!lzy department of energy!lzy * o aj ~cf department of energy washington, dc 20585 the honorable...

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Department of EnergyWashington, DC 20585

The Honorable John T, Conway

ChairmanDefense Nuclear Facilities Safety Board625 Indiana Avenue, NWSuite 700Washington, DC 20004

Dear Mr. Chairman:

Enclosed is Department of Ener-~ document. “Svstem Requirements Documentfor the C-23 3 Safe Storage System, Revision O.” It represents the deliverable forCornmm-nent 15 of the Department’s Implementation Plan for addressing theDefense Nuclear Facilities Safety Board’s Recommendation 97-1 concerning thesafe storage of Uranium-233 material.

The Board was briefed on this document by members of the DOE 97-1 TechmcaJTeam on May 13, 1998.

If you have any questions. please contact me, or have your staff contactHoyt Johnson of my staff at (202) 586-0191.

SincereIv,

James M. OwendoffActing Assistant Secretary for

Environmental Management

Enclosure

cc wfenclosure:M. Whitaker. S-3.1

RevisionMay 1998

System RequirementsDocument

for the

233USafe Storage System

SYSTEM REQUIREMENTS DOCUMENTfor the

233USAFE STORAGE SYSTEM

Revision O

May 1998

U.S. Department of EnergyDOE Idaho Operations Office

Idaho National Engineering and Environmental LaboratoryIdaho Falls, Idaho

2mtJSafe Storage System Revision OSystem Requirements Document May 1998

FOREWORD

Uranium-233 (Z33U)is a man-made uranium isotope primarily formed as a result of neutronirradiation of thorium-232 (~3zTh). Because %-J is fissile, its potential use as fuel for nuclearreactors and as nuclear weapons material was researched extensively by the Department ofEnergy (DOE) beginning in the 1950s. Since the completion of these research programs, variousfeasibility studies have been undertaken, but no major ’33U programs have been funded. Thus,the bulk of the ’33U have remained in different physical forms, which are contained by variousstorage packages and systems. Due to the lack of funding and facilities to handle the significantradiation emissions from these materials, many of these packages have not been inspected foryears. and their condition is unconfirmed.

The DOE has an inventory of approximately two metric tons of ‘3% in many different formsstored under a variety of conditions throughout the complex. The majority is located at the OakRidge National Laboratory (ORNL) and the Idaho National Engineering and EnvironmentalLaboratory (INEEL), with significantly lesser quantities at LOS Alamos National Laboratory

(LANL ). Even smaller quantities of material exist at numerous other sites. The material existsas oxides, metal, solutions. and tluorides. Some of this material is also being managed under theDepartment’s National Spent Nuclear Fuel Program and under the Implementation Plan (1P) forBoard Recommendation 94-1 (i.e., the Oak Ridge Molten Salt Reactor Experiment [MSRE]).

DNFSB Recommendation 97-1 added 23% material that is not covered by other programs to itsarea of safety concern. 97-1 is detailed in the DNFSB Recommendation, which is available atthe DNFSB web site at www.dnfsb.gov. The 97-1 Program is detailed in DOE ImplementationPlan for DNFSB Recommendation 97-1

Another driver for this program is the Department of Energy (DOE) Highly Enriched Uranium(HEU) Vulnerability Assessment (VA) that previously identified some of the concerns regardingthe state of the 97-1 ‘~~Uinventory for protection of workers and the environment. The HEU VAis detailed more extensively in DOE EH-0525. December 1996.

Ill

2=u Safe Storage System Revision OSystem Requirements Document May 1998

TABLE OF CONTENTS

FOREWORD............................................................................................................................................................111

ABBREVIATIONSANDACRONYMS..............................................................................................................VII1

1.0 INTRODUCTION................................................................................................................................................1

2.0 ~PPLICABLEDOCUMENTS...........................................................................................................................7

2.1 GOVERNMENTDOCUMENTS.... ... .. ