.2 Objectives 1

2.0 Program Documents 3

2.1 The TRUPACT-II Gas Generation Test Plan 3

2.2 Quality Assurance Program Plan (QAPP) 3

2.3 Test Standard Operating Procedure (TSOP) 5

2.4 Site Quality Assurance Project Plans (QAPjPs) 5

3.0 Test Procedure 5

3.1 Waste Selection Criteria 5

3.2 Test Apparatus 6

3.3 Data Quality Objectives 9

3.4 Test Startup and Test Completion 10

3.5 Determination of Drum Shippability 10

4.0 References 17

1.3.7.A2-i

I TRUPACT-II SAR Rev. 14, October 1994

LIST OF TABLES

Page

1. Decay,Heat Criteria for Drum Selection 7

2. Maximum Total Gas Release Rates for Test Categories 13

3. Maximum Hydrogen Generation Rates for Test Categories 15

LIST OF FIGURES

Page

1. TRUPACT-II Gas Generation Test Program Logic Flow Diagram 2

2. Documents Governing the TRUPACT-II Gas Generation Test Program 4

3. Schematic of the Test Apparatus 8

j 4. Test Category Criteria " 11

1.3.7.A2-ii

TRUPACT-II SAR Rev. 13, April 1994 }

1.0 INTRODUCTION

1.1 Background

CH-TRU wastes to be transported in the TRUPACT-II package fall into one of two

categories based on their gas generation potential—"analytical category waste"

or "test category waste." The wastes that can be shipped without the need for

testing comprise the "analytical category", and are qualified for shipment based

on limits derived from theoretical worst-case calculations. The CH-TRU waste

containers that exceed the applicable decay heat limits set for the analytical

category, or that do not have an established theoretical bounding gas generation

rate ("G-value"), belong in the "test category". These containers must be tested

to determine the actual rate of gas generation and hydrogen concentration prior

to shipment. The TRUPACT-II Gas Generation Test Program (the Program) consists

of performing controlled tests with actual containers of CH-TRU waste to

determine gas generation rates of waste under simulated thermal transportation

conditions. A logic flow diagram for the Program is presented in Figure 1.

1.2 Objectives

The Program has two primary objectives. The first, or short-term objective, is

to facilitate the shipment of waste in the test category by testing individual

containers of waste and showing compliance with applicable hydrogen and total gas

generation rate limits. Specifically, this objective consists of the following

determinations:

Total gas generation rate to ensure that the 50 psig limit on the design

pressure of the TRUPACT-II package is not exceeded.

Hydrogen generation rate to ensure that the 5% limit on hydrogen

concentration in the TRUPACT-II package is not exceeded.

The second, or long-term, objective of the Program is to improve waste

shippability for specific populations of waste, and redefine the decay heat

limits based on actual test data obtained from the Program. The decay heat

limits for the analytical category are currently based on theoretical, worst-case

G values. This long-term objective will cover the following areas:

Establishing a G value for Waste Type IV (Solidified Organics). Waste

belonging to this waste type does not have a bounding G value at this

time, and all of Waste Type IV is currently in the test category.

1.3.7.A2-1


I, II, III

Meets

iAnalytical Category J

Meets

OK to Ship

TRUCONWattage

Limit

Test Category

Test forTRAMPAC

Gas Generation

Cant Ship(Repackage or Treat)

Figure 1TRUPACT-II Gas Generation Test Program Logic Flow Diagram

1.3.7.A2-2

TRUPACT-II SAR Rev. 13, April 1994 j

• Establishing more realistic 6 values for Haste Types I, II, and III, or

subpopulations of these waste types, based on results obtained from the

Program.

Achieving the long-term objective will allow the shipment of more waste under the

analytical category, with the need for less testing. For the purposes of the

program, the only difference between the analytical category waste and the test

category waste is the hydrogen and total gas generation potential.

2.0 PROGRAM DOCUMENTS

The major documents (including this Test Plan) governing the implementation of

the Program are described in Sections 2.1 through 2.4. The relationship between

these documents is illustrated in Figure 2.

2.1 The TRUPACT-II Gas Generation Test Plan

The Test Plan (this document) provides the technical basis for the Program in

terms of its objectives (i.e., the transportation of test category waste).

Specifically, this document establishes the scope of the Program, defines the

different components of the Program and the relationship between these

components, describes the waste selection criteria for the tests, and documents

the transportation acceptance criteria applicable to the test results.

2.2 Quality Assurance Program Plan (OAPP1

The QAPP for the Program (Ref. 4.1) specifies the quality of data required to

meet the objectives of the Program in the form of data quality objectives (DQO)

and quality assurance objectives (QAO). These DQOs and QAOs have been written

to be consistent with the standards and guidance specified in DOE Order 5700.6C,

"Quality Assurance", and the EPA document, "Guidelines and Specifications for

Preparing Quality Assurance Program Plans", QAMS-004/80. The waste parameters

that must be characterized prior to testing, analytical methods and calibrations,

and administrative quality control measures are all described in detail in the

QAPP. The QAPP also includes the performance-based quality assurance/quality

control (QA/QC) requirements that must be met by each facility participating in

the Program. Work instructions (e.g., site-specific plans, procedures, and

specifications) for quality-related activities will be prepared, reviewed,

approved, and controlled in accordance with the requirements detailed in the

QAPP.

1.3.7.A2-3

! TRUPACT-II SAR Rev. 13, April 1994

TRUPACT-IICERTIFICATE OF

COMPLIANCE

i r

TRUPACT-II SARP,APPENDIX 1.3.7, ATTACHMENT 2

GAS GENERATION TEST PLAN

i

r

t

QAPP

i

SITE-SPECIFICQAPjP

} r

GASGENERATION

TEST SOP

r

OTHER SITEPROCEDURES

Figure 2Documents Governing the TRUPACT-II Gas Generation Test Program

1.3.7.A2-4

TRUPACT-II SAR Rev. 14, October 1994 j

2.3 Test Standard Operating Procedure (TSOP)

The TSOP (Ref 4.2) will provide written instructions for the methodology and

sequence by which each test activity will be performed. The purpose of the TSOP

is to standardize the tests across the DOE system, to the extent possible. .The

TSOP will provide detailed guidance on test startup, routine operations, and

criteria for determining test completion. The TSOP will also .contain

quantitative and qualitative criteria for verifying that the work has been

satisfactorily accomplished.

2.4 Site Quality Assurance Project Plans (OAPiPsl

The site QAPjPs provide detailed and comprehensive statements to effectively

implement the QA/QC requirements at each location. Each DOE facility

participating in the Program will prepare a site QAPjP in compliance with the

QAPP. The site QAPjPs will be supplemented by the TSOP that includes detailed

instructions for performing Program tasks. Additionally, each site will have

site-specific standard operating procedures (SOPs) for associated operations.

For example, SOPs will be maintained for the movement of waste from storage to

test area, operation of specific computer systems for collection and retrieval

of data, and implementation of health and safety directives.

3.0 TEST PROCEDURE

3.1 Waste Selection Criteria

This Program applies to the testing of individual 55-gallon drums. The drums

from each content code will be placed into a test category (e.g., I.1A2T,

IV.1A2T, etc.), if they fall into one of the following categories: j

The decay heat loading of the waste container exceeds the limit for the

shipping category of that payload container. Payload containers in

Waste Types I, II, or III belong in this category (Section 1.2.3 of the

TRUPACT-II SAR).

• A waste process does not have a fully characterized bounding G value

from previous sampling or waste stream analysis. Payload containers

in Waste Type IV belong to this category.

Drums selected for the testing must meet all other applicable transportation

limits (weight, Fissile Gram Equivalent, dose rate, etc.). Waste containers for

the Program shall be chosen only if their decay heat values are higher than the

1.3.7.A2-5

! TRUPACT-II SAR Rev. 14, October 1994

decay heat limit for the corresponding analytical shipping category, or they

belong to Waste Type IV. There is also a maximum limit on the decay heat for

each tested container that dictates the temperature at which the test must be

conducted. The test temperature is the maximum center drum wall temperature for

the maximum wattage limit applicable to the waste containers. The shipping

categories, corresponding test temperatures, minimum decay heat limit, and

maximum decay heat limits are listed in Table 1. The waste containers selected

for the testing will be chosen with decay heat values closer to the upper limit,

so that bounding estimates of the gas generation potential can be obtained.

3.2 Test Apparatus

A test apparatus will be used that allows measurement of the rate at which gas

is exhaled or inhaled by a drum. This setup will also allow sampling of the

. offgas during the test in order to measure the concentrations of hydrogen,

I methane, and compounds of interest for mass balance purposes. The test apparatus

will enclose a drum of waste, be heated to the predetermined temperature, and

monitor the temperature of the offgas and the drum, and the offgas rate, during

testing.

A diagram of the processes involved in gas generation testing appears in

Figure 3. Any combination of hardware and software which collects data that meet

the quality assurance objectives of the Program may be used to perform testing.

It is likely that facilities participating in this Program will use identical or

similar equipment for ease of performance validation. The steps in the procedure

are centered around the following activities:

• Measurement of barometric pressure

Temperature control and measurement (for the drum)

• Gas flow measurement

• Gas sampling

• Gas analyses.

In order to test the waste for gas generation, the temperature of the drum will

be raised. The selected waste container is placed in an insulated overpacking

drum enclosure. This apparatus is designed to efficiently heat the drum.

Insulation, heat tape, thermocouples, and controllers may be used to monitor and

control the temperature. The test temperature for each waste type has been

calculated based upon the maximum allowed wattage for shipped waste.

1.3.7.A2-6

TRUPACT-II SAR Rev. 14, October 1994 !

Table 1

Decay Heat Criteria for Drum Selection

ShippingCategory

I.1A0TLI AITI.1A2TI.1A3T

I.2A0TI.2A1TI.2A2TI.2A3TI.2A4T

I.3A0TI.3A1TI.3A2TI.3A3TL3A4T

H.1A0TH.1A1TH.1A2TH.lA2aTII.1A3TII.1A4Tn.lA5TII.1A6T

HI.1A0Tffl.lAlTin.lA2Tm.lA2aTIH.1A3Tm.lA4THI.1A5TIIUA6T

IV.1A1TIV.1A2TIV.1A3T

Minimum Decay Heat(watts)

0.20600.17970.15940.0466

0.25360.22120.19620.05730.0418

0.82410.71890.63750.18630.1359

0.22510.19240.08690.16800.05610.04140.03280.0272

0.11260.09620.04340.08400.02800.02070.01640.0136

NANANA

Maximum Decay Heat(watts)

10101010

1010101010

1010101010

2020202020202020

2020202020202020

777

TestTemperature

138°F

138°F

138°F

146°F

146°F

135°F

1.3.7.A2-7


Table 1 (Continued)Decay Heat Criteria for Drum Selection

ShippingCategory

I.1B0TI.1B1TI.1B2TI.1B3T

I.2B0TI.2B1TL2B2TI.2B3TI.2B4T

I.3B0TI.3B1TI.3B2TI.3B3TI.3B4T

H.1B0Tn.lBITH.1B2Tn.lB2aTIUB3Tn.lB4Tn.lB5TII.1B6T

IH.1B0Tm.lBlTm.lB2Tm.lB2aTIH.1B3TIH.1B4TIH.1B5Tm.lB6T

IV.1B1TIV.1B2TIV.1B3T

Minimum Decay Heat(watts)

0.14570.13200.12070.0426

0.17930.16250.14860.05240.0391

0.58270.52810.48280.17030.1272

0.17110.15160.07740.13600.05200.03920.03140.0262

0.08560.07580.03870.06800.02600.01960.01570.0131

NANANA

Maximum Decay Heat(watts)

10101010

1010101010

1010101010

2020202020202020

2020202020202020

777

TestTemperature

138°F

138°F

138°F

146°F

146°F

135°F

1.3.7.A2-7a


Measurement of Barometric Pressure

Temperature Controland Measurement (Drum)

N

Exhaust

Figure 3

Schematic of the Test Apparatus

Gas Analyses*

•HydrogenMethaneVolatile Organic CompoundsMass Balance ParametersPt-Pd Recombiner Poisons

Flow Measurement

1.3.7.A2-8


Barometric pressure will be determined in a-location that will give sufficient

information regarding the pressure of the sampled gas(es). Each sample analysis

must have an associated barometric pressure measurement.

Data will be gathered from-a flow measurement device. Measurements of the total

gas flow rate and associated hydrogen/methane gas concentrations will be used to

calculate the hydrogen/methane gas generation rate. A mass flow meter, or other

device, may be placed outside of the waste drum but within the overpacking drum

enclosure to avoid condensation of any gases within the flow device.

Sampling of gases may be accomplished using either of two methods. A sampling

manifold will be a part of the waste drum test unit. This manifold will be used

to either collect discrete samples in containers or to divert a stream of gas to

an analytical instrument. If discrete samples are collected, they will be sent

to an analytical laboratory for analyses. If a stream is diverted to an

analytical instrument, such as a mass spectrometer, this is called on-line

sampling and analysis.

Prior to gas generation testing, the headspace of the drums will be sampled and

analyzed for Volatile Organic Compounds (VOC). The target analyte list for VOC

analysis is the same as that proposed in the HIPP QAPP (Ref. 4.3). These samples

will be taken before heating of the drum begins to provide comparable data

between the two programs. Once heating of the test drum begins, any gas exhaled

by the drum will be analyzed for hydrogen; methane; mass balance parameters

(oxygen, nitrogen, carbon dioxide, and argon); and platinum-palladium recombiner

poisons (hydrogen sulfide, sulfur dioxide, and sulfur trioxide). Platinum-

palladium recombiner poisons will only be targeted at facilities that use

platinum-palladium recombiners to prevent the buildup of hydrogen.

3.3 Data Quality Objectives

DQOs are the qualitative and quantitative statements developed by data users to

specify the quality of data required from a particular data collection activity.

The DQOs for the Program are:

Gas Flow Measurement-Establish the total gas flow as a function of time.

This .information will be used to evaluate compliance with the limit on

the total gas generation rate for the waste container.

Hydrogen/Methane Gas Sampling and Analyses—Establish the concentrations

of hydrogen and methane in the total gas flow. This information will be

used to assess compliance with the limitations on flammable gas

concentrations during shipment.

1.3.7.A2-9

! TRUPACT-II SAR Rev. 14, October 1994

Volatile Organic Compound (VOC1 Sampling and Analyses—Establish the

headspace concentration of VOCs prior to the start of the test on each

drum. This information will be used to assure that shipped drums satisfy

! • the limits on flammable VOCs.

• Mass Balance Parameters—Obtain estimates of the relative humidity,and the

concentrations of oxygen, nitrogen, carbon dioxide, and argon for mass

balance purposes.

Other monitored variables include temperature and barometric pressure. In

addition, it should be noted that reliance on hydrogen recombiners is not

acceptable, and hydrogen recombiners must not be present in the drums that are

being tested. As specified in the drum selection and test criteria of the TSOP,

the testing procedure must ensure that recombiners are not present during the

test.

The QAPP defines the QAOs associated with these data measurements in terms of

precision, accuracy, representativeness, completeness, and comparability.

Sampling and analysis procedures for these measurements are also discussed in the

QAPP and will meet the QAOs set for the program. Specific quality assurance

measures will also be followed for sample custody, calibration of equipment, data

reporting, and data reduction.

3.4 Test Startup and Test Completion

The test startup consists of placing the waste drum in the test apparatus and

heating the test unit to the required test temperature. The TSOP describes the

sampling and analysis required on a routine basis. As described in the TSOP, the

test will be terminated after 60 days, or earlier if sufficient data are obtained

showing an observable trend for steady H2 generation.

3.5 Determination of Drum Shippabilitv

At the completion of the test, the test results will be analyzed to determine if

the drum can be shipped in the TRUPACT-II package under the test category.

Figure 4 displays a sample data sheet for entering the test category criteria

that must be recorded for each drum tested. The data sheet should be completed

as follows:

1.3.7.A2-10

TRUPACT-II SAR Rev. 13, April 1994 J

SAMPLE DATA SHEET

Payload Container I.D.:

Preliminary Shipping Category:

Date of Test Completion:

Total Gas Release Rate: (moles/sec)

Is limit on Total Gas Release Rate in Table 2 met? (Yes/No)

Hydrogen Generation Rate: (moles/sec)

Is limit on Hydrogen Generation in Table 3 met? (Yes/No)

Are all test category criteria satisfied? (Yes/No)

Test Certification Official: Date:

Figure 4

Test Category Criteria

1.3.7.A2-11

! TRUPACT-II SAR ' Rev. 14, October 1994

Step 1—Record the completion date of the test.

Step 2—Record the total gas generation rate for the payload container.

• Step 3—Compare the total gas release rate to the limit for the

corresponding shipping category shown in Table 2. Indicate by (Yes/No) if

the limit is met. The pavload container does not qualify for shipment if

the limit is exceeded.

The maximum gas release rate that can be allowed in a payload container

(in a TRUPACT-II) is 1/14 of the total gas release rate allowed in the

TRUPACT-II. Therefore, if a drum qualifies for shipment under this

restriction, a combined load of fourteen drums will meet the restriction.

For overpacks of drums, each drum that falls into the test category will

be tested individually. The limits for the total gas release rate will

.take into account the four drums overpacked in an SWB, and two SWBs in the

TRUPACT-II. Therefore, if a drum to be overpacked qualifies for shipment

under this restriction, a combined load of eight drums overpacked in two

SWBs will meet the restriction.

Step 4—Record the hydrogen generation rate for the payload container.

Step 5—Compare the hydrogen generation rate to the limit for the

corresponding shipping category in Table 3. Indicate by (Yes/No) if the

limit is met. The pavload container does not qualify for shipment if the

limit is exceeded.

If all of the above limits are met, the payload container satisfies the test

category criteria. This is indicated at the bottom of the data sheet (Figure 4).

The data sheet is then signed by the appropriate official. The payload container

qualifies for shipment after verification of all of the transportation

parameters. Once all the criteria are satisfied, the payload shipping category

j (I.1A2T, IV.1A4T, etc.) is marked on the payload container. The "T" in the

shipping category indicates that the assembled payload has been qualified for

shipment by testing. The test results and necessary data sheets for the entire

payload shall be available upon request. Containers that do not meet the test

category criteria are segregated for repackaging or reprocessing.

1.3.7.A2-12

TRUPACT-II SAR Rev. 13, April 1994 \

Table 2Maximum Total Gas Release Rates for Test Categories

55-GaIlon Drums

PayloadShipping Category

I.1A0T

1.1 AIT

I.1A2T

I.1A3T

I.2A0T

I.2A1T

I.2A2T

I.2A3T

I.2A4T

I.3A0T

I.3A1T

I.3A2T

L3A3T

I.3A4T

H.1A0T

II. 1 AIT

H.lA2aT

H.1A2T

H.1A3T

H.1A4T

H.1A5T

H.1A6T

Maximum Gas Release Rate(moles/sec/container)*

6.48E-07

6.48E-07

6.48E-O7

6.48E-07

6.48E-07

6.48E-07

6.48E-07

6.48E-07

6.48E-07

6.48E-07

6.48E-07

6.48E-07

6.48E-07

6.48E-07

6.36E-07

6.36E-07

6.36E-07

6.36E-O7

6.36E-07

6.36E-07

6.36E-07

6.36E-O7

Drums Overpacked in an SWB


I.1B0T

I.1B1T

I.1B2T

I.1B3T

L2B0T

I.2B1T

L2B2T

I.2B3T

I.2B4T

I.3B0T

I.3B1T

I.3B2T

I.3B3T

I.3B4T

H.1B0T

H.1B1T

H.lB2aT

H.1B2T

H.1B3T

H.1B4T

n.lB5T

H.1B6T

Maximum Gas Release Rate(moles/sec/container)'

3.24E-06

3.24E-06

3.24E-06

3.24E-06

3.24E-06

3.24E-06

3.24E-06

3.24E-06

3.24E-06

3.24E-06

3.24E-06

3.24E-06

3.24E-06

3.24E-06

3.20E-06

3.20E-06

3.20E-06

3.20E-06

3.20E-06 -

3.20E-06

3.20E-06

3.20E-06

° The maximum gas release rates were determined from analysis as described in Section 3.4.4 of theTRUPACT-II SAR.

1.3.7.A2-13


Table 2Maximum Total Gas Release Rates for Test Categories

(Continued)

55-GaIlon Drums

• PayloadShipping Category

IH.1A0T

HI. 1 AIT

m.lA2aT

IIL1A2T

IH.1A3T

IH.1A4T

HI.1A5T

HI.1A6T

IV. 1 AIT

IV.1A2T

IV.1A3T

Maximum Gas Release Rate(moles/sec/container)*

6.36E-07

6.36E-07

6.36E-07

6.36E-07

6.-36E-O7

6.36E-O7

6.36E-07

6.36E-07

6.51E-07

6.51E-07

6.51E-07



HI.1B0T

m.lBlT

m.lB2aT

HI.1B2T

HI.1B3T

HI.1B4T

IH.1B5T

HI.1B6T

IV.1B1T

IV.1B2T

IV.1B3T

Maximum Gas Release Rate(moles/sec/container) *

3.20E-06

3.20E-06

3.20E-06

3.20E-06

3.20E-06

3.20E-06

3.20E-06

3.20E-06

3.26E-06

3.26E-06

3.26E-06

' The maximum gas release rates were determined from analysis as described in Section 3.4.4 of theTRUPACT-II SAR.

1.3.7.A2-14

TRUPACT-II SAR Rev. 13, April 1994 |

Table 3Maximum Hydrogen Generation Rates for Test Categories

55-Gallon Drums


I.1A0T

1.1 AIT

I.1A2T

I.1A3T

I.2A0T

I.2A1T

I.2A2T

I.2A3T

I.2A4T

I.3A0T

I.3A1T

I.3A2T

I.3A3T

I.3A4T

ELIAOT

n.lAlT

H.lA2aT

H.1A2T

n.lA3T

H.1A4T

H.1A5T

H.1A6T

Maximum H2 Generation Rate(moles/sec/container)*

3.416E-08

2.980E-08

2.643E-08

7.721E-09

3.416E-08

2.980E-08

2.643E-08

7.721E-09

5.634E-O9

3.416E-08

2.980E-08

2.643E-08

7.721E-09

5.634E-09

3.966E-08

3.39OE-O8

2.961E-08

1.531E-08

9.883E-O9

7.298E-09

5.785E-09

4.791E-09



I.1B0T

I.1B1T

I.1B2T

I.1B3T

I.2B0T

I.2B1T

I.2B2T

I.2B3T

I.2B4T

I.3B0T

I.3B1T

I.3B2T

I.3B3T

I.3B4T

H.1B0T

H.1B1T

H.lB2aT

H.1B2T

H.1B3T

H.1B4T

H.1B5T

H.1B6T


2.416E-08

2.189E-08

2.002E-08

7.061E-09

2.416E-08

2.189E-O8

2.002E-08

7.061E-09

5.274E-09

2.416E-08

2.189E-08

2.002E-08

7.061E-09

5.274E-09

3.O15E-O8 .

2.670E-08

2.396E-08

1.364E-08

9.163E-09

6.898E-09

5.530E-09

4.616E-09

• The maximum H2 generation rates were determined from analysis as described in Section 3.4.4 of theTRUPACT-II SAR.

1.3.7.A2-15


Table 3Maximum Hydrogen Generation Rates for Test Categories

(Continued)

55-Gallon Drums


HI.1A0T

HI. 1 AIT

m.lA2aT

IH.1A2T

HI.1A3T

IIL1A4T

IH.1A5T

HI.1A6T

IV. 1 AIT

IV.1A2T

IV.1A3T


3.966E-O8

3.39OE-O8

2.961E-08

1.531E-08

9.883E-09

7.298E-09

5.785E-09

4.791E-09

3.390E-O8

2.961E-08

9.922E-09



EI.1B0T

ELIBIT

HI.lB2aT

IH.1B2T

IH.1B3T

IH.1B4T

HI.1B5T

IH.1B6T

IV.1B1T

IV.1B2T

IV.1B3T


3.015E-O8

2.670E-08

2.396E-08

1.364E-08

9.163E-09

6.898E-09

5.530E-09

4.616E-09

2.670E-08

2.396E-08

9.196E-09

* The maximum H2 generation rates were determined from analysis as described in Section 3.4.4" of theTRUPACT-II SAR.

1.3.7.A2-16


4.0 REFERENCES

4;1 QAPP for TRUPACT-II Gas Generation Test Program (Current Draft)

4.2 Teat Standard Operating Procedure for the TRUPACT-II Gas Generation Test

Program (Current Draft)

4.3 U.S. Department of Energy (DOE), 1992, "Quality Assurance Program Plan for

the Waste Isolation Pilot Plant Experimental Waste Characterization

Program," DOE /EM/48063-1. Rev. 2, U.S. Department of Energy, Washington D.C.

1.3.7.A2-17- !


ATTACHMENT 3.0

DOE ASSAY METHODS USED FOR DETERMINATION OF FISSILE MATERIAL CONTENT

AND DECAY HEAT VALUES OF CONTACT HANDLED TRANSURANIC (CH-TRU) WASTES

NuPac TRUPACT-II SAR Rev. 0, February 1989

-TABLE OF CONTENTS

1.0 INTRODUCTION 1

2.0 ASSAY OVERVIEW 6

3.0 ASSAY METHODS DESCRIPTIONS, CHARACTERISTICS, AND LIMITATIONS 10

3.1 Calorimetry ' 10

3.2 Passive Gamma Assay 11

3.2.1 Segmented Gamma Scanning (SGS) 11

3.2.1.1 Overview - 11

3.2.1.2 Applicability to CH-TRU Wastes 14

3.2.1.3 Instrument Calibration, Standards

Preparation, and Implementation 16

3.2.1.4 Operator Training Requirements and

Practices 17

3.2.1.5 Assay Procedures 17

3.2.1.6 Assay Precision, Bias, and Limit of

Detection 17

3.2.1.7 SGS Assay Results Comparisons 20

3.2.2 Nal (low-resolution) Assays " 20

3.3 Radiochemical Methods 21

3.4 Passive Neutron Coincidence Counting (PNCC) Assays 23

- 3.4.1 Overview 23

3.4.2 Applicability to CH-TRU Wastes 24

3.4.3 Instrument Calibration, Standards

Preparation, and Implementation 24

1.3.7.A3-1


TABLE OF CONTENTS(Continued)

3.4.4 Operator Training Requirements and Practices 25

3.4.5 Assay Procedures • 25

3.4.6 Assay Precision, Bias, and Limit of Detection 25

3.5 Passive-Active Neutron (PAN) Assay Systems 29

3.5.1 Overview 29

3.5.2 Instrumentation 30

3.5.2.1 Passive Assay Portion 30

3.5.2.2 Active Assay Portion 32

3.5.3 PAN Assay Matrix Corrections 33

3.5.4 Assay Algorithm and Data Acquisition System 41

3.5.5 Applicability to CH-TRU Wastes 44

3.5.6 Instrument Calibration, Standards Preparation,

and Implementation 44

3.5.7 Operator Training Requirements and Practices 45

3.5.8 Assay Procedures 47

3.5.9 Assay Precision, Bias, and Limit of Detection 48

3.5.10 PAN Assay Results Comparisons 49

3.5.11 Choice of Passive or Active Assay Value 56

4.0 FISSILE MATERIAL CONTENT AND DECAY HEATCALCULATIONS 59

5.0 NEW ASSAY DEVELOPMENTS 63

1.3.7.A3-ii


• • TABLE OF CONTENTS(Continued)

PAGE

6.0 QUALITY ASSURANCE (QA) AND QUALITY CONTROL (QC) PRACTICES 65

7.0 REFERENCES 68


LIST OF TABLES

PAGE

1. DOE Contractor CH-TRU Waste Generator and/or Storage Sites 1

2. CH-TRU Waste Assay Methods 2

3. Summary of CH-TRU Waste Assay Methods Presently Used

at DOE CH-TRU Waste Generating and Storage Sites 3

4. Typical SGS Assay Precisions for WG Pu in Low-Density WastesContained in 208-L Drum 18

5. Typical SGS Assay Biases 19

6. Summary of PNCC Assay Error Contributions for Low-Density WasteForms 27

1.3.7.A3-iv

NuPac TRUPACT-II SAR • Rev. 0, February 1989

LIST OF FIGURES

PAGE

1. Schematic Arrangement for Segmented Gamma-Ray Scanning

(SGS) System. 13

2. Schematic PAN System Layout. 31

3. Moderator Index Measured for PAN Systems Using

the Detector Ratio Method. 394. Use of the Moderator Index to Determine Passive Neutron

Coincidence Matrix Correction Factors for a PAN System. 40

5. PAN System Active Assay Matrix Correction FactorsMeasured at Hanford, INEL, and SRP with a Set of20 Standard Matrix Drums. 42

6. INEL PAN Standards Measurements (Pink Drum) PerformedOver a Three Year Period. 46

7. Comparison Assay Data Sets of 200 LLNL CH-TRU Waste Drums. 51

8. Comparison of 300 Hanford CH-TRU Waste Drum AssaysPerformed with the PAN System, Passive Neutron Comparedto Active Neutron. 52

9. Assay Comparisons of a Set of 300 RFP CH-TRU Waste Drums(Graphite Molds Matrix) 53

10. Batch Average Pu Assays of 1300 Sludge Drums Performed atRFP Compared to PAN Assays of the Same Drums Done at INEL. 54

1.3.7.A3-V


DOE ASSAY METHODS USED FOR DETERMINATION OF FISSILE MATERIAL CONTENTAND DECAY HEAT VALUES OF CONTACT-HANDLED TRANSURANIC (CH-TRU) WASTES

1.0 INTRODUCTION

Contact-handled transuranic (CH-TRU) waste must be assayed for determination of

fissile material content and decay heat values prior to shipment. Each

Department of Energy (DOE) contractor CH-TRU waste generating and/or storage

site generates and/or stores one or more types of waste forms (e.g., sludge,

general laboratory waste, etc.) which must be assayed.

•The contractor sites which generate and/or store CH-TRU waste are iisted in

Table 1, and the assay techniques used by DOE contractor sites are listed in

Table 2. The specific assay methods utilized at each site are given in Table 3.

Table 1. DOE Contractor CH-TRU Waste Generator and/or Storage Sites

1. Argonne National Laboratory - East (ANL-E)2. Idaho National Engineering Laboratory (INEL)3. Lawrence Livermore National Laboratory (LLNL)4. Los Alamos National Laboratory (LANL)5. Mound Facility (Mound)6. Nevada Test Site (NTS)7. Oak Ridge National Laboratory (ORNL)8. Richland Hanford (RH)9. Rocky Flats Plant (RFP)

10. Savannah River Plant (SRP)

The DOE and its site contractors have been historically, and continue to be the

dominant force in assay technology development and implementation, not only

within the United States but internationally as well. Some of the assay

technologies (passive gamma, radiochemistry, and PNCC) are highly developed and

1.3.7.A3-1

NuPac-TRUPACT-II SAR Rev. 0, February 1989

. Table 2. CH-TRU Waste Assay Methods

1. Passive Gamma (HPGe, Ge(Li), Nal: transmission-corrected

and non-corrected)

2. Radiochemical assay: gross alpha and gamma spectrometry

3. Passive neutron coincidence counting (PNCC)

4. Passive/active neutron assay (PAN)

5. Calorimetry

1.3.7.A3-2


Table 3. Summary of CH-TRU Waste Assay Methods Presently Usedat DOE CH-TRU Waste Generating and Storage Sitesa

Site

ANL-E

Hanford

INEL

LLNL

LANL

Mound

NTS

ORNL

RFP

SRP

SGS or Nal

X

X

X

X

X

X

X

X

PNCC

X

X

X

PAN ( drum")

X

X

X

X

X

X

PAN(box)

X

X

Radiochemistrv

X

X

X

X

X

Mobile PAN

X

X

X

aCalorimetry method is also used to obtain quantitative radionuclide content.

1.3.7.A3-3


have a long history of implementation first to nuclear products (in safeguards

and material accounting) and eventually to nuclear scraps and wastes. Other

assay technologies, such as PAN, are newer developments (circa 1980), and were

developed especially for application to bulk TRU wastes assays under sponsorship

of the DOE. Additional improvements to the assay technology continue to be made

and implemented as indicated in this document.

Where practical, the DOE sites perform multiple independent assays of waste

packages as well as real-time radiography (RTR) inspection. These independent

assays generally take the form of a passive gamma assay (usually SGS) at the

waste generator site followed by passive-active neutron assay at a central

certification facility.

These practices, as well as QA audits and administrative controls, provide

assurances that correct values of fissile material and decay heat are assigned

to each waste drum. In the case of special-case drums or of significant

differences among independent assay measurements, personnel at each site review

all available data, including the RTR information and assay records, to determine

the appropriate action. If a reasonable assay value cannot be ascertained,

remedial action is taken; either reassay if measurement errors are suspected,

or repackaging if the drum is suspected of nonconformance with respect to fissile

material content or decay heat.

This appendix describes the nondestructive and destructive assay methods for

CH-TRU waste employed by the DOE sites. The assay methods employed by the DOE

are shown to be reliable and accurate means of determining fissile material,

radionuclide, and decay heat content of CH-TRU wastes.

Assay topics addressed for an assay method include:

(1) An overview of the assay method

(2) Applicability to CH-TRU wastes

1.3.7.A3-4


(3) Calibration standards and implementation

(4) Operator training requirements and practices

(5) Assay procedures

(6) Assay precision, bias, and limit of detection.

More details are presented for the SGS and PAN assay methods, which are the

primary methods used within the DOE complex.

All systems or methods, except for PAN, have established ASTM, ANSI, and/or

Nuclear Regulatory Commission (NRC) guidelines or methods which describe proper

calibration procedures, proper equipment set-up, etc. PAN is a new technique

and does not yet have a guideline or method developed. However, comparisons of

PAN data with the more established assay methods (e.g., SGS or radiochemistry)

are discussed that demonstrate its reliability and accuracy.

Quality assurance and quality control practices used in assay methods are

presented. New nondestructive assay developments such as neutron assay imaging

are also discussed.

1.3.7.A3-5


2.0 ASSAY OVERVIEW

• This section describes the general features of nondestructive assay (NDA) and

destructive assay methods used by the DOE site contractors to determine the TRU

content of their bulk CH-TRU waste.

ANSI N15.20 (Ref. 7.1) defines NDA to be "The observation of spontaneous or

stimulated nuclear radiations, interpreted to estimate the content of one or

more nuclides of interest in the item assayed, without affecting the physical

or chemical form of the material.

active assay. Assay based on the observation of radiation(s) induced

by irradiation from an external source.

passive assay. Assay based on the observation of naturally occurring

or spontaneous nuclear radiation(s)."

Destructive assay refers to chemical analysis in which a sample aliquot is

removed from the item (after assuring homogenization of the batch) to be assayed

and prepared for alpha and/or gamma counting.

The NRC in NRC Regulatory Guide 5.11 (Ref. 7.2) describes the applicable NDA

passive measurements: "Radiations attributable to alpha particle decay, to

gamma-ray transitions following alpha and beta particle decay, and to spontaneous

fission have served as the basis for practical passive NDA measurements."

Gamma rays, X-rays, and/or neutrons, as well as other subatomic particles, are

emitted by the various TRU isotopes as they undergo de-excitation to their

respective ground states or more stable energy levels. NDA techniques based on

detection of each emitted radiation have been developed and utilized for CH-TRU

bulk-waste assay.

1.3.7.A3-6


The passive gamma, passive neutron coincidence counting, radiochemical, and

calorimetric methods are techniques which are described by the American Society

for Testing of Materials (ASTM), American National Standards Institute (ANSI),

Nuclear Regulatory Commission (NRC) , and American Society of Mechanical Engineers

(ASME) standards, guidelines, and/or regulations. These documents (Refs. 7.1-

7.10) provide information to the user for proper implementation of these

techniques.

Characteristics of any assay measurement include precision, bias, and detection

limit. Proper calibration methods must also be employed to reduce or eliminate

the bias of the assay results. Definitions of each of the above terms are given

below and were obtained from Ref. 7.11. Examples for each discussed assay method

are .found in the appropriate sections.

(1) Precision: A generic term used to describe the dispersion of a set of

measured values, (also referred to as "random" or "statistical error")

(2) Bias: A persistent positive or negative deviation of the method average

from the correct value or accepted reference value, (also referred to as

"constant" or "systematic error")

(3) Detection limit: A stated limiting value which designates the lowest

concentration or mass that can be estimated or determined with confidence

and which is specific to the analytical procedure used.

(4) Calibration: The determination of the values of the significant parameters

by comparison with values indicated by a reference instrument or by a set

of reference standards.

Estimates of precision can be calculated by standard error propagation techniques

(Ref. 7.10). Radioactive decay is random and described by Poisson statistics.

1.3.7.A3-7


For Poisson statistics, the variance in measuring N events in a-detector is equal

to N. (The standard deviation is the square root of the variance.)

The precision of a nondestructive assay measurement is not strongly related to

the measurement item's adherence to ideal matrix and nuclide density assumptions.

For destructive assay methods (e.g., radiochemical), which require sampling, the

precision of repeat measurements of a single item will be strongly influenced

by a lack of adherence to ideal nuclide density assumptions. However, for SGS

systems, measurement bias depends primarily on the adherence of the measurement

item to the assumptions of small particle size and homogeneity. Negative assay

bias (reported value less than actual value) will be encountered, for example,

when the nuclide is present in lumps that attenuate their own radiation to a

greater extent than the surrounding material (self-absorption). Radiochemical

methods that dissolve material samples will not be affected by lumps. Matrix

and nuclide density have no effect on calorimeter measurements. Techniques used

to correct for self-absorption effects are used in PNCC and PAN assay techniques

(Ref. 7.3, 7.12, and 7.13). Positive assay bias (reported value greater than

actual value) can occur when, for example, system multiplication effects become

severe at high-Pu sample loadings during PNCC measurements. Typical techniques

used to control this interference are: (1) equivalent reference standards used

for calibration, or (2) use of source addition techniques (Ref. 7.14).

Of course, to obtain precise assay measurements count-rate-dependent losses

resulting from phenomena such as pulse pileup and analyzer dead-time

characteristics must be monitored and corrected. These corrections are not

required for calorimeter measurements. Analyzer dead-time is defined as that

period of time, which is unique to the analyzer, in which it is unable to accept

input signals for analysis. This correction is accomplished through the use of

a combination of electronic modules, and/or radioactive sources, and/or computer

algorithms (which have been obtained through the assay of calibration standards) '.

1.3.7.A3-8

NuPac TRUPACT-II SAB. Rev. 0, February 1989

The uncertainty (w) in a measurement is the composite error, including both the

precision and bias of the measurement. The uncertainty in a quantity f that is

a function of n independent variables x? is given by:

w -nS w,-

1/2

where w. is the uncertainty in the variable x{.

Assay item preparation is generally limited to good waste/scrap segregation

practices that produce relatively homogeneous items that are required for any

successful waste/inventory management and assay scheme, regardless of the

measurement method used.

1.3.7.A3-9


3.0 ' ASSAY "METHODS DESCRIPTIONS. CHARACTERISTICS. AND LIMITATIONS

This section describes the various assay methods, presents their characteristics

(precision, bias, and detection limits), and discusses their limitations and

applicability to assay of CH.-TRU wastes. Assay methods discussed include

calorimetry, passive gamma assay (e.g., SGS), radiochemical methods, passive

neutron coincidence counting (PNCC), and passive-active neutron assay (PAN).

3.1 Calorimetrv

Calorimetry has been used for many years in the nuclear weapons program for

product assay of WG Pu. Many of the NDA Pu standards in use throughout the DOE

complex have been characterized by calorimetry. A large number of standard

radiochemical and gravimetric assay comparisons have been performed to verify

the accuracy of calorimetric assay measurements.

Basically, calorimeters measure the heat flow out of contained small packages.

Experimental difficulties grow exponentially with package size, so this method

is generally used only with small packages, a few liters in volume at most.

The primary heat release in WG Pu materials is from alpha and beta decay, and

with a knowledge of isotopic composition, precise Pu mass values are readily

obtained from virtually any physical or chemical form of Pu material, without

knowledge of precise compound stoichiometry (e.g., Pu to oxygen ratio).

The kinetic energy of the emitted alpha or beta particle and the energy of the

emitted alpha or beta particle and the recoil nucleus is transformed into heat,

together with some fraction of the gamma ray energies and conversion electrons

that may be emitted by the excited daughter nucleus in lowering its energy to

a more stable nuclear configuration. The electrons and low-energy gamma rays

are totally absorbed while the higher-energy gamma rays which may escape from

1.3.7.A3-10


the calorimeter chamber comprise less than 0.01Z of the total decay energy.

Thus, most of the energy associated with these transitions of the daughter

nucleus to ground state, as well as all of the energy associated with the alpha

particle and recoil nucleus, is absorbed within the calorimeter.

The calorimeter method measures the total decay heat produced by an item. The

relative isotopic abundances of the Pu and Am nuclides in the mixture and the

values of decay heat per gram for each nuclide are used to calculate the average

decay heat per gram of nuclide mixture. The total measured decay heat divided

by the average decay heat per gram yields the grams of nuclide mixture.

ANSI N-15.22 (Ref. 7.8) describes the calorimetry procedure and equipment used

for the assay technique. This standard method is used in DOE facilities for

calorimetry calibrations, setup, and as the guide to operational measurements.

3.2 Passive Gamma Assay

3.2.1 Segmented Gamma Scanning (SGS)

High Resolution (Hyperpure Germanium (HPGe), Lithium-drifted Germanium Ge(Li)),

Transmission and Count-Rate Corrected Assays

3.2.1.1 Overview

The first NDA measurements of TRU isotopes using passive gamma rays were

performed by DOE contractor personnel more than 40 years ago. Passive gamma-

ray NDA of TRU isotopes is a highly developed technology, and is also the most

widely implemented. The introduction more than 20 years ago of germanium solid

state detectors, and the subsequent incorporation of these detectors into

computer-based detection packages has improved the resolution and reliability

1.3.7.A3-11


of these systems. Commercial manufacturers of these systems include Canberra

of Meriden, CT and Nuclear Data of Schaumberg, IL.

The number of individual TRU isotopes or their daughters that can be assayed

with SGS is large; U-233, Pu-238, Pu-239, Np-237, Am-241, Am-243 being among

the more common ones. In each case one or more characteristic moderate-to-high

energy gamma rays are emitted in sufficient intensity to permit estimates of

quantities in low-to-moderate density waste packages as large as 208 L drums.

The recommended (ASTM C 853-82) experimental arrangement for SGS assays is shown

in Figure 1. This figure displays the essential elements required for SGS assays

of TRU isotopes in any package size.

To minimize assay errors due to axial inhomogeneities, assays are performed in

segments along a waste package's vertical axis. The effects of radial

inhomogeneities are minimized by rotating the drum during the assay measurement.

The detector is shielded in such a manner" so as to allow the waste drum to be

scanned in segments (typically 10 to 20 segments).

Gamma-ray attenuation is measured for each segment with a transmission source

in the indicated geometry of Figure 1. The energy of this source is selected

to match that of the gamma-ray line(s) being measured [e.g., ORNL uses a mixed

152Eu/154Eu oxide source for its large array of gamma-emitting radioisotopes (50

keV to 1600 keV) and ^Se is typically used for Pu-239 assays].

State-of-the-art counting electronics allow dynamic counting rate ranges of

factors of 10* to 105 or more, with dead-time corrections measured with a second

small, low-energy source positioned near the detector. Waste packages are

automatically rotated about their vertical axes and cycled through the required

segment heights with standardized, computer-controlled electronic motors and

precision mechanical turntable/elevator hardware. SGS hardware-software packages

are commercially available from several manufacturers.

1.3.7.A3-12


3ukgraund Detector Shield Count Ratt AXIS OF ROTATIONShield \ and Collimator Correction /

' Sourca J _" Tungsten

Shutter

*

Germanium Cadmium \LeadDetector Absorber AbsorberCrystal

a) Eievatiari View

J_SAMPLE / Transmission

[ / /Source

Detector Center-Line

Low Z Pedesul

Turntable andElevator Mechanism

BackgroundShield

TransmissionSourceShield

b) Plan View

Figure 1 Schematic Arrangement for Segmented Gamma-Ray Scanning (SGS) System

1 . 3 . 7 . A 3 - 1 3


3.2.1.2 Applicability to.CH-TRU Wastes

A prime factor which determines applicability of SGS to perform assay

measurements of CH-TRU waste packages is gamma-ray transmission through the

package. Other factors effecting- assay measurements include particle self-

absorption and nonhoraogeneity of the assayed item ("lumping"). Two conditions

must be met to optimize assay results. First, the particles containing the

nuclide must be small to minimize self-absorption of emitted gamma radiation.

Second, the mixture of material within a package segment must be reasonably

uniform in order to apply an attenuation correction factor, computed from a

single measurement of item transmission through the segment. Variations in item

composition and density within a vertical segment lead to indeterminate errors.

Such variations should be minimized through strict scrap and waste segregation

procedures.

A combination of analytical error analysis (Ref. 7.3) and experimental usage over

many years has determined that transmission factors greater than or equal to 0.52

are required for accurate SGS assays. The physical density of a waste package

that this requirement defines depends greatly on the package size [i.e., the

radial distance from the gamma-emitting source(s) to detector] and the energy

of the gamma rays used for the analysis. Four-liter packages having densities

as high as 2 g/cm3 meet the criterion, whereas 208 L packages are limited to

densities of 0.5 g/cm3 or less. To assure compliance with these limits, all

current SGS software packages include an automatic warning indicating when the

transmission factor for any sector falls below the prescribed limiting value.

The routine practice at some sites is to calculate a contribution from that

sector based on the lower-limit transmission (e.g., 0.5%).

The reason for maintaining the assay value, rather than disregarding it, is

because most SGS transmission failures occur for only one sector out of the 10

to 20 drum sectors assayed. This sector, on the average, contains only a small

fraction of the waste drum's total TRU inventory of gamma-emitting isotopes.

1.3.7.A3-14


On the average, estimating the TRU content for one or two failed segments in this

fashion results in only a small overall assay error for the waste drum. Other

sites (e.g., Hanford) flag such drums for management decision on whether the item

should be disassembled, examined, and repackaged, or reassayed on a neutron-

sensing assay instrument, which is less sensitive to density variations. Since

the SGS assay value for a transmission failure is truly a lower limit, and as

is discussed in detail in Section 3.4, passive neutron assays generally provide

upper limit assay values (especially for WG Pu); the combination of SGS and

passive neutron assay methods tends to bracket the actual assay value.

Some matrix forms are inherently unsuitable for SGS analysis. Such forms may

contain 'lumps' of nuclide, that is, nuclides contained in small volumes of

matrix material having a localized density substantially different from the bulk

density of the rest of the container. The dimensions of nuclide particles that

constitute a lump vary with the energy of the emitted radiation used for the

analytical measurement. The possible magnitude of the problem may be estimated

from the following example of attenuating effects. A plutonium metal sphere 0.02

cm in diameter will absorb approximately 4% of the 414 keV, Pu-239 gamma rays

produced. Approximately 15% of the 186 keV gamma rays of U-235 will be absorbed

in a uranium metal sphere of the same diameter.

As mentioned previously, another condition that will cause measurement problems

is presented by containers with several irregular regions, highly variable in

density, that prevent the calculation of a valid attenuation correction based

on the transmission measurement. In case of such a condition, an analytical

method less sensitive to nuclide and matrix densities, such as passive neutron

coincidence counting (PNCC), should be employed.

Careful inspection of the transmission and nuclide peak areas for each segment

may provide clues when a measurement should be suspect. Sudden, discontinuous

changes in the transmission values for adjacent segments or high nuclide count

1.3.7.A3-15


values for isolated segments are examples of signals indicating possible problem

items. .

3.2.1.3 Instrument Calibration. Standards Preparation, and Implementation

The recommended DOE facility standard guide used for preparation of SGS standards

is ANSI N-15.35 (Ref. 7.4). The recommended DOE facility standard for

implementation of these standards is ANSI N-15.20 (Ref. 7.1). ANSI N-15.20

calls for the preparation of the calibration material using intimate and stable

mixtures of the TRU isotope with matrix material and for preparation of a

suitable number of calibration standards to cover the anticipated isotopic

concentration region of interest (ROI). In the case of Pu-239, this range is

5 to 200g for 208 L drums.

When establishing a calibration curve for the SGS instrument, at least two

calibration standards are used for each content code. One standards drum

contains a TRU isotopic mass near the low end of the ROI (e.g. , 5g Pu-239) while

the other contains a TRU isotopic mass near the high end of the ROI (e.g., 200g

Pu-239). Both drums contain waste stream matrix mixtures and densities designed

to simulate the waste streams. Some sites use more than the two drums described

above to ensure a proper calibration factor. Other sites measurement control

programs require standards drums to be measured by the assay instrument multiple

times, both before and after each measurement session.

Acceptable ranges for calibration data are specified in the operating procedures

(e.g., ORNL accepts a variance of +/- 5%). If assay measurement falls outside

the acceptable range, no production assay measurements are performed until the

issue has* been resolved by a designated NDA expert.

1.3.7.A3-16

"—^5^"


3.2.1.4 Operator Training Requirements and Practices

Present-day commercial SGS systems, such as the Canberra and Nuclear Data models,

are . highly-automated, computer-based systems. The instruments are

computer-controlled using relatively interactive ("user-friendly") software.

Only trained personnel are allowed to operate the assay equipment. Personnel

are qualified according to DOE Order 5480.5 (Ref. 7.15).

Each site provides a specialized training program for NDA instrument operators.

The operators are directed and/or assisted by a designated site NDA expert.

Expertise is attained by education and experience.

3.2.1.5. Assay Procedures

The assay procedures cited in ASTM C 853-82, "Standard Test Methods for

Nondestructive Assay of Special Nuclear Materials Contained in Scrap and Waste"

(Ref. 7.3) are recommended for use at all DOE facilities. These procedures

stress usage of proper calibration standards, proper equipment and equipment

setup, avoidance of practices (such as misalignment of the waste package) known

to result in inaccurate assays, attention to proper record keeping and equipment

maintenance, and safe operation of the equipment.

3.2.1.6. Assay Precision. Bias, and Detection Limit

Assay precision is generally taken to mean measurement repeatability. In the

case of typical SGS systems, operated and calibrated according to the recommended

procedures, repeatability of results is limited only by statistical counting

errors. Counting statistics, in turn, are a strong function of TRU isotopic

loading a'nd counting time.

Reference 7.10 discusses SGS precision and bias in detail. Some of that

discussion follows. The precision of a SGS assay is a function of the precision

1.3.7.A3-17


of the peak areas measured for each segment. The precision of an assay is

normally better when the following conditions can be obtained:

Increased count time

- High transmission source activity

Low attenuation for gamma radiation in the energy range of interest

Typical SGS assay precisions for low-density wastes are listed in Table 4.

Certain matrices, such as graphite molds and cemented insulation, whose densities

are above the prescribed SGS-applicability limit of 0.5 g/cm3 for 208 liter

packages, and drum handling (homogeneity of calibration standards may be

jeopardized) can have a deleterious effect on assay precision (Refs. 7.3).

Table 4. Typical SGS Assay Precisions for WGPu in Low-DensityWastes Contained in 208-L Drum

WG Pu (z) Precision

1 +/" 100%

10 +/" 10%

30 +/- 3%

(Table 4 values reflect the assumption that the guidelines given inASTWL C 853-82 were adhered to in acquiring the data.)

The precision of an assay performed by SGS is not strongly related to the

measurement item's adherence to ideal matrix and nuclide density assumptions.

However, .measurement bias depends primarily on the adherence of the measurement

item to the assumptions of small particle size and homogeneity. Negative bias

will be encountered when the nuclide is present in lumps that attenuate their

own radiation to a greater extent than the surrounding material. Positive bias

can result from low transmission items with over-corrected end effects. Items

containing high-density areas may be biased, either high or low or be unbiased,

1.3.7.A3-18


depending on the relative position of the high density area and the nuclide of

interest. In the majority of measurement situations, however, it is expected

that when biases exist, measurement results will be lower than true values.

Several SGS and destructive assay comparison studies of several waste forms

indicate SGS assay biases of 10% or less, at the 95Z confidence level (Ref.

7.16). Assay biases for low-density waste matrices contained in 208-L drum

packages are 5% or less. In small package applications (based on numerous

Safeguards and Nuclear Materials Accounting applications) SGS assay biases of

less than 0.5% have been reported (Ref. 7.16). The basic assay formalism

associated with the SGS method, that is, transmission correction and the use of

small segments, is conducive to very accurate results if recommended procedures

are. correctly followed. Heterogeneous matrices and isotopic concentration

variations can have a severe and unpredictable effect on assay bias for a given

waste drum.

Typical SGS assay biases for two types of wastes are summarized in Table 5

(Ref. 7.16).

»Table 5. Typical SGS Assay Biases

Waste Type Biases

Heterogeneous salts 10%a

Low-density (e.g., 5%combustibles)

a Based upon assay of a number of 4-L waste packages prior to placingin a 208-L drum.

1.3.7.A3-19


(Table 5 values reflect the assumption that the guidelines given in

ASTM C 853-82 were adhered to in acquiring the data.)

SGS assay limit of detection for typical applicable wastes and standard counting

times in current routine use in DOE facilities (30 min or less per assay

measurement) is about 5g WG Pu. This is based on 30% assay precision. Usually

SGS assays are only performed on 208 L drums when screening indicates lOg or more

WG Pu to be present.

3.2.1.7 SGS Assay Results Comparisons

Calorimetric assay measurements of heterogeneous molten salt residues have

provided a total assay value for the Pu and Am, as an NDA comparison (referee)

technique for an assessment of SGS assay of RFP molten salts (Ref. 7.16).

Reliable interpretation of the calorimetry measurements depended on an accurate

determination of the Am/Pu ratio, since the relative amount of heat produced by

the Am in these samples was typically 50% or more.

Gamma-ray spectral isotopic analysis coupled with calorimetry was performed at

Mound on nine cans of molten salt, which were subsequently returned to RFP for

dissolution and solution quantification. Results of the Mound measurements show

a relative standard deviation range from 0.032% to 0.50% for Pu values and 0.23%

to 0.39% for Am values. No biases or statistical differences between pairs of

measurements were noted.

3.2.2 Nal (low-resolution') Assays

Both transmission-corrected and transmission-uncorrected Nal assay units are

used in DOE facilities. The transmission-uncorrected units are used, for

example, at RFP for low-density wastes containing up to 20g Pu.

1.3.7.A3-20


The Nal transmission-corrected assay instruments are special function units,

servicing isolated waste streams producing a single type of waste under generally

constant conditions. Typically, these Nal units consist of 5 individual

collimated Nal detectors mounted at different heights that view a rotating drum,

effecting a 5 segment assay. Transmission source geometry is similar to that

shown in Figure 1. The pertinent NDA guidelines outlined in ASTM C 853-82 are

applied to these systems in a fashion similar to that described for SGS units.

A two-window pulse height analysis is performed to correct for Am-241 and fission

product interferences, and software indicators flag segments containing excessive

Am or fission product amounts.

Calibration standards are carefully chosen for the particular waste stream being

monitored and assays are performed in a fashion similar to SGS assays. These

units produce, on the average, reliable results as determined by numerous

quantitative comparisons with SGS and PAN assays of the same waste drums

(Ref. 7.17). Analytical studies of assay biases for these systems indicate

+/-102 levels of bias. This has been verified with SGS and PAN comparisons of

a large number of drums assayed with these Nal systems (Ref. 7.17). It should

also be pointed out that assay standards practices and procedures are adhered

to in accordance with ASTM C 853-82 and ANSI N-15.35. Duplicate assays with SGS

or PAN (performed at the certification facility) provide additional assurance

that proper TRU assay values are being generated with these systems.

3.3 Radiochemical Methods

The basic application of radiochemical methods in TRU waste assays is in

quantifying radioisotopic content of process liquid or sludge waste forms.

Before final drying or cementation, a batch of process sludge is contained in

a single large tank. The sludge is then mixed for a sufficient period of time

to assure a homogenous mixture. This mixture is then sampled at several points

while circulating and the samples subjected to routine radiochemical processing

and analysis (precipitation and separation followed by alpha and/or gamma

spectrometry). The prepared aliquot samples are assayed in a standard alpha

1.3.7.A3-21


spectrometer. In'the cases of higher-activity sludges, these samples are assayed

using another method (e.g., passive gamma-ray spectroscopy). Assays of samples

obtained from individual sludge drums may also be performed.

Using standard analyses, the individual TRU isotopic activities are determined;

Pu-239, total Pu (WG Pu), and Am-241. These aliquot sample activities are then

used to determine the original batch TRU activity, on an individual isotopic

basis. By proper accounting for any volume reduction or increase produced in

the drying or cementation process, these batch activities can then be used to

determine an individual 208 L drum's specific Pu and Am content, simply by

weighing the drum and accounting for the amount of original batch sludge that

was deposited in that particular drum. Accurate final drum assays depend upon

following the procedure outlined in a careful manner, with maintenance of a

homogeneous mixture during both the crucial sampling and drum filling stages.

Standard test methods (e.g., ASTM C 696-80, ASTM C 697-86, and ASTM C 759-79,

References 7.5, 7.6, and 7.7, respectively) describe the radiochemical standard

aliquot sampling procedures used in the DOE facilities. Assay standards are

prepared and used as indicated in the standard test methods. Sampling, weighing

of the sample and handling the sample are done under conditions which assure that

the sample is representative of the lot or batch. A lot or batch is defined as

any quantity of solution that is uniform in isotopic, chemical, and physical

characteristics by virtue of having been mixed in such a manner as to be

thoroughly homogeneous. All containers used for a lot or batch are positively

identified as containing material from a particular homogeneous solution.

Assay biases at the final filled-drum stage are difficult to estimate, since

they depend primarily on the maintenance of homogeneous mixtures during the

sampling," drying/cementing, and final drum-filling stages.

1.3.7.A3-22


3.4 Passive Neutron Coincidence Counting (PNCO Assays

3.4.1 Overview

PNCC assays include assays conducted on small packages which are summed to give

the final reported assay value for a waste container, and the passive portion

of .the PAN assay system, which is discussed in detail in section 3.5.

PNCC method for determination of Pu assay in product materials has been used

for Safeguards verification purposes within the DOE complex for more than 20

years. PNCC has also been applied to the assay of TRU-bearing wastes and scraps

for many years (Ref. 7.1, sub-sections 20-28). In addition, the USNRC

Regulatory Guide 5.11 (Ref. 7.2) describes NDA techniques acceptable to the NRC

for assay of wastes and scraps, which includes PNCC. These standards and

regulatory guides are used to ensure proper application by the DOE of PNCC to

scrap and waste assay. In fact, DOE laboratories, primarily LANL, have been

largely responsible for the development of PNCC as a reliable assay technique

for TRU wastes, as well as for scraps and product.

The prototypical PNCC is comprised of a high-efficiency neutron detector large

enough to accommodate the waste package of interest. It operates by detecting

the number of time-correlated neutrons being emitted spontaneously by the assay

item. In fission events, bursts of 2,3,4,5,... neutrons are emitted

simultaneously, and the detection of two or more of these in time coincidence

serves to identify the original fission event within the material being measured.

Specialized counting electronics (e.g., shift register) have been devised to

accomplish and record these measurements. These are discussed in detail in Ref.

7.3.

Any TRU isotope that undergoes spontaneous fission at a measurable rate can be

quantified by PNCC. Comprising this category are the even isotopes of Pu, Cm,

and Cf. Most commonly within the DOE complex, the different grades of Pu

[weapons grade (WG), reactor grades (RG) of different isotopic compositions,

1.3.7.A3-23


heat source grade (HSG)] are quantified by coincidence counting of the included

mixture of even isotopes of Pu; predominantly Pu-240 for WG and RG, and Pu-238

for HSG. Thus, with knowledge of the Pu isotopics, the observed coincidence

rates can be interpreted to yield total Pu mass.

3.4.2 Applicability to CH-TRU Wastes

The primary requirement for application of PNCC to CH-TRU waste assay is

knowledge of the included isotopics, since normally the quantity of interest is

the total elemental mass (i.e., total Pu mass) rather than the even isotope

masses only. In addition, the wastes should not include mixed-element

spontaneous fission emitters. For instance, it is undesirable to have Cm and

Cf isotopes present in the same assay item containing Pu isotopes. Most DOE

CH-TRU wastes contain Pu even-isotope spontaneous fission emitters. A typical

average WG Pu isotope mix contains 5.8% Pu-240. Pu-240 is responsible for more

than 99% of coincidence neutrons detected in typical WG Pu wastes.

3.4.3 Instrument Calibration. Standards Preparation, and Implementation

Calibration of PNCC instruments, similar to SGS, is obtained by establishing a

curve of instrument response versus isotopic mass (Refs. 7.3 and 7.1). A minimum

of four calibration points are obtained over the mass range of interest using

standards that are representative of the materials being measured. Within each

content code, or waste category, the variation due to interference effects within

the boundaries defining the limits of that category is measured. Calibration

standards are constructed using containers identical to those for the scrap or

waste, with contents that are representative of the range of matrix conditions

to be encountered. It is not recommended to extrapolate beyond the calibration

range established during instrument calibration. Encapsulated Cf-252 sources',

such as those used at ORNL for passive PAN calibration, are available to be used

for PNCC calibration purposes.

1.3.7.A3-24


Acceptable ranges for calibration data are specified in the operating procedures.

If assay measurement values fall outside the acceptable range, no production

assay measurements are performed until the issue has been resolved. Operators

contact a designated NDA expert for consultation.

3.4.4 Operator Training Requirements and Practices

Present-day commercial PNCC systems, such as the JOMAR or National Nuclear

models, are highly-automated, computer-based systems. The instruments are

computer-controlled using relatively interactive ("user-friendly") software.

Only trained personnel are allowed to operate the assay equipment. Personnel

are.qualified according to DOE Order 5480.5 (Ref. 7.15).

Each site provides a specialized training program for NDA instrument operators.

The operators are directed and/or assisted by a designated site NDA expert.

Expertise is attained by education and experience.

3.4.5 Assay Procedures

The assay procedures cited in ASTM C 853-82, "Standard Test Methods for

Nondestructive Assay of Special Nuclear Materials Contained in Scrap and Waste"

(Ref. 7.3) are recommended for use at all DOE facilities. These procedures

stress usage of proper calibration standards, proper equipment and equipment

setup, avoidance of practices (such as misalignment of the waste package) known

to result in inaccurate assays, attention to proper record keeping and equipment

maintenance, and safe operation of the equipment.

3.4.6 Assay Precision. Bias, and Limit of Detection

Most PNCC units are used to assay small packages (4-L size) which are then

placed into larger waste containers, such as 208-L drums. Assuming proper

1.3.7.A3-25


administrative control of drum filling, this practice greatly-reduces the assay

errors associated with all PNCC performance effects except counting statistics

and isotopics. Additional errors caused by self-multiplication or system dead-

time are significant only when strong neutron sources are present.

Sources of assay biases and measurement uncertainties include:

(a) Counting statistics: A significant source of error at both extremes of

count rate. Measurement uncertainty can be significant at very low count

rates for all assay conditions. For every high count rates, when the rate

is due primarily to a strong (alpha, n) internal source or induced fissions,

assay bias is increased.

(b) Isotopics: For WG Pu waste assay biases produced by systematically

incorrect actual Pu isotopics are 32 or less, based on use of historic

average WG Pu isotopics. Uncertainties in the measurement of the isotopic

composition, generally considered to be unbiased, increase the uncertainty

of the assay value.

(c) Self-multiplication (or induced fissions): Generally a problem when fairly

large Pu amounts are present in conjunction with strong (alpha, n) sources

within the same drum (measurement value greater than actual value) . This

phenomenon is a source of potential bias producing uncertainty in the assay

value. Multiplication effects should not be significant when TRU gram

loadings are low and waste volumes are large.

(d) System dead-time: A problem when strong neutron sources are present,

(measurement value is less than actual value). This phenomenon is a source

of potential bias with an associated uncertainty.

(e) Calibration: Typically, assay uncertainties produced by uncertainties in

calibration are 3% or less.

1.3.7.A3-26


(f) Matrix effects: Matrix effects include neutron poisons (e.g., boron,

cadmium) and other neutron emitters [species that spontaneous fission or

have strong (alpha, n) reactions] and neutron moderators. See reference

7.12 for a discussion of moderator error estimation techniques.

Table 6 provides a summary of typical PNCC assay error contributions for low-

density waste forms.

Table 6 Summary of Typical PNCC Assay Error ContributionsFor Low-Density Waste Forms

Error Contribution

Counting statistics

Self-multiplication

System dead-time

Isotopics

Calibration

Matrix (low-density)

UG Pu

1 g10 g30 g

100 g

Typical Errors

+/- 50%+/- 10%+/" 5%+/- 3%

+/" 5"

+/- 3%

+/- 3%

+/- 3%

+/- 5-20%

Estimates of PNCC assay uncertainty can be calculated by standard error

propagation techniques from the various bias contribution variances. The grams

of plutonium calculated by PNCC is a function of net passive coincidence neutron

count rate (gross neutron coincidence count rate minus accidental neutron

coincidence rate) (SIGP), self-multiplication (MULT), system dead time (SYSDT),

isotopics (ISOP), calibration (CALIBP), and moderator index (MI).

1.3.7.A3-27


For thirty grams of plutonium, the uncertainty in the 30 grams of plutonium is

given by (see Section 2.0):

w - [f(SIGP)2 + f(MULT)2 + f(SYSDT)2 + f(ISOP)2 + f(CALIBP)2 + f(MI)2]1/2

- [(0.05)2 + (0.05)2 + (0.03)2 + (0.03)2 + (0.03)2 + (0.20)2]1/2

- 0.218 or 21.8%

The passive mass assay value reported by the PNCC assay algorithm would then

be:

Passive mass (grams) - 30.00 +/* 6-55

Reference 7.18, MLM-3009, Table 5, p. 33, shows overall neutron production rates

for several of the more common TRU isotopes and several of the more common

matrices which produce significant (alpha, n) reactions. For example, WG Pu,

which has an average alpha energy of 5.15 MeV, produces approximately 2

n/s/mCi-alpha in an oxide matrix and 215 n/s/mCi-alpha in a fluoride matrix.

Pu-238 and Am-241, which have an average alpha particle energy of 5.5 MeV,

produce approximately 2.5 n/s/mCi-alpha in an oxide matrix and approximately 310

n/s/mCi-alpha in a fluoride matrix. These values are representative of pure

chemicals and alloys. Neutron production rates for waste materials will be less,

since the TRU isotypes are more widely dispersed and the alpha particles are less

likely to encounter a productive target.

The more usual (alpha, n) reactions which can cause passive assay concerns

consist of normal WG Pu in which a sizeable fraction of the Pu is chemically

bound to either fluorides or bound in a salt mixture containing aluminum or

magnesium. Typically, metal oxide or nitrate forms of TRU isotopes (which

produce approximately 0.7-2 n/s/mCi-alpha) present no problems for passive

neutron assays (both passive PAN and PNCC). In practice, rates ranging to 20

1.3.7.A3-28


n/s/tnCi-alpha do not decrease passive assay precisions drastically as long as

the alpha sources present are only those associated with WG or RG Pu. However,

waste streams that include additional Am-241 can be difficult to assay passively

even if the TRU chemical form is the oxide.

3.5 Passive-Active Neutron (PAN) Assay Systems

•3.5.1 Overview

PAN assay systems consist of two independent assay units; passive and active

neutron. The combination of passive and active neutron assays within a common

system provides a unique set of information.

The passive assay portion of the PAN method described below is an adaptation of

the PNCC method using "self-measurement" matrix corrections. Two complete

passive assay detection systems are maintained with separate counting

electronics. Two detection systems are used separately or in combination

depending upon the neutron count rate. The passive coincidence measurement

provides quantitative information on even isotopes present in the waste

container, such as Pu-240. The passive singles neutron count rate (difference

between total neutron rate and that due to spontaneous fission events) provides

semi-quantitative information on alpha particle emitters present in the waste

container, such as Am-241.. The active assay provides quantitative information

on the Pu-239 and other fissile isotope constituents. See reference 7.19 and

7.25 for a more complete description of the system.

For WG Pu, the passive coincidence and active assays provide independent total

Pu assay- values. This fact has been extremely important in verifying the

accuracy or determining the bias of the PAN assay measurement technique, as

presented in reference 7.12. This formalism has also been verified by extensive

comparisons of both passive and active neutron assays with SGS (see reference

10).

1.3.7.A3-29

NuPac TRUPACT-II SAR ' Rev. 0, February 1989

PAN assay systems have been developed for both drums and boxes (see section 5.0

for discussion of box PAN assay systems). For these relatively large waste

containers, effects of the waste material (matrix) on the neutron signals

observed cannot be neglected.

3.5.2 Ins trumentation

A basic cross-sectional view of a typical LANL PAN detection system, showing

the schematic "interwoven" layout of the two distinct types of neutron detection

packages (bare He-3 and cadmium (Cd)-shielded He-3 detector tubes), is shown in

Figure 2.

3.5.2.1 Passive Assay Portion

The passive portion of the PAN assay system utilizes the two types of detection

packages to:

(a) determine a moderator index (MI) used to determine a correction to the

assay calculation to account for the matrix characteristics, and

(b) optimize counting statistics depending on the actual relative neutron

sources encountered.

For low count-rate waste containers all counts detected by the neutron detector

packages are summed to yield the lowest assay limit of detection possible. All

detector count rates (acquired by both bare and shielded detectors) are summed

electronically to obtain a "System Totals" neutron detection efficiency of

approximately 12%.

1.3.7.A3-30


NEUTRON GENERATOR

BARE^e DETECTOR PACKAGE

CADMIUM SHIELDED 3He DETECTOR PACKAGE

BORATED POLYETHYLENE

GRAPHITE

POLYETHYLENE

Cross-seccional views of the second-generation assay chambershow che layout and relative positions of both shielded andbare 3He detector packages.

Figure 2. Schematic PAN System Layout.

1.3.7.A3-31


For waste containers with higher Pu loadings (e.g., 100 g or more) coupled with

strong (alpha, n) backgrounds, the cadmium-shielded detectors are summed

independently, and the "Shielded Totals" count rate is formed with a resulting

neutron detection efficiency of 2.9%. However, this detection package possesses

a much faster "die-away" or "neutron-collection" time, approximately six times

faster than that of the slower "Systems Totals", that is approximately 15

microseconds. At low count rates the slower collection time is of no consequence

[i.e., accidental coincidences due to (alpha, n) reactions are small] and, thus,

the Systems Totals provides not only a more sensitive but also statistically more

precise passive assay measurement.

At higher count rates the faster die-away time of the Shielded Totals gains a

higher.precision than the less specific count rate (Systems Totals). As a

consequence, at high neutron count rates the Shielded Totals Coincidence rate

is used to obtain the more precise passive assay measurement value.

The cross-over count rate (i.e., the count rate at which the assay measurement

value obtained by the Shielded Totals supplants the Systems Totals) has been

experimentally determined to be approximately 2000 counts per second, cps,

(Systems Total count rate) and this value is used in the assay algorithm. There

is a substantial range in which either Systems Coincidence or Shielded

Coincidence rates both provide precise assay values. Many data comparisons have

been performed in this cross-over region to verify the self-consistency between

the two coincidence measurements (Ref. 7.17).

3.5.2.2 Active Assay Portion

The active portion of PAN systems performs a high-sensitivity, pulsed thermal

neutron interrogation assay of waste drums. As shown schematically in Figure 2

a small 14-Mev neutron generator placed within the assay chamber between the

waste drum and moderating walls provides short pulses (5-10 microseconds) of

1.3.7.A3-32


high-energy interrogating neutrons. In approximately 0.5 ms all original fast

neutrons in this interrogating pulse have been thermalized by multiple collisions

with the graphite and polyethylene walls and moderating materials within the

waste drum. This "thermalized interrogating pulse" persists (T1/2 about 400

microseconds) for some time, during which induced fissions within the waste drum

are produced, primarily in Pu-239 or other fissile isotopes. These events, in

turn, result in prompt-fission, spectrum neutrons being emitted by each

fissioning nucleus.

The cadmium-shielded detection packages have been designed to reject an external

thermal neutron flux to 1 part in 107, but to respond sensitively to fission

spectrum neutrons. The summed shielded detector packages shown in Fig. 2 detect

about 3% of all induced fission events that are produced within typical waste

drums.

An additional measurement feature not shown in Figure 2, but discussed at length

in reference 7.12, is the set of thermal flux monitors, one cadmium-shielded and

collimated and the other bare, that are also positioned inside the assay chamber

between the waste drum and the moderating walls. As discussed at length in

reference 7.12, the ratio of these flux monitors is highly sensitive to the

neutron absorption characteristics of the waste drum contents. This ratio is

used to form a drum "Absorption Index" (AI) (see section 3.5.3.).

3.5.3 PAN Assay Matrix Corrections

Two types of matrix effects can interfere with the active neutron measurements:

absorption and moderation (Ref. 7.12). The absorption effects occur almost

entirely -as an attenuation of the interrogating thermal neutrons, caused by the

presence of various neutron poisons within the waste matrix (e.g., boron,'

cadmium, chlorine, etc.).

1.3.7.A3-33

NuPac TRUPAGT-II SAR Rev. 0, February 1989

Moderation' effects occur at two.stages of the measurement. The original burst

of 14-Mev neutrons can be moderated to a considerable extent during passage

through the waste matrix. Generally, this results in a larger thermal neutron

interrogation flux than would have been produced in the absence of matrix. After

the interrogation flux has produced fission reactions within the waste matrix,

the same moderating materials can attenuate the prompt-fission signal neutrons

resulting in a decrease in observed response relative to the no-matrix case.

This attenuation of signal fission-neutrons also is the primary matrix effect

for the passive measurement.

The approach to matrix corrections has been to base corrections on measured

quantities determined as adjuncts to the primary active and passive TRU assay

measurements. The systematic matrix correction algorithm is based on an analytic

fit to assay measurements obtained for different positions of the source within

a matrix drum. These analytic fits then provide estimates of uncertainty for

the active and passive assay data.

The absorption matrix correction approach used by the PAN systems employs a

ratio of an unshielded in-chamber flux monitor to a cadmium-collimated, in-

chamber flux monitor (designated the barrel flux monitor). This ratio is termed

the absorber index (AI). The barrel flux monitor detects those neutrons which

have undergone drum matrix interactions. The ratio of the monitors strongly

reflects the neutronic properties of the matrix.

Absorption Index (AI) - [flux monitor response (0.7-4.7 ms)]/ (1)

[barrel flux monitor response (0.7-4.7 ms)]

The moderator index depends upon the responses of the two detection systems

(cadmium-shielded and bare) to moderated neutrons. The shielded detectors are

insensitive to thermal neutrons, while the bare detectors are very sensitive to

the thermal neutron flux. In turn, the thermalized fraction depends very

strongly on the moderator density of the matrix. To use this relationship in

1.3.7.A3-34


obtaining matrix correction factors, the ratio is normalized so that a value of

zero is obtained when no moderator is present and, in addition, a small

correction is made to account for self-absorption effects.

The general equation for a moderator index is given in Eq.(2).

Moderator Index (MI) - {1 - [(shielded totals)/(system totals)]/AQ} (2)

x {A1 + A2 x ln(AI)}

The term within the first set of brackets is the basic raw spectral data and

the term within the second set of brackets is the correction term for matrix

absorption effects. The same MI values are used for both active and passive

matrix corrections.

In order to obtain data to construct analytical models of matrix correction

factors, nineteen simulated waste matrices were fabricated (Ref. 7.12) and active

and passive calibration standards were placed in known locations throughout the

waste matrix drums. Both active and passive assay matrix response measurements

were obtained as a function of location (radius, r, and height, z) of the

standards. The resulting matrix response values varied smoothly as a function

of r and z. These studies determined that the systematic effects are due only

to gross neutron absorber and moderator amounts and are independent of the actual

nature of the materials themselves. That is, a drum filled with Rashig rings

(borated glass) produces the same responses as a drum filled with vermiculite

mixed with an equally absorbing amount of borax.

Most of the observed distributions have been found to fit a power law as given

in equation 3:

y - A + BrN " (3)

where A, B, and N are the fit parameters and r is the drum radius.

1.3.7.A3-35

NuPac TRUPACT-II SAR ' Rev. 0, February 1989

Volume-weighted average values were calculated using this equation, representing

the most probable measurement result for either a totally uniform or a totally

random distribution of source-material within the matrix.

The matrix correction factor (MCFA) for an active assay measurement is a function

of the AI and MI.

MCFA - MCFA(AI) x MCFA(MI) (4)

The MCFA values were fit to the power law (equation 3) as a function of their

AI values for the 19 simulated waste matrices. The following set of equations

describing the absorption portion of the active assay matrix correction factor

were obtained for one PAN system:

MCFA(AI) - 1.00 (5)

for the AI less than or equal to 2.72, and

MCFA(AI) - 0.54x(AI)0'612 (6)

for the AI greater than 2.72.

The moderator portion, MCFA(MI), of the active assay matrix correction factor

is obtained by dividing the total measured MCFA values by the calculated MCFA(AI)

values obtained in equations (5) or (6).

The analytic representation of these data is thus of the form

MCFA(MI) - 1.00, (7)

1.3.7.A3-36


for the MI less than or equal to 0.40,

MCFA(MI) - 0.483exp[1.817(MI)] (8)

for the MI greater than 0.40.

The passive neutron matrix corrections are determined by systematic drum matrix

measurements in a manner similar to the active measurements discussed previously.

The passive matrix correction factors, MCFP, are a strong function of the MI.

The MCFP analytic fits to the four independent quantities measured during a

passive assay scan are given below.

MCFP(system totals) - 1.00, (9)

for the MI less than or equal to 0.355,

MCFP(system totals) - -0.16 + 3.28(MI), (10)

for the MI greater than 0.355,

MCFP(shielded totals) - 1/[1 - MI], (11)

MCFP(system coincidence) - [(0.5967)/(l - MI) + 0.4187]2, ' (12)

MCFP(shielded coincidence) - [(0.8902)/(l - MI) + 0.2337]2. (13)

The matrix correction equations given above or variations thereof are contained

in the present PAN assay systems algorithms used throughout the DOE. Some sites'

perform additional matrix-dependent corrections to the assay results as discussed

in section 3.5.9.

1.3.7.A3-37


Figure 3 shows the "Moderator Index" (Ref. 7.12 for detailed discussion of the

MI) obtained with mock matrix drums containing various hydrogen densities

spanning the region of interest for general CH-TRU wastes. As can be seen, the

MI varies smoothly with average hydrogen density within a 208-L drum. Sludges

display one of the .highest average "hydrogen densities of any CH-TRU waste form,

with correspondingly high Mi's (0.4 to 0.8). Lightly moderating matrices, such

as combustibles, have Mi's falling typically in the 0.1 to 0.3 region, and

miscellaneous metals matrices, which generally contain no moderating materials,

have measured Mi's near 0.0.

Figure 4 shows the actual moderator correction factor (MCF) data (Ref. 7.12)

for the passive neutron coincidence counting portion of the PAN systems as

implemented at INEL, Hanford, and SRP. The MCF value is the multiplicative

factor required to normalize a given matrix measurement to the empty drum level

of PNCC sensitivity. As can be seen, the MCF value varies smoothly as a function

of the MI; Fig. 4 can be used to estimate typical MCF values. For example,

(a) Miscellaneous metals, MCF - 1.0 (i.e. , same sensitivity as with empty drum),

(b) Combustibles matrix, MCF - 1.35, and

(c) Sludges, MCF = 3.6.

The MCF range observed for a 3000 CH-TRU drum sludge assay campaign at INEL was

1.8 to 10.0.

When performing PNCC assays of highly-moderating matrices, such as sludges,

measurement of a MCF value is essential for accurate assay results to be

obtained.- A "calibration" based on a "typical" sludge drum would result in

assay errors of hundreds of per cent for some drums because of the large hydrogen

density variations observed.

1.3.7.A3-38

NuPac TRUPACT-II SARRev. 0, February 1989

0.0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1.0

EQUIVALENT WATER DENSITY

Figure 3. Moderator Index Measured for PAN Systems Using the Detector Ratio

Method

1.3.7.A3-39


3.0

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1/(1 - MODERATOR INDEX)

Figure 4. Use of the Moderator Index to Determine Passive Neutron CoincidenceMatrix Correction Factors for a PAN System.

1.3.7.A3-40

NuPac TRUPACT-II SAR • Rev. 0, February 1989

Figures 5a and 5b show plots of the systematic active assay correction factors.

As can be seen in Figures 5a and 5b some waste materials require no matrix

correction (relative to a standard response measured in an empty drum). Examples

of these waste matrices are cellulose-based combustibles, graphite molds and

scarfings, aluminum scrap, dry-to-moderately-wet dirt, and silica.

3.5.4 Assay Algorithm and Data Acquisition Svstem

All PAN units utilize a similar assay algorithm. At present, all drum- size

units are equipped with IBM/PC-based data acquisition systems as described in

reference 7.20. The system operating program (NEUT) controls all data

acquisition and contains the assay algorithm.

Each data acquisition consists of sequential active and passive neutron assays,

preceded by a user interactive initialization stage in which drum identification,

content code information, drum weight, etc. can be entered from the PC keyboard,

from a bar code reader, or from an RS-232 port by direct interaction with a

site's data management computer. The weight of the drum's contents is used in

calculating the nCi/g assay value which differentiates between TRU and non-TRU

wastes. The content code input is used to flag difficult-to-assay matrices or

"special case" drums (see section 3.5.11.). All data input modes are in current

use at the various sites. However obtained, that information becomes part of

the permanent record stored with the TRU assay and matrix measurement data.

Modifications and upgrades have been performed at various times since the

original algorithm was written in 1982. The development and upgrade of hardware

and software continue to the present time (Refs. 7.21, 7.12, 7.22, 7.23). The

software 'revisions can be readily accomplished within the Fortran software

framework of NEUT.

1.3.7.A3-41


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Figure 5. PAN System Active Assay Matrix Correction Factors Measured at Hanford,INEL, and SRP with a Set of 20 Standard Matrix Drums.

1.3.7.A3-42


Measured data as well as all initialization information, date and time stamp

from the internal PC clock/calendar, and final analyzed results are archived.

An on-line hard copy printout of the assay parameters and results is also

generated. All background and calibration measurements are routinely recorded

and archived in the same fashion as normal assays. Thus, a continuous and

traceable record of all data is maintained. Most sites, in fact, are maintaining

this complete set of data in interactive databases (e.g., Lotus 1,2,3 or

dBASE III) , wherein all single-run assay data occupies one row in a single

spreadsheet or data base record. In some cases, 10,000 such records exist at

a site (e.g., INEL). This data archiving technique is an extremely important

development as such extensive waste drum assay data bases have not been developed

previously in the NDA field, much less put into such readily accessible form.

This greatly facilitates internal consistency checks and comparisons of large

numbers of individual drum assays results obtained with different assay

techniques.

Reactor grade, RG, Pu (i.e., Pu containing high Pu-240 content) is accommodated

within the same PAN algorithm as is used for WG Pu. The PAN operator is queried

before each assay as to whether the drum contains WG Pu and, if not, what is the

correct Pu-240 percentage for that waste drum. Once the Pu-240 percentage is

entered the algorithm automatically corrects both passive and active assays for

the different Pu isotopics.

The basic Pu algorithm cannot, however, directly accommodate Pu-238 or heat

source grade Pu. Those sites assaying HSG Pu waste exercise a special algorithm

option in their Main Menus which allows for analysis of the basic passive and

active data in terms of HSG Pu. If selected this option:

(a) Interprets the active assay results in terms of a Pu isotopic mix consisting

of 182 Pu-239 and 82% Pu-238. Since only the Pu-239 fraction is fissile,'

total Pu mass is obtained by dividing the active assay result by the factor

0.18.

1.3.7.A3-43


(b) Interprets the passive assay data similarly. Pu-238 undergoes spontaneous

fission at a rate of 2600 n/s/g (for comparison, the Pu-240 rate is 990

n/s/g). Thus, passive coincidence counts can be used to obtain an estimate

of Pu-238 mass.

(c) As in all cases the Systems Totals Passive Singles rate can be used,

assuming oxide as the dominant chemical form, to estimate a total alpha

particle emission rate. This estimate can then be used to calculate the

Pu-238 mass.

The SRP possesses most of the DOE's Pu-238 waste, and is currently evaluating

their Pu-238 algorithm.

3.5.5 Applicability to CH-TRU Wastes

The PAN systematic matrix correction factors discussed in reference 7.12 and

section 3.5.3, and now implemented in all drum-size PAN units enables the

quantitative assay of virtually all DOE wastes presently packaged in 208-L drums.

At present, these six implemented PAN units have been used to assay,

collectively, about 20,000 CH-TRU waste drums at the various sites, including

2,000 drum assays performed with the mobile drum unit at NTS and LLNL.

3.5.6 Instrument Calibration. Standards Preparation, and Implementation

Calibration of PAN units includes a thorough initial calibration after

fabrication and routine calibrations using secondary standards.

Reference 7.12 lists the standards used in all the present PAN units, for which

all passive and active calibration standards have NBS-traceable or NBS-

ref erenceable origins. Absolute and matrix standards calibrations were conducted

of the PAN unit. The PAN units were then each provided a set of secondary

standards (placed in "Pink Drums" for conspicuous identification) consisting of

1.3.7.A3-44


standard, NBS-referenceable Cf-252 passive assay and U-235 active assay

materials. A baseline reference data set for both passive and active assays was

obtained for each PAN unit with these unique "Pink Drum" standards, and each unit

has subsequently performed standard Pink Drum assays prior to each set of PAN

waste drum assays.

A typical set of these standards measurements performed with the INEL PAN unit

and extending for almost a three year period is shown in Figure 6. The

individual passive and active standards measurements fall well within a +/- 5%

window, with no measurable systematic drift during the three year operational

history. Reference 7.12 lists the corresponding Pink Drum measurements for

Hanford, SRP, and the mobile drum unit. All display the same basic stability

of response.

3.5.7 Operator Training Requirements and Practices

The present generation of PAN units are highly-automated, computer-based systems.

The instruments are computer-controlled using relatively interactive ("user-

friendly") software. Only trained personnel are allowed to operate the assay

equipment. Personnel are qualified according to DOE Order 5480.5 (Ref. 7.15).

Standardized training requirements and guidelines for all DOE assay operators

are based upon such already-existing industry standard training requirements,

such as SNT-TC-1A. Each site provides a specialized training program for NDA

instrument operators. The operators are directed and/or assisted by a designated

site NDA expert. Expertise is attained by education and experience.

1.3.7.A3-45


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Figure 6. INEL PAN Standard Measurements (Pink Drum) Performed Over a Three YearPeriod. Top Graph Shows Passive Standard and Bottom Graph ShowsActive standard. Dashed Lines Indicate a +/-5% Measurement ErrorBand About Expected Standards Assay Values.

1.3.7.A3-46


3.5.8 Assay Procedures

The PAN assay systems are comparatively recent additions (approximately six

years) to NDA instrumentation and, as a consequence, ASTM and ANSI standards

have not, as yet, been developed for PAN assay systems. Active assay techniques

have been used for approximately 18 years, but the 14-Mev thermalized neutron

assay (active portion of PAN) is comparatively recent. Of course, the passive

coincidence portion of PAN is similar to the PNCC assay technique and, therefore,

PNCC ASTM, ANSI, and NRC standard practices and guidelines are followed for that

portion of the PAN system.

All PAN standard operating procedures instruct operators to acquire a background

and a "Pink Drum" data set before any assays on waste containers are performed.

These data sets are checked for consistency and, if the results fall outside a

predetermined (e.g., +/-l'0%) acceptance window, remedial action is taken. The

remedial action can include a repetition of the background and/or standards

measurements. If the second measurement is successful, general assays can

resume. If the problem persists qualified personnel are contacted to "debug"

the system. No CH-TRU waste drum assays can resume until the problem is

satisfactorily resolved. If the background or standards measurement is outside

the acceptance window, the diagnostic generally assumed is that a hardware

problem exists.

The assay procedure for PAN units equipped with the IBM/PC data acquisition

system is relatively straightforward. An operator inserts a waste drum into

the PAN unit and enters all drum identification information via an interactive

dialogue (PAN assay system software, NEUT, prompts the operator for the specific

information). Once NEUT has checked the information for correct format, the

assay record and programmable electronics hardware are properly indexed, gates

set, etc. NEUT then sends a message to the operator (via the CRT screen) that

the system is ready to begin an assay.

1.3.7.A3-47


At this point the operator presses one button, the start sequence button on the

MA165C neutron generator controller unit. This initiates the PAN active assay.

At the conclusion of the active assay, NEUT automatically records all data and

initiates the PAN passive assay. At the conclusion of the PAN passive assay,

all data is recorded, analyzed and printed out for immediate inspection. The

operator is then informed (via the CRT Screen) that the system is ready to

perform another assay.

3.5.9 Assay Precision. Bias, and Limit of Detection

The PAN assay algorithm contains a calculation of the measurement uncertainty

(Ref. 7.12) that combines statistical uncertainties and estimated systematic

biases based on the measured matrix correction factor. For a generally

heterogenous matrix and TRU materials distribution, the larger the indicated

matrix correction, the larger the expected assay uncertainty. These values are

reported with the actual assay values, for both passive and active neutron

assays. For many well-characterized waste streams a typical value for the

estimated uncertainty (not including the statistical contribution to the error)

is 20%.

When a systematic matrix correction formalism is used, the corresponding

systematic uncertainty in the passive assay measurement can be decreased to 5%

or less. This low an uncertainty is valid for dry, combustible, low-hydrogen

content waste, such as general laboratory waste. The passive assay value

uncertainty is calculated as for PNCC. The algorithm used in the passive

coincidence portion of the PAN units calculates a composite assay uncertainty

based on combining all the effects discussed above, which becomes part of the

permanent archived assay record.

The active assay value uncertainty estimate includes a systematic bias

contribution, which is a function of the matrix correction factor (AI and MI).

For reasonably uniform TRU isotope distributions (such as are found in sludges),

1.3.7.A3-48


AI measurements indicate assay uncertainties of +/- 10%. For nonuniform TRU

isotope distributions, the uncertainty is a function of the magnitude of the

matrix correction factor (Ref. 7.12). That is, the larger the matrix correction

factor, the larger is the associated assay uncertainty. The effects on the assay

measurement of concentrated TRU activity in different drum locations have been

calculated and plotted as a function of the total matrix correction factor. For

example, a matrix correction factor of approximately five yields a corresponding

uncertainty of 50% in the assay measurement.

Extensive comparisons have been performed for passive and active neutron assays

of the same drum, for a great variety of matrix types (e.g., four types of

sludges, job-control wastes, combustibles, graphite scarfings, miscellaneous

metals, tantalum crucibles, glassware, molten salts, filter media, dirt, and

others.) Some of these comparisons are shown in the figures of this appendix

and are discussed in references 7.16 and 7.17). It should be noted that the

matrix corrections applied to passive and active assays for a given type of

matrix (except where no matrix corrections are necessary) are quite distinct.

Thus, there is a very low probability of obtaining agreement by accident between

active and passive neutron assays for wastes with significant moderator and

absorber amounts. If one obtains agreement, both independent PAN assay

techniques are considered to yield unbiased assay measurement values.

The assay limit of detection for the active neutron portion of the PAN unit can

be as low as a few mg of Pu-239 placed anywhere within a typical 208-L waste

drum.

3.5.10 PAN Assay Results Comparisons

Comparisons of PAN assay results with SGS or radiochemical assay methods have

been performed. The PAN assays, both passive and active, have been compared with

SGS and radiochemistry assay results for (a) matrices requiring little or no

matrix corrections, such as graphite molds and general laboratory wastes, and

(b) homogeneous matrices (e.g., sludges).

1.3.7.A3-49


Two papers (Ref. 7.13 and 7.17) detail several comparisons of PAN and SGS assay

measurements. Reference 7.13 includes a total data base of some 5000 assays

performed at NTS, LLNL, Hanford, INEL, LANL, and SRP. The drum assay and matrix

correction formalism presented in reference 7.12 was extensively evaluated for

all types of waste matrices and waste content codes being generated within the

DOE complex. Reference 7.17 encompasses an even larger data base, but is

confined to INEL PAN assays and comparisons with RFP SGS assays.

Figures 7a, 7b, and 7c show a recent PAN/SGS comparison performed by LANL

personnel (reference 11) using a mobile PAN drum-sized unit. The data was

acquired at LLNL from assays of a set of some 200, 208-L, WG Pu waste drums

consisting of general laboratory wastes (e.g., glassware, cellulosics, plastics,

etc.) that had been assayed using the LLNL SGS unit. Figures 7a, 7b, and 7c show

the PAN passive neutron, PAN active neutron, and SGS assay measurements

comparisons. A statistical analysis of this data set indicates systematic

agreement between both PAN neutron data sets and the SGS assay results at the

5% level, (95% confidence level). Figure 8 shows a plot of similar waste stream

assays performed with the Hanfbrd PAN system, comparing passive and active

neutron assay values for a set of 400 waste drums.

Figures 9a and 9b show a set of over 300 "graphite molds" matrix waste drums

(RG Pu) assayed with the PAN unit at INEL and also with an SGS unit located at

the RFP. A statistical analysis of this data set indicates systematic agreement

of all three independent assay methods to within 10% on the average, at the 95%

confidence level.

Quantitative comparisons between radiochemical Pu (WG) and Am-241 determinations

and active PAN have been performed at "the INEL facility (SWEPP) (Ref. 7.13).

These comparison studies of approximately 1300 drums of RFP aqueous sludges

comprise more than 100 individual sludge batches. These sludges contain low Pu

and relatively high Am concentrations. The results of these comparisons are

shown in Figure 10.

1.3.7.A3-50


13 T

4 6 8 10 12SGS Mass g(Pu)

4 6 8SGS Mass g(Pu)

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Figure 7.' Comparison Assay Data Sets of 200 LLNL TRU Waste Drums. Waste Matrixis Non-Segregated General Laboratory Waste. Top Graph Shows PassiveNeutron (PAN) Compared to SGS. Middle Graph Shows Active Neutron(PAN) Compared to SGS. Bottom Graph Shows Comparison of the TwoIndependent PAN Passive Neutron Assay Systems. Straight Line (X-Y)Depicts Ideal Case, Where Assay Techniques Shown Yield Identical AssayMeasurement Results.

1.3.7.A3-51


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Figure 8. Comparison of 300 Hanford CH-TRU Waste Drum Assays Performed with thePAN System, Passive Neutron Compared to Active Neutron. Straight Line(X-Y) Depicts Ideal Case, Where Assay Techniques Shown Yield IdenticalAssay Measurement Results.

1.3.7.A3-52


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Figure 9. Assay Comparisons of a Set of 300 RFP CH-TRU Waste Drums (GraphiteMolds Matrix) Showing RFP SGS System Assays Compared to INEL PAN UnitPassive Neutron Assays (Top) and INEL PAN Active Neutron and PassiveNeutron Comparisons (Bottom). Straight Lines (X=Y) Depict Ideal Case,Where Assay Techniques Shown Yield Identical Assay MeasurementResults.

1.3.7.A3-53


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Figure 10. Batch Average Pu Assays of 1300 Sludge Drums Performed at RFPCompared to PAN Assays of the Same Drums Done at INEL. Straight Lineis a Linear Least Squares Fit to Data.

1.3.7.A3-54


The batch-average drum Pu assay as determined at RFP was compared to the same

quantity as measured with the INEL PAN unit. The indicated straight line shows

the relationship RFP Pu Mass - PAN Pu Mass. A statistical analysis of this same

data indicates a best straight-line fit relationship of

RFP Pu Mass - -0.06 + 0.85*PAN Pu Mass,

with a correlation factor of 0.51. The calculated correlation factor indicates

that 51% of the variance does fit a straight line. The 0.85 constant indicates

an approximately 15% average measurement bias between the two assay techniques.

The individual PAN systematic measurement error (discussed in detail in reference

7.12) for a typical sludge drum measurement is approximately 10% on average, due

primarily to possible systematic errors in the matrix correction formalism. That

error estimate is based on the observed standard deviation found for mockup

sludge drum calibrations. PAN systems are able to measure the total uncorrelated

neutrons, but cannot measure the individual contributions from mixed,

uncorrelated sources of neutrons [e.g., (alpha, n) reactions due to Cm-244 and

Am-241]. The contributions from Am-241, for example, can be calculated (obtained•

from passive single neutron rate) if no other (alpha, n) sources are present in

the waste.

The two assay measurement techniques appear to agree within probable systematic

errors associated with each technique (assuming a +/- 10% systematic error for

both techniques) . Other similar individual sludge drum NDA comparisons (passive

and active PAN neutron assays of high-Pu, low-Am activity sludge drums (Ref.

7.13) verify the basic PAN matrix corrections at the +/-10% level.

Reference 7.17 details additional such comparisons for a great variety of matrix

types, including heterogeneous matrices and highly neutron-absorbing matrices.'

In all cases the PAN assays are highly correlated with SGS assays and with each

other. Comparison studies reported in reference 7.17 indicate a slightly better

agreement between PAN and radiochemistry assay methods than the 10-15% discussed

above.

1.3.7.A3-55


3.5.11 Choice of Passive or Active Assay Value

Two assay values, a "passive" mass and an "active" mass, are obtained with each

PAN assay. A choice of the values to be reported as the PAN assay value is

performed within the assay algorithm by an analytical evaluation of assay

conditions. Content-code-specific algorithm options are developed by a site

based upon an evaluation by the assay data reviewer or expert of the individual

site's waste content codes.

When specific content code or matrix information is available that indicates,

for example, that passive assay results are more reliable than active assay

results for that content code, then the algorithm selects the passive assay

results when that content code is entered via the PAN operating software, NEUT.

Similar overrides involve the statistical accuracy of a measurement. For

example, if the passive measurement has a large error associated with it, then

the active measurement is selected.

The default PAN assay algorithm is known to underestimate the absorption

correction factor for various waste streams (e.g., tantalum crucibles). This

phenomenon is due to neutron tunneling effects caused by the stacked arrangement

of the crucibles. A correction factor based on the RFP SGS assay values is used

to adjust the PAN assay values.

A similar method is used at INEL to modify the moderator index (MI) obtained

during the assay of sludge drums. For sludge drums having low Pu content, an

average MI is used in the assay value calculations. The average MI value used

was obtained from previous assays of the same waste stream containing higher Pu

loadings and, thus, higher count rates and improved counting statistics.

One algorithim option which is used by Hanford is based on experimental results

indicating that fissile self-absorption effects in several of their content codes

were small for Pu mass loadings of 10 g or less, but increasingly probable for

successively higher Pu mass loadings. It also took into account the experimental

fact that Pu loadings in excess of 10 g led to statistically more precise passive

1.3.7.A3-56


assay measurements. Of course, the exact "cross-over" point between using the

PAN active or passive assay measurement depends on several experimental factors

such as waste form, (alpha, n) source strength, isotopics, etc.

INEL has modified their PAN algorithim option to reflect the phenomenon that

sufficiently strong (alpha, n) sources cause experimental measurement problems

for the PAN passive assay measurement, rendering it biased high. If the passive

assay error bar exceeds 40 g Pu, then the option selects the self-absorption

corrected active assay value. This algorithim option also reflects the

development of a fissile self-absorption model that is applied to all PAN active

assays. This model is purely empirical and assumes that the probability of

fissile self-absorption is a monotonically increasing function of the total

fissile loading in a waste drum. The function is determined from evaluations

of large sets of actual CH-TRU waste drum assays employing PAN active and passive

neutron and SGS measurements (Ref. 7.12). The derived functions, however,

produce large error bars at the higher fissile mass values. In the "near 200

g Pu" regime, for example, the self-absorption corrected active assays may have

relative errors of 40%.

PAN assay results may also be evaluated by the site NBA expert when special-case

waste drums are encountered. The various factors which determine what is a

"special case" drum include nominal assay values for CH-TRU waste drums near or

in excess of the 200 g criticality limit and a lack of tag isotopics information

(e.g., Pu-240 content). Both of these situations preclude proper interpretation

of PAN assay measurement data.

Approximately one out of 500 RFP CH-TRU waste drums assayed with the INEL PAN

system are assigned an assay value near or in excess of the 200 g criticality

limit. Typically, these drums contain very high (alpha, n) radioisotopic

sources, which due to the high numbers of neutrons present, results in poof

passive PAN coincidence measurements. The large numbers of neutrons

(approximately 104 neutrons per second or greater) decrease the signal to noise

ratio to below acceptable limits. Content codes 409 and 411 display this

characteristic and also contain "lumps" of Pu which invalidates the active

1.3.7.A3-57


neutron assay. -A panel of 3 or 4 INEL experts examines and compares all assay

and RTR information available, including a critical evaluation of the "tag" assay

values. After a consensus of the expert panel is achieved a suitable resolution

is proposed and the appropriate action taken. This action may include acceptance

of the less than 200 g tag value or the waste drum is returned to the waste

generator for repackaging. Both of these actions have occurred.

Hanford waste drum, tag values obtained by using an SGS and the certification or

check of the SGS assays with a PAN unit indicate assay values near or in excess

of the 200 g criticality limit. The approach used at Hanford is basically the

same one employed at INEL, but a two-expert panel is used to evaluate the

available data. The return-to-generator option is used frequently with drums

having assay values near the 200 g limit.

Invalid or unavailable isotopics information occurred when a small set of PNL

waste drums were assayed at Hanford using a PAN unit. These drums contained

Cm-244 but this isotope was not originally listed on the accompanying data

sheets. The PAN assay results indicated very high passive coincidence assay

values. Many of the assay values were well in excess of the nominal 200 g limit.

Experts resolved the problem through direct dialogues with the waste generator

who, subsequently, agreed to provide the proper isotopic information which would

then allow these drums to be properly assayed.

1.3.7.A3-58


4.0 FISSILE MATERIAL CONTENT AND DECAY HEAT VALUE CALCULATIONS

The fissile or fissionable isotope content for CH-TRU waste containers is

expressed in terms of Pu-239 fissile gram equivalents (FGE), as defined in

ANSI/ANS-8.15-1981 (Ref. 7.24). The standard lists the maximum subcritical mass

limits for fissile and non-fissile actinide nuclides. (U-233 and U-235 are

considered equivalent to Pu-239). The fissile material (e.g., Pu-239, U-235,

etc.) or fissionable content of a CH-TRU waste container may be obtained by using

any of the previously described assay techniques. However to obtain the number

of Pu-239 FGE, present, the isotopic composition contained in the waste form must

be known.

The PNCC assay method detects the coincident neutrons emitted by the even- number

TRU isotopes (e.g., Pu-240 and Cm-244). (See section 3.4 for a detailed

discussion of the PNCC' assay technique.) Once the coincident neutron

(spontaneous fission) emitters have been quantified and the proper correction

factors applied (e.g., self multiplication, system dead-time, etc.), one can

calculate the fissile material content by applying the known isotopic ratios.

After the mass of each TRU isotope present has been determined, the decay heat

can be calculated by multiplying the mass of each isotope by the decay heat per

gram of the isotope. For the general case of alpha and beta decay, the decay

heat per gram can be calculated by using Eq. 10 in reference 7.8 (Refs. 7.8 and

7.25).

The original PAN system algorithm used a very conservative means to estimate a

waste drum's decay heat. First, it was assumed that only the drum's alpha

particle inventory was responsible for the waste drum's decay heating. Second,

the conservative assumption was made that all neutrons detected were produced

by (alpha, n) reactions within the drum's waste matrix. In the original

algorithm this assumption led to the value of 98,000,000 MeV of alpha decay heat

energy being associated with each neutron emitted. This estimate is conservative

for two reasons:

1.3.7.A3-59


.(1) In all cases of WG Pu, a fraction of the neutrons detected are produced by

Pu-240 or other spontaneous fission reactions, with a much lower decay-

heat-per-neutron factor. Typically each spontaneous fission neutron is

associated with approximately 100 MeV of decay heat energy.

(2) In many waste packages the actual (alpha, n) production factor is higher

than the conservative value (2 n/s/mCi-alpha) used in the PAN algorithm.

Production factors as high as 14 n/s/mCi-alpha were observed for RFP CH-

TRU waste drums when assayed with the INEL PAN system (Ref. 7.26). For the

various fluoride, Mg, Al salt, and typical sludge matrices values as high

as 100 n/s/mCi-alpha are observed (Ref. 7.26).

To obtain more realistic estimates of the decay heat value for sludge wastes

and those containing fluorides, INEL has used an experimentally determined

(alpha, n) production factor. For example, an experimentally determined

production factor is being used for RFP aqueous sludges (Ref. 7.26). This

derived production factor has been incorporated into the PAN assay algorithm.

Hanford and SRP use an (alpha, n) production factor based on given Pu. isotopics

contained in the waste drum. The modified PAN assay algorithm assumes that the

entire 241 mass (i.e., sum of Pu-241 and Am-241) is in the form of Am-241. This

assumption is very conservative since Am-241 produces approximately 35 times the

decay heating associated with Pu-241.

ORNL uses a PAN decay heat calculation algorithm based upon the subtraction of

the spontaneous fission neutron portion (passive neutron coincidence) from the

observed total neutron count rate.

Error bars associated with the decay heat calculation propagate in the same

fashion as that described for PAN Pu mass calculation (see section 3.5.9.).

The administrative classification of 200 mrem/h for container surface dose rate

imposed for CH-TRU waste automatically limits the decay heat contributions from

beta- and gamma-emitting radioisotopes.

1.3.7.A3-60


To calculate the fission product inventories required to generate a surface dose

rate of 200 mr/h one can assume the total external surface dose rate is produced

by fission products (the beta-and gamma-emitters) . Any TRU radioisotopes present

are conservatively assumed not to contribute to the observed external dose rate.

One also assumes that the short-lived fission products have decayed sufficiently

to be of no concern. This is a conservative assumption since most waste drums

are more than one year old. Consequently, only a small number of "pure" beta-

emitters would then be present (e.g., Sr-90). The remaining predominant

radioisotopes producing the heat-generating radiation other than Sr-90 would then

be Cs-137 and Co-60.

Consider a CH-TRU waste drum containing 100 kg of medium atomic number wastes.

Assume the maximum allowable container external dose rate of 200 mrem/h and that

this rate is attributable solely to beta- and gamma-emitters (conservative

assumption). Also, assume that the radioisotope inventory of this waste drum

is a mixture of the dominant long-lived fission product species Sr-90 and Cs-

137 For long-term decay 6.5% Cs-137 and 2.22 Sr-90 are produced by reactor

fissions (Ref. 7.27). This fission product mixture produces a decay heating of

0.91 MeV, 502 derived from beta emission and 50% derived from gamma-ray emission

(Ref. 7.28).

If one also makes the following conservative assumptions: (1) that only the

Cs-137 0.67 MeV gamma ray exits the waste drum, (2) the Cs-137 is located in the

center of the waste drum, and (3) the mass attenuation factor is very

conservative (i.e. , 0.74 cm2/g) • one can calculate the curies required to produce

an container external dose rate of 200 mrem/h. These assumptions and

calculations yield an estimate of 0.25 Ci of Cs-137 present in the example waste

drum. Using the isotopic ratio discussed earlier, one calculates a beta and

gamma decay heating of 0.001 watt. This decay heating value is equivalent to

that produced by the alpha emissions of 0.4 g WG Pu.

1.3.7.A3-61


Detailed gamma-ray spectral studies of ORNL and RFP CH-TRU waste drums

(Refs. 7.19, 7.29, and 7.26) indicate that the detected gamma rays were

attributable to TRU isotopes and not to fission products. Consequently, from

the calculations above and the small quantities of observed fission products the

contributions to the waste drum decay heat from beta- and gamma-emitters is

negligible.

1.3.7.A3-62


5.0 NEW ASSAY DEVELOPMENTS

In keeping with the DOE's general policy of upgrading NDA hardware, software

and procedures, the DOE continues to support a vigorous NDA development program,

with specific support of TRU waste assay-related instrumentation. One recent

example of -this development is a significantly improved digital processing unit

(upgraded shift register) for use with PNCC units, that greatly reduces basic

dead-time limitations associated with older PNCC units. The improvement

considerably lowers processing errors. These newer processors are now either

installed or in the process of being installed in all DOE facilities using PNCC

assay techniques.

Another development nearing the implementation phase in support of the PAN assay

method is "neutron imaging" of 208 L waste drums (Ref. 7.30). With very little

change in the basic PAN hardware, 208 L waste drum assay data may be acquired

in a fashion which allows it to be processed with existing imaging software

similar to that used in medical CAT scans. Neutron imaging has already been

demonstrated using an upgraded DOE PAN unit (Ref. 7.30), the Mobile Drum System.

Improved matrix and self-absorption corrections to the basic assay data will then»

be possible using the neutron imaging technique. Accurate determination of the

TRU material distribution should result in considerably improved assay accuracies

since it is known that incomplete matrix and self-absorption corrections are a

major source of assay errors.

PAN box assay systems have been used in the DOE complex for several years. The

earlier versions are discussed in several of the references (7.21, 7.13, and

7.22) which include assay campaigns at NTS and RFP. Recently, some improvements

in the box PAN systems have been made and implemented at some sites. The new

box assay'unit at INEL and the Mobile System box assay unit are examples of this

implemented PAN technology. The improvements have been in four areas:

1.3.7.A3-63


(a) Improved matrix corrections made possible by development and deployment of

a "moving" shielded flux monitor that samples the emergent interrogating

flux along the entire length of a box,

(b) Improved detection uniformity throughout the box volume made possible by

a better detector layout,

(c) Smaller matrix inhomogeneity assay errors, achieved by implementation of

a source location algorithm, which effects matrix corrections correlated

with the location of the TRU material is based on crude neutron imaging,

and

(d) Implementation of IBM/PC data acquisition/controller hardware and software.

Improvement (a) is similar to the shielded flux monitor described in section

3.5 that is used in the drum-size PAN. These new developments are being

implemented simultaneously with the institution of a new standard waste box

(SWB) which has been optimized for shipment in the TRUPACT II.

1.3.7.A3-64

NuPac TRUPACT-II SAR - Rev. 0, February 1989

6.0 QUALITY ASSURANCE fOA") AND QUALITY CONTROL (PC) PRACTICES

Quality assurance (QA) and quality control (QC) are important functions at all

DOE facilities, especially in special nuclear materials (SNM) accounting areas.

The eighteen elements of NQA-1 are being implemented throughout the DOE

(Reference 7.15). TRU waste assay QA and QC practices adhere to the guidelines

established in NQA-1. Some of these practices have been discussed previously

in relationship to other subjects. A brief listing of some of these QA/QC

practices in common use to assay newly-generated and stored CH-TRU waste

throughout the DOE complex are:

(1) Expert NDA personnel check of NDA records before assay values assigned to

the waste package (NQA-1 Elements 1. Organization and 10. Inspection).

(The functions of these site NDA reviewers or experts have been discussed

previously in sections 3.2, 3.4, and 3.5),

(2) Assay standards used before and after waste assays (NQA-1 Element 12.

Control of Measuring and Test Equipment). Detailed discussions of

instrument calibration and calibrations standards preparation and

implementation have been discussed in detail for each assay method in

sections 3.2.1.3, 3.4.3, and 3.5.6),

(3) Automatic electronic system gain stabilization. (Element 3. Design

Control). For each assay method manufacturer's system instructions and

site operating procedures suggest to the assay system operators the correct

settings for proper system gain and stabilization,

(4) Automatic software flagging and tagging for special-case waste containers

(NQA-1 Element 5. Instructions, Procedures, and Drawings). For example,

less than 0.5% transmission segments are flagged for SGS assay measurements'

and special-case waste matrices are flagged by the computer algorithm in

PAN assay measurements,

1.3.7.A3-65


(5) Administrative tagging of failed segment assays as "LOWER LIMITS" (NQA-1

Element 15. Control of Nonconforming Items). This procedure is performed

for those SGS waste drums which qualify.

(6) Original segment assay and calibration data archived for future reference

(NQA-1 Elements 6. Document Control and 17. Quality Assurance Records).

PAN assay algorithm automatically archives all calibration data acquired

(see section 3.5.6),

(7) Detailed data sheets are prepared for each drum and accompany the drum

through all NDA, RTR, etc. stations. Some sites (e.g., INEL) use automated,

computerized data sheets and bar codes (NQA-1 Element 9. Control of

Processes),

(8) Most sites' SGS assays verified by one or two other independent NDA

measurements (at the certification facility). For example, RFP SGS assays

are verified by the INEL PAN passive and active assay measurements (NQA-1

Elements 9. Control of Processes and 18. Audits),

(9) Non-conforming drums returned for repackaging (NQA-1 Element 15. Control

of Nonconforming Items). When a drum is found to contain non-conforming

items after RTR inspection or to contain, for example, greater than the

acceptable nuclear criticality limit, it is returned to the waste generator

for repackaging,

(10) RTR inspection is used in appraisal of NDA "Special-Case" waste containers

to aid in the evaluation of matrix problems (NQA-1 Element 16. Corrective

Action). For example, special-case waste drums (e.g., INEL tantalum

crucible content code) are flagged by the PAN assay algorithm through

previous evaluation and identification of the content code by the site NDA

reviewer (expert). See section 3.5.11 for a more detailed discussion of

the special-case waste drums,

1.3.7.A3-66


(11) RTR inspection is used routinely to verify or evaluate waste form or content

code of all waste drums (NQA-1 Element 8. Identification and Control of

Items). RTR inspections are used to confirm the proper identification of

waste content codes.

(12) General practice of upgrading NDA hardware, software, and procedures

whenever available and fiscally possible is pursued (NQA-1 Elements 2.

Quality Assurance Program and 3. Design Control). See section 5.0 for a

discussion of new NDA developments.

It is DOE policy to conduct periodic audits of all WIPP certification activities

at each site (Ref. 7.31). The audit teams consist of technical NDA (and NDE)

and -administrative personnel knowledgeable in several of the NDA technologies

discussed in Section 3. The purpose of these audits is to provide independent

monitoring and evaluation of each site's NDA and NDE activities on a regular

basis and to foster compliance with certification plans. These in-depth

evaluations take place on site and a detailed audit team report, including

recommendations for improvements in areas judged deficient, follow each such

audit. In addition, each site conducts independent internal audits on at least

an annual basis, covering the same overall procedures as performed in the DOE

external audits. The effect of these audits is to provide considerable

independent oversight of each DOE site's NDA and NDE operations, as overlays to

each site's routine operations activities.

1.3.7.A3-67

NuPac TRUPAGT-II SAR Rev. 0, February 1989

7.0 REFERENCES

7.1 ANSI N15.20-1975, "American National Standard Guide to CalibratingNondestructive Assay Systems."

7.2 USNRC Regulatory Guide 5.22, "Nondestructive Assay of Special. NuclearMaterial Contained in Scrap and Waste," Revision 1, April 1984.

7.3 ASTM C 853-82, "Standard Test Methods for Nondestructive Assay of SpecialNuclear Materials Contained in Scrap and Waste."

7.4 ANSI N15.35, "Guide to Preparing Calibration Material for NondestructiveAssay Systems that Count Passive Gamma Rays.

7.5 ASTM C 696-80, "Methods for Chemical, Mass Spectrometric, andSpectrochemical Analysis of Nuclear-Grade Uranium Dioxide Powders andPellets."

7.6 ASTM C 697-86, "Methods for Chemical, Mass Spectrometric, andSpectrochemical Analysis of Nuclear-Grade Plutonium Dioxide Powders andPellets."

7.7 ASTM C 759-79, Methods for Chemical, Mass Spectrometric, Spectrochemical,Nuclear, and Radiochemical Analysis of Nuclear-Grade Plutonium NitrateSolutions."

7.8 American National Standard Calibration Techniques for the CalorimetricAssay of Plutonium Bearing Solids Applied to Nuclear Materials Control,ANSI-N15.22, American National Standards Institute, New York, 1987.

7.9 Standard Test Method for Determination of Plutonium Isotopic Compositionby Gamma-Ray Spectrometry, ASTM C 1030-84, ibid.

7.10 Standard Test Method for Nondestructive Assay of Special Nuclear Materialin Low Density Scrap and Waste by Segmented Passive Gamma-Ray Scanning,ASTM C 853. This draft standard has been referenced with permission fromASTM Subcommittee C-26.10.

7.11 ASTM C 859-87, "Standard Terminology Relating to Nuclear•Materials".

7.12 J. T. Caldwell, R.D. Hastings, G.C. Herrera, W.E. Kunz, E.R. Shunk, "TheLos" Alamos Second-Generation System for Passive and Active Neutron Assaysof Drum-Size Containers", Los Alamos Formal Report LA-10774-MS, September1986.

1.3.7.A3-68


7.13 J. T. Caldwell et.al, "System Evaluation Including Assay Algorithm, MatrixCorrections, and Operational Performance of the Los Alamos Passive/ActiveNeutron Assay Systems," Los Alamos Technical Report N2-87-222WP.

7.14 R. B. Perry, R. W. Brandenburg, and N. S. Beyer, "The Effect of InducedFission on Plutonium Assay with a Neutron Coincidence Well Counter,"Transactions of the American Nuclear Society, 15 674 (1972).

7.15 DOE Order 5480.5, "Safety of Nuclear Facilities," September 23, 1986.

7.16 Fleissner, John G. and Hume, Merril W. , "Comparison of Destructive andNondestructive Assay of Heterogeneous Salt Residues," RFP-3876, March 29,1986.

7.17 F. J. Schultz and J. T. Caldwell 1988 DOE Model Conference paper.

7.18 M. E. Anderson and J. F. Lemming, "Selected Measurement Data for Plutoniumand Uranium," MLM-3009 (or ISPO-157), November 1982.

7.19 F. J. Schultz, et al., Oak Ridge National Laboratory; J. T. Caldwellet al. , Los Alamos National Laboratory, "First-Year Evaluation of aNondestructive Assay System for the Examination of ORNL TRU Waste," ORNL-6007, April 1984.

7.20 T. H. Kuckertz et.al. , "Making Transuranics Assay Measurements Using ModernControllers," Proceedings 9th ESARDA Symposium on Safeguards and NuclearMaterial Management, London UK, pages 389-393, May 1987.

7.21 J. T. Caldwell, J.M. Bieri, and A.P. Colarusso, "The Los Alamos Second-Generation Passive-Active Neutron Assay System--FY86 Operations Record andSystem Evaluation", Los Alamos Technical Report LA-Q2TN-86-106, September1986.

7.22 A. P. Colarusso, et.al., "Mobile Nondestructive Assay System," Proceedingsof 28th Annual INMM Meeting, Newport Beach, Ca, July 12-15, 1987.

7.23 K. L. Coop, J. T. Caldwell, and C. A. Goulding, "Assay of Fissile MaterialsUsing a Combined Thermal/Epithermal Neutron Interrogation Technique, " ThirdInternational Conference on Facility Operations-Safeguards Interface, SanDiego, CA, November 29 - December 4, 1987.

7.24 ANSI/ANS-8.15-1981, "Nuclear Criticality Control of Special ActinideElements."

7.25 "Data Package Format for Certified Transuranic Waste for the WasteIsolation Pilot Plant," WIPP-DOE-157, Rev. 2, January 1989.

1.3.7.A3-69


7.26 C. E. Moss and J. T. Caldwell, "Assay of TRU Wastes Containing (alpha, n)Sources," LA UR 86-2220, June 22, 1986.

7.27 "Chart of the Nuclides," Knolls Atomic Power Laboratory.

7.28 David C. Kocher, "Radioactive Decay Data Tables, DOE/TIC-11026, 1981.

7.29 F. J. Schultz, et al., "Neutron and Gamma-Ray Nondestructive Examinationof Contact-Handled Transuranic Waste at the ORNL TRU Waste Drum AssayFacility," ORNL-6103, March 1985.

7.30 San Horton, "Neutron Imaging", U. S. Army, Ph.D. thesis, 1988.

7.31 WIPP-DOE 120, Quality Assurance.

1.3.7.A3-70

NoPao TRUPACT-II SAR Rev. 0 , Februaxv 1989

APPENDIX 1 .3 .8

PATLOAD ASSEMBLY DRAWINGS

1.3.8-1

NaPae TEDPACT-II SAR Rev. 0, February 1989

1.3.8 Pavload Assembly Drawings

This appendix provides assembly drawings for the TRUPACT-II packaging payload.

Drawing 2077-007 (1 sheet) presents the two possible payload configurations;

fourteen 55 gallon drums on a p a l l e t , or two Standard Waste Boxes. Drawing

2077-008 (2 sheets) presents de ta i l s associated with the pa l l e t and guide

tubes which are used in conjunction with the 14 drum payload configuration.

1.3.8-2

PLASTIC SLIREINFORCIW(OMITTED FOR(OPTIONAL)

74-1/4 73-7/16

PLASTIC RE I(OPTIONAL)

ALIGNMENT G\(REF NUPAC ((OPTIONAL)

PLASTIC STRET(OMITTED FOR(OPTIONAL)

PLASTJC SLI!AND REINFORI(OPTIONAL)

PLASTIC STRE(OMITTED FOR(OPTIONAL)

PAYLOAD DRUM,14 PLCS

PLASTIC SL|(OPTIONAL)

PAYLOAD PALI(REF NUPAC I

L_3.0

4-DRUM PAYLOAD ASSEMBLY

REVISION MIS10R1

LTR DESCRIPTION

C ISEE DCN

DATE

iHEET AND•LATE.ARITY)

»7I .0

RATCHET/WEBBING ASSY3 PLCS(OPTIONAL)

L I F T FRAME ATTACHMENT LUGS

ORCING PLATE

3E TUBE, 3 PLCS

3 2077-008)

I W A P OR METAL BANDING.ARITY)

HEET ANDNG PLATE

:H WRAP OR METAL BANDING

.ARITY)

i5 GAL.

SHEET

TO 2077-008)

• ©

• ©

•FILTER PORT (2 MIN.)PER SWB

74.0

2-SWB PAYLOAD ASSEMBLY

ITEU i OTY i NEXT ASSY

BO. N.J.SWANNACK 12-24-88

wn s.A.PORTERAPPO W.HENKELAPPD D.L.SWAMMCKAPPO D.SCHMOKERAPPD H.WJNSCHAPPD-M. R.RICHARDSAPPO L.E.ULBRICHTOA G.E.H1LLWECK H.LEVITT0RAWN H.KIOVfCS

2-2«-«92-2H92-23-892-23-S9

2-24-682-23-49

UNLESS OTHEftMSE SKCfKDTOLERANCES:FKACT1ONS ± H/kANCUS ± H/A

WUEHSIONS ARE W WCHES3 PLACE DEOUALS ± K/A2 PLACE OECIUALS 1 <t/A1 PLACE CEC1UAL ± V A

MUCLEV1RA Pacific Nuafor Company

FTDFRAL WAY, WASHINGTON

PAYLOAD ASSEMBLYDESIGN DRAWING

TRUPACT-I I

SCALE: 3 / 1 6 |WT. N/AREV- ISHECT or I

DWGSIZE

D J2077-007SNP]

C SEE DCN=AJI| sr

• 56

#70-7/8

\T

• 65-1/2

PAYLOAD PALLET

2 .0 . 12 PLCS

DETAIL-A.(sxr.2)

MT W. J.SVUAWWACX I l-l*-*»

. HENKEL.A.POSTER I M H I

I Z-?«-8»

p/mtcraGiNGA Poetic Muo*or Cuino—v

»»• W*Y

t ;-?*-8»I 2-ZI-M

^WL.E.ULBRICKTI trii-ti

PALLET AND ALIOACHT GUIDE TUBEOESICN DRAWING

TRUPACT - II

OA G.E.MILLCHCOC H . L E V I T T i i-n-n

I1IU I OTT I Kt»T ASSY . M x.mowcc •

uss OIXJItCUHANdintCD

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SCAU: 1 / 8 iWT. N/A

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sirOICM.

2077-008SNF

NOTES. UNLESS OTHERWISE SPECIFIED:

1. INTERPRET • RAW ING PER ANSI Y-14.5.

2. ALL WELDING PROCEDURES AND PERSONNEL SHALL BE QUALIFIEDIN ACCORDANCE WITH ASUE CODE. SECTION IX. WELDPROCEDURES AND WELDER QUALIFICATIONS SHALL BE AVAILABLEFOR AUDIT OR REVIEW.

3. ALL WELDS SHALL BE VISUALLY EXAMINED IN ACCORDANCE WITHAWS Ol.l. SECTION 8.15.1. VISUAL WELD INSPECTORSSHALL BE QUALIFIED PER AWS DI. I.

•. PALLET LIFTING FEATURES SHALL BE LOAD TESTED TO I50SOF THEIR UUCIMUM WORKING LOAD.

5. PRIOR TO ASSEMBLY. ALL COMPONENTS SHALL BE CLEANED OFCUTTING OILS. MARKING DYES. WELDING FLUX. SPATTER. SCALEGRIUE ANO ALL OTHER FOREIGN MATERIALS. FINISHED ASSEU3LYAND ALL INTERIOR SURFACES SHALL BE CLEANED ANO VISUALLYOR WIPE TEST INSPECTED IN ACCORDANCE WITH ASTM-A380.

6. WELDS SHALL BE LIQUID PENETRANT INSPECTED ON FINAL PASSIN ACCORDANCE WITH ASME CODE. SECTION III. DIVISION I.SUBSECTION NB. ARTICLE NS-5000 ANO SECTION V. ARTICLE 6.

BONO IN PLACE USING 1617 A-B FURANE ADHESIVE.

8. SKINS MAY HAVE ONE SPLICE IF REQUIRED FOR FABRICATION.IF BOTH UPPER ANO LOWER SKINS REQUIRE SPLICINC.UPPER ANO LOWER SPLICE LINES SHALL RUN PARALLEL.

9. SEAL ALL FASTENERS. HOLES AND CAPS WITH RTV SILICONSSEALANT.

[Tg> WELDS SHALL BE LIOUID PENETRANT INSPECTED AFTER LOAD TEST'"" PER G/N 6.

[Tt> LIFT POCKETS SHALL BE POTTED IN PLACE USING ISCCAST SYSTEMSU^^ UNCAST TWO A/B PER MANUFACTURER'S INSTRUCTIONS.

fl2> HEXCEL ALUMINUM H0NEYCCM3. CRIlt 5052 OR 5058. CELL SIZE:•"" 1/8 TO 3/8; FOIL THICKNESS: .0015 TO .005: DENSITY:

6.0 TO 6.9: PERFORATION OPTIONAL.

BONO IN PLACE USING NEWPORT ADHESIVE NO. N8I0ITR OR PER UIL-A Z5463A.

:£saei»iCM 3A1EI 3T

OPTIONAL SCUFF SHEET,SHT. II 3A (.125 THK)ASTU A2«0. TYPE 316STAINLESS STEEL CRTIVAR-IOO. VIRGIN

POLYMER

,— PIPE. ** 3CH. 80/ ASTM A3I2, TYPE 204/20+L/ STAINLESS STEEL

SHT. II OA (.125 THK)ASTU B209. 80SI-T6CR 707S-TS ALUMINUJ

NO BAR. 7/8 OIA X S.SASTM AS84, TYPE 630

STAINLESS STEEL

TYP

SHT. I* GA (.080 THK)ASTM B209. 606I-T6OR 707S-T6 ALUMINUM

SECTION 5-5 (SHT.i) 0 >SCALE: FULLTYP-3 PLC"S

-2-1/2

*I/2

PIPE. Z' SCH.56061-ToCR

3063-ToALUMINUU

ALIGNMENT GUIDE TUEESCALE: 1/2

S. A .PORTER . 2- i t -aj

'L.SWAHWACK I

». r. F.HILL • l-U-I gyi ft"

« : 3 j e aTCt£S»HCES.

" ^ C N S

NUCLE71R.

annruzA Poaflc Nue*or Comocn*

PALLET ANO AL1CMJENT CUIOE TUBE

OESiqN 0RAWINC

TRUPACT I I

IffiALt: NOTED •'-r ;

D 2077-008SNF

SHT. 16 CA (.063 THK--ASTM 8203. 606I-T2

ALUMINUM

NO. 10 x a/a LG.THREAD FORMING SCREW2 REQO AT 12 EQ. SP. PLACES

CCRE— j

=11 VETV<6 OIA X 1/2 LGALUMINUU

-BIWERPLT. 1-1/* THKUJ*«f POLYMER

/ i i \ ^4,*? ][••

1 k-1 /

ii...

7Z-LIETAIL A (SHT.I)

SCALE: FULL12 PLCS

3/8 THK. ASTM A2*0TYPE 20*/30*L

STAINLESS STEEL

J

HnPac T2EPACT-II SA2 Rev. 0, February 1989

AFPENDH 1.3.9

WASTE SAMPLING PROSHAMS AT DOE SITES

1.3.9-1

NaPac TRUPACT-II SAR Rev . 0 , F e b r u a r y 1939

APPENDE 1 . 3 . 5

7/ASTE SAMPLING PROGRAMS AT DOE"SITES "

1.0 SUMMARY

Previous and existing sampling programs at U.S. DOE sites provide valuable

information about the properties and transport parameters of retrievably

stored and newly generated #.7aste. Results from these programs nave provided a

basis for certifying retrievably stored waste -with, existing records and pro-

cess inowledge as the primary source of information, and with real-time radio-

graphy (RTR) as a verification technique. Actual sampling of a statistically

significant number of .vaste containers can then be used as secondary verifi-

cation. Although tiiese sampling programs were primarily aimed at meeting the

Y/aste Isolation Pilot Plant Waste Acceptance Criteria (WIPP ?/AC), they can be

extended to meet transportation requirements as well.

Sampling programs also provide a historical perspective of waste generation

processes and operations at the sites. Knowledge of these can be used to

address some of the issues that are transportation concerns (i.e. production

of 2C1 from payload containers, presence of volatile organics). This Appendix

provides a description of the sampling programs and their relevance to the

TRUPACT-II transportation parameters.

2.0 INTRODUCTION

The objective of this Appendix is to summarize the past and present sampling

programs for contact handled transuranic (CH-TRU) waste at sites and to demon-

strate I:ow the information obtained through these programs is applicable for

qualifying waste for transport in TRUPACT-II. The available data on sampling

of TRU waste originates from three sources:

1) The TRU "Jaste Sampling Program which consists of extensive random

sampling programs conducted between 1983-1985 at the Idaho National

Engineering Laboratory (INEL) (Reference 9.1).

1.3.9-2

NnPac TEDPACT-II SAR Rev. 1. May 1989

2) Stored Waste Examination P i l o t P l an t (SWEPP) C e r t i f i e d Waste

Sampling Program conducted from 1986 to present at INEL (References

9.2 and 9 .3) .

3) A controlled study of INEL re t r ievably stored waste to estimate gas

generation r a t e s from CH-TRU waste containers (Reference 9 .4) .

A background and summary of each of these programs wi l l be provided with an

evaluation of the aspects re la ted to the TRUPACT-II t ransportat ion requi re-

ments.

3.0 TRU WASTE SAMPLING PROGRAM AT INEL

The INEL TRU Waste Sampling Program (Reference 9.1) randomly selected and

sampled 181 TRU unvented waste (payload) containers from re t r ievable storage.

The waste ranged in age from six months to twelve years. The main objectives

of the study were to examine the waste contents both v i sua l ly and by RTR to

determine waste form compliance with the WIPP WAC, and to assess the va l id i ty

of using RTR as a nondestructive ce r t i f i ca t ion technique. The sampling program

included:

Analysis of the waste conta iner ' s headspace gas for composition

Determination of the packaging configuration

Description of the waste form

Reporting the physical s t a te of the waste for each item description

code (IDC)

Each of these parameters was assessed by visual, analytical analysis or RTR

examination.

It should be noted that the TRU Waste Sampling Program was initiated before

the TRUPACT-II shipping requirements were conceived. However, most of the

proposed controls for shipment of TRU waste in the TRUPACT-II were examined

during the sampling process. These results assist in generating a database

which demonstrates a safe history of handling, shipping and storage for the

waste.

1.3.9-3

NaPac TRUPACT-II SAE Rev. 0, February 1939

4.0 THE SWEPP SAMPLING PROGRAM

Tlie 3T7EPP Cert if ied Waste Sampling Program has incorporated -the resul t s from

the TIiU Tfaste Sampling Program described above, to determine acceptable sample

s izes . This program lias been iu progress since 1936> and the percentage of

containers to be sampled is updated yearly to incorporate the to ta l number of

aonconforznances for the previous year ' s input. Tie purpose of the ST7EPP Cer-

t i f ied ij'aste Sampling Program is to provide qual i ty control in support of the

waste ce r t i f i ca t ion process. The program consis ts of selecting a s t a t i s t i -

cally valid port ion of the TRU waste containers which have been i'/IPP i?AC cer-

t i f i ed , and v isua l ly examining the contents for compliance. This program sup-

plements 10C,b 2.TH of the vaste containers.

The combined data from the TRU Waste Sampling Program and the FI-1986 and F7-

1937 3W2PP Cert i f ied V.'aste Sampling Program demonstrated tha t , when a l l waste

forms are taken into consideration only 3 out of 228 (1.325) sampled con-

tainers showed nonconfornances to the WIPP WAC. These were uncemented sludge

drums, that showed no v is ib le liquid during RTR examination, yet actually

contained l iquid in excess of 0.7 gallons when examined v i sua l ly . The fai lure

to detect the l iquid was because the surface movement was res t r ic ted due to

formation of a soi id layer . I t is important to note that the visual examina-

tions did not reveal any problems with any other WIPP WAC requirements, which

include r e s t r i c t i o n s on ilie presence of non-radioactive pyrophoric mater ia ls ,

explosives, and conpressed gases.

An overall T.7IPP :7AC misc'ertification of 1.3~o is considered acceptable for

continuation of the SWEPP cer t i f ica t ion process without requiring any major

changes. INEL has defined (Reference 9.5) the sample size and sampling f re -

quencies for FY-1938 based on these r e s u l t s . Sampling 30 out of the 2900

drums expected to be SWEPP-certified in FY-1988 i s expected to give a 95%

confidence level that the estimate is correct . This is based on the assump-

tion that 27o of the SffEPP-certified drums are TCIPP WAC miscert if ied, and the

actual range of percent of mis cert if i cation i s O-79&.

1.3.9-4

XoPac T2UPACT-II SAR ilev. 0 , February 1989

5.0 3AS GENERATION STUDIES

l i e sas genera t ion s tud ies of tiie TSU Waste Sampling Program (Reference 9.4)

v/ere conducted to evaluate t i e e f fec t iveness of d i f f e r en t venting devices in

maintaining pressure equi l ibr ium oetveen . t i e payload conta iners and ambient

condi t ions . In add i t ion , concent ra t ions of Iiydrogen and other sases were

measured in en e f for t to quant i fy the gas genera t ion r a t e s in the drums.

A t o t a l cf s ix teen zewiy genera ted .Pu-239 waste drums from the Xocfcy F l a t s

Plant and s i s Pu-238 drums from Los Alamos Nat ional Laboratory were evaluated

under cont ro l led condit ions in t h i s s tudy. The Pu—239 drums were vented for a

period of 13 weeis and l a t e r sealed to measure gas generat ion r a t e s and tem-

poral v a r i a t i o n s in composition. Resu l t s from these s tud ie s are discussed in

Section 6.4 of t h i s Appendix.

6.0 EVALUATION OF TRUPACT-II TRANSPORTATION PARAMETERS

FROM SAMPLING PROSRAMS

The t r a n s p o r t a t i o n parameters for TRTFPACT-II and t h e i r methods for determina-

t ion and control a re descr ibed in Appendix 1.3.7 of the SAR. Sampling p ro -

grams provide confirmatory da ta on these parameters and the adequacy of the

v e r i f i c a t i o n techniques used ( records and data base , consis tency of waste

generat ion processes , "TR, e t c . ) . The t r a n s p o r t a t i o n parameters t h a t can be

addressed in a sampling program are l i s t e d below, and each i s discussed with

respec t to the sampling programs below:

Physical form

* Chemical p r o p e r t i e s

- Chemical c o m p a t i b i l i t i e s

* Gas d i s t r i b u t i o n and p res su re buildup

1.3.9-5

NnPac TRUPACT-II SAR Rev. 1 , May 1989

6.1 Physical Form

the transportation requirements for physical form are the same as WIPP WAC

requirements. The previous results from the sampling programs (see Section

4.0) have" shown the nonconf ormance rates for these criteria to be very low

(Reference 9.5).

6.2 Chemical Properties and Waste Type

The waste type restrictions on TRUPACT-II payload materials are described in

Appendix 1.3.7 of the SAR. The restrictions on non-radioactive pyrophorics and

explosives are regulated by the WAC and the sampling programs show that these

requirements are consistently met at the sites.

Sampling programs have demonstrated no visible deterioration of the plastic

confinement layers, even for containers that have been in storage for up to

fifteen years. This indicates the absence of reactive materials or corrosives

in the wastes. Inspections performed on the drums verified that they had not

deteriorated appreciably during storage.

All of the content codes from DOE sites are grouped into waste material types

(e.g., solidified aqueous or homogeneous inorganic solids, solid inorganics,

solid organics, and solidified organics), based on their gas generation poten-

tial which is quantified by the effective G values (see Appendix 3.6.7 of the

SAR). In order to conform to these limits, the chemicals/materials within a

given waste material type are restricted. The waste material types are

further classified into shipping categories depending on the type of the pay-

load container and the bagging configuration. The correlations between content

codes and shipping categories are listed in the TRUOON document. Only compa-

tible waste content codes are included in the TRUCON docnnent and considered

•for transport in TRUPACT-II. The TRU Waste Sampling Program discovered only

one payload container in 181 of the sampled containers to have been assigned

an incorrect IDC that would have resulted in a change of shipping categories.

These results indicated that procedural controls and process technology infor-

mation have ensured compliance with the waste type restrictions.

1.3.9-6

NnPac T2TJPACT-II SAR Xev. 0, February 1989

6.3 Chemical Compatibility

5.3.1 CTiesiical Cnrapa fci'oi li-i? :7ithi-n Pavload Containers

Payload materials scst be chemically compatible with, each other and v/ith the

materials of construction cf the TSUPACT-II ICV. The TEH waste sampling pro-

gram at KIEL included examination of several drums that had been in storage

for up to fifteen years. Uo effects of any adverse chemical reactions were

detected in any of these druas. 3aste containers generated in 1973 and sampled

in 1938 sho7/ed l i t t l e or no chemical deterioration of the inner confinement

layers, ezcept for coloring of the plast ic bags in some cases (Reference 9.6) .

The sampling of "7AC cert if ied drums in the STCEP? Sampling Program also showed

no evidence of adverse chemical reactions. The resul ts of these sampling

programs indicate that the *.vaste materials are chemically compatible with

themselves and with the payload containers. The detailed chemical compati-

b i l i t y analysis performed on waste from each DOE s i t e demonstrates that no

appreciable chemicai reactions will occur in the wastes or between the wastes

and the payload containers. Details of this analysis are presented in Appen-

dix 2.10.12.

o.3.2 Occurrence of Free Chlorides

None of the sampling programs reported the presence of EC1 gas in the head-

space of the sampled containers or (where applicable) in the inner confinement

layers. The production of BC1 gas is of concern due to i t s potential for

causing stress corrosion cracking of the package. Actual waste data shows

that even though UC1 production is possible, i t is highly improbable that

gaseous HC1 -.youid aver be produced and released from the payload containers.

An analysis of the source terms and release conditions for IIC1 in the payload

materials is presented in Appendix 2.10.9.

1.3.9-7

NnPac TSUPACT-II 3AR Rev. 0, February 1SSS

Occurrence o~f Vjlatiis Organic C

Jampling i'rogranis clso provide information en the relative amounts of volatile

organic compounds vVOCs) in the payioad materials. VOCs are a concern due to

potential rr.compati'bili ties ".vith tie butyl rubber 0-rings of TRUPACT-II and

due to the potential for pressure buildup from their vapor pressures. A

detailed discussion of the existing information on VOCs in the Taste from

sampling programs is presented in Appendix 2.10.11. Hssn.lts from the sampling

programs listed above are:

The source term for VOCs in the waste is limited.

Headspcce concentrations of VCCs in the payioad containers are

the range for saturation values.

Even in the case of organic sludges (which contain the YOCs in bound

form and belong to the test category) the release of the VOCs from

the 7/aste is limited.

VOC release rates from the payioad containers are estremely small

and the effects of any interaction between the VOCs and the butyl

rubber C—rings would be minimal and not affect the sealing

properties.

Ongoing sampling programs show that compared to retrievaoly stored

waste, newly generated waste has much lower concentrations of the

VOCs.

6.4 3as Concentrations and Pressure Build—Up

generation of gases from the TRUPACT-II payioad materials is of concern due to

the potential for pressure buildup and the occurrence of potentially flammable

fixtures of gases. The controls in place to restrict these parameters are

described in Appendix 1.3.7, and are summarized below:

1.3.9-8

NuPac T2UPACT-II 5A2. 2ev. 0, February 1989

Restrictions on materials that can be present within each payload

(limits on hydrogen generation potential of waste materials).

Limits on the number of internal layers of confinement -within each

payload container.

Linits en the decay heat within each payload container.

The relevance of the sampling programs to each of these parameters is

addressed ;

j.-i.l lies crictions on IJatsrials

The r e s t r i c t i o n on the -.aaterials that can be present in a payload was

addressed in Section 6.2 of this document. Sampling programs show that for

waste that is certified to the YTAC, the waste type restr ict ions are consis-

tently met, and none of the sampling programs showed any effects of chemical

activity within the drums.

6.4.2 Restrictions on Packaging Configuration

The second listed control is a packaging requirement, which res t r ic ts the

maximum number of plastic bag layers that can be present for a given content

code. This number is defined for each content code in the T2.UC0N document.

The TRU V/aste Sampling Program (Reference 9.1) conducted at INEL documented

packaging configurations for each payload container sampled. This includes

information on the number and type of l iner bags and bagout bags used for

v/aste packaging. This data has provided a basis for the retrievably stored

waste to'fce qualified for shipment. The packaging requirements l isted in the

TRUCON document for each content code (and correlating DCs) are consistent

with the reported data from the TRU Waste Sampling Program.

1.3.9-9

NuPac TEDPACT-II SAR Rev. 1, May 1989

6.4.3 Restr ic t ions on Decay Heat

This parameter controls gas generation in the payload containers by l imiting

the decay heat of the radionnclides in each shipping category. These decay

heats are determined based on an effective 6 value for generation of flammable

gas for each shipping category. An analysis of effective 6 values measured

for real wastes i s provided in Appendix 3 .6 .8 . An average 6 value in any

waste type ( I , I I , I I I ) was consistently l ess than the effective G values

being used to es tabl i sh possible hydrogen generation r a t e s . Experimental

resu l t s on estimates for hydrogen release r a t e s are provided in Appendix

3.6.10. The radionuclide content of a payload container i s r e s t r i c t ed such

that given the re lease ra tes and the effective G values, the hydrogen concen-

t ra t ion wil l not exceed 5% in any of the confinement layers . The concentra-

tions of hydrogen predicted in these calculat ions are derived using steady-

s ta te assumptions, and are much higher than those that could be produced in an

average drum in a given shipping category. For example, the wattage limit on a

drum of Waste Type I I I with four layers of p l a s t i c i s 0.0207 watts, or 6.89

grams of weapons grade plutonium.

Sampling programs mentioned above have shown tha t containers at steady-state

with much higher decay heat loadings had hydrogen concentrations well below 5%

for payload containers belonging to an analyt ical category. Especially for

retr ievably stored waste that had not been vented, the analytical calculations

show hydrogen concentrations much greater than the actual measured concentra-

t ions. The observed low concentrations could be due to lower hydrogen pro-

duction r a t e s , matrix depletion (reduction in the G value with time) and/or

the escape of hydrogen from the payload containers. Very few of the sealed

drums in the sampling programs were overpressurized, indicating possibly low

gas generation r a t e s , simultaneous consumption of oxygen or periodic leakage

of gas from the drums due to overpressurization ( the drums were not vented).

7.0 COMPLEXITY OF REAL WASTE SAMPLING

For visual inspection of the waste contents, necessary precautions must be

taken to ensure the safety of personnel performing the task. In the handling

of materials contaminated with TRU radionuclides, a ba r r i e r i s always in place

1.3.9-10

NaPac TRDPACT-II SAR Rev. 2, June 1989

between the individual and the radioactive materials (e.g., glove boxes,

gloves, bubblesuits, etc). Whenever a waste container is opened for sampling

or inspection, necessary precautions must be taken to prevent contamination

from the radioactive material. Sites have, in the past, utilized containment

structures under ventilation control with the individuals in supplied-air

bubblesuits to open and inspect the waste contents. Although the internal

exposures have been low, the sites have changed their waste handling tech-

niques by developing in some cases multi—million dollar remote handling con-

cepts to prevent this potential exposure. Due to the unique difficulties asso-

ciated with actual sampling of the waste (i.e., additional potential exposure

to workers and generation of excessive waste as byproduct of waste sampling),

alternate and effective nondestructive techniques are necessary to supply the

primary source of information on the waste. Visual inspection on a limited

basis can then serve as a supplemental verification system.

8.0 CONCLUSIONS

The following conclusions can be drawn from the waste characterization data

obtained through the various sampling programs:

1) A transportation qualification process using a statistical sampling

approach is valid for retrievably stored waste when 100% RTR is

supplemented with visual examination sampling programs.

2) The. use of an RTR system is an adequate non-destructive certifica-

tion technique for meeting certain WAC requirements, as described in

this appendix.

3) Process knowledge, existing records and database information ade-

quately provide primary sources for characterizing the shipping

parameter requirements of stored waste. RTR and sampling programs

can serve as secondary verification techniques.

4) Existing data on the sampling of real waste and ongoing sampling

programs can be used to assess the potential for gas generation and

to quantify effective G values.

1.3.9-11

MuPac TSDPACT-II SAR Rev. 0, February 1589

9.0 REFERENCES.

i.l Clements, I. L. , Hudera, D. E., 'TRU V/aste Sampling Program: Volume I —

"u'aste Characterization,' EG and S-WM-6503, September 1935

•i.l Arnold, ?. II., "Z.Z and C- Drna Sampling Program Results FY 1986,' RFP

4250, October 19 86.

9.3 7atson, L. Z., 'EG and 3 Sampling Program Results,' RFP 4251, December

1337

9.4 Clements, T. L. and Zudera, D. S., 'TRU Waste Sampling Program: Volume

II — Gas Generation Studies,' EG and G Idano, INEL, Idaho Falls, Idaho,

EG and G-WSI-6503, September 1985

9.5 Xudera, D., 1989, Personal Communication.

9.6 Rdggenthen, B. H., ilcFeeters, T. L., Nieweg, R. G., '17aste Drum Gas Gen-

eration Sampling Program at Rocky Flats During FI 1988', RFP-4311, March

1989 (in Press).

1.3.9-12

TRUPACT-II SAR ' Rev. 13, April 1994 |i

APPENDIX 1.3.10 !

USE OF TRUPACT-II FOR SHIPMENT OF TRITIUM-CONTAMINATED WASTE

1.3.10-1

! TRUPACT-II SAR Rev. 13, April 1994

1.0 GENERAL INFORMATION

j The TRUPACT-II shipping package has been designed and licensed to transport

| contact-handled transuranic (CH-TRU) materials for the U.S. Department of Energy

! (DOE). The DOE - Carlsbad Area Office has been requested to make shipments of

| solidified tritium-contaminated materials from various national laboratories to

! storage and/or disposal facilities using the TRUPACT-II. The purpose of this

! Appendix is to describe and justify the addition of solidified tritiated water

| as a content condition for the TRUPACT-II.

| 2.0 DESCRIPTION OF CONTENTS

j A high-quality stainless steel pressure vessel (primary container) is filled with

j adsorbent material, water containing small quantities of tritium is added, the

j water is adsorbed, and the primary container is sealed. The primary container is

! placed inside a 55-gallon drum and surrounded by dunnage and additional adsorbent

| material. An example of specific details and compliance with Appendix 1.3.7 of

! the SAR is described in Content Code SL 111, see TRUPACT-II Content Codes

I (TRUCON) document (Ref. 10.1). The proposed content description is as follows:

ij • Type and form of material-Dewatered or solidified tritium contaminated waste

j adsorbed onto inorganic material. The waste is sealed in a high-quality

J stainless steel pressure vessel. Explosives, corrosives, nonradioactive

j pyrophorics, free liquids and flammable organics are prohibited. The

! internal volume of each primary container is limited to not more than 20

j liters, and the internal pressure of each primary container is limited to

j not more than 1.5 atmospheres at the time of shipment. The primary

j containers are overpacked in 55-gallon drums.

i

| • Maximum quantity of material per package-Contents not to exceed 7,265 pounds

} including shoring and secondary containers, with no more than 1,000 per

j 55-gallon drum. The maximum number of 55-gallon drums per package is 14,

I ' assembled as shown in Figure 1.0-3 of the SAR. Decay heat not to exceed the

I values given in Tables 6.1 and 6.2, "TRUPACT-II Content Codes, (TRUCON)"

| (Ref. 10.1).

1.3.10-2

TRUPACT-II SAR Rev. 13, April 1994 |i

3.0 STRUCTURAL EVALUATION

The 55-gallon drums of tritium waste will be assembled as shown in the SAR, see

Figure 1.0-3, Representative TRUPACT-II 14-Drum Payload Configuration. The

maximum weights will be verified to be less than the following limits:

1,000 pounds per drum

7,265 pounds per payload assembly of 14 drums

19,250 pounds per loaded TRUPACT-II

The inorganic nature of the waste and limited wattage due to the small amount of

tritium present inside the primary payload containers limit the potential buildup

of pressure that could occur inside the TRUPACT-II inner containment vessel (ICV)

to less than the 50 psi design pressure during one year. Since payload

containers are 55-gallon drums, there are no special structural considerations

for either normal or hypothetical conditions of transport that are not already

discussed in the SAR. In summary, there are no structural impacts to the

TRUPACT-II packaging resulting from the shipment of 55-gallon drums containing

tritium waste.

4.0 THERMAL EVALUATION

The thermal limit for tritium shipments remains the same as discussed in

Section 3'of the SAR ... not to exceed a total of 40 thermal watts in 14 drums

per TRUPACT-II. There will be no thermal impact to the TRUPACT-II packaging as

a result of shipping tritium waste for either normal or hypothetical accident

conditions of transport.

5.0 CONTAINMENT EVALUATION

The containment criteria for tritium shipments remains the same as discussed in

Section 4 of the SAR ... not more than 1 x 10~7 standard cubic centimeters per

second. Prior to shipment, both the inner and outer containment vessels of the

TRUPACT-II will be tested in accordance with the SAR Appendix 7.4.2, Assembly

Verification Leak Test. There will be no impact on the containment capability

1.3.10-3

TRUPACT-II SAR ' Rev. 13, April 1994

j of the TRUPACT-II as a result of shipping 55-gallon drums of tritium waste for

j either normal or hypothetical accident conditions of transport.

J 6.0 SHIELDING EVALUATION

i! Tritium is a low-energy beta particle emitter and will be shielded by the

! .stainless steel primary container. For normal conditions of transport, the

! 55-gallon drums containing the solidified tritium waste can be contact handled

I as with other TRUPACT-II authorized contents ... each 55-gallon drum shall have

j a surface dose rate of less than 200 mrem/hr at the surface and less than 10

! mrem/hr at two meters. If one assumes as a worst case that both the primary

! container and the pay load container were damaged during a hypothetical accident,

! the TRUPACT-II stainless steel 1/4-inch thick ICV would provide adequate

! shielding. The shipment of tritium waste in the TRUPACT-II poses no radiation

! safety impact for normal or hypothetical accident conditions of transport.

ii

| 7.0 CRITICALITY EVALUATION

il

! Tritium is not a fissile material and, therefore, there will be no impact on the

j current criticality capabilities of the TRUPACT-II for both normal and

j hypothetical accident conditions of transport.

I 8.0 OPERATING PROCEDURES

i

! The TRUPACT-II will be loaded and unloaded in accordance with the standard

j operating procedures described on Section 7 of the SAR. Prior to transport, each

J TRUPACT-II will be leak tested in accordance with the SAR Appendix 7.4.2,

j Assembly Verification Leak Test. There are no changes to the TRUPACT-II

{ operating procedures resulting from the handling of 55-gallon drums of tritium

! waste.

1.3.10-4

TRUPACT-II SAR Rev. 14, October 1994 |

• • 9.0 ACCEPTANCE TESTS AND MAINTENANCE

There are no changes to the acceptance tests and maintenance described in

Section .8 of this SAR due to the shipment of drums of tritium waste. The

TRUPACT-II packaging will be in full compliance with the requirements of this

section prior to transport when loaded with 55-gallon drums of tritium waste.

10.0 REFERENCES

10.1 U.S. DOE, "TRUPACT-II Content Codes (TRUCON)," Rev. 8, October 1994, jDOE/WIPP 89-004.

1.3.10-5

NaPac TRUPACT-II SAR Rev. 0, February 1989

' APPENDIX 2 . 1 0 . 9

FREE EALIDES IN THE TEDPACT-II PAXLOAD-

SOURCE TERM AND RELEASE RATE ESTIMATES

2 . 1 0 . 9 - 1

NnPmc TRUPACT-II SAR Rev. 0, February 1989

APPENDIX 2 .10 .9

FREE HALIDES IN THE TRUPACT-II PAYLOAD-

SOURCE TERM AND RELEASE RATE ESTIMATES

1.0 SUMMARY

An evaluation of source terms for halides has demonstrated that very small

amounts of halides are available for chemical reaction to cause s tress corro-

sion cracking (SCO of the Inner Containment Vessel (ICV) of TRUPACT-II. This

is substantiated with sampling data from actual waste drums and radiolysis ex-

periments conducted on TRU waste materials. Extensive sampling programs of

both retrievably stored and newly generated waste did not detect hydrogen

chloride (HC1) gas in the head space of any of the payload containers. Exper-

iments designed to simulate alpha and gamma radiolysis of actual bagging and

TRU waste materials from generator s i t e s demonstrated HC1 gas generation to be

very low.

These observations support the conclusions that alpha radiolysis of actual

waste produces l i t t l e or no HC1 gas. Any small quantities of HC1 gas produced

are l i k e l y e i t h e r to d i s s o l v e read i ly in any absorbed water or moisture

present in the waste, or to react with the waste contents or payload

conta iners . This w i l l retard the re lease of HC1 gas from the payload

containers, precluding the poss ib i l i ty of stress corrosion cracking of the

TRUPACT-II ICV.

2.0 INTRODUCTION

The production of free halides from radiolysis of the payload materials can

potentially cause SCC of the TRUPACT-II Package. The primary material of con-

struction used for the ICV and the Outer Containment Vessel (OCV) of TRUPACT-

II i s Type 304 stainless s tee l (austeni t ic ) . This material may be susceptible

in the sensitized condition to SCC in the presence of chloride contamination.

However, Tokiwai et al . (Reference 6.1) have shown 304 stainless s tee l to be

resistant to SCC at temperatures below 55°C, even for heavily sensitized

2.10.9-2


m a t e r i a l a t s t r e s s e s near y i e l d , for maximum al lowable l e v e l s of NaCl

concentration and re la t ive humidities. Normal operating temperatures of the

cavity headspace or TRUPACT-II ICV walls are not expected to exceed 55°C. The

following discussion wi l l provide an analysis of the source terms for the

halides and the i r potent ia l to reach the ICV.

3.0 SOURCE TERMS FOR CHLORIDES AND FLUORIDES IN WASTE

The contaminants of concern are hydrogen chloride (HC1) and hydrogen fluoride

(HF) which could o r i g i n a t e from the r a d i o l y s i s of po lyv iny l c h l o r i d e or

halogenated organics.

3.1 Potential for Fluoride Production in Waste

Compounds containing fluorides considered as potent ia l sources for HF gas have

not been ident i f ied in the CH-TRU materials in s ignif icant amounts. Only

Teflon, inorganic fluoride s a l t s and a trace amount of Freon-113 occur in the

waste, and these do not produce HF from rad io ly i s (Appendix 3 .6 .8 ) .

3.2 Potential for Chloride Production in Waste

The potential for chloride production in the payload materials comes primarily

from radiolysis of the chlorinated compounds. Volatile organic compounds

(VOCs) capable of generating HC1 are not present in sufficient amounts in the

waste to be of concern for SCC. Appendix 2.10.11 discusses the source terms

and release rates of VOCs. The only other compound present in the waste with

a potential for HC1 production is polyvinyl chloride (PVC).

Experimental- evidence has shown average G(HC1) (moles of HC1 in the gas or

liquid state released per 100 eV of energy absorbed) values for radiolysis of

commercial grades of plasticized stablized PVC to be quite small (Appendix

3.6.7). Table 1 summarizes the available data on generation of HC1 from

radiolysis of PVC. Three independent experiments of alpha radiolysis on ac-

tual waste and packaging material from three U.S. DOE sites revealed very

little or no HC1. Contact handled TRU waste to be shipped in TRUPACT-II is

2.10.9-3

NuPac TRUPACT-II SAR ' Rev. 1, Hay 1989

TABLE 1

G(HC1) VALUES FOR PLASTICIZED POLYVINIL CHLORIDE

MATERIALS IN CH-TRU WASTE

Irradiat ion G(HC1)

Average G(HC1) for P las t ic ized PVC <x,y 0.64 a

Values for Materials used at U.S. DOE s i t e srC bagout bag (Ref. 6.2)

(Los Alamos National Laboratory)

PVC bagout bag (Ref. 6.2) a ~0b

Nine samples of PVC bag material (Ref. 6.3) . y 0 .21 c

(Rocky Flats Plant)

Samples of PVC bagout material (Ref. 6.4) a 0

(Rocky Flats Plant)

Samples of PVC gloves (Ref. 6.5) y 0

(Los Alamos National Laboratory)

Samples of PVC bags (Ref. 6.6) y <0.01d

(Savannah River Plant)

a Average of twenty-seven (27) l i t e r a t u r e v a l u e s for p l a s t i c i z e d PVC

(Appendix 3 .6 .7 of SAR)

Mass spectrometric analysis of gases did not detect any Cl~ or HC1. Vet

chemistry analysis of material inside glass react ion vesse l yielded 0.06%

Cl".c Tubes of irradiated PVC were opened under water, shaken, and t i trated

with NaOH. The presence of chlorides in so lut ion was ident i f ied qual i ta-

t ive ly . Only acid content (not Cl~) was measured quantitat ively. Acid

concentration in water could be due to (X>2 dissolved from atmosphere.

Personal communication for ongoing experiments.

2.10.9-4


contaminated predominantly with alpha-em i t t ing radionncl ides . For the two

gamma r a d i o l y s i s experiments c i t e d in Table 1 that measured G(HC1), the

quant i tat ive measurement was made by t i t r a t i o n of ac id i ty in samples with a

weak base. No direct evidence of HC1 gas was reported in these experiments

other than a qua l i ta t ive indicat ion of Cl~ (Reference 6 . 3 ) .

In conclusion, rad io ly t i c a c t i v i t y wi th in the drums of CH-TRU waste w i l l not

resu l t in the generation of any substant ia l amounts of HC1 gas. The source

term for HC1 gas i t s e l f (without any considerat ion of transport to the ICVO i s

expected t o be ins ign i f i cant in pay load containers transported in TRUPACT-II.

3.3 Gas Sampling of CH-TRU Waste Drums

Sampling programs at Idaho National Engineering Laboratory (INEL) (Reference

6.7) and Rocky F la t s Plant (Reference 6 .8) did not detect HF or HC1 gas in the

head space of any of the 249 drums of re tr i evab ly stored and newly generated

TRU waste that were sampled. In addit ion t o drum head space sampling, twenty-

two drums of retr ievably stored and newly generated waste were sampled for

gases within success ive layers of confinement up t o the innermost layer with

the waste. In a l l cases , HF or HC1 were never detected in any layers of

confinement.

4 .0 MECHANISMS FOR RETARDATION OF CHLORIDES INSIDE PAYLOAD CONTAINERS

Production of chlorides by r a d i o l y s i s of waste materials in payload containers

does not n e c e s s a r i l y imply the presence of a gaseous phase. Some of the

r a d i o l y s i s experiments did not observe HC1 gas in the void space of the

experimental apparatus but did measure chlor ides after washing of the i n t e r i o r

of the r e a c t i o n v e s s e l (Reference 6 . 2 ) . This s u g g e s t s the e x i s t e n c e of

mechanisms which can retard the re l ease of gaseous HC1.

2.10.9-5


4.2 Solubility of HC1 in Water

The presence of any free EC1 that is produced in a payload container will be

controlled in the headspace by the high solubility of HC1 gas in water.

Transfer of HC1 gas to the aqueous phase occurs with very little resistance in

the liquid phase and with very little back pressure of the gas (Reference

6.9).' For small quantities of HC1 gas produced in the payload containers* the

moisture content of the waste materials would probably be sufficient to absorb

the gas generated.

The partial pressures of gaseous ECl over aqueous solutions of EC1 are ex-

tremely small even at appreciable concentrations of ECl, due to its high

solubility (Reference 6.9). Table 2 provides the partial pressure of ECl above

HC1 aqueous solutions over a wide range of temperatures (Reference 6.10). The

partial pressures reported in the normal operating ranges of TRUPACT-II (Table

2) would minimize the possibility of ECl being present as a gaseous phase.

Waste types to be transported in TRUPACT-II payload containers contain varying

amounts of adsorbed/absorbed water as a by-product of processes (without the

presence of free liquids) in addition to water vapor from atmospheric humidity

inside the layers of confinement. Although water vapor was not quantitatively

measured in the headspaces of the drums examined at RFP as part of the TRU

waste sampling program (Reference 6.7), water was noted in all gas samples

(Reference 6.11). Hence it is probable that any ECl produced would dissolve

within the drums. It should be noted that anhydrous HC1 is noncorrosive to

304 stainless steel (Reference 6.12). Therefore, sufficient moisture exists

in the form of adsorbed/ absorbed water in layers of containment in payload

containers to depress the vapor pressure of any ECl that may be present.

4.3 Reactivity of Waste Materials and frnternal

Surfaces of the Pavload Containers

For any small quantities of SCI gas that could be present in the payload con-

tainers, it is highly unlikely that any chlorides would reach the ICV. The

payload containers in which the waste is packaged are either carbon or gal-

vanized steel. ECl is much more reactive with these materials than the 304

2.10.9-6

to

vo

SHCL

TA3LB 2

PARTIAL PRESSURES OF BC1 OVER AQtJEODS SOLUTIONS OF B C l * ' b

•>ng. °c

2 11.8037 4736 0.0000117 0.000023 0.000044 0.000084 0.000151 0.000275 0.00047 0.00083 0.00140 0.00310 0.0100 0

4 11.6400 4471 0.000018 0.000036 0.000069 0.000131 0.00024 O.OOO44 0.00077 0.00134 0.0023 0.00385 0.0064 0.0165 0.0405 0

6 11.2144 4202 0.000066 0.000125 0.000234 O.O00425 0.00076 0.00131 0.00225 0.003S 0.0062 0.0102 0.163 0.040 0.094 0

8 11.0406 4042 0.000118 0.000323 0.000583 0.00104 0.00178 0.0031 0.00515 0.0085 0.0136 0.022 0.0344 0.081 0.183 0

10 10.9311 3908 0.00042 0.00075 0.00134 0.00232 0.00395 0.0067 0.0111 0.0178 0.0282 0.045 0.069 0.157 0.35 0

12 10.7900 37C5 0.00099 0.00175 0.00305 0.0052 0.0088 0.0145 0.0234 0.037,

14 10.6954 3636 0.0024 0.00415 0.0071 0.0118 0.0196 0.0316 0.050 0.078

16 10.6261 3516 0.0056 0.0093 0.016 0.0265 0.0428 0.0685 0.106 0.163

18 10.4957 3376 0.0133 0.0225 0.037 0.060 0.095 0.148 0.228 0.345

20 10.3833 3245 0.0316 0.052 0.084 0.132 0.205 0.32 0.48 0.72

22 10.3172 3125 0.0734 0.119 0.187 0.294 0.43 0.68 1.02 1.50

24 10.2185 2995 0.175

26 10.1303 2870 0.41

28 10.0115 2732 1.0

30 9.8763 2393 2.4

0

0

1

3

.277

.64

.52

.37

0

0

2

5

.43

.98

.27

.23

0

1

3

7

.66

.47

.36

.60

1

2

4

10

.00

.17

.90

.6

1

3

7

13

.49

.20

.05

.1

2.

4.

9.

21.

17

56

90

0

3.

6.

13.

28.

14

50

8

6

4

9

19

39

.5

.2

.1

.4

6

12

26

53

.4

.7

.4

8

17

35

71

.9

.5

.7

0.058 0.091 0.136 0.305 0.66 1

0.121 0.185 0.275 0.60 1.25 2

0.247 0.375 0.55 1.17 2.40 4

0.515 0.77 1.11 2.3 4.55 8

1.06 1.55 2.21 4.4 8.5 15

2.18 3.14 4.42 8.6 16.3 29

16.9 31.0 54

32.5 58.5 100

64 112 188

124 208 340

* Party and Graaa. 1984 (Sataranoa 6.10)

• A - B/T, vhlck. kovavar. agraat only tpproilaataly witk tka ttbla. Tka tibia ia aora naarly corraot.

H

M

O

H

1VMH

nH

tooo

ifl£L.

00

32 9.7323 2457 3.7

34 9.6061 2316 13.1

36 9.3262 2229 29.0

38 9.4670 2094 63.0

40 9.2136 1939 130

42 S.9923 1800 233

44 I.1621 1681 310

46 940

1.3

18. 8

41.0

87.0

176

332

633

11.8

26.4

36.4

117

233

430

840

K.I

36.8

78

138

307

360

23.3

30.3

103.3

. 210

399

709

32.3

61.3

142

277

313

900

44.3

92

18 <

3<0

627

(0.0

122

246

463

830

81

161

322

398

107

211

416

73t

141

273

333

933

238

430

860

390 623

720

to

oo

sn

mn

8TABLE 2

PABTIAL PRESSURES OF EC1 OVEE AQUEOUS SOLUTIONS OF HCl*'b

««Hi. °C

(Contlnncd)

HM

* P.rry (nil 0r. .o . 1984 (B.f.r.oo. 6.10)A - B/I. vhich. how«T«r< *ft««i only approxluttlj vltk tk* t iblt . Tk« tabl* la aota laacljr oorcaot.

o

00

NnPac TRUPACT-II SAE Rev. 0, February 1989

SS. HC1 will also have an affinity for some contents of the waste. An ex-

ample of this is hydrolization of cellulose, which is present in substantial

amounts in the waste (Reference 6.13). The small amounts of HC1 produced are

expected to be consumed in reactions with these materials and therefore be

unavailable for transport into the ICV.

5.0 CONCLUSION

In assessing the potential for stress corrosion cracking, it is apparent that

the nature of the waste and the conditions under which the waste will be

transported, should preclude the possibility of producing significant quan-

tities of free HC1 gas in the payload containers. Alpha radiolysis of PVC

does not produce appreciable amounts of HC1 gas, and any small quantities of

the gas generated are likely to be retained in the payload containers, thereby

limiting transport to the ICV cavity.

6.0 REFERENCES

6.1 Tokiwai, et. al, Moriynsu Tokiwai, Hideo Kimiura, and Hideo Kusangi,

Corrosion Science. Vol. 25, No. S9, pp. 837-844, 1985.

6.2 Zerwekh, A., 1979, 'Gas Generation from Radiolytic Attack of TRU-

Contaminated Hydrogeneous Waste, 'Los Alamos National Laboratory, LA-

7674-MS, June 1979.

6.3 Kazanjian, A. R, and Brown, A. K., 'Radiation Chemistry of Materials Used

in Plutonium Processing,' The Dow Chemical Company, Rocky Flats Division,

RFP-1376, December 1969.

6.4 Kazanjian, A. R, 'Radiolytic Gas Generation in Plutonium Contaminated

Waste Materials,' Rockwell International, Rocky Flats Plant, RFP-2469,

October 1976.

2.10.9-9


6.5 Kosiewicz, S. T., 'Gas Generation from Organic Transuranic Wastes. I .

Alpha Radiolysis at Atmospheric Pressure, ' Nuclear T^nh^ology 54. pp. 92-

99, 1981.

6.6 Hobbs, David, Personal Communication,. Savannah River Plant, Feb. 1989.

6.7 Clements. T. L., J r . , and Zudera, D. E. , 'TRU Waste Sampling Program:

Volume I , Waste Characterization' , Sept. 198S, EGG-WH-6503.

6.8 Roggenthen, D. K., HcFeeters, T. L., and Nieweg, R.A., 'Waste Drum Gas

Generation Sampling Program at Rocky Flats During FI 1988', RFP-4311,

March 1989.

6.9 Treybal, R.E., 1980, Mass Transfer Operations. McGraw-Hill Book Company,

New York.

6.10 Perry, C. H. , and D. Green, Eds . , 1984 Chemical Engineers Handbook.

HcGraw Hil l Book Company, New York.

6.11 Simmons, B i l l , Rocky Flats Plant Personal Communications, 1988.

6.12 Kirk, R.E., and D.F. Othmer, Eds., 1966, Encyclopedia of Chemical

Technology. Vol. 11 , John Wiley and Sons, New York.

6.13 Young, R. A., and R. M. Rowell, Eds., 1986, 'Cellulose: Structure Modi-

f icat ion, and Hydrolysis', John Wiley and Sons, New York.

2.10.9-10

NuPac TRUPACT-II SAR Rev. 3, July 1989

APPENDIX 2.10.11

VOIATILE ORGANIC COMPOUNDS (VOC) IN THE TRUPACT-II

PAYLOAD - SOURCE TERM AND RELEASE RATE ESTIMATES

NuPac THUPACT-II SA2. Rev. 0, February 1939

APPENDIX 2.10.11

VOLATILE 02SANIC COMPOUNDS (VOC) IN THE TRUPACT-II

PAYLOAD - SOURCE TSRH AMD RELEASE RATE SSTIKATES

i.O SUMMARY

Volati le organic compounds (VOC) are used by some of the Department of Energy

(IX)E) s i tes as part of t he i r process operat ions . The "presence of VOCs in the

transuranic package t ranspor te r (TRUPACT)-II payload, and the i r possible r e -

lease into the TRUPACT-II cavity during t ranspor t , are of concern for two

reasons. F i r s t , is potent ia l damage to the butyl rubber 0-ring seals due to

interact ion "tith. the VOC vapors that could diffuse from the payload con-

t a i n e r s . Second, is the contr ibut ion to the overal l pressure in the inner

containment vessel (ICV) cavity by the vapor pressure that might be exerted by

these chemicals. This Appendix evaluates these concerns by an analysis of

•.vaste generation processes at the s i t e s , current and past sampling programs,

and the payload configuration in TRTJPACT-II.

T.7aste types <.hat are incwn to contain VOCs in appreciable amounts (sol id i f ied

crganics) are r e s t r i c t ed from being a par t of the TRUPACT-II payload, unless

i t can be shown ly actual t e s t ing that these content codes are safe for t r ans -

por t . The VCCs can. be present in the other waste types only in trace amounts

of less than one percent by weight. Sol idif ied aqueous or homogeneous inor-

ganic solids w a s t e Type I) are processed through a vacuum f i l t r a t i o n tech-

nique prior to s o l i d i f i c a t i o n in a payload container. The vacuum f i l t r a t i o n

process great ly reduces the amount of t race VOCs in the waste. A similar

reduction in VOCs also occurs for many inorganic and organic solid wastes

(Waste Types II and I I I ) generated in processes that are operated under

slightly negative pressures. Examples are wastes generated from gloveboz

lines. Results from sampling programs support these conclusions.

2.10.11-2

XnPac T33PACT-II 3AR Hev. 0, February 1939

•iiiy residual iuounts of VlsCs .-/ithin the v;aste in a payload container are i a -

.;sded croii being released during transport because of additional chemical and

physical l a r r i e r s . ?or .?ast e types with bound water ( i . e . , ' jeliuified aqueous

cr homogeneous inorganic so l ids ) , the vapor pressure of the organics is r e -

lucsd appreciably. Quantitative analysis , along v.'ith data from sampling pro-

; r a j j , is presented in folloTrins sections.

Izperi mental resul t s also indicate that the diffusion of the VOCs through the

carbon conposite f i l t e r s in the payload containers is extremely slow. Due to

the mul t ip le processes mentioned above, the source term for the YOCs i s

l i a i t e d . YOCs present ',a residual amounts in the waste are not expected to

diffuse from the heaaspace of the payload containers into the ICV of the

T7JEPACT-II lr. any >dgnif icant quan t i t i es . Therefore, for the ~aste types

expected to be transported in TRUPACT-II, the presence of VOCs in the TSUPACT-

I I cavity should not be an issue of concern.

2.0 INTRODUCTION

Volatile organic compounds (VOCs) include those organic compounds that esert

appreciable vapor pressures at normal temperatures. Zsamples are halogenated

compounds like 7reon-II3 and aethylene chloride, and lower molecular weight

ulcohois ( e . g . , .nethancl). Some of these compounds axe used at the DOE s i tes

as i^jlustrial soi /ents c.nd in decontamination operations. The potential of

ihese voiat i les being present in the payload cf TPJJPACT-II is of concern for

the following reasons:

The vapor pressure ezerted by the volat i les isay contribute to the

to t a l pressure in the THUPACT-II cavity.

Some of the organic solvents could potent ial ly cause damage to the

butyl rubber 0-rings in the package during t ransport .

2encs, evaluation of the VOCs vri th respect to the payload and the package is

necessary in order to ensure safe transport of THUPACT—II. The following

sections discuss the source term of the VOCs in the TSOPACT-II payload and

estimates cf the -please of these VOCs into the T2U?ACT-II cavity. Data from

2.10.11-5

NnPac THDPACT-II SAR Rev. 0, February 1989

past and ongoing sampling programs a t the DOE s i t e s and laboratory experiments

are analyzed to draw conclusions about these parameters. Wherever relevant,

the different waste types expected to be part of the pay load are discussed

separately. (For a description of the c las s i f i ca t ion of waste materials into

waste types, please see Section 1.2.3.2 of the SAR.)

3.0' SOURCE TERM OF VOCS IN DIFFERENT WASTE TYPES

Solidified organics (Waste Type IV) are the only waste type with organic so l -

vents as the main constituents of the waste. At the present time, pay load

containers belonging to th is waste type cannot qualify for shipment unless i t

can be demonstrated by test ing each pay load container that i t is safe for

transport purposes. The t e s t procedure to be followed i s detailed in Attach-

ment 2.0 of Appendix 1.3.7. For example, a container in th is class would have

to be tes ted under normal transport conditions to demonstrate that the maximum

pressure l imits imposed on the package are not exceeded. The same is true for

the other t ransport parameters. Testing of a population of payload containers

from a content code belonging to Waste Type IV could qualify the content code

for shipment.

The remainder of the waste types have VOCs only in trace amounts of less than

one percent by weight. While this i s an upper bound on the amount of VOCs,

waste genera t ion procedures l i m i t the VOC c o n c e n t r a t i o n s in these waste

streams to much lower concentrations:

* Generation of sol idif ied aqueous or homogeneous inorganic solids

(Waste Type I) usually involves a vacuum f i l t r a t i o n step (to dewater

the waste stream) which reduces the amount of trace VOCs in the

waste.

Solid inorganic and organic wastes (Waste Types I I and I I I ) are

generated from gloveboxes that are operated under negative pressures

which acts to reduce the amounts of residual VOCs in the waste.

2.10.11-4

HuPac T2SPACT-II 3A2. Ilev. 0, February 1939

* 3enerat3r znu storage sites will cit3 reportabls quantities of some

VCCJ wen if the material is suspected of being present in negligi-

ble quantities. This reporting is necessary to comply vith Sesourc-?

Conseirva tion and Zecovery Act (B.C2A) regulations tliat a l i s t ed

material is in a '.Taste until proven to be absent (belev testability

l imit) .

4.0 eCCTZSZ.'CZ ?.~ VOCS IN' CH-T3U WASTE FROM SA ISLING PROGRAMS

4.1 Svi-5er.ee ?rc:3 Sampling ?ra?raa at Rocky F la t s Plaat (5FP)

Ai j ; r t of a recent sampling program at Rocky F l a t s Plant i?JFP) (Reference

7.1), twenty- c::o .Iruzis ./ere sampled for headspace-gas composition and for

organic compounds in tke inner confinement l ayers , and where possible , in the

innermost layer of confinement with the waste. Table 1 l i s t s the r e s u l t s of

this sampling along v>'ith re levant information en the individual drums. The

r e s u l t s of t h i s sampling program are discussed by "jraste type below.

4.1.1 Analyses cf Sol id i f ied Aqueous Inorganic Solids ~ '.Vasts Type X

Ten drums in th i s category were tes ted as part of the sampling program. The

drur-s ;?ere analyzed for t h i r i y - s i z (36) compounds that are l i s t e d in Table 2 .

The tan Taste drums represent a cross sect ion of drums generated at the Rocky

Flat:: Plant end re t r i evab ly s tored a t INEL. Five of the ten drums Vfere f i l l e d

between 1983 and 1934, two were f i l l e d in 1973, and three were newly generated

in 1S3S. Only tv/o of the ten drums had carbon composite f i l t e r tfents in the

drum l ids p r io r to opening. For five of the ten drums, the sludge also was

analyzed for v o l a t i l e organic componds.

2.10.11-5


TABLE 1SUMMARY OF ROCKT FLATS PLANT SAMPLING PROGRAM

Gas Sample A n a l y s i s a '(Head Space) (Vol %)

DrumMtmbe r

625425972862815

7411-28087411-25787412-03850

7412-029177412-03492-4145058642

7440238724065874316881

74317069741204577747034467431693025004840028006582425332349063201073

WasteTvtie

II

I

II

II

II I II I II I II I

IV

rvi

i

IV

rvI II II II I

Date DrumFilled

6-21r886-20-887-10-884-9-732-9-738-2-849-7-83

3-9-846-7-886-7-881-22-736-22-83

4-3-8412-5-843-26-851-7-855-25-844-17-859-28-82

2-21-842-21-8412-5-83

CC14 TRIC FREON

3.91.5

0.3

0.8

3.5 0.80.40.1

0.8

COL. Carbon tetrachlorideTRIC = 1,1,1 - TrichloroethaneFREON = 1,1,2 - Trichloro - 1,2,2 - Tr if luoroe thaneCH2&2 = Methylene chloride (dichl orme thane)

Detection limit: 500 ppm for al l gases.

2.10.11-6

I.'nPac mUPACT-II JAS ?.ev. 0 . .Tebriiary 1239

TABLE 2

ORGANIC COMPOUNDS CAtilLLJ *7OR 121 RCCSY FLATS ?LAM PR

'Jilcroae th.ans

_<rono..ie tliane

Jiilorostliaue

.letLylene ciiloridu-

Ace tone

Carbon disulfi.lc

I , I-D i ch.1 oro e the n e

1,1-Dichloroethane

1,2-Dici.loroethene (total)

Clilorcf oru

1,2-Dicj.Icroe thane

2-Butanone

i,l#l-Trichloroethane

Carbon Tetrachloride

FREON TF

2roaodichloromethane

1,2-Dicliioro pro pane

Cis-I»3-Dichloropropene

Trichloroethene

Dibromochloromethane

1,1,2-Trichloroethane

Benzene

Irans-i,3-Dichloropropene

Droinof era

4-lie thy 1-2-Pentanone

2-Hexanone

Te trachloroethene

1,1,2,2,-Tetrachloroethane

Toluene

Clilorobenzene

Zthylbenzene

Styrene "

liylenes (total)

Isopropanol

outanoi

2.10.11-7

NoP»c TRUPACT-II SAR Rev. 1, May 1989

None of the drums had detectable quantities of VOCs in the head space (between

the liner and the outer bag), the outer and inner bags or inside the inner bag

next to the waste. Analysis of s o l i d i f i e d inorganic waste from f ive

retrievably stored drums did not detect any traces of VOCs in four out the

five drums (Table 3) . The waste from one drum (No. 7411-2808) contained nine

of the organics at low ppm levels (0.9 ppm to 19 ppm). These organics did not

appear in any of the containment layers or in the headspace of the drum

between the l iner and outermost drum liner bag.

None of the newly generated waste drums showed any traces of the organics in

the headspace or layers of confinement. The drum with the ppm levels of some

of the organics was the one f i l l ed in 1973 and vented at the INEL fac i l i ty .

This means that the drum had been vented for at least a period of eight weeks

prior to being part of the sampling program. The absence of detectable

quantities of VOCs in nine of ten solidified inorganic solids demonstrates

that the vacuum f i l t r a t i o n technique for these sludges i s e f f ec t ive in

lowering the concentration of VOCs in the waste. The presence of ppm amounts

of the VOCs in the one sludge and the absence of the VOCs from the headspace

(in spite of the vented drum) are evidence to the fact that any residual VOCs

tend to stay with the waste. These data support the conclusion that the VOCs

present in the waste are in low ppm or less amounts, with the source term

itse l f being very limited.

4.1.2 Analysis of Solid Inorganics - Waste Type II

Five drums of Waste Type II were analyzed for gaseous components in the dif-

ferent confinement layers and the head space of the drums. Three of the five

drums did not show any of the organics, one (No. 242553) had up to 0.1 volume

percent of 1,1,1-trichlorethane, while the f i f th drum (No. 002800658) had up

to a maximum of 0.4 volume percent of l ; l , l - trichloroethane in some of the

individual packages. These drums were made up of mostly glassware, some of

which contained residual amounts of the 1,1,1-trichloroethane. The concen-

trations measured in these drums are well below the saturation concentration

of the organic liquid (13% from vapor pressure considerations), indicating

that the organic liquid is present in only very small amounts.

2.10.11-8

NuP*c TRUPACT-II SAR Rev. 0, February 1989

TABLE 3

VOLATILE OEGANIC ANALYSIS OF SLUDGE SAMPLES

Amount (PPM) by Drm Number

Volati leCompounds

1,2-Dichloroethene

(Total)

Chloroform

7411-2808

7.8

1.8

7412-02917

Ua

U

7412-03492

U

U

7412-03850

U

U

1,1,1-Trichloroethane 8.8

Tetrachloroethene 1.7

1,1,2,2- 4.7

Tetrachloroethane

Toluene

Ethylbenzene

Styrene

Total Xylenes

0.9

5.3

9.6

19.

u

u

u

u

u

u

u

u

u

u

u

u

u

u

7411-

2578 BLD1

U

U

U

U

U

U

U

U U

0.1 PPM

0.1

0.1

0.1

0.1

0.1

0.1

0.1

0.1

a U = undetected.

^ BLD = Beyond lower detection limit.

2.10.11-9

NuPac XEUPACT-U 2X3. Rev. 0, 7ebruary 1389

Analysis jf Colid 3r; 3 ~ '»aste

I l ree iru^s bslo^gi-^ ;•: -;Iiis ".vaste type vere analyzed- in t ie sampling pro-

^ran, 2nd none of tiiem had any detectable amounts of t i e lialogenated organics.

Lov/ concentrations (0.08 volume ii) of hydrocarbons were present in one of the

4.1.4 Analysis of Solidified Oraaaics — ;."aste Tves IV

As mentioned earlier ir. t.h.is Appendix, Waste Type IV belongs in tiie test cate-

gory due to the possible presence of appreciable amounts of VOCs in the head-

space of the pay load containers. 2esults froa the sampling of four of the

druas in this \:a£te I7pe ere presented here as supporting evidence that tie

VGCs are generally present in a non-volatile form in the waste. While VCCs

coulil have been present at near-saturation levels in these drums (solidified

organics waste type and the drum not vented), the results show that the VOCs

are present in fa i r ly low concentrations. One of the four drums (Mo.

74316930) did not have any detectable quantities of YQCs in any of the con-

finement layers. I.'o analyses of the organic sludge samples are available.

The aaziama concentration of any VOC found in the three other drums was 3.9

volume percent for carbon tetrachloride.

These results seem to indicate that even if a finite supply of the organics

v/as available, the nature of the waste limits release of the vapors into the

hsail space. Until .luantified information can be obtained, this -.raste type is

assigned to the test category.

Carbon tetracloride has the lowest saturated vapor pressure (Table 4) of the

four common solvents found in defense waste ( i . e . , carbon tetrachloride,

Freon-113, methylene chloride and 1,1,1-trichloroethane). The fact that only

carbon tetrachloride vas detected in the headspace of the solidified organic

drums provides evidence that the other organic solvents commonly associated

with this waste form have volatilized prior to drum closure.

2.10.11-10

MnPac T2UPACT-II GAR Rev. 0, rebruary 1589

4.2 ITLTJ "vaste Sanrplim: Program at IMEL

Tlie T2U "..'aste 3iaipli;i^ Program vas conducted between 1283-1935 at JICEL

("lefarence 7.2/ in an effort to characterize the retrievably scored ./aste at

J.'.EL'. In this i.-rogran, 210 drums v/ere sampled and analyzed for headspace gas

composition. Table 5 summarizes the resul ts on th.e VOC analyses ay T/aste type

and provides mailnun, uininam and average concentrations along with the sample

jize.

Axnon;: the thirty-t-.ro drums sampled in Waste Type I , four of the VOCs were not

present in any of ;he drums, and average concentrations of the other four

ranrred between 0.0025 and 0.193 volume percent. Tiiis sampling program was

-czducted even jefore transport requirements for the TRSFACT-II package were

formulated. The results of the program indicate that by process history, the

source term of The VOCs is limited. Similar results can be seen for *>7aste

Types I I and I I I v/here the average VOC concentrations were orders of magnitude

below their saturation levels. Even among th.e twenty—three drums of Tfaste

Type IV that were sampled, three of the VOCs were not present in the head

space at a l l , and average concentrations of those present vfere below 1.4

volume percent. These results once again i l lustrate that th.e VOCs are in the

vaste in limited quantities and/or the bound nature of the VOCs even in the

case of the organic sludges.

2.10.11-11


TABLE 4

VAPOR PRESSURES OF ORGANIC SOLVENTS

ABOVE A PURE LIQUID PHASE*

Comp ound

Vapor Vapor

Pressure Temperature P r e s s u r e Temperature

Xylene 20 mm Hg 104°F 60 mm Hg 146°F

1,1,1-Triphloroe thane 400 mm Hg 130°F 760 mm Hg 165°F

1,1,2-Trichloro - 760 mm Hg 118°F 1520 mm Hg 158°F

1,2,2-Trifluoroethane

(Freon-113)

Carbon Tetrachloride 200 mm Hg 100°F 760 mm Hg 170°F

Methlyene Chlor ide

(Dichloromethane)

760 mm Hg 105 °F

* Green, D. W., 'Perry's Chemical Engineers' Handbook,', 6th ed., McGraw-

Hill Book Company, 1984

2.10.11-12

NuPac T2UPACT-II 3AR Hev. 0 , February 1989

SUMARIVX ANALYSIS Hi T2U WASIE SAMHJHG IR0G2AM

Waste , 1.2 TOTALm

Type TRICE3 n S C P 0 T^ re rny 0 CCU SOf* DCEIHAe ERBCNf CYC5ESg 3CEBY11 VOC

•I1 laffi 0.94 0 0.04 0.04 0.22 0 0 0 0 1.17

I 3N 0 0 0 0 0 0 0 0 0 —

I AVG 0.1378 0 0.005 0.0025 0.0203 0 0 0 0 —

IIJ IIS 2.34 0 0.17 0.09 0.42 0.4 0.81 0.17 0.03 2.34

ii a i o o o o o o o o o —I I AVG 0.2669 0 0.0043 J.0029 0.0230 0.0106 0.0103 0.0021 0.0003 —

inkJ2fi 1.06 0.62 0.14 0.29 0.25 0 2.37 0 0 3.37

m M o o o o o o o o o —i n AVG 0.1238 0.0201 0.0087 0.0068 0.0089 0 0.0389 0 0 —

I71 5HS 7.48 0 0.14 4.09 0.71 0 10.4 0 0 17.88

r/ raw o o o o o o o o o —IV AVG 1.3582 0 0.C213 0.6734 0.0726 0 1.0717 0 0 —

a. 12IC3L = Tricaloroetiane

b. URCP = Isopropyl alcohol

c. TPXEHII = Trichloretiylene

d. DCI = Bichlorcnse thane

e. 1,2 DCEIEA = 1,2 - Dichloroethane

f. rREON = rKEOf-113 (1,1,2 - Trichloro - 1,2,2 - Trifluoroethane)

g. CZCSEX = Cyclohexane

h. DCEmr = Dichloroethylene

i . 32 drcms V/aste Type I •v/ere sanroled.

j . 73 drums Waste Type I I were sampled.

k. 77 drnns Waste Type I I I were sampled.

1. 23 drums '.7aste Type IV were sampled.

zi. IJaziaxm total ^JCC in any drum

2.10.11-13


5.0 RELEASE OF VOCS FROM THE WASTE INTO THE PAYLOAD CONTAINER

The vapor pressure of a pure compound is generally not completely exerted when

the compound is in a combined form with other substances. Any residual VOCs

present in the waste wil l therefore exert only a portion of the i r vapor pres-

sures and tend to stay in a bound form. An example is presented below for the

case of methyl alcohol, which is the most vo la t i l e alcohol documented in the

waste from an analysis of process technology.

The maximum amount of methyl alcohol expected in any of the waste forms based

on process technology i s 250 ppm. If a waste form contains bound water, the

v o l a t i l i t y of the alcohol wil l be reduced. A waste type containing 50% bound

water ( typical for Waste Type I) and 250 ppm of methyl alcohol would have the

alcohol exerting a vapor pressure of only 0.12 mm Hg over the aqueous mixture

at 40°C (Reference 7 .3) . The vapor pressure at 60°C would be 0.26 mm Hg. The

data presented in the previous section for halogenated organic compounds d i s -

played evidence of reduced v o l a t i l i t i e s in actual waste mater ia ls .

6.0 5SLEASE OF VOCS FROM PAYLOAD CONTAINERS

All pay load containers in the TRUPACT-II pay load are f i t t e d with carbon com-

posite f i l t e r s , one in each drum and two in each Standard Waste Box (SWB).

Experiments were conducted to speci f ica l ly evaluate release r a t e s of two of

the VOCs (1,1,1-tr ichloroethane and carbon tetrachloride) through the carbon

composite f i l t e r s . Results from this tes t ing are presented in Attachment 1.0,

along with a discussion of the possible mechanisms for diffusion of the VOCs

through the carbon composite f i l t e r s . Release ra tes of these VOCs through the

f i l t e r s (even under saturated conditions of the vapor on one side, which is

not representative of the waste) are extremely slow. Assuming saturated con-

di t ions of carbon tetrachloride in the headspace of fourteen drums in a

TRUPACT-II payload, and a diffusion coefficient of 1.05E-11 mole/sec/mole

fraction (Table Al-1, Attachment 1) , the maximum concentration reached in the

TRUPACT-II cavity vfould be only around 1.0E-3 mole percent in an assumed

sixty-day shipping period. Independent evidence of the slow release of the

VOCs from the payload containers i s seen from the experimental studies con-

2.10.11-14

NnPac T2TJPACT-II 3AR Ilev. 0, February 1989

ducted at the I2TEL faci l i ty (Zeference 7.4) . The concentrations of t r ichloro-

etiiane and methyiene chloride i s the head space of a drum of combustible -.Taste

{which -.7as rented with a carbon composite f i l t e r remained constant at 6 and

i . - i respectively during thirteen weeks of venting (see Figure A-8d, I b id . ) .

These yoncentraticns -.?ere lower than the saturated concentrations of 13ft for

trichloroe thane and 3£-.i for uiethylene chloride vaich indicates that the source

of rhe VOCs ir. the waste is limiting. I t is also possible that the vapor

presence of the organics are depressed by the presence of other compounds.

After purging and sealing the drum, the concentration of each VOC remained

oeiow 3vi, once Lgain indicating that the source term of the VOCs was limited.

Conciusi c~s

Ths following conclusions can be dravm from an evaluation of existing informa-

tion on VOCs in CII-TRU .7aste:

1. For materials espected to be shipped in T2.TJPACT-II, the source term of

the YOCs is rery small by the very nature of waste generation

processes. T/aste types inown to contain appreciable amounts of VOCs are

not allowed to be a part of the TE.UPACT-II pay load unless each container

is tested under shipping conditions and shown to be safe for transport

•.intil sufficient data have been collected to allow a content code to be

certified for shipment.

2. Izperiaental studies jhow that VOCs present in the waste are well below

saturation levels and in ppm levels in most cases.

3. The residual YOCs in the -waste tend to be bound in the waste and do not

migrate out of the payload containers. Thus, the residual VOCs do not

pose a problem with respect to incompatibilities with the T2IJPACT-II

package.

4. The carbon composite f i l t e r s in the payload containers tend to retain any

VOCs that aay be present in the head space of the containers. Experimen-

tal resul ts ind previous sampling programs support this conclusion.

2.10.11-15

NnP»c TKUPACT-II SAR Rev. 0, Febrnary 1989

• • 7.0 REFERENCES

7.1 Roggenthen, D. K., T. C. McFeeters, R. G. Nieweg, 'Waste Drum Gas Genera-

. t ion Sampling Program at Rocky F la t s During FT 1988' ' RFP 4311, March

1989.

7.2 Clements, T. L., and D. E. Kudera, 'TRU Waste Sampling Program: Volume

I—Waste Character izat ion, ' EG and G Idaho, INEL, Idaho Fa l l s , Idaho,

EGG-WM-6503, September, 1985.

7.3 Perry , H. H., ' P e r r y ' s Chemical Eng inee r s ' Handbook,' 6 th E d i t i o n ,

McGraw-Hill, Inc . , New York, New York, Table 3-8, p . 3-61, 1984.

7.4 Clements, T. L., and D. E. Kudera, 'TRU Waste Sampling Program: .Volume

II—Gas Generation Studies , ' EG and G Idaho, INEL, Idaho Fa l l s , Idaho,

EGG-Wtf-6503, September, 1985.

7.5 Smith, J . M. , Chemical Engineering Kinetics, McGraw Hi l l , NY, 1981.

2.10.11-16

NuP*c TRUPACT-II SAR Rev. 0, February 1989

ATTACHMENT 1.0

SUMMARY OF VOC DIFFUSIVITIES THROUGH CARBON COMPOSITE FILTERS

The estimated diffusion coeff ic ients of carbon t e t r ach lo r ide and 1 ,1 ,1 - t r i ch -

loroethane diffusing through the carbon f i l t e r s a t 12 and 24°C are summarized

in Table Al -1 . These diffusion coef f ic ien t s are approximately five orders of

magnitude lower than what would be predicted from a combination of k ine t i c

theory and corresponding s ta tes arguments for ordinary (molecular or Fickian)

diffusion^ Ihudsen diffusion in which the gas molecules tend to col l ide with

the fil ter, rather than with each other, is insignificant since the mean-free-

paths of the diffusing gas molecules are small in comparison to the diameter

of the pores (33-54 micrometers). Another transport mechanism which is pro-

bably important in the diffusion of the gas molecules through the filters is

surface diffusion. This phenomenon takes place by the jumping of molecules

between adsorption sites. Two alternatives are available to an adsorbed mole-

cule: desorb into the gas phase by overcoming the energy of desorption, or

hop to an adjacent active site on the pore wall by overcoming an energy for

surface diffusion (Reference 7.5).

2.10.11.A1-1

NuPac TRUPACT-II SAR Rev. 3 , July 1989

TABLE Al-1

SUMMARY OF ORGANICS MASS DIFFUSIVITIES THROUGH FILTER

DiffusionTemperature Coeff ic ient

F i l t er Description (°C) (so m/sec)

DiffusionCoefficient

(mole/sec/molefraction)

NFT-16 : Carbon-Tetrachloride

24 3.13E-12 5.60E-12

NFT-18 : Carbon-

Tetrachloride

24 4.10E-12 7.34E-12

NFT-22 : Carbon-

Tetrachloride24 5.86E-12 1.05E-11

NFT-16 : 1,1,1-

Trichloroethane

12 7.47E-12 1.39E-11

NFT-18 : 1,1,1-

Trichloroethane24 4.14E-12 7.41E-12

NFT-18 : 1,1,1-


NFT-22 : 1,1,1-


NFT-22 : 1,1,1-


NFT-16 : Carbon-

Tetrachloride

12 1.03E-12 1.92E-12

NFT-18 : Carbon

Tetrachloride

12 1.01E-12 1.88E-12

NFT-22 : Carbon

Tetrachloride

12 9.62E-13 1.79E-12

2.10.11.A1-2


APPENDIX 2.10.12

CHEMICAL COMPATIBILITY OF WASTE FORMS


APPENDIX 2.10.12

CHEMICAL COMPATIBILITY OF WASTE FORMS

1.0 INTRODUCTION

This appendix describes the method used for demonstrating chemical compatibility

in a given payload container, within a given content code and among content

codes to simulate mixing of waste during hypothetical accident conditions.

2.0 CHEMICAL COMPATIBILITY ANALYSES

The chemical compatibility analysis was performed using the methods described

in the EPA document "A Method for Determining the Compatibility of Hazardous

Wastes" which is Reference 3.1. Content codes are classified as 'incompatible'

if the potential exists for any of the following reactions:

corrosion

explosion

heat generation

gas generation (flammable gases)

pressure build up (nonflammable gases)

toxic by-product generation

Each generator and storage site has produced a comprehensive list of all pos-

sible chemicals present in their waste. The 'chemical components found in each

waste generation process are determined by examining the process technology, by

chemical analysis, or by process flow analysis. Under this system, all chemi-

cal inputs into the system are accounted for, even though all of these components

may not be a part of the waste. For example, generator sites might include both

acids and bases in their lists, even though the two groups have been neutralized

prior to placement in a payload container.

The chemical concentration levels are reported as either Trace (T)(<1X by

weight), Minor (M)(l-10%), or Dominant (D)(>10%). The list is divided into

2.10.12-1


groups based on chemical properties and structure (e.g., acids, caustics, metals,

etc.). Table 1 lists all the groups and their number designations. As noted in

the table, the groups and examples listed are only for illustrative purposes, and

do- not necessarily represent components of waste materials in a TRUPACT-II

payload. A listing of all chemicals present in the waste by waste material type

| (i.e., I.I, 1.2, 1.3, II.1, II.2, III.l and IV.1) is provided in Appendix 1.3.7.

(Subsequent references to waste types will use the condensed list of I, II, III

and IV.) If incompatible groups are combined, the possibility exists for the

reactions listed above. For example, a reaction between Group 1 (Acids, Mineral,

Non-oxidizing) and Group 10 (Caustics) could result in heat generation. The

chemical compatibility criteria (Reference 3.1) were entered into a computer

database program to determine all combinations of such potential incompatibilities

in the waste types. Incompatibilities have been defined within each content code,

. and where mixing of content codes could occur under hypothetical accident

conditions.

Interactions between compounds present in trace quantities (<1 percent by weight)

and compounds present in concentrations > 1 percent by weight (i.e., D x T, M x T,

or T x T) do not pose an incompatibility problem for the following reasons:

• Total trace chemicals within a payload container are limited to less than

5 weight percent.

The trace chemicals reported by the sites are in concentrations well

below the trace limit of 1 weight percent. An example is the Volatile

Organic Compounds (VOCs) discussed in detail in Appendix 2.10.11.

Sampling programs show that the concentration levels of these compounds

are significantly lower than the upper limit of 1%.

The trace chemicals are usually dispersed in the waste which further

dilutes concentrations of these materials.

Trace chemicals that might be incompatible with major and dominant

materials/chemicals would have reacted during the waste treatment process

prior to placement in payload containers.

2.10.12-2


TABLE 1

EPA LIST OF CHEMICAL GROUPS AND MATERIALS*

GROUP NUMBER

1. 234

. 5678

910111213

' 14151617181920

21

GROUP NAME

Acids, Mineral, Non-OxidizingAcids, Mineral, OxidizingAcids, OrganicAlcohols and GlycolsAldehydesAmidesAmines, Aliphatic and AromaticAzo Compounds, Diazo Compoundsand HydrazinesCarbamatesCausticsCyanidesDithiocarbamatesEstersEthersFluorides, InorganicHydrocarbons, AromaticHalogenated OrganicsIsocyanatesKetonesMercaptans and otherOrganic SulfidesMetals, Alkali and AlkalineEarth, Elemental

EXAMfLt.

Hydrochloric AcidNitric Acid (>1X)Acetic AcidMethanolFormaldehydeAcetamideAnilineHydrazine

CarbarylSodium HydroxidePotassium CyanideManebVinyl AcetateTe trahydro furanPotassium FluorideTolueneCarbon TetrachlorideMethyl IsocyanateAcetoneCarbon Disulfide

Metallic Sodium

Modified from "A Method for Determining the Compatibility of HazardousWastes," Reference 3.1.

NOTE: The chemical groups and materials listed in this table are a comprehensivelisting of chemical compounds that may be incompatible. This is not meant toinfer that all the listed chemical compounds and materials are present in TRUwaste.

2.10.12-3


GROUP NUMBER

TABLE 1


(CONTINUED)

GROUP NAME EXAMPLE

22

23

24

25262728

29

30

3132

3334

Metals, other Elemental andAlloys in the form of Powders,Vapors or SpongesMetals, other Elemental andAlloys as Sheets, Rods,Moldings, Drops, etc.Metals and Metal Compounds,ToxicNitridesNitrilesNitro CompoundsHydrocarbons, Aliphatic,UnsaturatedHydrocarbons, Aliphatic,SaturatedPeroxides and HydroperoxidesOrganicPhenols, CresolsOrganophosphates,Phosphothioates, andPhosphodithioatesSulfides, InorganicEpoxides

Titanium

Aluminum

Beryllium

Sodium NitrideAcetonitrileDinitrobenzeneButadiene

Cyc1ohexane

Acetyl Peroxide

PhenolMalathion

Zinc SulfideEpoxybutane

* Modified from "A Method for Determining the Compatibility of HazardousWastes," Reference 3.1.

NOTE: The chemical groups and materials listed in this table are a comprehensivelisting of chemical compounds that may be incompatible. This is not meant toinfer that all the listed chemical compounds and materials are present in TRUwaste.

2.10.12-4


TABLE 1


(CONTINUED)

GROUP NUMBER

101

102103104105106

107

GROUP NAME

Combustible and FlammableMaterials, MiscellaneousExplosivesPolymerizable CompoundsOxidizing Agents, StrongReducing Agents, StrongWater and Mixtures ContainingWaterWater Reactive Substances

EXAMPLE

Cellulose

Ammonium NitrateAcrylonitrileHydrogen PeroxideMetallic SodiumWater

Sulfuric Acid (>70%)

Modified from "A Method for Determining the Compatibility of HazardousWastes," Reference 3.1.

NOTE; The chemical groups and materials listed in this table are a comprehensivelisting of chemical compounds that may be incompatible. This is not meant toinfer that all the listed chemical compounds and materials are present in TRUwaste.

2.10.12-5

j TRUPACT-II SAR Rev. 14', October 1994i

Because of restrictions imposed by the Environmental Protection Agency

(EPA) on reporting of hazardous wastes, some chemicals are listed in

trace quantities even if they have already reacted. Hazardous waste

regulations as promulgated by the EPA (Reference 3.2) (known as the

mixture rule) require that a mixture of any solid waste and a hazardous

waste listed in 40 CFR Part 261, Subpart D be considered a hazardous

waste subject to RCRA regulations. However, Subpart D does not list

minimum concentrations for these listed wastes, with the result that any

such mixtures must be considered hazardous waste even if the Subpart D

constituent is at or below detection limits.

The waste is either solidified and immobilized (solidified materials) or

present in bulk form as a solid (solid materials). In almost all cases,

any possible reactions take place before the waste is generated in its

final form. Specific examples are outlined in Section 2.1.

Potential incompatibilities between minor and dominant compounds have been

analyzed on a case-by-case basis for each site. Some chemicals listed as being

present in the waste have reacted prior to becoming part of the waste. For

example, a site listing a caustic (Group 10) and an acid (Group 1) in their waste

has only the neutralized product present in an immobilized form. Further

reactions of this type do not occur once the waste is generated in its final form.

An additional constraint on the chemicals and materials that can be present within

each waste material type is their gas generation potential due to radiolysis.

Allowable chemicals in concentrations of greater than 1 weight percent within each

waste material type are provided in Appendix 3.6.7. These chemicals are

compatible within each waste type. In addition to being either solid or

solidified materials, the chemicals on the lists are restricted to bulk materials

that are in nonreactive forms. This means that within each waste material type,

materials are compatible across all ten DOE sites for Waste Material Types I.I,

1 1.2, 1.3, II.1, II.2, III.l, and IV.1.

Unresolved incompatibilities between minor and dominant, minor and minor, or

dominant and dominant waste constituents were identified and segregated. These

2.10.12-6


wastes cannot be transported until they are demonstrated safe (by testing) for

transport in TRUPACT-II. Chemical incompatibilities do not exist in content

codes listed in TRUCON. This has been ensured by a knowledge of the processes

generating the wastes and the chemical compatibility analysis. The following

section details the chemical compatibility analysis for the different content

codes at the Rocky Flats Plant (RFP), which is provided only as an example of

the type of analysis performed for each site.

2.1 Chemical Compatibility Analysis for RFP Waste

The chemical compatibility analysis was performed using a database management

system. The EPA method (Reference 3.1) was utilized to analyze both the chemical

compatibility of each content code (i.e., within individual waste containers)

and the compatibility of the TRUPACT-II payload during the hypothetical accident

condition (i.e., between contents of individual waste containers). This

discussion of chemical compatibility includes analysis between different content

codes. Mixing of payload shipping categories within a TRUPACT-II payload is not

allowed.

2.2 Chemical Compatibility of Each Content Code

Chemical compatibility has been analyzed for each content code based on the

chemical constituents within each content code, as indicated in Table 2.

Nineteen potentially incompatible combinations were identified and are listed

in Table 3. Each of the nineteen cases were evaluated. It was determined that

the required processing, prior to placing the waste in the waste containers, ob-

viated the potential incompatibility. Therefore, it was concluded that the

chemicals/materials in each content code are chemically compatible. The detailed

evaluation of each content code is as follows:

CONTENT CODE RF 111A - SOLIDIFIED AQUEOUS WASTE

Brief Description - The sludges are precipitated at a pH of 10-12 (basic). Any

acid that is present in the waste generating process is neutralized. The sludge

2.10.12-7

NuPac TRUPACT-II SAR Rev- 1. MaY 1 9 8 9

Table 2

Rocky Flats PlantList of Chemicals and Materials

in TRU Waste Content Codes

Content Codes RF 111A

SOLIDIFIED AQUEOUS WASTE

GROUP 4: ALCOHOLS AND GLYCOLS

BUTANOL T2ETHANOL T2ISOPROPANOL T2METHANOL T2

GROUP 16: HYDROCARBONS, AROMATIC

ETHYL BENZENE T2TOLUENE T2XYLENE T2

GROUP 17: HALOGENATED ORGANICS

1,1,1-TRICHLOROETHANE ' T21,1,2- TRICHLORO -1,2,2- TRIFLUOROETHANE TlCARBON TETRACHLORIDE T2METHYLENE CHLORIDE Tl

GROUP 24: METALS AND METAL COMPOUNDS, TOXIC

BERYLLIUM T2CADMIUM T2LEAD T

GROUP 32: ORGANOPHOSPHATES, PHOSPHOTHIOATES AND PHOSPHODITHIOATES

TRIBUTYL PHOSPHATE T3

GROUP 101: COMBUSTIBLE AND FLAMMABLE MATERIALS, MISCELLANEOUS

POLYETHYLENE (Packaging Material) M

POLYVINYL CHLORIDE (Packaging Material) M

D - Dominant Component (>10 % by wt.)M - Minor Component (1 - 10 % by wt.)T - Trace Component (<1 X by wt.)Tl - Trace Component (<0.1 % by wt.)T2 - Trace Component (low PPM range)T3 - Trace Component (<1 PPM range)

2.10.12-8

NuPac TRUPACT-II SAR Rev. 1. May 1989

Table 2(Concinued)

Rocky Flats PlaneList of Chemicals and Materials


Content Codes RF 111A(Continued)


GROUP 106: WATER AND MIXTURES CONTAINING WATER

AQUEOUS SOLUTIONS AND MIXTURES TSLUDGE (Fixed in matrix) DWATER T

OTHER ORGANICS

FLOCCULATING AGENT (POLYELECTROLYTE) T

OTHER SOLIDIFICATION MATERIAL/ABSORBENTS

DIATOMITE D

PORTLAND CEMENT (Hydrated) D

D - Dominant Component (>10 % by wt.)M - Minor Component (1 - 10 % by wt.)T - Trace Component (<1 % by wt.)Tl - Trace Component (<0.1 t by wt.)T2 - Trace Component (low PPM range)T3 - Trace Component (<1 PPM range)

2.10.12-9


Table 2(Continued)



Content Codes RF 111B



BUTANOL T2ETHANOL T2ISOPROPANOL • T2METHANOL T2


ETHYL BENZENE T2TOLUENE T2XYLENE ' T2


1,1,1-TRICHLOROETHANE T21,1,2-TRICHLORO-l, 2,2-TRIFLUOROETHANE TlCARBON TETRACHLORIDE " T2METHYLENE CHLORIDE Tl

GROUP 23: METALS, OTHER ELEMENTAL AND ALLOYS, AS SHEETS, RODS, MOLDINGS,DROPS, ETC.

LOW CARBON STEEL M


BERYLLIUM T2

CADMIUM T2LEAD T

D =- Dominant Component (>10 X by wt.)M - Minor Component (1 - 10 % by wt.)T - Trace Component (<1 X by wt.)Tl - Trace Component (<0.1 X by wt.)T2 - Trace Component (low PPM range)T3 - Trace Component (<1 PPM range)

2.10.12-10

NuPac TRUPACT-II SAR Rev- L M aY 1 9 8 9

i

Table 2 I(Continued) j

!Rocky Flats Plant j

List of Chemicals and Materials |in TRU Waste Content Codes

Content Codes RF 111B(Continued)








AQUEOUS SOLUTIONS AND MIXTURES T

SLUDGE (Fixed in matrix) DWATER T

OTHER ORGANICS


OTHER INORGANICS

CLAY (BENTONITE) D

SODIUM CHLORIDE D


DIATOMITE D


D - Dominant Component (>10 % by wt.)M - Minor Component (1 - 10 % by wt.)T - Trace Component (<1 X by wt.)Tl - Trace Component (<0.1 X by wt.)T2 - Trace Component (low PPM range)T3 - Trace Component «1 PPM range)

2.10.12-11


Table 2(Continued)



Content Codes RF 112A *

SOLIDIFIED ORGANICS


POLYETHYLENE GLYCOL M


XYLENE ' M


1,1,1-TRICHLOROETHANE D1,1,2-TRICHLORO-l,2,2-TRIFLUOROETHANE MCARBON TETRACHLORIDE MCHLOROFORM D


OIL DPOLYETHYLENE (Packaging Material) TPOLYVINYL CHLORIDE (Packaging Material) T


WATER T


ENVIROSTONE (CaS04) DPOTASSIUM SULFATE M

* Can be shipped only as a test category.D - Dominant Component (>10 % by wt.)M - Minor Component (1 - 10 % by wt.)T - Trace Component (<1 % by wt.)Tl - Trace Component (<0.1 % by wt.)T2^- Trace Component (low PPM range)T3*- Trace Component (<1 PPM range)

2.10.12-12


Table 2(Continued)



Content Codes RF 113A *

SOLIDIFIED LABORATORY WASTE

GROUP 3: ACIDS, ORGANIC(Constituents reacted prior to loading in payload containers.)

ACETIC ACID TASCORBIC ACID TCITRIC ACID TOXALIC ACID T


BUTANOL TlETHANOL TlISOPROPANOL • Tl

METHANOL Tl


XYLENE Tl

GROUP 19: KETONES

THENOYL TRIFLUOROACETONE (TTA) T


TRIBUTYL PHOSPHATE T

TRIOCTYL PHOSPHINE OXIDE T


POLYETHYLENE (Packaging Material) T

POLYVINYL CHLORIDE (Packaging Material) T

* Can be shipped only as a test category.D - Dominant Component (>10 % by wt.)M - Minor Component (1 - 10 % by wt.)T - Trace Component (<1 % by wt.)Tl - Trace Component (<0.1 X by wt.)T2 - Trace Component (low PPM range)T3 - Trace Component (<1 PPM range)

2.10.12-13


Table 2(Continued)

Rocky Flats PlantList of Chemicals- and Materials


Content Codes RF 113A *(Continued)

SOLIDIFIED LABORATORY WASTE


AQUEOUS SOLUTIONS AND MIXTURES (Fixed in matrix) MWATER T

OTHER ORGANICS

1,10-PHENANTHROLINE T3ALPHA-HYDROXYQUINOLINE TEDTA TSODIUM ACETATE TSODIUM CITRATE . T


MAGNESIA CEMENT (Hydrated) DPORTLAND CEMENT (Hydrated) D

* Can be shipped only as a test category.D - Dominant Component (>10 % by wt.)M - Minor Component (1 - 10 % by wt.)T - Trace Component (<1 % by wt.)Tl - Trace Component (<0.1 1 by wt.)T2 - Trace Component (low PPM range)T3 - Trace Component (<1 PPM range)

2.10.12-14


Table 2(Continued)




CEMENTED INORGANIC PROCESS SOLIDS


BUTANOL T2

METHANOL T2


XYLENE T2


1,1,1-TRICHLOROETHANE Tl1,1,2-TRICHLORO-l, 2,2-TRIFLUOROETHANE TlCARBON TETRACHLORIDE TlMETHYLENE CHLORIDE Tl


LEAD . Tl





WATER T

D - Dominant Component (>10 1 by wt.)M - Minor Component (1 - 10 1 by wt.)T - Trace Component (<1 % by wt.)Tl - Trace Component (<0.1 X by wt.)T2 - Trace Component (low PPM range)T3 - Trace Component (<1 PPM range)

2.10.12-15


Table 2(Continued)





OTHER INORGANICS

FIREBRICK DGRIT • DSAND DSLAG DSOOT D

OTHER•SOLIDIFICATION MATERIAL/ABSORBENTS


D - Dominant Component (>10 % by wt.)M - Minor Component (1 - 10 % by wt.)T - Trace Component (<1 % by wt.)Tl - Trace Component (<0.1 % by wt.)T2 - Trace Component (low PPM range)T3 - Trace Component (<1 PPM range)

2.10.12-16


Table 2(Continued)






BUTANOL T2

METHANOL T2


XYLENE T2


1,1.1-TRICHLOROETHANE Tl

1,1,2-TRICHLORO-1,2,2-TRIFLUOROETHANE TlCARBON TETRACHLORIDE TlMETHYLENE CHLORIDE Tl


LOW CARBON STEEL M


LEAD Tl

GROUP 101:. COMBUSTIBLE AND FLAMMABLE MATERIALS, MISCELLANEOUS



D - Dominant Component (>10 % by wt.)M - Minor Component (1 - 10 % by wt.)T - Trace- Component (<1 % by wt.)Tl - Trace Component (<0.1 % by wt.)T2 - Trace Component (low PPM range)T3 - Trace Component (<1 PPM range)

2.10.12-17

NuPac TRUPACT-II SAR Rev. 1, Mav 1989

Table 2(Continued)






WATER

OTHER INORGANICS

CLAY (BENTONITE)FIREBRICKGRITSANDSLAGSODIUM CHLORIDE

SOOT


PORTLAND CEMENT (Hydrated)

DDDDDDD


2.10.12-18


Table 2(Continued)




GRAPHITE WASTE


POLYETHYLENE (Packaging Material) TPOLYVINYL CHLORIDE (Packaging Material) T

OTHER ORGANICS

MOLDS AND CRUCIBLES, GRAPHITE D


2.10.12-19


. Table 2(Continued)

Rocky Flats PlantList of Chemicals, and Materials



GRAPHITE WASTE

GROUP 23:.METALS, OTHER ELEMENTAL AND ALLOYS, AS SHEETS, RODS, MOLDINGS,DROPS, ETC.

LOW CARBON STEEL M




OTHER ORGANICS

MOLDS AND CRUCIBLES, GRAPHITE D

OTHER INORGANICS

CLAY (BENTONITE) D

SODIUM CHLORIDE D

D » Dominant Component (>10 X by wt.)M = Minor Component (1 - 10 1 by wt.)T - Trace Component (<1 % by wt.)Tl - Trace Component (<0.1 % by wt.)T2 - Trace Component (low PPM range)T3 - Trace Component (<1 PPM range)

2.10.12-20


Table 2(Continued)




COMBUSTIBLE WASTE

GROUP 15: FLUORIDES, INORGANIC(Constituents reacted prior to loading in payload containers.)

CALCIUM FLUORIDE T

SODIUM FLUORIDE T


1,1,1-TRICHLOROETHANE T

1,1,2-TRICHLORO-1,2,2-TRIFLUOROETHANE TCARBON TETRACHLORIDE TlMETHYLENE CHLORIDE Tl


PAPER DPOLYETHYLENE DPOLYVINYL CHLORIDE • DSYNTHETIC RUBBER D


OIL-DRI M

DMTTlT2T3

- Dominant Component I- Minor- Trace- Trace- Trace- Trace

ComponentComponentComponentComponentComponent

( 1 •

(<1«o.

>10 % by wt.• 10 % by wt.% by wt.).1 % by wt.)

(low PPM range)

«1 PPM range)

2.10

))

.12-21


Table 2(Continued)




COMBUSTIBLE WASTE


CALCIUM FLUORIDE T

SODIUM FLUORIDE • T


1,1,1-TRICHLOROETHANE T• 1,1,2-TRICHLORO-1,2,2-TRIFLUOROETHANE TCARBON TETRACHLORIDE TlMETHYLENE CHLORIDE Tl


LOW CARBON STEEL • M


PAPER DPOLYETHYLENE DPOLYVINYL CHLORIDE DSYNTHETIC RUBBER D

OTHER INORGANICS

CLAY (BENTONITE) DSODIUM CHLORIDE D

D - Dominant Component (>10 % by wt.)M - Minor Component (1 - 10 % by wt.)T - Trace Component (<1 % by wt.)Tl - Trace Component (<0.1 7. by wt.)T2 - Trace Component (low PPM range)T3 - Trace Component (<1 PPM range)

2.10.12-22


Table 2(Continued)




COMBUSTIBLE WASTE


OIL-DRI M


2.10.12-23


Table 2(Continued)




METAL WASTE


CALCIUM FLUORIDE T

SODIUM FLUORIDE T


1,1,1-TRICHLOROETHANE T21,1,2-TRICHLORO-1,2,2-TRIFLUOROETHANE T2CARBON TETRACHLORIDE T2METHYLENE CHLORIDE Tl


ALUMINUM DCOPPER DIRON DLEAD DSTAINLESS STEEL DTANTALUM DTUNGSTEN • D


BERYLLIUM DCOPPER DLEAD D


2.10.12-24


Table 2(Continued)




METAL WASTE


POLYETHYLENE (Packaging Material) MPOLYVINYL CHLORIDE (Packaging Material) M


OIL-DRI M

D - Dominant Component (>10 % by wt.)M - Minor Component (1 - 10 % by wt.)T - Trace Component (<1 X by wt.)Tl - Trace Component (<0.1 X by wt.)T2 - Trace Component (low PPM range)T3 - Trace Component (<1 PPM range)

2.10.12-25


Table 2(Continued)




METAL WASTE


CALCIUM FLUORIDE T

SODIUM FLUORIDE T


1,1,1-TRICHLOROETHANE T2

1,1,2-TRICHLORO-1,2,2-TRIFLUOROETHANE T2CARBON TETRACHLORIDE T2METHYLENE CHLORIDE Tl


ALUMINUM DCOPPER DIRON DLEAD DLOW CARBON STEEL MSTAINLESS STEEL DTANTALUM DTUNGSTEN D


BERYLLIUM ' DCOPPER DLEAD D

D - Dominant Component (>10 % by wt.)M - Minor Component (1 - 10 % by wt.)T - Trace Component (<1 % by wt.)Tl - Trace Component (<0.1 X by wt.)T2 - Trace Component (low PPM range)T3 - Trace Component (<1 PPM range)

2.10.12-26


Table 2(Continued)




METAL WASTE



.OTHER INORGANICS

CLAY (BENTONITE) D

SODIUM CHLORIDE D


OIL-DRI M

D - Dominant Component (>10 % by wt.)M - Minor Component (1 - 10 % by wt.)T - Trace Component (<1 % by wt.)Tl - Trace Component (<0.1 X by wt.)T2 - Trace Component (low PPM range)T3 - Trace Component (<1 PPM range)

2.10.12-27


Table 2(Continued)



Content Code RF 118A

GLASS WASTE


1,1,1-TRICHLOROETHANE T31,1,2-TRICHLORO-l,2,2-TRIFLUOROETHANE T3CARBON TETRACHLORIDE T3


ALUMINUM TLEAD D

' STEEL TTUNGSTEN T


LEAD D

MERCURY T2




OTHER INORGANICS

GLASS, LABWARE DGLASS, RASCHIG RINGS DMOLDS AND CRUCIBLES, CERAMIC D


OIL-DRI M

D •• Dominant Component (>10 % by wt.)M - Minor Component (1 - 10 % by wt.)T • Trace Component (<1 % by wt.)Tl - Trace Component (<0.1 % by wt.)T2 - Trace Component (low PPM range)T3 - Trace Component (<1 PPM range)

2.10.12-28


Table 2(Continued)



Content Code RF 118B

GLASS WASTE


1,1,1-TRICHLOROETHANE T31,1,2-TRICHLORO-l,2,2-TRIFLUOROETHANE T3CARBON TETRACHLORIDE T3


ALUMINUM TLEAD DLOW CARBON STEEL MSTEEL TTUNGSTEN T


LEAD D

MERCURY ' T2




OTHER -INORGANICS

CLAY (BENTONITE) DGLASS, LABWARE DGLASS, RASCHIG RINGS - DMOLDS AND CRUCIBLES, CERAMIC DSODIUM CHLORIDE D

D = Dominant Component (>10 % by wt.)M = Minor Component (1 - 10 % by wt.)T => Trace Component (<1 % by wt.)Tl = Trace Component (<0.1 % by wt.)72 = Trace Component (low PPM range)T3 = Trace Component (<1 PPM range)

2.10.12-29


Table 2(Continued)




GLASS WASTE


OIL-DRI M

D - Dominant Component (>10 % by wt.)M - Minor Component (1 - 10 % by wt.)T - Trace Component (<1 % by wt.)Tl - Trace Component (<0.1 1 by wt.)T2 - Trace Component (low PPM range)T3 - Trace Component (<1 PPM range)

2.10.12-30


Table 2(Continued)




FILTER WASTE


1,1,1-TRICHLOROETHANE Tl1,1,2-TRICHLORO-1,2,2-TRIFLUOROETHANE TlCARBON TETRACHLORIDE ' TlMETHYLENE CHLORIDE T2


ALUMINUM D


POLYETHYLENE (Packaging Material) MPOLYPROPYLENE (Ful-Flo Filters) DPOLYVINYL CHLORIDE (Packaging Material) MWOOD D

OTHER INORGANICS

HEPA FILTERS (or filter media) DOTHER FILTERS DPLENUM PREFILTERS (FIBERGLASS) D

OTHER SOLIDIFICATION MATERIAL/ABSORBENTS .

PORTLAND CEMENT (Hydrated) M

D — Dominant Component (>10 % by wt.)M - Minor Component (1 - 10 % by wt.)T - Trace Component (<1 % by wt.)Tl - Trace Component (<0.1 % by wt.)T2 - Trace Component (low PPM range)T3 - Trace Component (<1 PPM range)

2.10.12-31


Table 2(Continued)




FILTER WASTE

GROUP 17: HALOGENATED ORGAN1CS

1,1,1-TRICHLOROETHANE Tl1,1,2-TRICHLORO-l,2,2-TRIFLUOROETHANE TlCARBON TETRACHLORIDE TlMETHYLENE CHLORIDE T2


ALUMINUM D

LOW CARBON STEEL M


POLYETHYLENE (Packaging Material) MPOLYPROPYLENE (Ful-Flo Filters) DPOLYVINYL CHLORIDE (Packaging Material) MWOOD D

OTHER INORGANICS

CLAY (BENTONITE) DHEPA FILTERS (or filter media) DOTHER FILTERS DPLENUM PREFILTERS (FIBERGLASS) DSODIUM CHLORIDE D


PORTLAND CEMENT (Hydrated) M

D - Dominant Component (>10 % by wt.)M - Minor Component (1 - 10 % by wt.) -T - Trace Component (<1 % by wt.)Tl - Trace Component (<0.1 % by wt.)T2 - Trace Component (low PPM range)T3 - Trace Component (<1 PPM range)

2.10.12-32


Table 2(Continued)




ORGANIC SOLID WASTE


1,1,1-TRICHLOROETHANE T

METHYLENE CHLORIDE Tl


ASPHALT DPHENOLIC RESINS TPOLYETHYLENE (Packaging Material) TPOLYMETHYL METHACRYLATE DPOLYVINYL CHLORIDE (Packaging Material) TWOOD D

OTHER INORGANICS

SAND ' D

SOIL ' D


CONCRETE D

OIL-DRI M


2.10.12-33


Table 2(Continued)




ORGANIC SOLID WASTE


1,1,1-TRICHLOROETHANE TMETHYLENE CHLORIDE Tl


LOW CARBON STEEL M


ASPHALT DPHENOLIC RESINS TPOLYETHYLENE (Packaging Material) TPOLYMETHYL METHACRYLATE DPOLYVINYL CHLORIDE (Packaging Material) TWOOD ' D

OTHER INORGANICS

CLAY (BENTONITE) DSAND DSODIUM CHLORIDE DSOIL D


CONCRETE DOIL-DRI M

D = Dominant Component (>10 % by wt.)M - Minor Component (1-10 7. by wt.)T - Trace Component (<1 7. by wt.)Tl - Trace Component (<0.1 7. by wt.)T2 - Trace Component (low PPM range)T3 - Trace Component (<1 PPM range)

2.10.12-34


Table 2(Continued)




SOLID INORGANIC WASTE


1,1,1-TRICHLOROETHANE TCARBON TETRACHLORIDE TlMETHYLENE CHLORIDE Tl



OTHER INORGANICS

FIREBRICK D

INSULATION D


OIL-DRI D


2.10.12-35


Table 2(Continued)




SOLID INORGANIC WASTE


1,1,1-TRICHLOROETHANE TCARBON TETRACHLORIDE TlMETHYLENE CHLORIDE Tl


LOW CARBON STEEL M .




OTHER INORGANICS

CLAY (BENTONITE) . DFIREBRICK DINSULATION DSODIUM CHLORIDE D


OIL-DRI • D


2.10.12-36


Table 2(Continued)




LEADED RUBBER


LEAD (Rubber Gloves) D


POLYETHYLENE T

POLYVINYL CHLORIDE TRUBBER GLOVES, LEADED D


2.10.12-37


Table 2(Continued)




LEADED RUBBER


LOW CARBON STEEL M


LEAD (Rubber Gloves) D


POLYETHYLENE T

POLYVINYL CHLORIDE TRUBBER GLOVES, LEADED D

OTHER INORGANICS

CLAY (BENTONITE) ' DSODIUM CHLORIDE D

D - Dominant Component (>10 % by wt.)M - Minor Component (1 - 10 % by wt.)T - Trace Component (<1 7. by wt.)Tl - Trace Component (<0.1 % by wt.)T2 = Trace Component (low PPM range)T3 - Trace Component (<1 PPM range)

2.10.12-38

• " ' .


Table 2(Continued)




PYROCHEMICAL SALT WASTE

GROUP 10: CAUSTICS

(Constituents dispersed in chloride salts.)

CALCIUM OXIDE M


MAGNESIUM OXIDE Tl



POLYVINYL CHLORIDE (Packaging Material) TGROUP 107: WATER REACTIVE SUBSTANCES

(Constituents dispersed in chloride salts.)

CALCIUM OXIDE M

OTHER INORGANICS

CALCIUM CHLORIDE DCESIUM CHLORIDE DMAGNESIUM CHLORIDE DMETAL CANS (for salt) MPOTASSIUM CHLORIDE DSODIUM CHLORIDE D


2.10.12-39

NuPac TRUPACT-II SAR Rev. 2, June 198 9

Table 2(Continued)


in TRU Haste Content Codes


CEMENTED ORGANIC PROCESS SOLIDS


ION EXCHANGE RESIN (Dowex) DPOLYETHYLENE TPOLYVINYL CHLORIDE . T



D - Dominant Component (>10 % by wt.)M - Minor Component (1 - 10 % by wt.)T - Trace Component (<1 % by wt.)Tl - Trace Component «0.1 % by wt.)T2 - Trace Component (low PPM range)T3 - Trace Component «1 PPM range)

2.10.12-40

NuPac TRUPACT-ZZ SAR Rev. 2, June 1989

Table 2(Continued)



Content Coda RF 126B

CEMENTED ORGANIC PROCESS SOLIDS


LOW CARBON STEEL M


ION EXCHANGE RESIN (Dowex) D

POLYETHYLENE TPOLYVINYL CHLORZDE T

OTHER INORGANICS

CLAY (BENTONITE) D

SODIUM CHLORIDE D



D - Dominant Component (>10 % by wt.)M - Minor Component (1 - 10 % by wt.)T - Trace Component (<1 % by wt.)Tl - Trace Component (<0.1 % by wt.)T2 - Trace Component (low PPM range)T3 - Trace Component «1 PPM range)

2.10.12-41


Table 2(Continued)

RocJcy Flats PlantList of Chemicals and Materials



COMBINED SOLID ORGANICS AND SOLIDIFIED INORGANIC WASTE


BUTANOL T2ETHANOL T2ISOPROPANOL T2METHANOL T2

GROUP IS: FLUORIDES, INORGANIC(Constituents reacted prior to loading in payload containers.)

CALCIUM FLUORIDE TSODIUM FLUORIDE T


ETHYL BENZENE T2TOLUENE ' T2XYLENE T2


1,1,1-TRICHLOROETHANE T .1,1,2-TRICHLORO-1,2,2-TRIFLUOROETHANE TCARBON TETRACHLORIDE TlMETHYLENE CHLORIDE Tl


ALUMINUM DLOW CARBON STEEL M

0 * Dominant Component (>10 % by wt.)M - Minor Component (1 - 10 % by wt.)T - Trace Component Kl % by wt.)Tl - Trace Component «0.1 % by wt.)T2 - Trace Component (low PPM range)T3 - Trace Component «1 PPM range)

2.10.12-42


Table 2(Continued)

Rocky Flats PlantList of. Chemicals and Materials


Content Code RF 127A(Continued)



BERYLLIUM T2CADMIUM T2

LEAD 0

GROUP 32: ORGANOPHOSPHATES, PHOSPHOTHIOATES AND PKOSPHODITHIOATES


GROUP 101: COMBUSTIBLE AND FLAMMABLE MATERIALS, MISCELLANEOUS -

ASPHALT • . D

PAPER DPHENOLIC RESINS TPOLYETHYLENE DPOLYMETHYL METHACRYLATE DPOLYPROPYLENE (Ful-Flo Filters) DPOLYVINYL CHLORIDE DRUBBER GLOVES, LEADED DSYNTHETIC RUBBER DWOOD D


AQUEOUS SOLUTIONS AND MIXTURES TSLUDGI (Fixed in matrix) ~ DWATER T

D - Dominant Component (>10 % by wt.)M - Minor Component (1 - 10 % by wt.)T - Trace Component (<1 % by wt.)Tl • Trace Component (<0.1 % by wt.)T2 - Trace Component (low PPM range)T3 - Trace Component «1 PPM range)

2.10.12-43


Table 2(Continued)



Content Code RF 127A(Continued)


OTHER ORGANICS


OTHER INORGANICS

CLAY (BENTONITE) DHEPA FILTERS (or filter media) DOTHER FILTERS - DPLENUM PRSFILTERS (FIBERGLASS) 0SAND D

. SODIUM CHLORIDE . DSOIL D


CONCRETE DDIATOMITE DOIL-DRI MPORTLAND CEMENT (Hydrated) D

0 - Dominant Component (>10 % by wt.)M - Minor Component (1 - 10 % by wt.)T - Trace Component (<1 % by wt.)Tl - Trace Component (<0.1 % by wt.)T2 - Trace Component (low PPM range)T3 - Trace Component «1 PPM range)

2.10.12-44


TABLE 3

SUMMARY OF POTENTIAL INCOMPATIBILITIES FOR WASTE FORMS

ContentCode

Potential ChemicalConroatibilitv Reaction

Concentrationof Reactants#

ReactionCode *

RF'111A

RF 111B

RF 112A

RF 113A

RF 114A

RF 114B

RF 115A

RF 115B

RF 116A

RF 116B

RF 117A

RF 117B

Metal and Compounds, Toxic xWater (24 x 106)

T x D

Halogenated Organics x Metals and Tl x Mother elemental and alloys assheets, rods, etc. (17 x 23)

Metal and Compounds, Toxic X T x DWater (24 x 106)

None

None

None

Halogenated Organics x Metals and Tl x Mother elemental and alloys assheets, rods, etc. (17 x 23)

None

None

None

Halogenated Organics x Metals and T x Mother elemental and alloys assheets, rods, etc. (17 x 23)

Halogenated Organics x Metals and Tl x Dother elemental and alloys assheets, rods, etc. (17 x 23)

Halogenated Organics x Metals and Tl x Dother elemental and alloys assheets, rods, etc. (17 x 23)

H F

H F

H F

H F

H F

Reaction Code: H - heat generation, S - solubilization of toxic substances,F - fire, GF - flammable gas generation, G - non-flammable gas generation.

Concentration of Reactants: T - Trace (<1X by w e ) , Tl - Trace (<0.1%),T2 - Trace (low ppm range), T3 - Trace (<1 ppm. range), M - Minor(l-lOZ).and D - Dominant (>10X).

2.10.12-45


TABLE 3 (cont.)


ContentCode

Potential ChemicalCompatibility Reaction

Concentration

of ReactantM_

ReactionCode *

RF 118A Halogenated Organics x Metals and T3 x Dother elemental and alloys assheets, rods, etc. (17 x 23)

RF 118B Halogenated Organics x Metals and T3 x Dother elemental and alloys assheets, rods, etc. (17 x 23)

RF 119A Halogenated Organics x Metals and. Tl x Dother elemental and alloys assheets, rods, etc. (17 x 23)

RF 119B Halogenated Organics x Metals and Tl x Dother elemental and alloys assheets, rods, etc. (17 x 23)

RF 121A None

RF 121B Halogenated Organics x Metals and T x Mother elemental and alloys assheets, rods, etc. (17 x 23)

RF 122A None

RF 122B Halogenated Organics x Metals and T x Mother elemental and alloys assheets, rods, etc. (17 x 23)

RF 123A None

RF 123B None

H F

H F

H F

H F

H F

H F


.Concentration of Reactants: T - Trace (<1X by wt.), Tl = Trace (<0.1X),T2 - Trace (low ppm range), T3 - Trace (<1 ppm range), M - Minor (1-10X),and D - Dominant (>10X).

2.10.12-46


TABLE 3 (cont.)


ContentCode .

Potential ChemicalCompatibility Reaction

Concentrationof Reactants#

ReactionCode *

RF 124A

RF 126A

RF 126B

RF 127A

RF 127A

Caustics x Metal and Compounds,Toxic (10 x 24)

M x Tl

Metals and Compounds, Toxic x Water Tl x MReactive Substances (24 x 107)

Combustible and Flammable Materials T x Mx Water Reactive Substances(101 x 107)

Caustics x Water Reactive M x M

Substances (10 x 107)

None

None

Halogenated Organics x Metals and T x Xother elemental and alloys assheets, rods, etc. (17 x 23)

Metal and Compounds, Toxic xWater (24 x 106)

D X D

PotentiallyReactive

PotentiallyReactive

Not Valid

H F


Concentration of Reactants: TT2 - Trace (low ppm range), T3and D - Dominant (>10%).

Trace (<1Z by wt.), Tl - Trace (<0.12),Trace (<1 ppm range), M - Minor (1-10X),

2.10.12-47


is then vacuum filtrated to a solidified material or immobilized with concrete.

The dewatered or cemented sludge has sorbents added to immobilize any residual

•fluids. The drum is inspected for the presence of any residual liquids.

Chemical Compatibility - Only one potential chemical incompatibility was found

for this content code. This incompatibility is possible solubilization of toxic

metals, which is not a concern since the water from the sludge is fixed in the

cemented product and would, not be available for reaction. In addition,

solubilization of toxic metals does not present a transportation concern for

TRUPACT-II. This content code is considered to be chemically compatible.

CONTENT CODE RF 111B - SOLIDIFIED AQUEOUS WASTE

Brief Description • The sludges are precipitated at a pH of 10-12 (basic). Any

acid that is present in the waste generating process is neutralized. The sludge

is then vacuum filtrated to a solidified material or immobilized with concrete.

The dewatered or cemented sludge has sorbents added to immobilize any residual

fluids. The drum is inspected for the presence of any residual liquids.

Naturally occurring salt, clay (bentonite) and wire screen (steel) have been

added to the pay load containers. for experimental purposes.

Chemical Compatibility - Only two potential chemical incompatibilities were

found for this content code. The first incompatibility is possible

solubilization of toxic metals, which is not a concern since the water from the

sludge is fixed in the cemented product and would not be available for reaction.

In addition, solubilization of toxic metals does not present a transportation

concern for TRUPACT-II. This content code is considered to be chemically

compatible.

The second potential chemical incompatibility is the reaction of halogenated

organics (Group 17) with metals and other elemental and alloys as sheets, rods,

etc. (Group 23). The halogenated organics are present in only trace quantities

(TK0.1X) and are fixed in the cemented sludge and would not be available to

react with the metals.

2.10.12-48

NuPac TRUPACT-II SAR * Rev. 2, June 1989

CONTENT CODE RF 112A • SOLIDIFIED ORGANICS

Brief Description - CH-TRU solidified organic waste is produced from liquid

organics such as oils, solvents, and lathe coolants. The organic liquids are

mixed with gypsum cement (Envirostone). After solidification, Che drum is

inspected for any residual liquids.

Chemical Compatibility - No potential chemical incompatibilities were identified

within this content code. This content code is currently assigned to a test

category due to an incomplete effective G value characterization (a measure of

the gas generation potential). This content code cannot be transported until

this characterization is complete.

CONTENT CODE RF 113A - SOLIDIFIED LABORATORY WASTE

Brief Description • Aqueous laboratory wastes that are not compatible (i.e.,

strong acids or bases) with che primary aqueous creacmenc system are neutralized

and solidified as content code RF113A. The final content code is obtained by

mixing portland and magnesia cement with che waste.

Chemical Compatibility • No potential chemical incompatibilities were identified

within this content code. This content code is currently assigned to a test

category due to che incomplete effective G value characterization (a measure of

Che gas generation potential). This content code cannot be transported until

Chis characterization is complete.

CONTENT CODE RF 114A • CEMENTED INORGANIC PROCESS SOLIDS

Brief Description - All line'generated particulate and sludge-like wastes are

immobilized in portland cement. A formula for each waste type is used co

precondicion Che waste (e.g., neutralize, chicken, etc.). The waste is usually

cemented in 1-gallon cans and then removed for placement in che waste drum.

2.10.12-49


Chemical Compatibility • No potential chemical incompatibilities were identified

in the content code*.

CONTENT CODE RF 114B • CEMENTED INORGANIC PROCESS SOLIDS

Brief Description • All line*generated particulate and sludge-like wastes are

immobilized in portland cement. A formula for each waste type is used to

precondition the waste (e.g., neutralize, thicken, etc.). The waste is usually

cemented in 1-gallon cans and then removed for placement in the waste drum.

Naturally occurring salt, clay (bentonite) and wire screen (steel) have been

added to the pay load containers for experimental purposes.

Chemical Compatibility • Only one potential chemical incompatibility was found

for this content code. This potential chemical incompatibility is the reaction

of halogenated organics (Group 17) with metals and other elemental and alloys

as sheets, rods, etc. (Group 23). The halogenated organics are present in only

trace quantities (T1<O.1X) and are fixed in the cemented sludge and would not

be available to react with the metals.

CONTENT CODE RF 115A - GRAPHITE WASTE

Brief Description • CH-TRU graphite waste consists of scarfed graphite molds

and graphite chunks, and coarse graphite pieces which have been used for casting

molten plutonium.

Chemical Compatibility • No potential chemical incompatibilities vere identified

for this content code.

CONTENT CODE RF 115B - GRAPHITE WASTE

Brief Description • CH-TRU graphite waste consists of scarfed graphite molds

and graphite chunks, and coarse graphite pieces which have been used for casting

molten plutonium. Naturally occurring salt, clay (bentonite) and wire screen

(steel) have been added to the payload containers for experimental purposes.

2.10.12-50


Chemical Compatibility - No potential chemical incompatibilities were identified* •


CONTENT CODE RF 116A - COMBUSTIBLE WASTE

Brief Description - 'Combustibles' consists of paper, rags, cloth coveralls,

plastics, rubber, wood, and other similar items.

i



Note - Spills of acids (e.g.. HNOj) can occur and are wiped up with cellulosic

materials. The Rocky Flats Plant has very strict controls on the washing and

drying of cellulosics that have been used to clean up acid spills: Even old

(12+ years old) waste, retrieved from storage as part of the INEL sampling study

(Reference 3.3) showed no signs of yellow or brown stains on the cellulosic waste

materials. This is a positive indication that good washing techniques are

practiced and no oxidation is occurring due to nitric acid residues.

CONTENT CODE RF 116B - COMBUSTIBLE WASTE

Brief Description - 'Combustibles' consists of paper, rags, cloth coveralls,

plastics, rubber, wood, and other similar items. Naturally occurring salt, clay

(bentonite) and wire screen (steel) have been added to the payload containers

for experimental purposes.

Chemical Compatibility - Only one potential chemical incompatibility has been

identified • the reaction of halogenated organics (Group 17) with metals and

other elemental and alloys as sheets, rods, etc. (Group 23). The halogenated

organics are present in only trace quantities absorbed on combustibles and are

not present as free liquids to react with the metals.

Note • Spills of acids (e.g., HNOj) can occur and are wiped up with cellulosic

materials. The Rocky Flats Plant has very strict controls on the washing and

drying of cellulosics that have been used to clean up acid spills. Even old

(12+ years old) waste, retrieved from storage as part of the INEL sampling study

2.10.12-51


(Reference 3.3) showed no signs of yellow or brown stains on the ccllulosic waste

materials. This i's a positive indication that good washing techniques are

practiced and no oxidation is occurring due to nitric acid residues.

CONTENT CODE RF 117A - METAL WASTE

Brief Description • Typical metal waste contains iron, copper, aluminum,

stainless steel, tungsten, lead, and tantalum. Pyrophoric materials are

specifically excluded.

Chemical Compatibility • The only potential chemical incompatibility is the

potential reaction between halogenated hydrocarbons and metals, other elemental

and alloys A* sheets, rods, drop, moldings, etc. Although this is a potential

incompatibility, the potential effects are considered minimal for the following

reasons. First, the halogenated hydrocarbons are only present in trace

quantities (<1 percent by weight) in the content code. Second, although the

metals of concern (aluminum and magnesium) occur in minor-to-dominant quantities

in the content code, the metals only occur as large pieces of metal and not in

powder form, which is more reactive with the halogenated hydrocarbons. Due to

the trace quantities of halogenated organics in the content code and the

non-powder size of the metal pieces, any reaction that may occur will produce

minimal heat. Therefore, this content code is considered to be chemically

compatible.

CONTENT CODE RF 117B • METAL WASTE

Brief Deacriptlon • Typical metal waste contains iron, copper, aluminum,

stainless steel, tungsten, lead, and tantalum. Pyrophoric materials are

specifically excluded. Naturally occurring salt, clay (bentonite) and wire

screen (steel) have been added to the payload containers for experimental

purposes.

Chemical Compatibility - The only potential chemical incompatibility is the


and alloys as sheets, rods, drop, moldings, etc. Although this is a potential

incompatibility, the potential effects are considered minimal for the following

2.10.12-52.


reasons. First, the halogenated hydrocarbons are only present in trace

quantities (<1 percent by weight) in the content code. Second, although the

metals of concern (aluminum and magnesium) occur in minor-to-dominant quantities

in the content code, the metals only occur as large pieces of metal and not in

powder.form, which is more reactive with the halogenated hydrocarbons. Due to

the trace quantities of halogenated organics in the content code and the

non-powder size of the metal pieces, any reaction that may occur will produce

minimal heat. Therefore, this content code is considered to be chemically

compatible.

CONTENT CODE RF 118A - GLASS WASTE

Brief Description -' Glass waste consists of approximately 50 percent Raschig

rings and 50 percent other glass, such as laboratory glassware, process equip-

ment, and glovebox windows.


identified - the reaction of halogenated organics (Group 17) with metals and


organics are present in only very small trace quantities (T3<lppm) as coatings

on glass. The halogenated organics are present only as residual films on the

glass and not as free liquids that could react with metals.

CONTENT CODE RF 118B - GIASS WASTE

Brief Description - Glass waste consists ,of approximately 50 percent Raschig

rings and 50 percent other glass, such as laboratory glassware, process equip-

ment, and glovebox windows. Naturally occurring salt, clay (bentonite) and wire


purposes.




organics are present in only very small trace quantities (T3<lppm) as coatings

on glass. The halogenated organics are present only as residual films on the

glass and not as free liquids that could react with metals.

2.10.12-53

NuPac TRUPACT-II SAR R«v. 2, June 1989

CONTENT CODE RF 119A - FILTER WASTE

Brief Description - CH-TRU filter waste consists of absolute dry box filters,

high efficiency particular air (HEPA) filters, filter media, Ful-Flo filters,

processed filter media, and plenum filters. The filters are mixed with portland

cement to neutralize any residual acid and adsorb any residual liquid.




incompatibility, the probable effects are considered minimal for the same reason

outlined in Content Code RF 117A (Metal Waste).

Due to the trace amount of halogenated organics (<1 percent by weight) in the

content code and the absence of powdered metals, any reaction that may occur

will produce minimal heat. This content code is considered to be chemically

compatible.

CONTENT CODE RF 119B - FILTER WASTE

Brief Description - CH-TRU filter waste consists of absolute dry box filters,

high efficiency particulate air (HEPA) filters, filter media, Ful-flo filters,

processed filter media, and plenum filters. The filters are mixed with portland

cement to neutralize any residual acid and adsorb any residual liquid. Naturally

occurring salt, clay (bentonite) and wire screen (steel) have been added to the

payload containers for experimental purposes.




incompatibility, the probable effects are considered minimal for the same reason

outlined in Content Code RF 117B (Metal Waste).

Due to the trace amount of halogenated organics (<1 percent by weight) in the

content code and the absence of powdered metals, any reaction that may occur

2.10.12-54


will produce minimal heat. This content code is considered to be chemically*

compatible.

CONTENT CODE RF 121A - ORGANIC SOLID WASTE

Brief Description • CH-TRU organic solid waste refers specifically to large,

massive (2-to 4-inch thick) sheets or slabs of solid organic material (e.g.,

Plexiglass, Benelex, etc.).

Chemical Compatibility - No potential cheaical incompatibilities were identifiedi


CONTENT CODE RF 121B • ORGANIC SOLID WASTE

Brief Description - CH-TRU organic solid waste refers specifically to large,

massive (2-to 4-inch thick) sheets or slabs of solid organic material (e.g.,

Plexiglass, Benelex', etc.). Naturally occurring salt, clay (bentonite) and wire


purposes.



other elemental and alloys as sheets, rods, etc. (Group 23). The haiogenated

organics are present in only trace quantities (T - <1Z) as coatings on the

organic solid materials. The halogenated organics are not present as free

liquids that could react with metals present.

CONTENT CODE RF 122A • INORGANIC SOLID WASTE

Brief Description - Inorganic solid waste consists of firebrick and Oil-Dri

(clay).



2.10.12-55


CONTENT CODE RF 122B - INORGANIC SOLID WASTE

Brief Description - Inorganic solid waste consists of firebrick and Oil-Dri

(clay). Naturally occurring salt, clay-(bentonite) and wire screen (steel) have

been added to the payload containers for experimental purposes.

Chemical Compatibility • Only one potential chemical incompatibility has been



organics are present in only trace quantities (T - <1Z) as coatings on the

inorganic solid materials. The halogenated organics are not present as free

liquids that could react with metals present.

CONTENT CODE RF 123A • LEADED RUBBER

Brief Description - Leaded rubber gloves contain layers of Hypalon and lead

oxide impregnated neoprene.

Chemical Compatibility - Waste certification procedures specifically identify

a possible reaction between concentrated nitric acid and leaded rubber gloves

to produce a potential pyrophoric problem. Procedures specify that gloves have

to be washed prior to certification as TRU waste. No potential chemical

incompatibilities were identified for this content code.

CONTENT CODE RF 123B • LEADED RUBBER

Brief Description • Leaded rubber gloves contain layers of Hypalon and lead

oxide impregnated neoprene. Naturally occurring salt, clay (bentonite) and wire


purposes.

Chemical Compatibility - Waste certification procedures specifically identify

a possible reaction between concentrated nitric acid and leaded rubber gloves

to produce a potential pyrophoric problem. Procedures specify that gloves have

2.10.12-56


to be washed prior to certification as TRU waste. No potential chemical

incompatibilities were identified for this content code.

CONTENT CODE RF 124A - FYROCHEMICAL SALTS

Brief Description - Spent chloride salt from molten salt extraction, electro*

refining or direct oxide reduction.

Chemical Compatibility • Four potential chemical incompatibilities have been

identified for this waste form. One potential incompatibility is the possible

solubilization of toxic metals (Group 24) in caustics (Group 10). The caustic

in content code RF 124A is calcium oxide, a solid, which is dispersed in the

chloride salts. In this case, solubilization is not possible. In addition,

solubilization of toxic metals does not present a transportation concern for

TRUPACT-II.

Two other potential incompatibilities are possible reactions between metals and

metal compounds, toxic (Group 24) or combustible-and flammable materials (Group

101) and water reactive substances (Group 107). Both the metals and combustibles

are present only in trace quantities (< 1Z by weight). Calcium oxide, the only

water reactive substance present, is dispersed in the chloride salts. Based on

the immobilization of the calcium oxide in the salt, reactions are considered

highly unlikely. This content code is considered to be chemically compatible.

The fourth potential chemical incompatibility is an artifact of the EPA method.

Calcium oxide appears in Groups 10 and 107, and is compatible within itself.

CONTENT CODE RF 126A • CEMENTED ORGANIC PROCESS SOLIDS

Brief Description - The leached and cemented resins consist of anion and cation

exchange resins that have been used in the purification and recovery of plutonium

and americium. The washed resin is mixed with portland cement and water to form

a solid mass.

2.10.12-57


Chemical Campatibilicy • No pocencial cheaical incompacibilicies were idencified

for chis concenc co'de.

CONTENT CODE RF 126B • CEMENTED ORGANIC PROCESS SOLIDS

Brief Description • The leached and cemented resins consist of anion and cation

exchange resins that have been used in Che purification and recovery of plutonium

and americium. The washed resin is nixed with portland cement and water to form

a solid mass. Naturally occurring salt, clay (bentonite) and wire screen (steel)

have been added Co che payload containers for experimental purposes.

Chemical CoiroatibillCv • No pocencial chemical incompatibilities were idencified

for chis concenc code.

CONTENT CODE RF 127A • COMBINED SOLID ORGANICS AND SOLIDIFIED ORGANICS

Brief Descrlpcion: 'The waste consists of paper, rags, cloth, coveralls, plastic,

rubber, wood and other similar items. In addition, there are small quantities

of metals (e.g., iron, copper, aluminum, stainless steel, tungsten, lead and

tantalum) and glass and ceramic waste from recovery, maintenance and laboratory

operations. The aqueous effluent from uranium and plutonium processing

activities is treated and mixed with approximately 30Z portland cement.

Naturally occurring salt, clay (bentonite), and wire screen (steel) have been

added to the pay load containers for experimental purposes.

Chemical Compatibilicv • One pocencial chemical incompatibilicy is che pocencial

reaction between halogenated hydrocarbons and metals, other elemental and alloys

as sheets, rods, drop, moldings, etc. Although chis is a pocencial

incompatibilicy, che probable effeccs are considered minimal for Che same reason

outlined in Concent Code RF 117A (Metal Waste).

Another potential chemical incompatibilicy was found for chis concenc code.

This incompatibility is possible solubilization of toxic metals, which is not

a concern since che wacer from che sludge is fixed in che cemented product and

would not be available for reaction. In addition, solubilization of toxic metals

2.10.12-58

NuPac TRUPACT-II SAR *«*• 3, July 1989

does not present a transportation concern for TRUPACT-II. This content code is

considered to be chemically compatible.

2.3 Chemical Compatibility During Hypothetical Accident Conditions

The hypothetical accident conditions for chemical compatibility is defined as

a'situation where all the individual waste containers within the TRUPACT-II are

breached during an accident. The waste from individual waste containers are

assumed to intimately mix, but there is no breaching of the TRUPACT-II ICV

containment boundary. Under current payload shipping category restrictions,

mixing of shipping categories is not allowed. The following analysis of chemical

compatibility is, however, extended across all content codes from the site.

The database management program was used to evaluate the potential chemical

incompatibility conditions that may occur during an accident. The analysis

assumed that mixing of any one content code could occur with any other content

code during the accident. A summary of the potential incompatibilities

identified is provided in Table 4.

Several potential chemical incompatibilities were identified which included

Group 10 or Group 107 from content code RF 124A. As explained in Section 2.2

of this appendix, calcium oxide is the only chemical base (Group 10) present in

content code RF 124A in greater than trace quantities. The potential

incompatibility (Case 1) between Groups 10 and 107 is invalid because calcium

oxide is chemically compatible with itself and this was discussed under content

code RF 124A.

In content code RF 124A, the calcium oxide is finely dispersed and immobilized

in the fused chloride/fluoride salts from pyrochemical reactions and thus any

interaction between the calcium oxide (Group 10 or 107) and any other

constituents during hypothetical accidents is highly unlikely and not a chemical

compatibility problem (Cases 1 - 5).

The only remaining potential chemical compatibility within the Rocky Flats waste

during hypothetical accident conditions is Case 6, the interaction between metals

and compounds, toxic (Group 24) and water and mixtures containing water (Group

1Q6).

2.10.12-59


The potential reaction that may occur is the mixing of metals and metal compounds

with water-and mixtures containing water. This potential reaction between toxic

metals and compounds (RF-117A, B, or 118A, B, or 123A, B, or 127A) and water and

mixtures containing water (RF-111A, B, or 114A, B, or 127A) is highly unlikely

because liquid waste forms in content codes are prohibited, and only very small

amounts of residual water are ever found in the content codes. Even if small

amounts of residual solutions are present in the waste, this reaction does not

generate any heat or gases. It only dissolves any toxic metals or compounds

present in the waste. The presence of toxic metals does not present a

transportation concern for TRUPACT-II.

This is the' comprehensive chemical compatibility analysis for the waste from

Rocky Flats Plant. Similar analyses by waste material type have been made for

all ten DOE sites to ensure that only compatible content codes are transported

in TRUPACT-II.

2.10.12-60

NuP»c TRUPACT-II SAR Rev. 3, July 1989

TABLE 4

SUMMARY OF POTENTIAL INCOMPATIBLE CONDITIONS

FOR THE HYPOTHETICAL ACCIDENT

CaseHistoryNo, Content Codes

PotentialChemical Compatibility Reaction

124A

111B, 114B, 115B, 116B117A, U7B, 118A, 118B,U9A, 119B, 121B, 122B,123B, 126B, 127A

124A

117A, 117B, 118A, 118B,123A, 123B, 127A

111B, 114B, 115B, 116B,117A, 117B, 118A, 118B,119A, 119B, 121B, 122B,123B, 126B, 127A

124A

117A, 117B, 118A, 118B,123A, 123B, 127A

124A

111A, 111B, 116A, 116B,117A, 117B, 118A, 118B,119A, 119B, 121A, 121B,122A, 122B, 123A, 123B,126A, 126B, 127A

124A

U7A, 117B, 118A, 118B,123A, 123B, 127A

111A, 111B, 114A, 114B127A

Caustics (Group 10)

Metals, other elemental and alloysas sheets, rods, etc. (Group 23)

Caustics (Group 10)

Metals and Compounds, Toxic (Group 24)

Metals, other elemental and alloysas sheets, rods, etc. (Group 23)

Water Reactive Substances (Group 107)



Combustible and Flammable Materials(Group 101)



Water and Mixtures Containing Water(Group 106)

2.10.12-61


3.0 REFERENCES

3.1 Hatayama, H. K., Chen, J.J., de Vera, E.R., Stephens, R.D., Stora, D.L.,

"A Method for Determining the Compatibility of Hazardous Wastes,"

EPA-600/2-80-076, EPA, Cincinnati, Ohio, 1980.

3.2 U.S. Environmental Protection Agency, Code of Federal Regulations, Part

190 to 399 U.S. Government Printing Office, Washington, D.C, 1988.

3.3 Clements, T. L., Kudera, D. E., "TRU Waste Sampling Program: Volume 1 •

Waste Characterization," EGG-WM-6503, September 1985.

2.10.12-62

NnPac TBDPACT-II SAR Rev. 1, May.1989

3.4.4 Maximum Internal Pressure

The evaluation of the maximum internal pressure for the TEUPACT-II Package

considers the factors which affect pressure to demonstrate that the pressure

increases are below the allowable pressure for the package. Included in the

evaluation i s a demonstration that accumulation of potentially flammable gases

is precluded.

3.4.4.1 Design Pressure

The TRTJPACT-II Package has a design pressure of 50 psig. Section 2.0 d i s -

cusses the abi l i ty of the package to withstand (50 psig) for both normal con-

ditions of transport and hypothetical accident conditions. The ICV or both

the OCV and ICV were pressurized to 50 psig in many of the full-scale t e s t s

for hypothetical accident conditions as described in Appendix 2.10.8. The

maximum normal operating pressure (JNOP) i s discussed in Section 3 .4 .4 .5 .

3.4.4.2 Factors Affecting Pressure

The gauge pressure within a sealed OCV or ICV of a TRUPACT-II Package may po-

tent ial ly be changed (increased or decreased) due to one or more of the

following factors which can affect pressure:

o Radiolytic gas generation (or consumption)

o Temperature-related pressure change

o Barometric pressure change

o Chemical reactions

o Biological gas generation

o Thermal decomposition

Each of these factors is discussed below. Depending on the payload shipping

category, the relative contribution from each factor may vary from negligible

to a significant fraction of the total pressure change. Section 3.4.4.3 eval-

uates the worst case combination of conditions for pressure increases for each

3-43


pay load shipping category. Section 3,4.4.4 evaluates the accumulation of

potentially flammable gases for each category.

3.4.4.2.1 Radiolvtic Gas Generation

Radiolytic gas generation (radiolysis of the payload materials by the radio-

active contaminants) is a potentially significant factor affecting pressure

for some payload shipping categories. Radiolytic gases are generated when

materials absorb radiation energy and produce gas molecules. Oxygen in the

initial atmosphere within an ICV of a TRUPACT-II Package may also be consisted

in some radiolytic processes. Gases are generated from radiolysis due to

alpha, beta, gamma or neutron interactions with matter. Contact-handled

transuranic (CH-TRU) waste is contaminated with transuranic radionuclides that

emit alpha radiation, with subordinate amounts of other types of radiation.

The radiation breaks chemical bonds in the target (potential gas producing

material) and causes chemical reactions to occur in the payload materials

and/or in the atmosphere in the payload cavity that could produce excess gas

or potentially flammable gases by radiolysis. This may result in the net

generation or consumption of gases. During transport, radiolysis of waste

materials in the TRUPACT-II Package payloads could result in either the net

increase or decrease of pressure in the ICV.

Maximom or bounding radiolytic gas generation rates are predictable for known

materials and amounts of radioactivity. The predictions are basod on experi-

mental data that relate the rate at which energy is being absorbed to the gas

generation rate for a given target material. This relationship uses a corre-

lation factor called the G value that is unique for a given material.

The gas generation rate, n , is determined from the following equation:

n = W x F x G x C

Where:

n = the gas generation rate (moles/sec).

3-44

NoPac TRUPACT-II SAR Rev. 1, May 1989

W = the total decay heat (watts),

F = the fraction of the total ionizing radiation that is absorbed by

the target material (potential gas producing material),

G = the mmber of molecules of gas generated per unit (100 eV) of

ionizing radiation absorbed by the target material, and

C = a conversion factor based on the units of measurement.

The gas generation rate depends on the 6 value of the material (molecules of

gas produced per 100 eV of energy absorbed), the fraction, F, of the emitted

energy which is absorbed by the target material, and the emitted energy avail-

able in the form of alpha (dominant for CH-TRU waste), beta, gamma, or neutron

radiation. The G value may be positive (in the case of hydrogen, carbon

dioxide, etc.) or negative (often the case for oxygen). The variable, F,

depends on the type of the radiation emitted, the spatial distribution of the

rad ioac t ive contaminants, and the t a rge t materials inside the payload

container.

In experiments designed to measure the G value of a material, care is taken to

obtain intimate contact between the radionuclides and the target material.

The F factor then approaches 1.0 (100% of the emitted energy is absorbed). In

CH-TRU wastes, the F factor is unlikely to be equal to 1.0 due to the presence

of non- target materials and the d i s t r i b u t i o n of the source and t a rge t

materials. Alpha radiation is the predominant type of radiation from trans-

uranics and has a very limited range. Since special care is needed to achieve

an F factor of 1.0 in laboratory conditions, in actual waste materials the F

factor will usually be much less than 1.0 and the energy absorbed by target

materials only a fraction of the energy emitted.

For payloads in the TRUPACT-II Package, the analysis of potential gas produc-

tion in the CH-TRU materials is based on an effective G value (or the product

of F times G). When several different waste materials may be present and the

distribution of TRU radionuclides is not well known, all vof the energy is

assumed to be absorbed by the material having the highest G value. By using

this approach, if actual values for gas generation were measured from a

3-45

NoP»c TRTJPACT-II SAR Rev. 1, May 1989

specific payload container, r e s u l t s would be bounded by the analytic predic-

tion. A detailed discussion of the effective G value assigned to each of t i e

payload shipping categories is provided in Appendix 3 .6 .7 . The effective G

value for each category i s used to determine the allowable gas generation ra t e

to r e s t r i c t the hydrogen concentration in the innermost layer of confinement

to a value less than five (5) volume percent and to calculate the decay heat

limit for each payload shipping category.

The discussion of effective G value in Appendix 3.6.7 considers both the G

value for materials and the select ion of an appropriate F factor for each

payload shipping category. The F factor used in calculat ions varies depending

on the waste material type in the shipping category and the configuration of

the layers of p las t ic bags confining the CH-TRU mater ia ls . This approach is

very conservative since the F factor may approach zero in many payload con-

ta iners . Matrix depletion is another reason for a lower-than-theoretical

effective G value. This s i tua t ion occurs in older waste where the alpha

radiat ion chemically changes the gas producing t a rge t material immediately

surrounding i t and decreases the F factor . Frequently in the sampling of

payload drums, no excess gas was detected even though the wattage and the

material present would be predicted to produce detectable quant i t ies of excess

gas.

3.4.4.2.2 Temperature Related -Pressure Change

The thermal performance of the package has two factors affecting pressure.

The f i r s t is the thermal expansion of the gases ( a i r , helium, vapors or radio-

ly t i c gases) within the TRUPACT-II Package ICV cavity with an increase in

temperature. This increase is calculated using the ideal gas law equation:

PV = nRT. The temperature, T, i s the average a i r temperature calculated from

the average temperature of a l l of the surfaces within the ICV and OCV. This

value w i l l vary depending on the wattage allowed in a spec i f i c payload

category. Tables 3.4-1 through 3.4-5 l i s t the average a i r temperature for 0,

10, 20, 30, and 40 wat ts . Figures 3.4-5 through 3.4-14 provide many of the

TRUPACT-II Package temperatures as a function of the decay heat for 0 to 40

watts .

3-46


The second pressure increase re la ted to temperature i s the pa r t i a l pressure of

moisture and po ten t ia l ly vo la t i l e chemicals within the TEUPACT-II Package ICV

cavity. The assumption for a l l payload shipping categories is that sufficient

water exists to maintain a saturated atmosphere. The par t i a l pressure exerted

by water vapor i s combined with other pressure contributions using Dalton's

Law. The water vapor pressure is obtained from the steam tab les , based on the

coolest wall temperature within the ICV, which is the temperature that mois-

ture will condense. The assumption for a l l analyt ical categories i s that the

par t ia l pressure contribution from poten t ia l ly vo la t i l e chemicals in the waste

is insignificant for pressure increases (Appendix 2.10.11). For the cate-

gories qualif ied for transport by t e s t , the pa r t i a l pressure contribution from

chemicals in a payload container will be measured and considered in the pres-

sure increase l imi t .

3.4.4.2.3 ^ r f t lKt r i? Press^rft

The design of TRUPACT-II Package meets the regulatory requirement for an ex-

ternal pressure of 3.5 psia per 10 CFR 71.71(c)(3) , Reference 3 .6 .1 .1 . This

external pressure is well below the maximum barometric pressure decrease

expected during transport due to elevation and weather changes. The expected

maximum barometric pressure decrease would only resu l t in an external pressure

of approximately 8 ps ia .

The analysis in Section 2.6.1 demonstrates that the TRUPACT-II Package is

capable of safely containing 61.2 ps ig . The conservative approach of using

the regulatory requirement of 3.5 psia reduces the safe pressure increase

limit by 11.2 ps i for a maximum allowable internal pressure of 50-psig. The

pressure r i se calculation for each payload category is based on the design

pressure l imit of 5 0 ps ig . Therefore, barometric pressure changes wil l not

affect the safety of the package and are accounted for in the use of a 50 psig

increase.in pressure.

3-47

NnPae THUPACT-II SAR Rev. 4, August 1989

3.4.4.2.4 Chemical Reactions

Potential pressure increases from gas-producing or exothermic chemical reac-

tions in the payload materials were considered. The chemical compatibility

evaluation performed for each payload shipping category determines the poten-

tial for chemical reactions. The chemical list for each shipping category is

restricted to preclude the occurrence of chemical reactions that produce ex-

cessive gas or heat (see chemical lists in Appendix 1.3.7).

These chemical lists are evaluated for potential incompatibilities in accor-

dance with, a U.S. Environmental Protection Agency (EPA) method that looks at

gas production and exothermic reactions. This method is discussed in Appendix

2.10.12 and Section 2.4.4.4. Use of the EPA method ensures that incompatible

chemicals do not contribute to increased pressures in the TSOPACT-II Packaging

ICV.

3.4.4.2.5 Biological Gas Generation

Several different types of microorganisms have the potential to cause gas pro-

duction from biological decomposition of material in the payload. These in-

clude aerobic, anaerobic, faculative anaerobes, and obligate anaerobes. Each

of these microorganisms requires a specific environment to multiply and pro-

duce gas.

Cellulosic materials within the payload materials can serve as substrate for

microorganisms. However, additional conditions are required for gas genera-

tion than just the presence of cellulosic materials. The environment within

the payload is hostile and incompatible for these microorganisms due to in-

sufficient nutrients (associated with a suitable substrate [nitrogen and phos-

phorus]), segregation of waste types, a high pH (in some waste types), excess

oxygen (for some microorganisms), and/or insufficient water content. These

factors will greatly reduce the potential for biological gas generation during

the shipping period. Aerobic bacteria, which are the most likely micro-

organisms to be present, will deplete oxygen and produce CC^, causing no net

increase in pressure. The limited potential for biological gas generation in

the TKUPACT-II Package payload is discussed in Appendix 3.6.5.

3-* 8


3.4.4.2.6 Thermal Decomposition

Some materials produce gases from thermal decomposition when'they are heated

above a threshold temperature at which the material becomes thermally (and in

some cases chemically) unstable. Usually these temperatures are close to the

combustion temperature or phase-change temperature of the material.

As demonstrated in the thermal evaluation (Section 3.4 .2) , the temperatures of

the pay load within the TRTJPACT-II Package are re la t ive ly low. In most cases,

the temperatures are well below the normal usage range for the material.

Under the increased temperatures for normal and accident conditions, thermal

decomposition wil l not occur.

CH-TRU materials that could potential ly produce gases from thermal decomposi-

tion are res t r ic ted to t e s t categories. Hence, they will be tested for gas

release at the maximum temperature for transport conditions. Thermal decom-

position as a factor affecting pressure is discussed in detail in Appendix

3.6.6.

3.4.4.3 Maximum Pressure for Normal Conditions

The maximum pressure in the TRUPACT-II Package ICV under normal conditions of

t ranspor t i s ca lcula ted below and shown to be very low for each of the

analytical payload shipping categories. As discussed in Section 3.4.4.2, the

major factors affecting the ICV internal pressure are radiolytic -gas genera-

t ion, thermal expansion of gases, and the vapor pressure of water within the

ICV cavity. Barometric changes that affect the external pressure, and hence

the gauge pressure of the TRUPACT-II Package containment vessels, are bounded

by the r.egulatory condition of a 3.5 psia external pressure and considered in

the use of the 5O.psig pressure increase l imi t . ICV internal pressure would

not increase significantly due to chemical reactions, biological gas genera-

tion or thermal decomposition. For the payload shipping categories qualified

for transport by gas generation and release t es t ing , the maximum pressure

increase allowed in the TRUPACT-II Package .ICV for normal conditions is the 50

3-49


psig pressure increase limit. The moles of gas released per second per

payload container is also calculated below for each, of the test categories.

The calculation allows for gases which may be released by any of the factors

which affect pressure.

Calculation of maximum pressure in the ICV for al l categories considers imme-

diate release of gases from the innermost layer of confinement around the

waste to the available void, volume of the ICV cavity. The available void

volume for accumulation of gas in the ICV i s conservatively estimated. The

available ICV void volume is the ICV void volume less the volume occupied by

the payload assembly. The ICV void volume i s the internal volume within the

ICV containment boundary less the volume occupied by the materials of con-

struction of the end spacers. Since the end spacers were purposely designed

to use perforated aluminum honeycomb, each has a large void volume for gas

accumulation.

The volume occupied by the payload assembly i s the volume of the payload con-

tainers plus the volume occupied by the p a l l e t , s l i p sheets , reinforcing

plates, and guide tubes for a fourteen (14) drum payload assembly. The e s t i -

mate of the void volume of the ICV considers only the volume in the ICV out-

side of the payload containers with no credit for the void volume present

.within the payload containers. Since drum payload containers have a s igni f i -

cant void volume that has historical ly averaged over 50% of the internal

volume, neglecting the void volume in the drums will overestimate the pressure

increase in the ICV.

The void volume within the ICV containment boundary less the volume of the

material of the end spacers i s approximately 5,750 l i t e r s . The volume

occupied by fourteen (14) drums plus pal let , slipsheets, reinforcing plates,

and guide tubes is approximately 3,300 l i t e r s . The volume occupied by two (2)

SWBs is approximately 4,000 l i t e r s . The net void volume for gas accumulation

in the ICV is 2,450 l i ters for a payload assembly of drums and 1,750 l i t ers

for an assembly of SWBs.

The net void volume in the ICV is assumed f i l l e d with air at 70 °F and 14.7

psia when the ICV is sealed for transport. Sufficient water is assumed pre-

sent for saturated water vapor at any temperature. The pressure increase due

3-50

NoPac TRDPACT-II SAR Rev. 4, August 1989

to water vapor is obtained from the tabulated thermodynamic properties of

saturated water and steam.

The maximum ICV pressure in each analytical payload shipping category at the

end of both a sixty (60) day shipping period and one year is provided in

Tables 3.4.4.3-1 through 3.4.4.3-4. The basis for a sixty (60) day maximum

shipping period is discussed in Appendix 3.6.4.

The method used to calculate the maximum ICV pressure is provided below for an

example payload shipping category. The number of moles per second of total

gas generated by radiolysis is calculated from the following equation:

ng = Geff(T) x W x C

Where:

n = the rate of radiolytic gas generation (moles/sec),

^eff(T) ~ t i i e temperature-corrected effective G value, the total nunber of

molecules of gas generated per 100 eV of energy emitted (mole-

cules/100 eV) at the temperature of the target material,

W = the total decay heat (watts),

C = a conversion constant for the units used,

[1.04(10)~5](g-moles)(eV)/(molecule)(watt-sec).

The effective G values are provided in Appendix 3.6.7 for the analytical pay-

load shipping categories. The maximum decay heat allowed in each of the

analytical payload shipping categories is provided in Sec.tion 1.2.3.3. The

maximum decay heat for each category determines the average contents tempera-

ture for that category. As discussed in Appendix 3.6.7, the effective G

values provided at room temperature (RT) are a function of temperature based

on the activation energy (E&) for the material. The effective G values used

in the calculation for pressure increase in the ICY are corrected to the

average contents temperature for each category using the activation energy of

the material in the category which is provided in Appendix 3.6.7.

3-51

Table 3.4.4.3-1TRUPACT-II Pressure Increase with a 14-Drum Payload

During a 60-Day Shipping Period

Payload

ShippingCategory

I.1A0MAI

1.1A2

1.1A3

I.2A0I.2A1

I.2A2

I.2A3I.2A4

I.3A01.3A1

I.3A2

I3A3I.3A4

II.1A0

II.1A1II.lA2a

1I.1A2

II.1A3II.1A4

II.1A5II.1A6

H.2AM

III.IAOIII.1A1

III.lA2aIII.1A2

III. 1 A3III.1A41II.1A5III.1A6

DecayHeat/Cont.

(Watts)

0.2060

0.1797

0.15940.0466

0.2536

0.22120.1962

0.05730.0418

0.8241

0.71890.6375

0.1863

0.1359

0.22510.19240.1680

0.08690.0561

0.04140.0328

0.027240.0000

0.1126

0.09620.0840

0.04340.0280

0.0207O.OI640.0136

DecayHeat/

TRUPACT-II(Wans)

2.88

2.52

2.230.65

3553.10

2.750.80

0.59

11.5410.06

8.932.61

1.90

3152.69

2.351.22

0.790.580.46

0.3840.00

1.58

1.351.180.61

0.390.290.230.19

Average

ContentsTemp.

(deg. F)

128.9

128.5128.2

126.7

129.6

129.1

128.7126.8

126.6

137.5136.1

134.9128.6

127.9

129.2

128.7128.4127.2

126.8126.6

126.5126.4163.0

127.6

127.3127.2'126.6

126.4126.3126.2126.2

EffG-val.

for TotalGas (mol/

lOOeV)

2.42.42.42.4

2.0

2.02.0

2.02.0

0.60.60.60.60.6

1.71.7

1.71.7

1.71.7

1.71.70.0

8.48.48.4

8.48.48.48.48.4

Activ.Energykcal/

g-mole

0

000

000

0

0

0

00

00

0.80.80.8

0.80.80.8

0.80.8

0

2.2.2.1

2.12.12.12.2.

Temp CorrEffG-val.

(mol/lOOeV)

2.4

2.42.42.4

2.0

2.02.02.0

2.0

0.60.60.60.60.6

19191.919191.91.91.90.0

11.411.411.4

11.3

11.311.311.311.3

Radiolytic

Gas gener.Rate

(moles/sec)

7.20E-076.28E-O7

5.57E-O7

1.63B-O7

7.38E-O76.44E-O7

5.71E-O71.67E-O7

1.22E-O7

7.20E-O76.28E-O75.57E-O7

1.63E-O71.19E-O7

6.28E-O7

5.36E-O74.68E-O7

2.41E-O71.56E-O71.15B-O79.10B-087.54E-O8

O.OOE+00

1.B7E-O61.59E-O61.39E-O6

7.16B-O74.62E-O73.41EO72.701:072.25E-O7

Radiolytic

Gas gener.STP/60days

(liters)

83.5972.9264.68

18.91

85.7574.80

66.34

1938

14.13 •

8360

72.9364.6718.90

13.79

72.9162.26

54.3328.0318.08

13.3410.568.760.00

216.97185.14

161.5183.1853.6039.61

31.3726.08

Average

ICVgas

Temp.(deg. F)

127.7127.5

127.3126.4

128.1

127.9127.6

126.5126.4

132.9132.0

131.4127.6

127.1

127.9127.6

127.4

126.7

126.5126.3

126.3126.2148.0

126.9126.8

126.7126.4126.2126.2126.1126.1

RadiolyticGas press.Increase

(psia)

0.600.520.46

0.14

0.62

0.540.48

0.140.10

0.60

0.530.470.140.10

0.52

0.45

0.390.20

0.130.10

0.080.06

0.00

1.551.321.16

0.590.380.280.22

0.19

IncreasedInitial gas

Pressure(psia)

16.3016.3016.2916.26

16.3116.3016.30

16.2716.26

16.4516.4216.4016.3016.28

16.3116.30

16.29

16.2716.2716.26

16.2616.26

16.86

16.2816.28

16.2716.2616.2616.2616.2616.26

MinimumICVwall

Temp.(deg. F)

122.4

122.3122.1

121.3

122.8

122.5122.4

121.4

121.3

126.8126.0

125.5

122.3122.0

122.6

122.3122.2

121.6

121.4

121.3121.2

121.2142.0

121.8

121.7121.6

121.3121.2121.1121.1121.1

WaterVapor

Pressure

(psia)

1.821.81

1.801.76

1.831.821.811.761.76

2.042.00

1.971.81

179

1.821.81

1.81

1.771.76

1.75

1.751.75304

1.781.781.78

1.751.751.751.751.75

PressureIncrease

at 60 days

(psig)

4.02

3.933853.46

4.06

3963893.473.42

4.394.254.143.543.48

3953.85

3.793.543.46

3.41

3.39• 3.37

5.20

4.914.68

4.51

3913693593.533.49

13

n

I

to

Table 3.4.4.3-1 (continued)TRUPACT-II Pressure Increase with a 14-Drum Payload

During One Year

Payload

Shipping

Category

MAO

MAIMA2

MA3

I.2A0I.2A1I.2A2

I.2A3I.2A4

I.3A0

I.3A11.3A2

I.3A3I.3A4

II.1A0

IMA1Il.lA2a

1MA2II.1A3II.1A4

IMA5II.1A6II.2AM

M.1A0

III.1A1IIMA2a

III.1A2

III. 1 A3III.1A4III.1A5III.1A6

Decay

Heat/

Cont.

(Watts)

0.2060

0.17970.15940.0466

0.25360.2212

0.1962

0.05730.0418

0.8241

0.71890.63750.1863

0.1359

0.22510.19240.1680

0.08690.0561

0.04140.03280.0272

40.0000

0.11260.0962

0.0U40

0.04340.0280

0.02070.01640.0136

Decay

' Heat/

TRUPACT-II

(Watts)

2.882.52

2.230.65

3553.10

2.750.80

0.59

11.5410.06

8.932.61

1.90

315

2.692.351.22

0.790.580.46

0.3840.00

1.58

1351.18

0.61

0.390.29

0.230.19

AverageContents

Temp.

(deg. F)

128.9128.5128.2126.7

1296129-1128.7126.8126.6

137.5136.1134.9128.6

127.9

129.2

128.7128.4127.2126.8126.6

126.5126.4163.0

127.6

127.3127.2126.6

126.4

126.3126.2126.2

EffG-val.

for Total

Gas (mol/

lOOeV)

2.42.42.42.4

2.02.02.02.0

2.0

0.6

0.60.60.60.6

1.71.71.71.71.71.71.71.70.0

8.4

8.4

8.48.4

8.48.48.48.4

Activ.

Energylecal/

g-mole

0000

000

00

00

000

0.80.80.80.80.80.80.80.8

0

2.12.1

2.1

2.12.12.12.12.1

Temp CorrEffG-val.

(mol/lOOcV)

2.42.42.42.4

2.02.0

2.0 .2.0

2.0

0.6

0.60.60.60.6

1.9191-91.9191.919190.0

11.411.4

11.4

11.311.3

11311.311.3

Radiolytic

Gas gener.

Rate

(moles/sec)

7.20E-O76.2BE-O7

5.57E-O71.63E-O7

7.38E-O76.44E-O75.71E-07

1.67E-O71.22E-O7

7.20E-076.28E-O75.57E-O71.63E-O71.19E-O7

6.28E-O7

5.36E-O74.68E-O72.41E-071.56E-O71.15E-O79.10B-087.54E-O8

O.OOE+00

1.87B-O61.59E-O6

1.39E-O6

7.16E-O7

4.62E-O73.4lli-O72.7(11:072.25H-O7

Radiolytic

Gas gener.STP/lyear

(liters)

508.5044358

393.47

115.03

521.67455.02

403.59117.8785.98

508.57443.65393.41

114.9783.87

443.56378.76

330.49170.54110.00

81.14

64.27

53.290.00

1319921126.25

982.49506.03326.08

240.93190.82

158.67

Average

ICVgas

Temp.(deg. F)

127.7

127.5

127.3126.4

128.1

127.9127.6

126.5126.4

132.9132.0

131.4127.6

127.1

127.9127.6127.4

126.7126.5126.3126.3126.2148.0

126.9126.8

126.7126.4126.2

126.2126.1126.1

RadiolyticGas press.

Increase(psia)

3.643.18

2.820.82

3.743.26

2.890.840.61

3.68

3.202.840.820.60

3.18

2.712.371.22

0.790.580.460.38

0.00

9.458.06

7.033.622.331.721.36113

IncreasedInitial gasPressure

(psia)

16.3016.3016.2916.26

16.3116.3016.3016.2716.26

16.4516.4216.4016.3016.28

16.3116.3016.29

16.2716.2716.2616.26

16.2616.86

16.28

16.28

16.2716.2616.2616.2616.2616.26

MinimumICVwall

Temp.(deg. F)

122.4

122.3122.1

121.3

122.8

122.5122.4121.4

121.3

126.8126.0

125.5122.3122.0

122.6

122.3122.2121.6

121.4

121.3121.2121.2142.0

121.8

121.7121.6

121.3121.2121.1

121.1121.1

Water

VaporPressure

(psia)

1.821.811.801.76

1.831.821.811.761.76

2.042.00

1971.81

1.79

1.821.811.81

1.771.76

1.751.751.753.04

.78

.78

.78

.75

.75

.75

.75

.75

Pressure

Increase

at 1 year

(psig)

7.076.586.21

4.15

7.196.696.304.173.94

7.466.936.514.233.98

6.616.125.774.564.113893.773695.20.

12.81

11.4210.386.935645.034.674.44

£?

.<VO

s?O(D

&nri

O

I

Table 3.4.4.3-2TRUPACT-II Pressure Increase with Eight Drums Overpacked Into Two Standard Waste Boxes


Payload

ShippingCategory

I.I DO

I.1D1I.1B2

I.1B3

I.2B0I.2B1I.2B2

I.2B3I.2B4

I.3B0

I.3B1I.3B2

I.3B3I.3B4

I1.1B0II.1B1

II.lB2aII.1B2

II.1B3H.1B4

1I.1B3II.1B6

II.2BM

III.1U0

III.1U1

III.lB2a

III.1B2

I1I.1B3111.1114111.105111.1116

DecayHeat/

Com. .

(Wans)

0.5828

0.52800.4828

0.1704

0.71720.6500

0.59440.2096

0.1564

2.33082.11241.93120.6812

0.5088

0.68440.60640.5440

0.30960.20800.15680.12560.1048

40.0000

0.34240.3032

0.27220.1548

0.10400.07840.06280.0524

Decay

Heat/

TRUPACT-I1(Watts)

1.171.06

0.970.34

1.431.30

1.190.42

0.31

4.664.223.861.36

1.02

1.371.21

1.090.620.42

0.310.250.2140.00

0.680.61

0.54

0.310.210.16

0.130.10

AverageContents

Temp.

(deg.F)

129.61293129.0127.1

130.4130.0129.7127.3127.0

140.5139.1138.0130.2129.2

130.21298129.4

127.9127.3127.0126.8

126.6238.0

128.1

127.9127.7127.0126.6

126.5126.4

126.3

EffG-val.for Total

Gas (mol/

lOOeV)

2.4

2.42.42.4

2.02.02.02.02.0

0.6

0.60.60.60.6

1.71.7

1.71.7

1.71.7

1.71.70.0

8.48.4

8.48.4

8.48.48.4H.4

Activ.

Energykcal/

g-mole

00

00

00

000

0000

0

0.80.8

0.8

0.80.80.8

0.80.80

2.1

2.12.12.1

2.12.12.12.1

Temp CorrEffG-val.

(mol/

lOOeV)

2.42.4

2.42.4

2.02.02.02.02.0

0.6

0.60.60.60.6

1 91.9

1.91.91 91.9

1.91.90.0

11.411.4

11.411.4

11.3

11311.3113

Radiolytic

Gas gener.

Rate

(moles/sec)

2.91E-O7

2.64E-O72.41E-O78.51E-O8

2.98E-072.7OE-O72.47E-O78.72E-086.51E-O8

2.91 E-072.64E-O72.41E-O78.50E-O86.35E-O8

2.73E-O72.42E-O7

2.17E-O71.23E-O78.26E086.22E-084.98E-084.15B-O8

O.OOB + 00

8.14E-O77.2OB-O7

6.46E-073.66E-O7

2.45E-O71.851:071.481:071.231:07

Radiolytic

Gas gener.STP/60 days

(liters)

33.78

30.61

27.999 8 8

34.6531.40

28.7110.137.56

33.78

30.61

27.999 8 7

7.37

31.7428.1025.18

14.29

9597.22

5.784.820.00

94.5483.60

74.98

42.4728.48

21.4517.17

14.33

Average

ICVgas

Temp.

(deg.F)

126.7126.6

126.6126.2

126.9126.8

126.7126.3126.2

128.8

128.5

128.3126.8126.6

126.8

126.7126.7126.4126.2126.2126.2

126.1148.0

126.4

126.4

126.3126.2126.1

' 126.1126.1126.1

Radiolytic

Gas press.Increase

(psia)

0.34

0.310.28

0.10

0.35

0.310.29

0.100.08

0.34

0.310.280.10

0.07

0.320.28

0.250.140.10

0.070.06

0.050.00

0.950.84

0.75

0.430.29

0.210.170.14

Increased

Initial gas

Pressure

(psia)

16.2716.27

16.27.16.26

16.28

16.2716.2716.26

16.26

16.33 •16.32

16.3216.28

16.27

16.28

16.2716.2716.2616.26

16.2616.26

16.2616.86

16.2616.26

16.2616.26

16.2616.2616.26

16.25

MinimumlCVwall

Temp.(deg. F)

122.7122.6

122.6122.2

122.9122.8

122.7122.3122.2

124.8

124.5124.3122.8122.6

122.8

122.7

122.7122.4122.2122.2122.2

122.1144.0

122.4122.4

122.3122.2122.1122.1

122.1122.1

Water

VaporPressure

(psia)

1.83

1.831.821.81

1.84

1.831.831.811.80

1.941.921911.841.83

1.831.821.821.811.801.801.801.803.20

1.811.811.801.801.801.801.80I.K0

PressureIncrease

at 60 days(psig)

3.743703.673.46

3.763.72

3693.473.44

3913.863.81

3513.47

3.72

3.673.64

3523.46

3433.423.405.36

4.32

4.214.11

3.783.64

3.573.5J3.50

=5

n

C/l

VO

o(D

IBM

VO

O

I

u>

Table 3.4.4.3-2 (continued)TRUPACT-II Pressure Increase with Eight Drums Overpacked Into Two Standard Waste Boxes

During One Year

Payload

ShippingCategory

I.I BO

I.1B1

I.1B2

I.1B3

I.2B0

I.2B1I.2B2

I.2B3I.2B4

I.3B0

I.3B1I.3B2

I3B3I.3B4

U.I BO

II.1B1

H.lB2aII.1B2

1I.1B3II.1B4

II.1B5II.1B6

II.2BM

III.1B0

III.1B1III.lB2a111.1112

I11.1B3III.11)4

111.1115III.HK>

DecayHeat/Cont.

(Wans)

0.5828

0.52800.4828

0.1704

0.7172

0.65000.5944

0.20960.1564

2.33082.11241.93120.6812

0.5088

0.68440.6064

0.54400.30960.20800.15680.1256

0.104840.0000

0.34240.30320.27220.15480.10400.07840.06280.0524

Decay

Heat/TRUPACT-II

(Watts)

1.171.06

0.970.34

1.431.30

1.190.42

0.31

4.664.223.861.36

1.02

1.37 •1.21

1.090.62

0.42

0.310.250.2140.00

0.680.61

0.54

0.310.210.16

0.130.10

AverageContents

Temp.(deg.F)

12961293129.0127.1

130.4130.0129.7127.3127.0

140.51391138.0130.2

129.2

130.2

129.8

129.4

127.9127.3127.0

126.8126.6238.0

128.1

127.9127.7,127.0126.6

126.5126.4

126.3

EffG-val.

for Total

Gas (mol/lOOeV)

2.42.42.42.4

2.02.0

. 2.02.02.0

0.60.60.60.60.6

1.71.71.71.71.71.71.71.70.0

8.48.48.48.48.48.48.48.4

Activ.

Energykcal/

g-mole

00

0

0

0

0

000

00000

0.8

0.8

0.80.80.80.8

0.80.80

2.12.2.

2.2.2.2.2.

Temp CorrEffG-val.

(mol/lOOeV)

2.4

2.42.4

2.4

2.0

2.02.02.02.0

0.60.60.60.60.6

191.91919191919190.0

11.411.411.411.4

11.311.311.311.3

Radiolytic

Gas gener.Rate

(moles/sec)

2.91 E-072.64E-O72.41 E-078.51E-O8

. 2.98E-O72.70E-O7

2.47E-O78.72E-086.51E-O8

2.91 B-072.64E-07

2.41 E-078.50E-OS6.35E-O8

2.73E-O72.42E-O7

2.17B-O7

1.23E-O78.26E-O86.22E-O84.98E-O84.15E-O8

o.oon+oo

8.14E-O77.20E-O7

6.46E-O73.66E-O7

2.45E-O71.85IM>71.48H-O71.23U07

Radiolytic

Gas gener.STP/1 year

(liters)

205.52

186.19

170.25

60.09

210.76

19101174.6761.5945.96

205.48186.23170.2560.0544.86

193.10170.921532186.9358.3243.9435.1829350.00

575.11

508.59456.11

258.35173.26130.50104.4887.14

AverageICVgasTemp.

(deg. F)

126.7126.6126.6

126.2

126.9126.8

126.7

126.3126.2

128.8

128.5128.3126.8126.6

126.8

126.7126.7126.4126.2126.2126.2126.1148.0

126.4126.4126.3126.2126.1126.1126.1126.1

RadiolyticGas press.Increase

(psia)

2.061.861.710.60

2.111911.750.620.46

2.071.871.710.60

0.45

1931.711.530.870.580.440.350.290.00

5.765.094.572.591.731.311.050.87


Pressure(psla)

16.2716.2716.2716.26

16.2816.2716.2716.2616.26

16.3316.3216.3216.2816.27

16.2816.2716.2716.2616.2616.2616.2616.2616.86

16.2616.2616.2616.2616.2616.2616.26

16.25

MinimumlCVwall

Temp.(deg.F)

122.7122.6

122.6122.2

122.9

122.8

122.7

122.3122.2

124.8

124.5124.3122.8122.6

122.8

122.7

122.7122.4122.2122.2122.2

122.1

144.0

122.4122.4

122.3122.2122.1122.1122.1122.1

WaterVapor

Pressure(psia)

1.84

1.831.821.81

1.841.84

1.841.811.B0

1971951.931.84

1.83

1.831.82

1.82.81.80.80

.80

.801.20

.81

.81

.81

.80

.80

.80

.80

.80

PressureIncreaseat 1 year

(psig)

5.47.5.275.09397

5535335.163993.82

5.675.445.264.02385

5.345.114.934.243.943.80

3.713.655.36

9138.467.945.945.09A.664.404.23

o

TABLE 3.4.4.3-3

TRUPACT-II Pressure Increase with Two Standard Waste BoxesDuring a 60-Day Shipping Period

11HW

5

Paytoad

SWppInoCategory

I. ICOI.2C0I.3C0

II. ICOII.IC11I.IC2II.IC3II.1C4II.2CM

III. ICOIII.ICIIII.1C2III.1C3III.1C4

Dacay

Haat/Cont.

IWatta)

0.91321.12403.6500

1.02060.70290.53610.12220.069040.0000

0.51030.35150.26800.06110.0345

Dacay

Haatf

TRUPACTII

IWattt)

1.82642.24807.3056

2.04121.40581.07220.24441.1380

40.0000

1.02060.70300.53600.12220.0690

Avaraga

Contanta

Tamp.

I'FI

131.7133.0148.6

132.3130.4129.3126.8126.4238.0

129.2128.2127.7126.4126.2

EttactlvaQ-Valua (orTotal Qaa

(mol/IOOaV)

2.42.00.6

1.71.71.71.71.70.0

8.48.48.48.48.4

Actlv.Enargykcal/

0-mota

0.00.00.0

0.80.80.80.80.80.0

2.12.12.12.12.1

TamparaturaCorractad

EH QValua(nwl/100aV)

2.42.00.6

1.91.91.91.91.90.0

11.511.411.411.311.3

RadMytki

Qai Qanararatlon

Rata

(motat/aec)

4.56E-074.68E-O74.56E-07

4.09E-072.81E-072.14E-074.85E-082.73E-08

O.OOE+00

1.22E-O68.36E-O76.36E-O71.44E-O78.12E-08

Radlolyttc

Qaa DalmatianSTP/60 daya

(Htats)

52.9454.3052.94

47.5432.6124.825.633.170.00

141.7197.0873.8116.719.43

AvaragaICV QatTamp.

l°Fi

127.1127.3130.4

127.2126.9126.7126.2126.1148.0

126.6126.4126.3126.1126.0

Radlolyttc

Qaa Praaaura

Incraaaa(ptlai

0.530.540.53

0.480.330.250.060.030.00

1.420.970.740.170.09

Incraaaad

Initial Qaa

Prataura

Iptla)

16.2816.2916.37

16.2916.2816.2716.2616.2616.86

16.2716.2616.2616.2616.25

MinimumICV WaiTamp.I*F»

123.1123.3126.4

123.2122.9122.6122.1122.1144.0

122.6122.4122.3122.1122.0

WatarVapor

Pmtauralp*la)

1.851.862.02

1.851.841.821.801.803.20

1.821.811.811.801.79

Praaaura

Incraaaaat 60 daya

tp»lo)

3.974.004.23

3.913.743.643.423.395.36

4.814.354.113.523.44

on(totrID

TABLE 3.4.4.3-3 (continued)

TRUPACT-II Pressure Increase with Two Standard Waste BoxesDuring One Year

3

MM

win

Payload

SMppingCatagory

I.ICOI.2C0I.3C0

II.ICO1I.1CIII.1C2II.IC3II.IC4II.2CM

III. ICOIII.1CIIII.IC21II.1C3II1.1C4

Decay

Haat/

Com.(Watt*)

0.91321.12403.6528

1.02060.70290.53610.12220.069040.0000

0.51030.35150.26800.08110.0345

Dacay

HaatfTRUPACT-II

IWatt*)

1.82642.24807.3056

2.04121.40581.07220.24440.138040.0000

1.02060.70300.53600.12220.0690

Avaraga

Contanti

Tamp.

t'FI

131.7133.0148.6

132.3130.4129.3126.8126.4238.0

129.2128.2127.7126.4126.2

Effactlva

Q-Valua for

Total QaaImol/IOOaVI

2.42.00.6

1.71.71.71.71.70.0

8.48.48.48.48.4

Actlw.

Enargykcal/

g-mola

0.00.00.0

0.80.80.80.80.80.0

2.12.12.12.12.1

Tampa ratura

Corraetad

EN Q-ValuaImol/IOOaVi

2.42.00.6

1.91.91.91.91.90.0

11.511.411.411.311.3

O n QananratlonRata

ImoUs/Mc)

4.56E-074.68E-074.56E-07

4.09E-072.81 E-072.14E074.85E-082.73E-O8

O.OOE+00

1.22E-068.36E-076.36E071.44E-078.12E-08

Radlotytk

Qaa Oanaratlon

8TP/1 yaar(•lira)

322.03330.30322.03

289.20^98.37150.9734.2319.310.00

862.04590.58449.00101.6457.34

Avaraga

ICV Oat

Tamp.I»FI

127.1127.3130.0

127.2126.9126.7126.2126.1148.0

126.6126.4126.3126.1126.0

RadlolyttcOat Pranura

Incraata

Iptla)

3.233.313.25

2.901.991.510.340.190.00

8.635.914.491.020.57

InciaasadMtMQatPratiura

lp*la)

16.2816.2916.37

16.2916.2816.2716.2616.2616.86

16.2716.2616.2616.2616.25

MinimumICV Wai

Tamp.

I*FI

123.1123.3126.4

123.2122.9122.6122.1122.1144.0

122.6122.4122.3122.1122.0

Watar

VaporPrattura

Iptla)

1.851.862.02

1.851.841.821.801.803.20

1.821.811.811.801.79

Pranura

Incraata

at 1 yaar

ip*igl

6.666.776.94

6.345.414.903.703.555.36

12.029.297.874.373.92

%

onrtocr(D

ID

Table 34.4.3-4TRUPACT-II Pressure Increase with Two Bins Overpacked Into Two Standard Waste Boxes


Paytoad

ShippingCategory

I.1D21.202I.3D2

U.1D2

UI.1D2

III. IDS

Decayllcal/Com.

(Waits)

0.3922

0.48271.568?

0.4271

0.2135

0.0235

Decayllcat/

TRUPACT-II(Watu)

0.784409654

31378

0.8542

0.42700.0470

Avenge

Contents

Temp.

(deg.F)

128.4129.0135.7

128.6

127.3126.1

EffG-val.for Toul

Gas (mo)/

lOOeV)

2.42.00.6

1.7

8.48.4

Acttv.

Energy

teal/g-mote

000

0.8

2.1

2.1

TempCorrEffG-val.

(mol/

lOOeV)

2:42.00.6

19

11.4

113

RadiolyilcGas gener.

Rate(moles/sec)

1.96E-O72.0IE-O7

1.96E-O7

1.7012-07

5-O5E >75.53B-O8

Radiolytic

Gas gener.STP/60days

(liters)

22.742332

22.74

19-74

58.696.42

AverageICVgasTemp.

(deg. F)

126.5126.6

1279

126.5

126.9126.0

RadiolyticGas press.

Increase

(psia)

0.230.23

0.23

0.20

0.590.06


Pressure(psia)

16.2716.2716.31

16.27

16.28

16.25

MinimumICVwallTemp.

(deg. F)

122.5122.6

123-9

122.5

122.9

122.0

WaterVapor

Pressure(psia)

1.821.821.89

1.85

1.841.80

PressureIncrease

at 60 days

(Pi'g)

361363372

362

4.01342

I

iHM

in

tn

XO

o

Table34.4.3-4 (continued)TRUPACT-II Pressure Increase with Two Bins Overpacked Into Two Standard Waste Boxes

During One Year

• atoo

Paytood

ShippingCategory

I.ID2I.2D2I.3D2

U.1D2

M.ID2in. IDS

Decay

lieat/Com.

(Watts)

039220.48271.5689

0.4271

0.2135

0.0235

Decay

lleal/

TRUPACT-n(Waits)

0.7844096)431378

0.8542

0.42700.0470

AverageContents

Temp.

(<kg F)

128.41290

135.7

128.6

127.3126.1

EffGval.for Tout

Gas (mo)/lOOeV)

2.42.0

* 0.6

1.7

8.48.4

Activ.Energykcal/

g-molc

000

0.8

2.12.1

Temp CorrEffG-val.

(mol/lOOeV)

2.42.00.6

19

11.4

113

RadioryllcGas gencr.

Rale(moles/sec)

1.966-072.01 B-071.96B-O7

1.7OE-O7

5OJE^)75.53E-O8

RadiotyticGas gencr.

STP/1 year(liters)

138.30

141.85

138.31

120.10

357.033904

AverageICVgas

Temp.

(**«")

126.5126.6

1279

126.5

1269126.0

RadiolytlcGas press.Increase

(psla)

1.381.42

139

1.20

358

0.39


(psla)

16.2716.2716.31

16.27

16.2816.25

MinimumICVwall

Temp.(deg.F)

122.5122.6

1239

Mil

122.9122.0

WaterVapor

Pressure

(psla)

1.821.82

1.89

1.85

1.841.80

PressureIncreaseat lyrar

(pslg)

4.774.814.88

4.62

7.003.74

n

«o

o

o

NaPae TRUPACT-II SAR Rev. 3, July 1989

For an example using payload shipping category I.1A0, the effective 6 value at

room temperature is 2.4 (from Appendix 3.6.7). and the maximum decay heat is

2.8840 watts (Table 1.2.3.3-3) for the tota l pay load of fourteen (14) drums.

The temperature-corrected effective G value is calculated using the following

equation:

Geff(T) = Geff(RT) o x* C < V R ) t ( T " % r ) / ( T x TRT)]}

Where:

^eff(RT) = t l i e effective G value at room temperature [the umber of mole-

cules of gas generated per 100 eV of energy (molecules/100 eV)

for target material at room temperature],

Eft = the activation energy for the target material, kcal/g-mole,

R = ideal gas constant, 1.99 cal/g-mole-°K,

T = temperature of the target material, the average contents tempera-

ture,

^RT = r o o m temperature, 25 °C.

The temperature-corrected effective G value for category I.1A0 is calculated

at the average contents temperature based on the maximum decay heat for that

category. Figures 3.4-6 through 3.4-14 provide the normal condition, steady

state temperatures for decay heat values from 0 to 40 watts for package tem-

peratures of interest including average contents temperatures. The average

contents temperature for category I.1A0 is 128.9 °F. From Appendix 3.6.7, the

activation energy is zero (0) for water which is the target material. The

temperature corrected effective G—value i s :

Geff(129 °F) = ^** nolecules/100 eV) x exp {(0 kcal/g-mole)/

[1.99(10)~3 cal/g-mole-°K]

[(327 °K - 298 °K)/(327 °K x 298 °K)]}

Geff(129 °F) = ^"

3-55

NoP*c TRUPACT-II SAR- Rev. 4, August 1989

Using this temperature-corrected effective G value, the radiolytic gas genera-

tion rate i s :

n = (2.4 molecules/lOO eV) x (2.8840 watts)

x [1.04(10)~5](g-moles)(eV)/(molecule)(watt-sec)

n = 7.20(10)"^ moles/sec

The total nmber of l i t e r s of radiolytic gases which is generated, VR, when

corrected from moles to l i t e r s at SIP (32 °F and 1 atmosphere pressure) at the

end of a sixty (60) day shipping period would be:

VJJ = n x 60 -days x conversion factors

VR = 7.20(10)~7 moles/sec x 60 days x 86,400 sec/day

x'22.4 liters/mole

VR = 83.59 l i t e r s at STP

At the end of one year, V R ( ^ a r j would be 508.50 l i t e r s at STP. The generated

volume of radiolytic gases (corrected to STP) is heated to the average ICV gas

temperature for normal conditions of transport. The average ICV gas tempera-

ture is also available from the TRUPACT-II Package temperatures given in

Figures 3.4-6 through 3.4-14. For payload shipping category I.1A0 (decay heat

of 2.8840 watts), the average gas temperature is 127.7 °F. The radiolytic gas

would occupy a volume, V of:

Vrg = (83.59 liters)(460 °R + 127.7 °F)/(460 °R + 32 °F)

99.9 l i t e r s at 127.7 °F

VR(year)-= <5°8.50 l i te rs) (460 °R + 127.7 °F)/(460 °R + 32 °F)

606.2 l i t e r s at 127.7 °F

3-56

NaPac TRUPACT-II SAR Rev.. 4 . August 1989

This gas contributes a pressure, p , of

p rg °* (99.9. l i t e r s ) / (2 ,450 l i t e r s )

= 0.041 atm (0.60 psia) a t 127.7 °F

Prg(year) = <-606'2 l i t e r s ) / 2 ,450 l i t e r s= 6.247 atm (3.64 psia) a t 127.7 °F

3-5 6 a

NaPac TRDPACT-II SAR - Rev. 4, August 1989

The i n i t i a l volume of gas present in the ICV a t 70 °F and 14.7 psia i s also

heated to 127.7 °F fox a decay heat of 2.8840 wat t s for payload shipping ca te-

gory I.1A0. The. increased pressure associated with th i s heat-up, p^ u , i s :

p h u = [(14.7 psia) / (460 °R + 127.7 °F)/(460 °R + 70 °F)]

= 16.30 psia

The water vapor pressure i s based on the temperature of the coolest or conden-sing surface of the ICV. The minimum ICV wall temperature i s also availablefrom the TRUPACT-II Package temperatures in Figures 3.4-6 through 3.4-14. Forpayload shipping category I.1A0 with a decay heat of 2.8840 wat ts , the minimumICV wall temperature i s 122.4 °F, and the corresponding water vapor pressure,p ¥ v , i s 1.82 ps i a .

The maximum ICV pressure a t the end of sixty (60) days for pay load shippingcategory I.1A0, p m a z , i s the sum of the three pressure components less anassumed atmospheric pressure, p , of 14.7 ps ia , or :

Pmax Prg Phu Pwv "" Pa= 0.60 psia + 16.30 psia + 1.82 psia - 14.7 ps ia- 4.02 psig

At the end of one year, the maximum ICV pressure would be 7.06 psig for cate-

gory I.1A0. Thus, the pressure increase for payload shipping category I.1A0

is well below the allowable pressure increase limit of 50 psig. The maximum

pressure increase for every analytical payload shipping category is also well

below the limit as shown on Tables 3.4.4.3-1 through 3.4.4.3-3. The maximum

pressure for normal conditions does not affect the performance of the TRUPACT-

II Package for the analytical payload shipping categories.

The maximum allowable pressure increase in one year for all of the "test cate-

gories is the design pressure limit of 50 psig. The allowable number of moles

per second of gases (excluding water vapor) released from a payload container

may not exceed this limit. The maximum gas release rate calculated for each

of the test categories is provided in Table 3.4.4.3-5. The calculation is

based on the maximum decay heat for each test category. This provides the

minimum ICV wall temperature for determining the vapor pressure of water, and

the' average ICV gas temperature for determining the pressure rise due to

heating the gases

3-57

TRUPACT-II SAR Rev. 14. October 1994

TABLE 3.4.4.3-5Maximum Gas Release Rates for Test Categories

55-Gallon Drum °

I—PayloadShipping

II CategoryP"I.1A0T1.1 AITI.1A2TI.1A3T


I.3A0TI.3AITI.3A2TI.3A3TI.3A4T

II.1A0TH.1A1TII.lA2aTII.1A2TII.1A3TII.1A4TII.1A5TII.IA6T

III.1A0TI IH.1A1T

HI.lA2aTIII.1A2TIII.1A3TIII.1A4TIII.1A5TIH.1A6T

IV.1A1TIV.1A2T

1 IV.1A3T

3 = = = = = =

DecayHeat/

TRUPACT-II(watts)

10.010.010.010.0

10.010.010.010.010.0

10.010.010.010.010.0

20.020.020.020.020.020.020.020.0

20.020.020.020.020.020.020.020.0

7.07.07.0

= = = = =MinimumICV Wall

TemperatureI'fl

126.0126.0126.0126.0

126.0126.0126.0126.0126.0

126.0126.0126.0126.0126.0

132.0132.0132.0132.0132.0132.0132.0132.0

132.0132.0132.0132.0132.0132.0132.0132.0

123.3123.3123.3

WaterVapor

Pressure(psia)

2.002.002.002.00

2.002.002.002.002.00

2.002.002.002.002.00

2.342.342.342.342.342.342.342.34

2.342.342.342.342.342.342.342.34

1.971.971.97

AverageICV Gas

Temperature(°F)

132.0132.0132.0132.0

132.0132.0132.0132.0132.0

"132.0132.0132.0132.0132.0

137.0137.0137.0137.0137.0137.0137.0137.0

137.0137.0137.0137.0137.0137.0137.0137.0

130.2 I130.2130.2 '

IncreasedInitial GasPressure

(psia)

16.4216.4216.4216.42

16.4216.4216.4216.4216.42

16.4216.4216.4216.4216.42

16.5616.5616.5616.5616.5616.5616.5616.56

16.5616.5616.5616.5616.5616.5616.5616.56

16.3716.3716.37

= = = = = =Allowable

GasRelease(liters)

7713.407713.407713.407713.40

7713.407713.407713.407713.407713.40

7713.407713.407713.407713.407713.40

7633.627633.627633.627633.627633.627633.627633.627633.62

7633.627633.627633.627633.62 !7633.627633.62 I7633.627633.62 I

7726.727726.727726.72 I

• i lMaximum gasRelease Rate(moles/sec/container) |

'6.48E-076.48E-076.48E-076.48E-07

6.48E-076.48E-076.48E-076.48E-076.48E-07

6.48E-076.48E-076.48E-076.48E-076.48E-07

6.36E-076.36E-076.36E-076.36E-076.36E-076.36E-076.36E-076.36E-07

6.36E-07. 6.36E-07

6.36E-076.36E-076.36E-076.36E-076.36E-076.36E-07

6.51 E-076.51 E-076.51 E-07

3-58


TABLE 3.4.4.3-5 (continued)Maximum Gas Release Rates for Test Categories

Overpacked SWB

PayloadShippingCategory




II.1B0TII.1B1TII.lB2aTI1.1B2TII.1B3TII.1B4TII.1B5TII.1B6T

III.1B0THI.IBITHI.lB2aTIII.1B2TIH.1B3TIII.1B4TIII.1B5TIH.1B6T


DecayHeat/

TRUPACT-II(watts)

10.010.010.010.0

10.010.010.010.010.0

10.010.010.010.010.0

20.020.020.020.020.020.020.020.0

20.0• 20.0

20.020.020.020.020.020.0

7.07.07.0

MinimumICV wall

Temperature(°F)

127.0127.0127.0127.0

127.0127.0127.0127.0127.0

127.0127.0127.0127.0127.0

130.0130.0 .130.0130.0130.0130.0130.0130.0

130.0130.0130.0130.0130.0130.0130.0130.0

123.3123.3123.3

WaterVapor

Pressure(psia)

2.052.052.052.05

2.052.052.052.052.05

2.052.052.052.052.05

2.222.222.222.222.222.222.222.22

2.222.222.222.222.222.222.222.22

1.941.941.94

AverageICV gas

Temperature(°F)

132.0132.0132.0132.0

132.0132.0132.0132.0132.0

.132.0132.0132.0132.0132.0

136.0136.0136.0136.0136.0136.0136.0136.0

136.0136.0136.0136.0136.0136.0136.0136.0

130.2130.2130.2


(psia)

16.4216.4216.4216.42

16.4216.4216.4216.4216.42

16.4216.4216.4216.4216.42

16.5316.5316.5316.5316.5316.5316.5316.53

16.5316.5316.5316.5316.5316.5316.5316.53

16.3716.3716.37

AllowableGas

Release(liters)

5503.625503.625503.625503.62

5503.625503.625503.625503.625503.62

5503.625503.625503.625503.625503.62

5470.175470.175470.175470.175470.175470.175470.175470.17

5470.175470.175470.175470.175470.175470.175470.175470.17

5522.655522.655522.65

Maximum gasRelease rate(moles/sec/container)

3.24E-063.24E-063.24E-063.24E-06

3.24E-063.24E-063.24E-063.24E-063,24E-06

3.24E-063.24E-063.24E-063.24E-063.24E-06

3.20E-063.20E-063.20E-063.20E-063.20E-063.20E-063.20E-063.20E-06

3.20E-063.20E-06

- 3.20E-063.20E-063.20E-063.20E-063.20E-063.20E-06

3.26E-063.26E-063.26E-06

3-59

TRUPACT-II SAR Rev. 14, October 1994 ,i

THIS PAGE INTENTIONALLY LEFT BLANK

3-60

NnPac TKDPACT-II SAR Rev. 0, February 1989

i n i t i a l l y present when the ICV is sealed. Assuming that atmospheric pressure

is 14.7 psia, the allowable absolute pressure in the ICV, P a b s , i s :

pabs = 5 0 Psig + 14.7 psia= 64.7 psia

This abso lu te p re s su re i s decreased by the water vapor p re s su re and the

increased pressure of the gas i n i t i a l l y present in the TRBPACT-II Package ICV.

The maximum gas release ra te in moles/sec per payload container for each t e s t

payload shipping category is provided in Table 3.4.4.3—4. The method used to

calculate the maximum gas release ra te i s provided below with an example for

t e s t category I.1A0T.

The maximum decay heat provides the minimum ICV wall temperature and the

average ICV gas temperature needed to determine water vapor pressure and the

pressure increase from heating the gases i n i t i a l l y present in the ICV. The

maximum decay heat in t e s t category I.1A0T is 10 watts . From the TEOPACT-II

Package temperature information in Figures 3.4-6 through 3.4-14, the

minimum ICV wall temperature is 126 °F and the average ICV gas temperature i s

132 °F. The corresponding water vapor pressure i s 2.00 psia and the increased

pressure of the ICV gas i n i t i a l l y present (assuming a i r a t 70 °F and 14.7

ps ia ) , p i n i , i s :

p i n i = [(14.7 ps ia) x (460 °R + 132 °F)/(460 °R + 70 °F)]

= 16.42 psia

The allowable absolute pressure in the ICV available for acctmmlation of gas

released from the payload containers,

p a l l = 64.7 ps ia - 2.00 ps ia - 16.42 ps ia

= 46.28 psia (3.15 atm)

For an available void volume in the ICV of 2,450 l i t e r s , the amount of gas

that may be released from the payload containers a t 132 °F, V , i s :

3-61


V. = (3.15 atm) x (2,450 l i t er s )3 7,713 l i t er s at 132 °F and 1 atmosphere pressure

Thus, the number, of moles per second at SIP allowed for one year from all

fourteen (14) payload containers in test category I.1A0T, N , i s :

N = (7,713 l i t ers ) x (460 °R + 32 °F)/(460 °R + 132 °F)

x (1 mole/22.4 l i t e r s ) x (1 shipment/365 days)

x (1 day/86,400 sec)]

= 9.07(10)"6 moles/sec

The number of moles/sec per payload container, N , would be:

Np = [9.07(10)~6 moles/sec)/(14 drums/TRDPACT-II)

=• 6.48(10)"' moles/sec/pay load container (drum)

The maximum allowable gas release rate for one year for a payload container

from test category I.1A0T i s 6.48(10)"' moles/sec/pay load container. The

limit for moles/sec/payload container for each tes t category is provided in

Table 3 .4 .4 .3-5 . The maximum allowable gas release rates provided in the

table ensure that the maximum pressure increase in one year under normal con-

ditions of transport wil l not exceed the 50 psig design l imit .

The maximum allowable internal pressure in the OCV i s also 50 psig. The OCV

would only experience significant internal pressure i f the ICV had such a

pressure and the gases were free to communicate with the ICV. In th is case,

the maximum internal pressure is 50 psig in the ICV and the additional void

volume in the OCV would result in a maximum pressure in the OCV of 'less than

50 psig.

3.4.4.4 Flammable Gas Control

The accnnulation of potentially flammable gases, primarily hydrogen, generated

by radiolysis of the payload materials, i s a concern for the TRUPACT-II pay-

load. Appendix 3.6.7 describes the methodology for arriving at the effective G

3-62

NoPac TRUPACT-II SAR Rev. 1, May 1989

values (a measure of the potential for generating gas from radiolysis) for the

different waste types. Flammable gas generation due to other mechanisms is

insignificant and is addressed in Appendices 2.10.12, 3.6.5 and 3.6.6. The

concentration of any hydrogen generated due to radiolysis is maintained below

the flammable limit by the methods described below. The analysis of .these

methods is provided in Appendix 3 .6 .9 .

3 .4 .4 .4 .1 Control Methods

The hydrogen concentration in payload materials is limited to a molar quantity

that would be no more than 5% by volume (or equivalent limits for other flam-

mable gases of the payload container void at STP), in accordance, with Refer-

ence 3.6.1-15. The payload CH-TRTJ waste materials are generally inside of

layers of plastic bags, the nonber of which is specific to each content code,

and is provided in the TRUGON document. The hydrogen concentration i s calcu-

lated in al l layers of confinement in the payload and in the ICV. Since al l

of the act iv i ty in a payload container i s assumed to be in the innermost layer

(to provide a margin of safety in the hydrogen release rate estimates), the

concentration gradient of hydrogen decreases from the innermost bag to the

outermost cavity (the TRUPACT-II Package ICV c a v i t y ) . Accumulation of

flammable gases is controlled by ensuring that the concentration of hydrogen

in the innermost confinement layer in a payload container i s below five (5)

volume percent. Subsequent sections describe the basis for arriving at a

decay heat limit per payload container in each shipping category that ensures

compliance with this hydrogen concentration l imit .

Since the payload materials in any TRUPACT-II are restricted to a single

shipping category, the hydrogen generation rates (proportional to the effec-

t ive 6 value) and the release rates (across the different barriers of confine-

ment) from each container can be matched to provide information on the concen-

trations £>f hydrogen in the different layers. The inputs into the hydrogen

release calculations are described below with an example. Appendix 3.6.9 des-

cribes the basis for these calculations.

3-63


3.4.4.4.2 Release of Gas from Pavload Materials

The predominant source of hydrogen generation in the TRUPACT-II Package is

r ad io lys i s of the hydrogenous mater ia ls in the payload. The amount of

hydrogen that can be generated from each material is proportional to i ts G

(flam gas) value, i . e . , the number of molecules of hydrogen gas produced per

100 eV of energy absorbed, and the fraction, F, of the emitted energy which is

absorbed by gas producing material. The product of F times G (flam gas) is

the effective G (flam gas) value. The effective G (flam gas) value charac-

terizes the source term for the predicted hydrogen generation rate in each

payload container. The methodology for arriving at an effective G (flam gas)

value for each payload shipping category is described in Appendix 3.6.7. The

sink for this hydrogen is transport across various layers of confinement

( i . e . , the plast ic bags, the punctured drum l ine r , and the f i l t e r s in the

payload containers). Since hydrogen generation is a direct consequence of

radiolysis, the need to control the radiolytic gas generation rate imposes an

upper bound on the quantity of radionuclides which can be transported per

drum. The magnitude of this upper bound depends on a number of parameters.

These are:

' Waste configuration ( i . e . , the nmber and type of confinement layers) .

Release rates of hydrogen from each of these confinement layers.

* Hydrogen generation rates quantified by the effective G (flam gas)

value of a waste material type (the number of molecules of hydrogen

produced per 100 eV of energy emitted).

* Operating temperature for the TRUPACT-II Package payload.

* Available TRUPACT-II Package ICV void volume.

* Duration of the shipping period.

These parameters are discussed in detail in Appendix 3.6.9.

3-64


3.4.4.4.3 Flammable Gas Calculations

The purpose of this section is to provide the logic and mathematical analysis

used to arrive at the maximum decay heats for each pay load shipping category.

At steady state, the flow rate of hydrogen across each of the confinement

layers is equal to the same value and to the hydrogen generation rate . The

maximum hydrogen concentration in a payload container with f i l t e r vents per

Appendix 1.3.5 is reached at steady s ta te . That i s , a f i l t e r vented container

with a hydrogen generation source has increasing concentrations of hydrogen

with time unti l steady state conditions are reached. For the purpose of these

calculations, i t has been assumed that a l l payload containers are at steady

state at the s tar t of transport.

The temperature dependence of decay heat l imits is discussed in Appendix

3.6.12. As shown in that appendix, for Waste Types I I and I I I , minimum values

for the decay heat l imits are obtained by using the hydrogen generation and

release rates at an ambient temperature of 70°F. For Waste Type I, the lowest

values for the decay heat l imits are obtained by using the hydrogen generation

and release rates at the minimum operating temperature of -20°F.

In the decay heat calculations presented in this section, i t has been assmed

that the conditions under which the TRUPACT-II is sealed for transport are an

ambient temperature of 70 F, for a l l waste types. This asstmption is conser-

vative for Waste Type I , which uses the hydrogen generation and release rates

at the minimum operating temperature.

Once the payload containers are sealed inside the TRUPACT-II Package ICV,

concentrat ions of hydrogen in the di f ferent layers increase due to the

accumulation of hydrogen in the ICV cavity. Some of the hydrogen generated

during the transport period would accumulate in the payload containers, with

the remainder being released into the cavity. For the purpose of these

calculations, the mole fraction of hydrogen in a bag layer is set equal to the

steady state value plus the mole fraction of hydrogen that has accumulated in

the cavity. The ICV cavity mole fraction of hydrogen is obtained by assuming

that a l l of the hydrogen generated is released into the ICV cavity. The

maximum hydrogen concentration in the innermost layer is then limited to five

(5) volume percent at the end of the shipping period by suitably choosing the

3-65

NnPac TRTJPACT-II SAR • Rev. 3, July 1989

gas generation r a t e s . The maximum number of moles of hydrogen which can

accumulate in the ICV cavity i s :

Ngen = ( C O X a ^ X t ) (1)

Where:

N ft = to ta l moles of hydrogen generated.

CG = hydrogen gas generation r a t e per innermost layer of confinement

(moles/sec)

3-65 a


ngen = number of hydrogen generators (drums, SWBs, or overpacked drums

inside a SWB or a TDOP)

. t = shipping period duration (60 days)

The maximum mole fraction of hydrogen in the TRUPACT-II ICV cavity is then equal

to:

xfh = <Ngen/Ntg>=<Ngen/tP<Vvoid>/RT]> (2)

Where:

Xfk = maximum mole fraction of hydrogen in the TRUPACT-II ICV cavity

Ngen = tofcal moles of hydrogen generated

Nt_ = total moles of gas inside the TRUPACT-II ICV cavity

P = pressure inside the TRUPACT-II, assumed to be constant at 1 Atm,

because the amount of gas generated is much less than the total

amount of air originally in the cavity

vvoid = v o i d v o l u m e inside the TRUPACT-II ICV cavity, 2,4.50 liters for

55-gallon drums, 1,750 liters for Standard Waste Boxes (see

Section 3.4.4.3), and 1277 liters for a TDOP. |

R = gas constant = 62.361 mm Hg-liter/mole-°K

T = absolute temperature = 294°K

The gas generation rate per innermost confinement layer which will yield a

maximum hydrogen concentration of five (5) volume percent is then computed as the

following:

xinner = xfh + <CG><reff>

3-66

NuPac TREPACT-II SAR Rev. 2, June 1989

Where:

^ijiner = a 0 * e fraction hydrogen in innermost confinement layer (a value of

0.05 has been used for this paraaeter since this is the nariaum

permissible concentration)

: maximum mole fraction of hydrogen in the T2DPACT-II ICV cavity

CG = hydrogen gas generation rate per innermost confinement layer

(moles/sec)

the effective resistance to the release of hydrogen (sec/mole)

The effective resistance is computed by summing the individual confinement

layer resistances. The resistance of a layer is equal to the reciprocal of

the release rate from that layer. After substituting equations (1) and (2)

into (3) and solving for the gas generation rate the following resul ts :

0 8 " ( X inner ) / C reff + E<t) (ng e a)/N t gH (4)

where a l l terms are as defined previously. The decay heat per innermost

confinement layer is then computed as:

Q£ = [(CG)(NA)/(G molecules/100eV)][1.602(10)"19 watt-sec/eV] (5)

Where:

Q. - Decay Heat per innermost confinement layer (watts) I

Nt = Avogadro's number = 6.023(10) molecules/mole

G = Gfif£ (flam gas) = effective G value for flammable gas (molecules

of hydrogen formed/100 eV emitted energy)

The logic for arriving at the input parameters is detailed in Appendix 3.6.9.

3-67

NnPac TRUPACT-II SAR Rev. 3, July 1989

As an example, the decay heat l imit per innermost confinement layer will be

computed for shipping category I.1A2.

The effective resis tance i s the sum of the following res is tances (see Appendix

3.6.10 for a derivation of the res i s t ances ) :

There are two l ine r bags, thus the combined resis tance i s twice the

resis tance of one l iner bag, 2 x 214,133 sec/mole or 428,266 sec/mole.

Resistance of the drum l ine r which is 19,646 sec/mole, and

• Resistance of the drum f i l t e r which is 729,327 sec/mole.

The effective res i s tance , r e££, is therefore 1,177,239 sec/mole.

Assuming an atmospheric pressure of 14.7 psia and 70 °F, the t o t a l moles of

gas inside the TRUPACT-II Package ICV cavity, Nt , i s computed using the ideal

gas law,

Where:

P = 760 mm Hg

Vvoid = 2 ' 4 5 0 l i t e r s (14 drums/TRUPACT-II)

T = 294 °K

R = 62.361 mm Hg-liter/mole-°K

so that ,

Nt '= (PMVvo id)/RT = 101.56 moles

There wi l l be 14 drums of one shipping category inside TRUPACT-II Package so

that the number of gas generators, n n = 14.

3-68

NuP»c TRDPACT-II SAR Rev. 3, July 19*89

The hydrogen gas generation ra te per the innermost confinement layer may then

be computed using equation (4) assuming a maximum five (5) volume percent

concentration at the end of sixty days.

CG = (0.05)/{I,177,239 sec/mole

+ [(60 days) (86,400 sec/day) (14) / (101.56 moles)]}

= 2.643U0)"8 mole/ sec

For shipping category I.1A2 the effective G (flam gas) value is 1.60. There-

fore, the decay heat l imit per innermost confinement layer, Q.^, through equa-

tion (5) i s :

GLL = [2.643(10)"8 mole/sec] [6.023(10)2 3 molecules/mole]

x [1.602(10)~19 watt-sec/eV]/[1.6 molecules/100 eV]

= 1.59U0)"1 watts

The parameters which are used in the calcula t ions and ident i f ied in Table

3.4 .4 .4-1 are described below.

Parameter Description

Payload Shipping

Category (Waste

Material Type)

Identifies shipping category

(Form of the waste)

G e f f (flam gas) Number of molecules of hydrogen produced per 100 eV

of emitted energy. There is a charac te r i s t i c effec-

tive G (flam gas) value associated with each waste

material type as described in Appendix 3 .6 .7 .

Number of Gener.

i n ICV e . g . .

The number of generators inside the TRUPACT-II ICV,

i n t he c a s e of SWB o v e r p a c k , t h e number

of generators is eight (4 drums per SWB) x (2 SWBs

per ICV).

3-69

I

o

TABLB 3.4.4.4-1

Maximum Decay Heats For Shipping Category - A55-GaIlon Drums

FayloadShipping

Category

I.1A0MAII.1A21.1A3

I.2A01.2A1I.ZA2I.2A3I.2A4

I.3A0I.3A1I.3A21.3A3I.3A4

n.lAOD.1A1D.lA2aH.1A2D.1A3D.1A4U.1A50.1A6H.2AM

m.lAODI.1A10I.lA2aDI.1A210.1A3HI.1A4m.iA511I.1A6

G

Value

CH2)

1.601.601.601.60

1.301301.301.301.30

0.400.400.400.400.40

1.701.701.701.701.701.701.701.700

3.403.403.403.403.403.403.40340

Numberof Gener-

ator* inICV

14141414

1414141414

1414141414

141414141414141414

1414141414141414

Number of

InnerBags

0002

00023

00023

000123450

00012345

Number

Of linerBags

0121

01211

01211

01211111

N/A

012

nTotal

Numberof Bast

0123

01234

01234

01223456

N/A

01223456

NNumber ol

ContainerInlCV

14141414

1414141414

1414141414

141414141414141414

1414141414141414

V»Void Vol.

In ICV(Uteri)

2,4302,4502,4502,450

2,4502,4502,4502,4502,450

2,4502,4502,4502,4502,450

2,4502,4502,4502,4502.4502.4502,4502,4502,450

2,4502.4502.4502,4502,4502,4502,4502.450

rEff. Total

Resistance(sec/mole)

74S.973963,106

1.177.2395,760,834

748,973963,106

1,177,2395,760,8348,159.678

748,973963,106

1,177,2395.7603348.159.678

545,962760,095974,228

2,352,2104,344,3256,136,4407,928,5559.720,670

N/A

545.962760.095974,228

2,552,2104,344,3256,136,4407,928,5559.720,670

NmNumber ofMoiecin

ICV

101.56101.56101.56101.56

101.56101.56101.56101.56101.56

101.56 '101.56101.56101.56101.56

101.56101.56101.56101.56101.56101.56101.56101.56101.56

101.56101.56101.56101.56101.56101.56 .101.56101.56

egGas

Generation

(moles/sec)

34I6B-O82.960E-O82.643B-O87.721BO9

3.416E-082.980E-062.643B-087.721B-O9S.634E49

3416B-OB2.980B-O82.643E-O87.721B-O9S.634B49

3.966B-O83.390B-OB2.961B-O81.S3IE-O89.883B-O97.298B-O95.7B5B-O94.791E-O9

N/A

3966E-O83.390E-C82.96IB-081.531E-O89-883E-O97.298E-O95.7B5E-O94.791E-O9

W

Wans

p «Generator

0.20600.17970.15940.0466

. 0.25360.22120.19620.05730.0418

0.82410.71890.63750.18630.1359

0.22510.19240.16800.08690.05610.04140.03280.027240.0000

. 0.11260.09620.08400.04340.02800.02070.01640.0136

po

ICA

7o

TABLH 3.4.4.4-1 (continued)Maximum Decay Heats For Shipping Category - B

Overpack Four SS-Gallon Drums

1

Payload

Shipping

Category

I.1B0I.1B1I.1B2I.1B3

I.2B0I.2B1I.2B2I.2B3I.2B4

I.3B0I.3B1I.3B2I3B31.3B4

II.1B01I.1B1n.lB2aII.1B2II.1B3II.1B4II.1B5II.1B6II.2DM

II1.1B0Hi.lBlin.lB2aIII.1B2III.1B3III.1B41(1.11)5III.1B6

G

Value

(H2)

1.601.601.601.60

1.301.301.301.301.30

0.400.400.400.400.40

1.701.701.701.701.701.701.701.700.00

3.403.403.403.403.403.403.403.40

Numberof Gener-

ators in1CV

8888

88888

88888

888888888

88888888

Number of

Inner

Bags

0002

00023

00023

000123450

00012345

Number

Of Liner

Bags

0121

01211

01211

012

N/A

01

• 2

nTotal

Number

of Bags

0123

01234

01234

01223456

N/A

01223456

NNumber of

ContainersInlCV

2222

22222

22222

222222222

22222222

W

Void Vol.

inlCV(liters)

1,7501.7501,7501,750

1,7501,7501,7501,7501,750

1,7501,7501,7501,7501,750

1,7501.7501,7501,7501,7501,7501,7501,7501,750

1,7501,7501,7501,7501,7501,7501,7501,750

rEff. Total


1,498,0111,712,1441,926,2776,509,872

1,498,0111,712,1441.926,2776.509.8728,908,736

1,498,0111,712,1441,926,2776.509.8728,908,736

1,086,5021,300,6351,514,7683,092,7504,884,8656,676,9808,469,09510,261,210

N/A

1,086,5021,300,6351,514,7683,092.7504,884,8656,676,9808,469,09510,261,210

NmNumber of

Moles inICV

72.5472.5472.5472.54

72.5472.5472.5472.5472.54

72.5472.5472.5472.5472.54

72.5472.5472.5472.5472.5472.5472.5472.5472.54

72.5472.5472.5472.5472.5472.5472.5472.54

CgGas

Generation

(moles/sec)

2.416E-O8 '2.189B-O82.002E-O87.O61E-O9

2.416E-O82.189E-O82.O02E-O87.O61E-O95.274E-O9

2.416E-O82.189E-O82.O02B-O87.061E-O95.274E-O9

3.O15E-O82.670E-082.396B-O81.364E-089.163B-O96.898E-O95.530EO94.616E-O9

N/A

3.015H-082.670E-082.396B-O81.364B-aB9-I63E-O96.898E-O95.530I--O94.6161-09

WWatts

perGenerator

0.14570.13200.12070.0426

0.17930.16250.14860.05240.0391

0.58270.52810.48280.17030.1272

0.17110.15160.13600.07740.05200.03920.03140.026240.0000

0.08560.07580.06800.03870.02600.01960.01570.0131


Maximum Decay Heats for Shipping Category CStandard Waste Box

Ito

Payload

Shipping

Category

I.1C0

I.2C0

I.3C0

II. ICO1I.1CI

II.1C2

II.IC3

H.1C4

II.2CM

III. ICO

III.1C1

III.IC2

III.1C3

III.IC4

G-Vatua

IH2)

1.60

1.30

0.40

1.70

1.70

1.70

1.70

1.70

0.00

3.40

3.40

3.40

3.40

3.40

Number of

Ganaratora

In ICV

2

2

2

2

2

2

2

2

2

22

222

Numbar of

Innar Baga

0

0

0

00

0

1

2N/A

0

0

0

1

2

Numbar of

Unar Baga

0

0

0

0

1

22

2

N/A

0

1

2

2

2

nToul

Numbar of

Baga

0

0

0

0

1

2

3

4

N/A

0

123

4

NNumbar of

Contain* ra

in ICV

2

2

2

2

2

22

2

2

2

2222

Vv

Void Votuma

In ICV

(litara)

1,750

1.7B0

1,750

1,750

'1.750

1.750

1,750

1.7501,750

1,750

1.750

1.750

1.750

1.750

r

Eff. Total

Raaiatanca

(aac/mola)

187,260

187,260

187,260

135,135

260,795

386,455

2,178.570

3,970,685

N/A

135,135

260,795

386,455

2,178,570

3,970,685

NmNumbar of

Motaa in

ICV

72.54

72.54

72.54

72.54

72.54

72.54

72.5472.5472.54

72.54

72.54

72.54

72.54

72.54

Cg

Qaa

Generation

(molet/iac)

1.514E07

1.514E-07

1.514E-07

1.798E-O7

1.238EO7

9.445E08

2.154E-O8

1.215E-08

N/A

1.798E-O7

1.238E-O7

9.445E-08

2.154E-O8

1.215E-O8

WWatta

par

Generator

0.9132

1.1240

3.6528

1.0206

0.7029

0.5361

0.1222

0.0690

40.0000

0.5103

0.3515

0.2680

0.0611

0.0345

ooftotrron

TABLE 3.4.4.4-1 (continued)Maximum Decay Heats For Shipping Category - D

Bins Overpacked In Standard Waste Box

Payfoad

ShippingCategory

1.1 D2

I.2D2I3D2

II.1D2

III.1D2m.lDS

G

Value(H2)

1.601.300.40

1.70

3 4 03 4 0

Number

of Gener-ators In

ICV

222

2

22

Number of

InnerBags

000

0

0

3

Number

OfUnerBags

222

2

22

nTotal

Numberof Bags

222

2

2

5

NNumber ofContainers

In ICV

222

2

22

W

Void Vol.In ICV

Jllters)

1,7501.7501.750

1.750

1.7501.750

rEff. Total


625.839625.839

625.839

521.590

521.590

5.897,935

Nm

Number ofMoles In

ICV

72.54

72.5472.54

72.54

72.5472.54

egGas

Generation(moles/sec)

6.504 E-066.5O4B-OB6.504B4S

7.524B-O8

7.524E-O8

8.277E-O9

W

Watts

P«Generator

0.39220.4827

1.5689

0.4271

0.21350.0235

1tor»

I

to

to

8?

S?oa

o

NoP*c TRUPACT-II SAR Rev. 0, February 1989

Parameter. Description

Number of Inner Bags These are the small bags, such as those used to bag-

out solid inorganics and organics. Only the leakage

from the closure has been used as the hydrogen

release rate.

Number of Liner Bags These are the large bags, such as those used to con-

tain the solidified aqueous or homogeneous inorganic

solids or which serve as drum liners for waste types

II or III. Hydrogen release from both permeation

through the bag material and diffusion through the

closure has been used in computing hydrogen release

rates.

Total number of Bags Sum of the number of inner and liner bags.

Number of Containers

in ICV

Number of payload containers inside the TRUPACT-II

ICV cavity.

Void Vol.

in ICV

Void volume inside the TKDPACT-II Package ICV cavity

( l i t e r s ) .

Effective Total

Resistance

Effective total resistance to the release of hydrogen

computed by summing the individual confinement layer

resistances.

Number of Moles

in ICV

Number of moles in the TRUPACT-II Package ICV cavity

computed via the ideal gas law equation.

Gas Generation Gas generation rate per generator (CG) which is com-

puted from input parameters via equation (4) .

Watts Per Generator Decay heat limit per generator (watts) which is com-

puted using equation (5) .

3-73

NoPae TRUPACT-II SAR Rev. 3, July 1989

The decay heat limit in watts per generator for each payload shipping category

is presented in Table 3.4.4.4.-1. The temperature dependence of hydrogen gas

generation and release rates for calculation of decay heat limits is con-

sidered in Appendix 3.6.12;

For payload containers in the test categories, the restriction on the hydrogen

concentration in the innermost confinement layer is determined by actual

measurement of the hydrogen generation rate under simulated normal conditions

of transport. The test procedure for a payload container in these categories

is described in Attachment 2.0 of Appendix 1.3.7. The criteria to be met by

the payload containers in order to qualify for transport are given in Section

1.2.3.

A payload container in a test category is tested for the hydrogen generation

rate under steady state conditions as described in Appendix 1.3.7. The mea-

sured generation rate must be less than an acceptable value to ensure that a

five (5) volume percent hydrogen concentration is not exceeded in the inner-

most confinement layer of the payload container during transport. An allow-

able generation rate for hydrogen for each payload shipping category is deter-

mined as part of the calculation shown above for the analytical categories.

The effective G value and the limit on decay heat control the maximum hydrogen

concentration which is equivalent to controlling the calculated hydrogen gene-

ration rate for a particular analytical shipping category. Similarly for a

particular test category, the measured hydrogen generation rate is sufficient

to control maximum hydrogen concentration. For example, for a payload contai-

ner belonging to the shipping category I.1A2T, the maximum allowed generation

rate is the same as that for the analytical shipping category I.1A2, i.e.,

2.643(10) moles/sec (as derived above). Since the limit on watts for the

analytical categories is based on very conservative effective G (flam gas)

values, higher watts are acceptable for the test shipping categories. The

measured hydrogen generation rate is used directly to determine if the allow-

able conce-ntration will be exceeded and a measured effective G value is also

determined. Table 3.4.4.4-2 lists the maximum allowable hydrogen gas genera-

tion rate for each test category.

3-74


TABLE 3.4.4.4-2Maximum Hydrogen Generation Rate for Test Categories

55-Gallon Drums


I.1A0TI.1A1TI.1A2TI.1A3T



H.1A0TII.1A1Tn.lA2aTII.1A2TII.1A3TII.1A4TII.1A5TII.1A6T

III.1A0T• ffl.lAlTm.lA2aTIH.1A2THI.1A3TIH.1A4Tffl.lASTffl.lA6T

- IV. 1 AITIV.1A2TIV.1A3T

MaximumDecayHeat

(watts)

10101010

1010101010

1010101010

2020202020202020

2020202020202020

777

Maximum H2Generation

Rate(moles/sec)

3.416E-082.980E-082.643E-087.721 E-09

3.416E-082.980E-082.643E-087.721 E-095.634E-09

3.416E-082.980E-082.643E-087.721 E-095.634E-09

3.966E-083.390E-082.961 E-081.531E-089.883E-097.298E-O95.785E-094.791 E-09

3.966E-083.390E-082.961 E-081.531 E-089.883E-O97.298E-095.785E-094.791 E-09

3.390E-082.961 E-089.922E-09

Maximum TotalH2 Generation

60 Days(moles)

0.177090.154480.137010.04003

0.177090.154480.137010.040030.02921

0.177090.154480.137010.040030.02921

0.205620.175760.153500.079340.051240.037830.029990.02484

0.205620.175760.153500.079340.051240.037830.029990.02484

0.175760.153480.05144

3-75


TABLE 3.4.4.4-2 (Continued)Maximum Hydrogen Generation Rate for Test Categories

55-Galion Drums Overpacked in an SWB





II.1B0TII.1B1TII.lB2aTH.1B2TH.1B3TII.1B4TII.1B5TII.1B6T

IH.1B0TIII.1B1THI.lB2aTHI.1B2TIII.1B3TIH.1B4Tin.lB5TIII.1B6T


MaximumDecay -Heat

(watts)

10101010

1010101010

1010101010

2020202020202020

2020202020202020

777

Maximum H2Generation

Rate(moles/sec)

2.416E-082.189E-082.002E-087.061 E-09

2.416E-082.189E-082.002E-087.061 E-095.274E-09

2.416E-082.189E-082.002E-087.061 E-095.274E-09

3.015E-082.670E-082.396E-081.364E-089.163E-096.898E-095.530E-094.616E-09

3.015E-O82.670E-082.396E-081.364E-089.163E-096.898E-095.530E-094.616E-09

2.670E-082.396E-089.196E-09

Maximum TotalH2 Generation

60 Days(moles)

0.125250.113480.103780.03660

0.125250.113480.103780.036600.02734

0.125250.113480.103780.036600.02734

0.156310.138440.124210.070730.047500.035760.02867-0.02393

0.15631. 0.13844

0.124210.07073 .0.047500.035760.028670.02393

0.138440.124210.04767

3-76

TRUPACT-II SAR Rev. 14, October 1994 j

THIS PAGE INTENTIONALLY LEFT BLANK

3-77

KuPac TRUPACT-II SAR Rev. 9, December 1990

For bins in the test category, the limits on total gas generation rates (Table

3.4.4.3-5) and the hydrogen generation rates (Table 3.4.4.4-2) are met as

follows: The drums used to load the bins (up to six per bin) are the ones chat

are tested by the gas generation test procedure. To load a bin, these should

be chosen such that the sum of the gas generation rates of the drums do not

exceed the limits specified for the bin (payload shipping categories HD" in

Tables 3.4.4.3-5 and 3.4.4.4-2).

3-77a


3.4.4.5 Maximum Normal Operating Pressure

The TRUPACT-II Package was designed to withstand 50 psig of internal pressure

to accommodate the transport of payload materials with the potential to generate

gases and increase pressure within the ICV. The differences between how the

analytical payload shipping categories and the test categories are evaluated for

gas generation results in two different approaches for how the maximum normal

operating pressure (MNOP) for each type of category is determined. For the

analytical payload shipping categories, the pressure increase in one year for

each category is provided in Tables 3.4.4.3-1 through 3.4.4.3-4. The maximum

pressure increase for an analytical category is for category III.1A0 and is only

12.81 psig. This value would be the MNOP for the ICV for the analytical

categories but is not the limiting MNOP for the ICV since a higher value is

established by the test payload shipping categories. As discussed in Section

3.4.4.3, the maximum pressure increase in the ICV in one year for a test category

is allowed to be 50 psig. Since the ICV pressure is allowed to increase to the

design pressure of 50 psig, the MNOP for the ICV in the TRUPACT-II Package is

50 psig.

The MNOP for the OCV is low and the pressure increase is due solely to the

temperature increase of the air in the OCV cavity when the TRUPACT-II Package

reaches the maximum normal operating temperature. Per the tables in Section

3.4, the normal condition steady state temperature of the ICV and OCV walls with

40 watts of decay heat is less than 156°F. Conservatively assuming 156°F is the

OCV air temperature at the maximum normal operating temperature, the pressure

increase after sealing the OCV at 70°F and 14.7 psia would be:

P156°F " P70°F<T156°F/T70OF)

P156°F • < 1 4* 7 Psia)[(460 + 156)/(460 + 70)]

• P^Of - 17.1 psia, or 2.4 psig

Thus, for normal conditions of transport, the MNOP for the OCV is only 2.4 psig.

The design pressure for the OCV is the same as that for the ICV or 50 psig and

ensures pressure retention by the OCV in a non-normal situation in which the ICV

cavity communicates with the OCV cavity.

3-77b

NaPac TRUPACT-II SAR R « v - ° ' February 1989

APPENDIX 3.6.4

SHIPPING PERIOD FOR TRDPACT-II

3.6.4-1

NoPac TRUPACI-II SAR Rev. 4, August 1989

APPENDIX 3.6.4

SHIPPING PERIOD FOR TRUPACT-II

1.0 INTRODUCTION

The purpose of this Appendix i s to develop, on a conservative basis, the time

for the shipping period from closure until venting that should be considered

for the analysis of gas generation in TRUPACT-II.

2.0 BACKGROUND

A large nmber of shipments of contact handled transuranic (CH-TEU) waste to

WIPP from ten DOE f a c i l i t i e s have been planned. These shipments Ti l l be made

by a f leet of trucks, each capable of transporting up to three TRUPACT-II

packages. The TRUPACT-II packages are loaded on specially designed tra i lers

and travel over the routes shorn in Figure 3 .6 .4-1 . The waste transportation

activity will span a twenty-five year period. Because of the large number of

trips and because of the agreements for notification to the states through

which these shipments wi l l pass on their way to WIPP, a state-of-the-art

sate l l i t e tracking system wi l l be employed to monitor the progress, and posi-

t ion of each shipment. This monitoring capabi l i ty w i l l be avai lable to

authorities in the affected states as well as the transportation management

people at the WIPP site and other DOE s i tes .

3.6.4-2

NmPac TRUPACT-II SAR Rev. 0. February 1989

FIGURE 3.6.4-1

TRU Waste Generating/Storage Site and Potential Shipnent Corridor States

3.6.4-3

NmPac TRUPACT-II SAR Rer. 0 , February 1989

3 . 0 APPROACH

The approach to be taken in establishing the shipping period will be to

develop a normal or expected shipment time based on the planned loading,

transport and unloading times. Then a mazimom shipment time will be based on

adding to the normal shipment time delays caused by a number of factors. This

maximum shipment time will assume that each of these delays occurs. The pro-

bability of each of these delays occurring is small. The joint probability of

all of these delays occurring would be extremely small. Thus the development

of a maximum shipment time based on the sum of extended delays for each of the

factors is considered to have a large margin of error. In the event that a

particular shipment is experiencing delays (for one reason or another)

resulting in an abnormal shipment time, close monitoring of the delay by WIPP

will ensure minimum delays in the schedule.

3.1 Normal or Expected Shipment Tina

The normal transport time is the sum of the times associated with loading the

TRDPACT-II packages, the normal transit time, and the unloading of the pack-

ages. The loading time to be considered as important i s the time interval

from closing (sealing) the f i r s t of the three TRUPACT-II packages in each

shipment until the truck leaves the waste shipper's fac i l i ty . The transit

time i s that time interval beginning with departure from the shipper's

fac i l i ty and ending with the arrival at the WIPP s i t e . The unloading time is

that time interval beginning with the arrival at the s i te and ending with the

venting of the last of three TRUPACT-II packages. This total time defines the

expected shipment time.

3 . 2 Off—Normal or Majtiffpufl Shipment Time

The maximum shipment time includes those delays which could extend the ship

ment time. These delays are:

Delays in loading or releasing the truck at the shipper's f a c i l i t y .

3.6.4-4


Delays in transit caused by adverse weather conditions leading to

road closures, or road closures due to accidents involving other

vehicles .

Accidents involving the shipment vehicle. These delays would in-

clude the time required for notif ication of appropriate authorities

(including the DOE Emergency Response Team)* and the tine to take

corrective action. This corrective action may involve transfer of

the TEDPACT-II packages to a back-up truck which would require the

services of heavy equipment.

Delays in transit caused by mechanical problems with the truck.

This factor would include such things as t ire problems, broken belts

and hoses, and any other such minor problems.

Delays caused by one or both of the drivers becoming i l l .

Delays in unloading the TRUPACT-II packages at the WIPP s i t e . These

could potentially be caused by factors such as truck arrival at the

start of a long holiday weekend or equipment problems at the WIPP

Waste Handling Building.

4.0 DISCUSSION

4.1 Normal or Expected Shipment Time

As stated previously, the normal or expected shipment time is that time in-

terval beginning with the sealing of the f i r s t of three TRDPACT-II packages

(making up a particular shipment) at the shipper's fac i l i ty and ending with

the venting of the last of these three packages in the WIPP Waste Handling

Building.

3.6.4-5

WaPac TRUPACT-II SAR Rev. 0, February 1989

4.1*1 I'MJPACT-TT Loading

The TRUPACT-II package is designed so that i t can be loaded within one hour.

The loading operation is fac i l i t a ted by design features and contents handling

methods aimed at a quick turnaround during ei ther loading or unloading. For

example* the closure l ids on both the inner and outer containment vessels are

fastened with a breech-lock type of mechanism. Whether the contents are 55-

gallon drums (in seven-pack assemblies) or SWBs, they are handled in ve r t i ca l

sets as a payload assembly, and only one l i f t i s required. All steps in the

loading process (from -attaching the l i f t ing f ixture to the crane u n t i l the

l i f t fixture l i f t links are disconnected from the outer closure following

loading) can be accomplished in two hours or l e s s . Thus the time associated

with loading the three TRUPACT-II packages for a single shipment is expected

to be less than eight hours. However, to be conservative, one day (twenty-

four hours) i s a l lot ted for this ac t iv i ty .

4.1.2 TfiftnSS11 Time

Specific routes have been selected for transport of waste from each of the ten

DOE facilities to the WIPP s i te . The distances are given in Table 3.6.4-1.

•

These shipments wi l l a l l be made by trucks having two dr ivers . Regulations

governing maximum driving and on-duty times are given in 49 CFR 395, 'Hours of

Service of Drivers' (Reference 6.2) .

These regulations permit a driver to drive not more than ten (10) hours

following eight (8) consecutive hours off duty or, be in the on-duty s ta tus

not more than fifteen (15) hours. If the fif teen hours on-duty s tatus i s

reached, a driver must be out of the vehicle in an off-duty s ta tus for eight

hours. Drivers using sleeper berth equipment may cumulate the eight (8) hours

off duty (for the ten hour on-duty status) resting in the sleeper in two

separate periods (each period must be at least two hours) to ta l ing eight (8)

hours. Drivers cannot be on duty more than seventy (70) hours in eight con-

secutive days. By using the two drivers and a rotational on-duty/off-duty

system of approximately five (5) hours, the vehicle can .be maintained opera-

tional for twenty-four (24) hours per day for seven days.

3.6.4-6

NsPae TRUPACT-II SAR Rev. 0, February 1989

Experience at the Idaho national Engineering Laboratory (INEL) has shown that

shipments of this type can achieve an average speed of 45 mph. This average

speed includes stops for vehicle inspections every two hours* fueling, meals*

driver rel ief and state vehicle inspections.

The normal transit time ranges from 0.6 day for shipments from Rocky Flats

Plant to 1.7 days for shipments. from Hanford (WHO as shown in Table 3 .6 .4-1 .

For the purpose of conservatism three days i s assumed- for a maximum normal

transit time.

TABLE 4.1.2-1

TBDPACI-IINOBMAL T2DEACT TRANSIT TIMES

TO

WIPP

FROM:

RFP

INEL

WEE

LANL

SEP

1121.

NES

CBNL

VL

ANL

DIS-

TANCE

(MILES)

666

1434

1847

352

1447

1345

1017

1493

1460

1404

40 MEH

16.7

37.1

46.2

8.8

36.2

33.6

25.4

37.3

36.5

35.1.

TRANSIT

4 5 MEH

14.8

33.0

41.0

7.8

32.2

29.9

22.6

33.2

32.4

31.2

TDE IN EDORS'

50HEH

13.3

29.7

36.9

7.0

28.9

26.9

20.3

29.9

29.2

28.1

55 MEH

12.1

27.0

33.6

6.4

2 6 . 3 '

24.5

18.5

27.1

26.5

25.5

40 MEH

0.7

1.5

1.9

0.4

1.5

1.4

1.1

1.6

1.5

1.5

TRANSIT

4 5 MEH

0.6

1.4

1.7

0.3

1.3

1.2

0.9

1.4

1.4

1.3

TIME IN I M S

5 0 MEH

0.6

1.2

1.5

0.3

1.2

1.1

0.8

1.2

1.2

1.2

5 5 MEH

0.5

1.1

1.4

0.3

1.1

1.0

0.8

1.1

1.1

1.1

JI ,$

3.6 .4-7

NaPac TRUPACT-II SAR Rev. 0, February 1989

4.1.3 Unloading

Normal loading w i l l be accomplished in l ess than a day. The whole waste r e -

ceipt system has been designed to perform the waste unloading in less than a

half day since on the average, WIPP w i l l be receiving three to four shipments

per day, and the waste handling equipment and procedures have been designed

and developed to meet this demand. Once the truck has undergone the heal th

physics survey and security checks, the t r ac to r i s disconnected, and a t r a i l e r

jockey is connected to the t r a i l e r . The t r a i l e r and TRUPACT-II packages are

cleaned, and the t r a i l e r i s moved to the unloading area . The TRUPACT-II pack-

ages are removed from the t r a i l e r , passed through an a i r lock into the Waste

Handling Building and placed into TRUPACT-II unloading stands. The outer and

inner l ids are removed after the containment vessels have been vented through

a fac i l i t y gas-handling system, and other procedural steps are then taken.

The Waste Handling Building has unloading capacity for two t r a i l e r s , each

carrying three TRUPACT-II packages; tha t i s , the WIPP surface f ac i l i t y in -

cludes para l le l docks and para l le l or redundant handling equipment. Thus, the

normal unloading of a t r a i l e r with three TRUPACT-II packages wi l l be accom-

plished in less than a half day. The storage space i s adequate to accommodate

the contents of every TRUPACT-II in the f l e e t . The unloading time i s , thus ,

conservatively assigned a value of one day.

4.1.4 Total Normal or Expected Shipment Time

The total normal or expected shipment time is three to five days depending on

the origin of the waste. Normal loading time is one day, transit time is one

to three days and unloading time is one day.

4.2 Off—Normal or Maximum Shipping Time

4.2.1 Loading Delav^

There are a number of factors which could extend the time interval between the

sealing of the first of three TRUPACT-II packages and the truck getting under

way:

3.6.4-8

NaPao TRUPACT-II SAR Rev. 0, February 1989

Loading could begin on a day preceding a holiday weekend.

Difficulty testing the Inner Containment Vessel (ICV) ox Outer Con-

tainment Vessel (OCV) sea l s .

Handling equipment fai lure.

In the most severe sequence, one TRUPACT-II of the load would already have

been f i l l e d and sealed. Loading could begin on a day preceding a long (ho l i -

day) weekend. If, for example, loading began on a Friday preceding a three-

day weekend, loading would not be completed unti l the following Tuesday. This

would result in a four day loading period.

The TRUPACT-II inner or outer seal may fa i l the leak t e s t , which would gen-

erally cal l for some maintenance. The worst case would probably be a fai lure

in the leak test equipment which could take up to two days to correct.

The crane or the l i f t ing fixture with center of gravity load compensation

could also f a i l , forcing a delay in any further TRUPACT-II loading unti l cor-

rected. This could also take two days.

It would be very unlikely for more than two of these scenarios to happen

simultaneously, so a total of six days i s deemed to be a reasonable maximum

time to account for delays associated with loading. If there were conditions

which could cause long, total ly unanticipated delays, the TRUPACT-II packages

can be vented at the shipper's f a c i l i t y .

4.2.2 TTtTlfii* Time Delays

There are several factors which could extend the normal transit time of three

days from the ten DOE waste s i tes to the WIPP s i t e . Adverse weather condi-

tions could lead to delays and road closures. A telephone survey of each of

the states in the waste shipment corridor states was conducted to ascertain a

reasonable time to assume for weather delays. Table 3.6.4-2 provides the

3.6.4-9


results of th.it survey. One can conclude from this survey that weather condi-

tions may close a major highway for two to five days. Long term interruptions

in normal traffic caused by bridge outages etc .* would result in rerouting

traffic to alternate routes. Accidents involving other vehicles could also

cause delays and road closures of up to a day. I t i s concluded that a total

transit delay of five (5) days i s reasonable to assume for weather delays or

road closures.

Accidents involving the shipment vehicle i t s e l f could cause lengthy delays.

These delays would include the accident response time for notifying appro-

priate authorities (including Radiological Assistance Teams, i f required) and

the time to take corrective action or to mitigate the accident. One day i s

conservatively assumed for the response to the accident. (In addition to

normal accident responses, monitoring of the sa te l l i t e tracking system would

also fac i l i tate an early response to accidents). Corrective action may in-

volve retrieving the TRUPACT-II packages from a damaged trai ler (including the

possibility that the truck could be over an embankment), and transferring them

to a back-up truck. Special equipment such as cranes may be required to a

carry out these operations. An accident mitigation time of five days wi l l be

assumed. This time includes the time for delivery of a back-up truck, and the

time to move in special heavy equipment and rig special l i f t ing fixtures to

retrieve and transfer the packages to the back-up vehicle.

Delays in transit could be caused by routine mechanical problems with the

track. These problems could include tire fa i lures , broken belts and hoses,

electrical failures and similar minor problems; or more significant problems

necessitating bringing a back-up truck into service. It i s conservatively

assumed that appropriate responses to mechanical failures of the truck can be

made in four days.

3.6.4-10

NnPac TRUPACT-II SAR Rev. 0 , February 1989

Snxr«r of Weather Related

State/Citr

1. Alabaaa/Montgoacry

2. Arizona/Phoenix

3. Arkansas/Little Kock

4. California/Sacraaento

TABLB 3.6.4-2Delays on Interstate Highway* of

OfficeContacted

State DOT

Dept. of PublicSafety

State DOT

Constructionof Maintenance

State DOT High-way Dept.

9. Indiana/Indiasapolit

10. Kentucky/Frankfort

11. Loaisi ana/BostonRange

12. Mississippi/Jackson

13. Missonri/Tefferson City

14. Nevada/Carson City

DateContacted

2/4/88

2/4/88

2/17/88

2/18/88

5.

6.

It

8.

Colorado/Denver

Georgia/Atlanta

Idaho/Boise

Illinoix/Spxingfield

State DOT

State DOT Main-tenance

State DOT

State DOT

2/5/88

2/2/88

2/4/88

2/7/88

Dept. of 2/5/88Highway

Operations

State DOT High- 2/5/88way Maintenance

State DOT Office 2/3/88of Highway Trafficand Planning

State DOTHighway Dept

2/17/88

Highway Patrol 2/4/88

The TSV Waste Shipment Corridor States

Typa ofWeather Related Delavt

24 hr». »ax.

8 hrs. aaziaua for any typeof emergency.

1/2 day aaxiaaa.

All

All

All

State DOTMaintenance Div.

2/4/88

2 days due to snow every 2 1-5to 3 years. Few Biantes to 2 1-15to 3 weeks due to flood. 2 Route 14weeks dne to earthquake.Detours prorided.

12 hrs. aaxisnia.

No inforaation available.

3 to 4 hrs. dne to blizzard.

10 days because a bridge pierslipped. (Tracks were offthe road for 14 days).Detours provided.

2 days dae to saowstora orblizzard/wind.

8 hrs. aaxiaoa.

No inforsation available.

Nona.

1/2 to 1 day dae to flooding. 1-701 to 1-1/2 days with detoarsprovided.

4 to 8 hrs. dne to snow. 1-80

Northbound1-90, 1-94

1-65

3.6.4-11

NnPae TRUPACT-II SA£ Rev. 0, Febrnary 1989

IS.

16.

17.

18.

Survey of feather Related

Sttte/C1tv

New llexico/Santa Fe

Ohio/Coluabns

Oklahooa/OklahoaaCity

Oregon/Salea

TABLE 3.6.4-2Delays on Interstate Eighvays of

(Costinned)

OfficeContact ei

State DOT

State DOT

State DOT

State DOT

DateContact*&

2/9/88

2/5/88

2/5/88

2/4/88

The TRU Waste Shipment Coxxidoz States

19. South Carolina/Columbia

20. Tennessee/Kashrille

State DOT StateDept. of Healthand Control

State DOT

2/3/88

2/3/88

21.

22.

23.

24.

Texas/Austin

Utah/Salt Lake City

Washington/Olympia

Wyonint/Cheyenne

State, DOT

State DOTTraffic Enir.

State DOT

State DOTMotor VehicleSafe ty

2/16/8

2/4/88

2/4/88

2/4/88

Vet tic Related Delars

Closed periodically doc tosnow and/or wind bat for avery short pexiod of t ine.

8 hrs. aaxiauB.

1 aonth doe to a bridge *aswashed out oa Ciaaaron River.

8 hrs. aaxiaua.

Generally, usage of highwaystopped for trucks/oversizedvehicles for np to 8 hours foricy conditions.

No information but generally8 hrs. aaxiamm.

96 hours due to rain.

72 Hours due to rain/highwater level.

2 to 3 hours due to flooding.

8 hours aaxiasa due to snow.

4 to 5 hours due to blizzard.

2 days due to avalanche.

4 to 5 days predominantlydue to weather.

Type ofHi thwav

Interstate

All

1-35

Interstate

State Route54 N in Haywood

County

State Route188

1-20

1-15

1-90

1-80

3.6.4-12

KnPac TRUPACT-II SAR Rev. 0, February 1989

Lastly, one or both of the drivers could become i l l during the tr ip , necess i -

tating the poss ibi l i ty that one driver must do a l l the driving or re l ief dri -

vers would have to be sent to wherever the truck i s parked. If one driver has

to. do a l l the driving, the transit time would be doubled ( i . e . , add three

days). If re l ief drivers are required, a two-day delay wil l occur to allow

for travel time of the replacement driver(s) .

4.2.3 Unloading Delays

Delays in unloading the TRUPACT-II packages at the WIPP s i te could be caused

by a number of factors: A truck could arrive at the WIPP site late on a

Friday preceding a three day weekend, and the normal processing and unloading

would not be completed unti l the following Tuesday, causing a delay in un-

loading of, say 4-1/2 to 5 days. There could be equipment problems in the

Waste Handling Building that could cause delays in unloading the TRUPACT-II

packages. Venting and handling equipment could break down. A total unloading

time of four days wi l l be assumed i f unloading begins just before a regular

weekend or five days for a holiday weekend. This i s a reasonable maximum time

to account for delays associated with unloading because the TRUPACT-II pack-

ages can be vented at the WIPP s i t e (using workers overtime) i f a to ta l ly

unanticipated chain of delays were to occur.

4.4.4 Total Off—Normal or Maximum Shipment Time

The total off-normal or maximum shipment time is summarized in Table 3.6.4—3.

A maximum shipment time of thirty-one (31) days is projected assuming the

worst-case scenario of a l l off-normal occurrences happening in the same

shipment.

3.6.4-13

NnPmo TRUPACT-II SAR Rev. 6 , February 1989

TABLE 3 . 6 . 4 - 3

SHIPMENT TIME SUMMARY

Activity

Normal Shipment Time

Loading

Transit time

Unloading

Time (Davs)

1

1-3

1

Maximum Normal Shipment Time: 3-5

Off-Normal or Maximum Shipment Timea

Loading

Tr an s i t Ti me

" Normal (max.)

* Weather delays and road closures

* Accident response

* Accident mitigation

* Truck maintenance problems

* Driver illness

Unloading

3

5

1

5

4

2

5

Maximum Off-Normal Shipment Time: 51 days

Adding all the times for relatively low-probability, independent delays

provides a conservative value for the maximum off—normal transit time.

3.6.4-14

HaPac TMJPACT-II SAE K«r. 4 . August 1989

5.0 SUMMARY AND CONCLUSIONS

The to ta l normal or expected shipment time froa the ten DOE f a c i l i t i e s t o the

WIPP s i t e w i l l be three to f i v e days with the longest time assoc iated with the

tr ip froa Hanford to WIPP. The maximum or off-noraal shipment t i r o that has

been postulated to occur as a consequence of a ser ies of acc idents or other

off-normal events and delays i s thirty-one (31) days. This maximum shipment

time i s s i x times the maximum normal expected shipment time. This j u s t i f i e s

• the »e> of- using a thirty-one (31) day period for the b a s i s of deteraining

potent ia l buildup of flammable concentrations in the TRUPACT-II under the spe-

c i f i e d normal conditions with the absence of venting or operational controls

during t r a n s p o r t . However, t o add an a d d i t i o n a l margin of s u f e t y , the

shipping period i s nearly double the t o t a l off-normal shipment time or 60

days, which i s more than an order of magnitude longer than the maximum noraal

shipment time.

6.0 REFERENCES

6.1 10 CFR 71, 'Packaging and Transportation of Radioactive Materials'

6.2 49 CFR 395, 'Hours of Service of Drivers'

3.6.4-15

NUPAC TRUPACT-II SAR Rev. 0, February 1989

APPENDIX 3.6.5

BIOLOGICAL ACTIVITY ASSESSMENT


APPENDIX 3 . 6 . 5

BIOLOGICAL ACTIVITY ASSESSMENT

1.0 SUMMARY

This appendix addresses the impact of biological ac t iv i ty within the waste on

TRUPACT-II shipments. The primary concerns in this regard are the possible

generation of gases by biot ic processes which might contribute to the build up

of pressure in the TRUPACT-II cavity, or produce potent ial ly flammable gases.

An analysis of the waste forms and their environment shows that biological

activity wil l be minimal and wil l have l i t t l e impact on TRUPACT-II during a

potential shipping period of up to sixty days. Gas production by microbial

processes is not a concern for transport of contact-handled transuranic (CH-

TRU) waste in TRUPACT-II.

2.0 INTRODUCTION

Some of the CH-TRU waste forms and most of the packaging inside the payload

containers (polyethylene [PE] and polyvinyl chloride [PVC] bags in drums or

Standard Waste Boxes) are organic in nature. The potential for microbial

act ivi ty would exist if a suitable environment exists for the degradation of

these organics. As wil l be shown in the following sections, the waste en-

vironment during TRUPACT-II transport is not conducive for microbial p ro l i -

feration. Wherever a dis t inct ion between retrievably stored and newly gener-

ated waste is necessary, i t will be made.

3.0 TYPES OF BIOLOGICAL ACTIVITY

There are different types of microorganisms to be considered in the degrada-

tion of contact handled transuranic (CH-TRU) waste. Aerobic microorganisms,

which produce carbon dioxide (CO2) and water (1^0), require oxygen for growth

(Reference 8.1). Anaerobic microorganisms, which can produce CO2 and hydrogen

(Hj* predominantly as an intermediate) or methane (CH^), as well as other

3.6.5-1


products, degrade materials in anoiic (oxygen-free) environments (Reference

8 .1 ) . Facul ta t ive anaerobes can l i ve with or without oxygen. Obligate

anaerobes, on the other hand, cannot tolerate any oxygen and will only grow in

s t r i c t anoxic environments. Hicroorganisms most l ikely to be found in waste

products include bacteria and fungi. Bacteria u t i l i ze only the surface of a

material and can be either aerobic or anaerobic. Fungi can access the matrix

of the material but are generally only found in aerobic environments. Micro-

organisms can also be classified based on the optimum temperature they require

for growth. Hesophiles have an optimum temperature for growth between 20 and

55°C, while thermophiles grow best at temperatures above 50°C.

4.0 WASTE FORMS—IMPLICATIONS OF SUBSTRATE AND NUTRIENT AVAILABILITY

Various waste forms wi l l be transported in TRUPACT-II, but , in terms of the

poten t ia l for gas generation, only one form i s important; namely, ce l lu los ic

materials (sol id organics) . Materials made of rubber and p l a s t i c are more

r e s i s t a n t to microbial ac t ions . The contr ibut ion of these compounds to the

to t a l gas generated wil l be neg l i g ib l e , (especia l ly over the shipping period,

of sixty days) primarily because of t h e i r i ne r t na ture . Evidence from stored

drums (in re t r ievable storage for periods up to f i f teen years) that were

ppened up as par t of a sampling program shows l i t t l e or no degradation of the

packaging materials (see Appendix 1 .3 .9) . Even under conditions designed to

promote microbial p ro l i f e r a t ion , these compounds degrade very slowly, i f at

a l l . Similar ly, the so l id i f i ed inorganic sludges should not exhibit any s ig-

nif icant microbial gas generation due to t h e i r r e l a t i ve ly high a lka l in i ty (pH

= 10-12), which would be hos t i l e for most common microorganisms. This aspect

is discussed further in the next sect ion on environmental factors affecting

microbial growth.

Examples of ce l lu los ic materials that could be present in the TRUPACT-II pay-

load are -cotton, Kimwipes, and paper. Cellulose is a polymer composed of

chains of glucose monomers. Biodegradation of cel lulose requires the hydro-

lys i s of the polymer into the monomer u n i t s . Biological depolymerization is a

slow process which can s ign i f ican t ly inh ib i t fermentation r a t e s . Even though

there are organisms that can degrade cel lulose under different condit ions, i t

i s a complex process requir ing very specif ic enzymes. Wood w i l l a lso be pre-

3.6.5-2

NaPae TRUPACT-II SAR Rev. 1. Hay 1989

sent in TRU waste but i s degraded at a much slower rate than cellulose, in the

form of cotton. Wood contains l ignin which i s much more resistant to micro-

bial at.tack than cellulose. In addition, bacterial action i s ' a strong func-

tion of surface area and substrate avai labi l i ty . The bulk form and segregated

nature of the TRU waste creates conditions which are not very conducive to

high microbial metabolic a c t i v i t i e s , especially during a limited period of

sixty days. As shown in subsequent sections, the waste environment i s such

that, even for stored waste, the re lat ive ly long time period in i t s e l f i s not

sufficient to promote active microbial growth.

The avai labi l i ty of the nutrients, nitrogen and phosphorus, i s another factor

that can severely limit the extent of microbial act iv i ty in TRUPACI-II. The

dry weight of a bacterial ce l l typically contains 14% nitrogen and 3% phos-

phorus (Reference 8.2). While some of the waste forms do contain sources of

nitrogen, phosphorus i s l imiting in most cases. Even where sources of n i tr -

ogen are present, the waste form environments are far from optimum for bac-

terial growth. An example i s inorganic sludges which contain nitrates but are

lacking in carbon substrates, and which are basified to a pH of 10-12. In

other words, even without any consideration of the non-ideal environmental

conditions of the TRUPACT-II payioad, substrate and nutrient limitations by

themselves wi l l maintain microbial activity at minimal levels in the TRUPACT-

II cavity.

5 .0 ENVIRONMENTAL FACTORS AFFECTING MICROBIAL ACTIVITY IN THE PAYLOAD

Environmental factors such as temperature, pH, Eh, oxygen, moisture content,

and water a v a i l a b i l i t y are very important in determining the r a t e s ( k i n e t i c s )

and feasibi l i ty (thermodynamic aspects) of microbial act iv i ty . For the

TRUPACT-II payioad, almost all of these environmental variables are either

- sub-optimal or hostile. Each of these is considered in detail below.

3.6.5-3

NoPac TRDPACT-II SAR Rev. 1, May 1989

5.1 T>H and Temperature

The pH is an important factor to consider in the microbial degradation of CH-

TRU waste. Usually, most bac ter ia wi l l be most ac t ive a t neutral pHs. The

sludges to be transported in TRUPACT-II are f a i r l y basic (pH of 10-12), which

wil l inhib i t the ac t iv i ty of most bac te r ia and fungi. Specific organism

groups l ike the methanogens (methane producers) also have sensi t ive pH ranges

for growth (Reference 8 .2) . Even under careful ly control led laboratory condi-

t ions , methanogenesis has a very long s t a r t -up phase and a fa i r ly unstable

operating phase. Establishment of an act ive population of methanogens i s

therefore unl ikely in TRUPACT-II during the shipping period.

As mentioned in Section 3.0, microorganisms can be c lass i f i ed based on the

optimum temperature they require for growth. Methanogens, for example, have

an optimum temperature range between 90 to 100°F. Anaerobic digestion un i t s

(aimed at digest ing sewage sludge and the production of methane) are usual ly

provided with external heat exchangers to maintain optimum temperatures for

methanogenesis (Reference 8 .2) . These constant and optimal conditions are not

l ike ly to exis t even for waste that has been s tored for long periods of time.

Fluctuations in the temperature also prevent the establishment of a stable

microbial population in the waste containers.

5.2 Eh and Oxygen Avai lab i l i ty

Eh (the redox potent ia l ) i s an indication of whether an environment i s oxi-

dizing or reducing. Many microorganisms have s t r i c t Eh requirements for

growth. Methanogens, for example, require a very reducing environment in

which the Eh must be less than -200 mV (Reference 8.3) . They are obligate

anaerobes and cannot to le ra te even small amounts of oxygen. I t i s very un-

l ikely that any signif icant quant i t ies of methane wil l be produced during

transport of CH-TRU waste. Methanogenesis from cel lulose requires a complex

set of organisms and conditions to be successful and is eas i ly upset i f

favorable conditions are not maintained. The production of methane requires

not only the depletion of oxygen but also the reduction of n i t r a t e s and su l -

fates (Reference 8 .3) . Even in a process plant under optimum conditions, i t

3.6.5-4

NuPac TKDPACT-II SAR Rev. 1, May 1989

is difficult' to produce methane from cel lulose. Even experiments done under

controlled laboratory conditions showed no methane generation with C02 being

the major gaseous product (Reference 8 .4) . (These experiments are not appli-

cable to the transport conditions of TRUPACX-II - a bacterial inoculum was

added to synthetic waste along with required nutrients in these experiments.)

Radiolytic production of oxygen even in trace quantities would act as an in-

hibitor of anaerobic act ivi ty . In addition, the requirement of having a car-

bon composite f i l t e r on a l l the waste containers before transport provides a

means of communication with the environment, further destabilizing a constant

environment even for the stored waste.

5.3 Moisture Content and Water Availability

One of the prime requirements for microbial proliferation i s the availabil i ty

of sufficient amounts of water. Approximately 80% of a bacterial cel l mass i s

water. Microbial act ivity can be sustained even at relative humidities below

the saturation value, but metabolic ac t iv i t i e s under these conditions wil l be

very slow. Hence, microbial gas generation rates in short time periods (l ike

the sixty-day shipping period) wil l be insignificant. As pointed out earl ier,

even if some of the content codes have pockets of damp waste, other require-

ments for biological act iv i ty (substrate, nutrients, suitable pH and Eh con-

ditions) wi l l not necessarily be present in these areas.

5.4 Radiation Effects on the Microorganisms

An additional factor that contributes to making the microbial environment non-

ideal in TRUPACT-II i s the radiation from the payload, which can result in the

death of a portion of the microbial population. Radiation effects can poten-

t i a l l y compound the existing hosti le environment of the microorganisms in the

•payload.

3.6.5-5


6.0 SOURCE TERM OF THE MICROORGANISMS

The waste packaging configuration in the payload containers r e s t r i c t s the

source term for the microorganisms. While an i n i t i a l microbial inoculum may be

present in the waste, the p l a s t i c bagging acts as a barrier for the ava i l -

a b i l i t y of the waste substrates t o the microorganisms. In addit ion, the car-

bon composite f i l t e r s on the waste containers have a f i l t e r i n g e f f i c i ency of 2.

99.9%, wi th 0 .3 to 0 .5 micron p a r t i c l e s , DOP ( d i o c t y l p h t h a l a t e ) smoke

(Appendix 1 . 3 . 5 ) . Typical dimensions of bacteria are between 0.5 to 3 microns

(Reference 8 .2 ) . This means that the f i l t e r s would act as e f f e c t i v e bacterial

f i l t e r s (though not 100%) to prevent continuous contamination of the waste

with microorganisms.

3.6.5-5a

NnPac TRTJPACT-II SAR Rev. 0, February 1989

7.0 CONCLUSIONS

The nature and configuration of the payload for TRUPACT-II are such that bio-

logical act iv i ty wil l be minimal and of very l i t t l e concern during the s ix ty -

day shipping period. The environment in the TRUPACT-II cavity w i l l be sub-

optimal or host i le for the growth of most microorganisms due to the segrega-

tion of the waste and essential nutrients and the l imitations of usable sub-

s trate , nitrogen and phosphorus sources. The following factors support this

statement:

1. Cellulose, which is the most l ike ly waste product to be degraded by

bacteria, i s degraded by a complex process that requires a speci f ic

set of organisms. Some of these organisms may be present in the

waste but may not be in a suff ic ient quantity to contribute to the

overall gas generation.

2. The proper nutrients (primarily nitrogen and phosphorus) must be

present in order for the microorganisms to degrade any material.

Nitrogen from the a i r cannot be e f f i c i e n t l y u t i l i z e d by micro-

organisms; i t must come from a source such as n i trate . Sufficient

phosphorus, however, i s very l ike ly to be missing or limiting in

many drums.

3. It i s very unlikely that methane would be produced during transpor-

tat ion of the waste for several reasons:

- The environment for methanogenesis must be very reducing (no

oxygen)

- Very s p e c i f i c microorganisms are required, which e x i s t in

narrow ranges of suitable environments, and

- The process can be self-poisoning i f intermediates produced are

not controlled or neutralized.

4. Although hydrogen may be produced during intermediate s teps in

anaerobic processes, i t i s very unlikely that i t wi l l be present as

3.6.5-6

NuP»c TRUPACT-II SAR. Rev. 0, February 1989

a final product. I t is used as a reducing agent almost as quickly

as i t is produced.

5. Another factor limiting bacterial degradation is substrate surface

area. The cellulosic materials that are put into bags are in a very

bulky form that is not easily accessible to surface-decomposing

bacteria .

6. Any aerobic decomposition wil l resul t in insignificant pressure

changes due to the simultaneous consumption of oxygen with the pro-

duction of carbon dioxide.

7. Even retrievably stored waste does not provide the necessary condi-

tions for continuous and prolonged microbial ac t iv i ty . Fluctuations

in environmental variables l ike the temperature and oxygen avai l -

a b i l i t y (due to the carbon composite f i l t e r ) act to prevent

anaerobic biological activity at any significant level . Evidence

from sampling programs shows very l i t t l e deterioration of the pack-

aging materials even after years of storage. In addition, l imitat-

ions in substrate and nutrient avai labi l i ty and segregation of these

nutrients apply to retrievably stored waste as well.

8.0 REFERENCES

8.1 Atlas, R. M., Microbiology! Fundamentals and Applications. Hacmillan

Publishing Company, New York , 1984.

8.2 Bailey,' J . E, and Ol l is , D.F., Biochemical Engineering Fundamentals.

McGraw Hill Book Company, New York , 1977.

8.3 Weiss, A. J . , R. L. Tate I I I , and P. Colombo, 'Assessment of Hicrobial

Processes on Gas Production a t Radioactive Low-Level Waste Disposal

S i tes , ' BNL-51557, Brookhaven National Laboratories, 1982.

8.4 Molecke, M. A., 'Gas Generation from Transuranic Waste Degradation: Data

Summary and Interpretat ion, ' SAND79-1245, Sandia National Laboratories,

1979.

3.6.5-7


APPENDIX 3.6.6

THERMAL STABILITY OF PAYLOAD MATERIALS AT TRANSPORT TEMPERATURES


APPENDIX 3.6.6

THERMAL STABILITY OF PAYLOAD MATERIALS AT TRANSPORT TEMP.ERATURES

1.0 SUMMARY

This appendix describes the thermal stability of payload materials near 130°F

(54°C) and 160°F (71°C), demonstrating that thermal degradation will be minimal

for payload materials during transport in TRUPACT-II.

2.0 INTRODUCTION

The thermal stability of the TRUPACT-II payload materials is addressed for the

wastes inside drums or Standard Waste Boxes, and payload materials outside the

waste containers, including the drum binding material (stretch wrap), plastic

reinforcement plates, and slip sheets.

Inorganic payload materials will be thermally inert, with the possible exception

of small amounts of gases adsorbed on the surfaces, most of which will be water

vapor. The pressure calculations performed in Section 3.4.4 of the SAR assume

saturated water vapor is present in all cases.

Organic materials are placed into shipping categories that are shown to meet

transport requirements by analysis or into shipping categories which are shown

to meet transport requirements by test, depending on the chemical makeup and

decay heat of the wastes. Thermal analyses of TRUPACT-II discussed in Section

3.4 of the SAR show that a waste temperature of 130°F (54°C) bounds the payload

temperature for solid organic wastes transported in analytically determined

shipping categories. Thermal stability of payload materials at and below 130°F

(54°C) is addressed in terms of the maximum continuous-use temperatures for

commercial applications, which depend on maintaining material properties and an

atmosphere with little contamination from outgassing. The effect of irradiation

of the materials on their thermal properties at this temperature is shown to be

3.6.6-1

NuPac TRUPACT-II SAR Rev. 1, May. 1989

negligible. For the test shipping categories, any gases produced thermally are

included in the measurement of total gas generation.

Plasticizers added to polymers to increase flexibility are typically less

thermally or chemically stable than the polymers (Reference 6.1). However, the

vapor pressures of most common plasticizers (e.g., phthalates, sebacates, and

other esters) are only 1 mmHg at 160°F (71°C) or above (Reference 6.2) and can

be ignored in pressure calculations.

Oxidation is the major degradation process for polymers heated in the presence

of oxygen. In a sealed system, oxygen typically is depleted at a rate faster

than the rate of formation of oxygen-containing gases such as carbon dioxide or

carbon monoxide, leading to a net pressure decrease.

The SAR analyses also show that the maximum drum wall temperature during normal

conditions of transport is 160°F (71°C). This temperature is used to evaluate

the thermal stability of the polyethylene stretch wrap, reinforcement plates,

and slip sheets. These materials are outside the waste containers and will have

experienced little or no radiation.

3.0 CONTINUOUS-USE TEMPERATURES FOR PLASTICS AND OTHER POLYMERS

There are two generally accepted categories of plastics: thermoplastic resins

and thermosetting resins. Thermoplastic resins consist of long molecules, each

of which may have side chains or groups that are not attached to other molecules

(i.e. , are not cross-linked) . Thus they can be repeatedly softened and hardened

by heating and cooling. In thermosetting resins, reactive portions of the

molecules form cross-links between the long molecules during polymerization:,

and thus once cured, the material cannot be softened by heating. Some plastics

can be processed as thermoplastics and then converted to thermosets.

Common thermoset plastics include epoxies, melamines, phenolics, glass-filled

polyesters, silicones, ureas, and urethanes. All of these have maximum con-

tinuous-use temperatures of 170°F (77°C) or above and can be considered ther-

mally stable at 170°F (77°C).

3.6.6-2


Maximum continuous-use temperatures for the thermoplastics are generally lower

than for the thermosets. The lower bound for the maximum continuous-use tem-

perature for some of the thermoplastics is 130 to 140°F (54 to 60°C) . Common

thermoplastics include acrylonitrile-butadiene-styrene copolymer (ABS), acry-

lics, cellulosics, fluoropolymers, nylons, polyesters, polycarbonate, poly-

ethylenes, polypropylenes, polystyrenes, polyurethanes, polyvinyl chloride (PVC),

and styrene-acrylonitrile copolymer (SAN).

Ranges of continuous-use temperatures for generic types of plastics are shown

in Figure 1 (Reference 6.3). Most plastics have continuous-use temperatures

above 150°F (66°C). Flexible vinyl and polyethylene are two generic types that

have maximum continuous-use temperatures below 150°F (66°C). Table 1 ranks

continuous-service temperatures for a number of commercial plastics for 176°F

(80°C) and below (Reference 6.3). Those having maximum continuous service

temperatures below 130°F (54°C) include a few specific polypropylenes and

polyurethanes. Ethyl cellulose, used for electrical insulation, has a maximum

continuous use temperature varying from 115 to 185°F (46 to 85°C) (Reference

6.4). Polyethylene and polyvinyl chloride, which are the most common plastics

in the wastes, have continuous service temperatures that typically are 140°F

(60°C) or above.

All of the maximum service temperatures for natural and synthetic•rubbers are

well above 130°F (54°C) (Reference 6.5). Neoprene (polychloroprene) and Hypalon

(chlorosulfonated polyethylene) have maximum service temperatures of 250°F

(121°C) or above, while styrene-butadiene rubber has a maximum service tem-

perature of 225°F (107°C) or above.

3.6.6-3

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ENGLISH

176

176

176

176

176

176

176

176

176

176

176

176

176

176

176

176

176

176

176

176

176

176

176

176

176

176

175

175

TABLE 1

METRIC

80

80

80

80

80

80

80

80

80

80

80

80

80

80

80

80

80

80

80

80

80

80

80

80

80

80

79

79

: CONTINUOUS SERVICE TEMPERA!PLASTICS FROM 105°F TO 176°F

COMMERCIAL NAME

Polyman 507

Conapoxy 1000-07

Conapoxy 1010-07

ThermoseC DC-151

Thennosec DC-291

Technyl C 216

Technyl A 216

Technyl A 221

Technyl B 216

Technyl D 316

Technyl D 317

Technyl DP 100

Geon 8730

Geon 8737

Geon 8801

Geon 8804

Geon 8825

Geon 8830

Sicron VC 86/1

Telenor Apex 124

Telenor Apex 128

Teknor Apex 130

Telenor Apex 241~

Teknor Apex 260

Tekaot Arex 265

Teknor Apex 329

Comalloy 220-3010

Comalloy 220-3030

TIRES Of COMMERCIAL(REF. 6.3)

GENERIC TYPE

ABS/PVC t

Epoxy

Epoxy

Epoxy

Epoxy

Nylon 6

Nylon 6/6

Nylon 6/6

Nylon 6/6

Nylon 6/10

Nylon 6/10

Nylon 6/10

Polyvinyl Chloride

Polyvinyl Chloride

Polyvinyl Chloride

Polyvinyl Chloride

Polyvinyl Chloride

Polyvinyl Chloride

Polyvinyl Chloride

Polyvinyl Chloride

Polyvinyl Chloride

Polyvinyl Chloride

Polyvinyl Chloride

Polyvinyl Chloride

Polyvinyl Chloride

Polyvinyl Chloride

ABS t

ABS :

PAGE*

B-27

B-113

B-113

B-171

B-171

B-253

B-299

B-300

B-300

B-327

B-327

B-327

B-947

B-947

B-948

B-948

B-948

B-949

B-955

B-970

B-970

B-970

B-971

B-971

B-971

B-971

B-5

B-5

3.6.6-6


ENGLISH

175

175

170

170

170

170

170

170

170

170

168

168

167

167

167

167

167

167

165

160

158

158

158

158

158

158

158

158

METRIC

79

79

77

77

77

77

77

77

77

77

76

76

75

75

75

75

75

75

74

71

70

70

70

70

70

70

70

70 •

COMMERCIAL NAME

Comalloy 220-3040

Comalloy 210-3020

D-10FG-0100

D-13FG-0100

A-20FG-0100

Beetle

Plaskon UIG-102

Plaskon Urea FCG

Plaskon Urea HGFCG-39

Plaskon Urea SMG

Fostafoam 4775

Fostafoam 5775

Degalan 6

Degalan 6E

Lexan FL.-910

Fostafoam 3486

Fostafoam 4486

Fostafoam 5486

Fostafoam 4786

Comalloy 110-1520

Nylon 12 huels L1700




Nylon 12 huels L196O


Sicron EC 70

Sicron EC 81/1

GENERIC TYPE

ABS :

Polystyrene t

ABS i

ABS t

Polystyrene :

Urea Formaldehyde t

Urea Formaldehyde

Urea Formaldehyde

Urea Formaldehyde

Urea Formaldehyde

Polystyrene i

Polystyrene t

Acrylic

Acrylic

Polycarbonate t

Polystyrene i

Polystyrene :

Polystyrene t

Polystyrene :

Polypropylene t

Nylon 12

Nylon 12

Nylon 12

Nylon 12 i

Nylon 12 t

Nylon 12

Polyvinyl Chloride

Polyvinyl Chloride

PAGEa

B-5

.B-835

B-21

B-21

B-864

B-1013

B-1013

B-1014

B-1015

B-L0I5.

B-829

B-829

B-43

B-43

B-439

B-829

B-829

B-829

B-829

B-692

B-347

B-348

B-349

B-349

B-349

B-350

B-953

B-953

3.6.6-7


ENGLISH

158

'158

158

158

158

158

158

158

158

158

157

150

150

150

150

150

150

150

145

143

>140

>140

>140

140

140

140

140

140

METRIC

70

70

• 70

70

70

70

70

70

70

70

69

66

66

66

66

66

66

66

63

62

• >60

>60

>60

60

60

- 60

60

60

COMMERCIAL NAME

Sicron EC 93/1

Sicron FL 68/1

Sicron FL 83/1

Sicron PT 80

Sicron VC 60/2

Sicron VC 70/2

Sicron VC 76/2

Tenneco 2800

Tenneco 2803

Tenneco 2804

Plexiglas VM

Comalloy 110-1220

Comalloy 110-1240

P-40CC-0100

Comalloy 310-3020

V-20FG-0100

Kraton D 1111

Kraton D 4140

Comalloy 310-3015

ALPHA DURAL 202V

Hercules K-type

Hercules N-type

Hercules T-type

Plexiglas VS

Norchem NPE 130

Norchem NPE 190

Norchem NPE 320

Norchem NPE 350

GENERIC TYPE

Polyvinyl Chloride

Polyvinyl Chloride

Polyvinyl Chloride

Polyvinyl Chloride

Polyvinyl Chloride

Polyvinyl Chloride

Polyvinyl Chloride

Polyvinyl Chloride

Polyvinyl Chloride

Polyvinyl Chloride

Acrylic

Polypropylene t

Polypropylene t

Polypropylene t

Polyvinyl Chloride t


Thermoplastic Elastomer

Thermoplastic Elastomer

Polyvinyl Chloride :

Polyvinyl Chloride

Ethyl Cellulose

Ethyl Cellulose

Ethyl Cellulose

Acrylic

Polyethylene t

Polyethylene t

Polyethylene

Polyethylene

PAGE3

B-953

B-954

B-954

B-955

B-955

B-955

B-955

B-957

B-957

B-957

B-51

B-691

B-692

B-794

B-930

B-973

B-1005

B-1005

B-930

B-914

B-179

B-180

B-180

B-51

B-608

B-608

B-608

B-608

3.6.6-8


ENGLISH.

140

140

140

140

140

140

140

140

140

140

140

140

140

140

140 .

140

140

140

140

140

140

140

140

140

140

140

140

140

METRIC

.60

60

60

60

60

60

60

' 60

60

60

60

60

60

60

60

60

60

60

60

60

60

60

60

60

60

60

60

60

SI COMMERCIAL NAME

Norchem NPE 510

Norchem NPE 810

Norchem NPE 820

Norchera NPE 831

Norchem NPE 860

Norchem NPE 861

Norchem NPE 940

Norchem NPE 952

Norchem NPE 953

Norchem NPE 954

Norchem NPE 960

Norchem NPE 980

P-20CC-0100

Comalloy 310-3010

Ethyl 7042

Geon 2042

Geon 84059

Geon 84295

Geon 84319

Geon 84343

Geon 84350

Geon 84360

Geon 8610

Geon 8720

Geon 8803

Geon 8806

Geon 8818

Geon 8852

GENERIC TYPE

Polyethylene

Polyethylene

Polyethylene

Polyethylene

Polyethylene

Polyethylene

Polyethylene

Polyethylene

Polyethylene

Polyethylene

Polyethylene

Polyethylene

Polypropylene t


Polyvinyl Chloride

Polyvinyl Chloride

Polyvinyl Chloride

Polyvinyl Chloride

Polyvinyl Chloride

Polyvinyl Chloride

Polyvinyl Chloride

Polyvinyl Chloride

Polyvinyl Chloride

Polyvinyl Chloride

Polyvinyl Chloride

Polyvinyl Chloride

Polyvinyl Chloride

Polyvinyl Chloride

PAGEa

B-609

B-609

B-609

B-609

B-609

B-609

B-609

B-610

B-610

B-610

B-610

B-610

B-791

B-930

B-937

B-941

B-943

B-943

B-943

B-943

B-943

B-944

B-945

B-946

B-948

B-948

B-948

B-949

3.6.6-9


ENGLISH

140

140

140

140

140

140

140

140

140

140

140

140

140

140

140

140

140

140

140

140

140

140

140

140

140

140

130

130

METRIC

60

60

60

60

60

60

60

60

60

60

60

60

60

60

60

60

60

60

60

60

60

60

60

60

60

60

54

54.

COMMERCIAL NAME

Geon 8863

Geon 8896

Teknor Apex 102

Teknor Apex 118

Teknor Apex 139

Teknor Apex 164

Teknor Apex 586

Tenneco 2052

Tenneco 2300

Tenneco 2580

Tenneco 2700

Tenneco 2710 C4

Tenneco 2712

Tenneco 3066

Tenneco 3070

Tenneco 3078

Tenneco 3086

Tenneco 3092

Tenneco 3098

Tenneco 3160

Tenneco 3169

Tenneco 3174

Tenneco 3179

Tenneco 3189

Tenneco 3270

V-10FG-0100

PR-2042/90

ALPHA DURAL 114

GENERIC TYPE

-Polyvinyl Chloride

Polyvinyl Chloride

Polyvinyl Chloride

Polyvinyl Chloride

Polyvinyl Chloride

Polyvinyl Chloride

Polyvinyl Chloride

Polyvinyl Chloride

Polyvinyl Chloride

Polyvinyl Chloride

Polyvinyl Chloride

Polyvinyl Chloride

Polyvinyl Chloride

Polyvinyl Chloride

Polyvinyl Chloride

Polyvinyl Chloride

Polyvinyl Chloride

Polyvinyl Chloride

Polyvinyl Chloride

Polyvinyl Chloride

Polyvinyl Chloride

Polyvinyl Chloride"

Polyvinyl Chloride

Polyvinyl Chloride

Polyvinyl Chloride

Polyvinyl Chloride :

Epoxy

Polyvinyl Chloride

PAGE9

B-949

B-949

B-970

B-970

B-970

B-971

B-972

B-956

B-956

B-956

B-956

B-957

B-957

B-959

B-959

B-959

B-959

B-959

B-959

B-959

B-960

B-960

B-960

B-960

B-960

B-973

B-145

B-914

3.6.6-10

KuPac TRUPACT-II SAR Rev. 1, May 1989

ENGLISH

130

120

120

115

115

110

105

105

METRIC

54

49

49

46

46

43

41

41

COMMERCIAL NAME

ALPHA DURAL 211A2

Koppers 6100-10

Thexmocomp CF-1004

Escorene PP-1032

Escorene PP-1042

U-10FG-0100

Escorene PP-1052

Polyflam RPP958

GENERIC TYPE

Polyvinyl Chloride

Polyester

Polystyrene t

Polypropylene

Polypropylene

Polyurethane (TP) t

Po lypr opylene

Polypropylene :

PAGE*

B-914

B-499

B-847

B-702

B-702

B-888

B-702

B-767

Note: "Page refers to the page numbers in Ref. 6.3 where the materials aredescribed.

3.6.6-11


4.0 EFFECT OF RADIATION ON THERMAL PROPERTIES OF MATERIALS AT 129°F (54°O

Radiation chemically changes materials and can affect their thermal properties.

For example, for an absorbed dose of 500 Mrad in vacuum, the melting point of

polyethylene was decreased about 9°F (5°C) (Reference 6.6).

Polyethylene film irradiated in vacuum or under a nitrogen atmosphere were

subsequently heated in the presence of oxygen at 230°F (110°C). The weight

change between unirradiated and irradiated polyethylene films (exposure times

up to 1150 hr) was compared (Reference 6.7). The major difference between

irradiated and unirradiated materials was that the irradiated materials began

to absorb oxygen and increase in weight after 50 hr without antioxidant, or after

500 hr with antioxidant.

The rate of weight loss versus temperature of polyethylene was measured for

samples irradiated in air and then heated in air (Reference 6.8). Thermal

degradation was detectable above about 302°F (150°C), with only minor differences

found between irradiated and unirradiated materials.

The conclusions reached are that while there are measurable differences in the

thermal properties of polymers when they are irradiated, the effects are

relatively small even near 392°F (200°C), and can be neglected for a temperature

of 129°F (54°C).

5.0 THERMAL DEGRADATION OF POLYETHYLENE AT 160°F (71°O

The temperature of the polyethylene stretch wrap, reinforcement plates, and slip

sheets may exceed the maximum normal-use temperature for polyethylene (nominally

140°F [60°C]). These materials will have experienced little or no radiation,

since they are outside the waste containers.

3.6.6-12


Thermal degradation of organic materials occurs according to an Arrhenius

relationship:

k - Aexp(Ea/RT)

where k - rate constant

A - pre-exponential factor (I/time)

Ea - activation energy for thermal degradation (calories/mole)

T - temperature (K)

R - gas constant.

Thermal oxidation of low-density polyethylene shows gradual energy absorption

until melting occurs at about 230°F (110°C) , and then combustion occurs at about

482°F (250°C) (Reference 6.9). Demas concludes that polyethylene can be used as

an electrical insulation material for temperatures up to 140-167°F (60-75°C)

without creating a toxicological problem for humans, indicating that production

of toxic or flammable gases is minimal at these temperatures.

Kosiewicz (Reference 6.10) describes experiments measuring thermal degradation

of common waste materials at 68°, 104°, 158°, and 212° (20°, 40°, 70°, and 100°C),

including various cellulosics, plastics, and rubbers. He measured the amount

of gas evolved at a given temperature that was maintained for a long period of

time. The gas amount was determined by the pressure reached in an experimental

cylinder. A gas production rate of 1E-7 mole/day-g was reported for experiments

conducted at 158°F (70°C) for more than 340 days for both uncontaminated samples

and samples contaminated with plutonium at 4E5 nCi/g of material. None of the

samples were sterilized, so some of the gas evolved could have come from

microbial degradation. The gas composition was not reported. Similar

experiments conducted using paper resulted in a very low gas generation rate at

104°F (40°C) and a maximum rate of 7E-8 moles/day-g at 158°F (70°C) .

3.6.6-13


Over the sixty-day t ranspor t time, the moles of gas generated per pound of

material would be:

moles/lb - 1E-7 moles/day-g x 60 days x 1E3 g/2.2 lb

- 2. 7E-3 moles/lb.

In one year, the moles of gas generated per pound of material would be:

moles/lb - 1E-7 moles/day-g x 365 days x 1E3 g/2.2 lb

- 1.7E-2 moles/lb.

Carbon dioxide and carbon monoxide are common thermal degradation products of

polymers, so much of this gas would be nonflammable.

The maximum weight of the slip sheets and stretch wrap is 100 lb. The maximum

amount of gas generated during transport at 160°F (71°C) would then be 0.3 moles

for 60 days or 1.7 moles for one year. This gas would be generated outside the

payload containers.

The conclusions reached are that generation of flammable gas through thermal

degradation of the waste materials at 130"F (54°C) and of polyethylene at 160°F

(71°C) (stretch wrap, reinforcement plates, and slip sheets) will be negligible.

3.6.6-14


6.0 REFERENCES

6.1 Deanin, R. D., Polymer Structure. Properties and Applications. Chaners

Books, Boston, 1972.

6.2 AIP Handbook, American "Institute of Physics Handbook. Second Edition,

McGraw-Hill Book Company, New York, 1963.

6.3 Plastics Desk-Top Data Bank, Plastics Edition 6 Desk-Top Data Bank. Book

A, The International Plastics Selector, Inc., 1983.

6.4 Harper, C. A., ed., Handbook of Plastics and Elastomers. McGraw-Hill Book

Company, New York, 1975.

6.5 Dean, J. A., Handbook of Organic Chemistry. McGraw-Hill Book Company, New

York, 1987.

6.6 Black, R. M., and A. Charlesby, "The Oxidation of Irradiated Polyethylene-

II Thermal Oxidation," Inter. J. Appl. Radiat. Isotopes 7, PP. 134-140,

1959.

6.7 Kato, K., et al., "Structural Changes and Melting Behavior of Gamma-

Irradiated Polyethylene," Jap. J. Appl. Phys. 20, pp. 691-697, 1981.

6.8 Igarashi, S., "Thermogravimetric Analysis of the Effect of Ionizing

Radiation on Thermal Stability of Polyethylene," J. Appl. Polym. Sci., Vol.

8, pp 1455 - 1464, 1964.

6.9 Demas, P., "Emissions of Volatiles from Non-Metallic Shipboard Materials

-- 'Electrical Insulations," 75-ENAs-35, American Society of Mechanical

Engineers, New York, 1975.

6.10 Kosiewicz, S. T., et al., "Studies of Transuranic Waste Storage under

Conditions Expected in the Waste Isolation Pilot Plant (WIPP)," Interim

Summary Report, LA-7931-PR, October 1, 1977 -- June 15, 1979.

3.6.6-15

certificate of compliance no. 9218 revision 6 march 30,1995

Documents

Transcript of certificate of compliance no. 9218 revision 6 march 30,1995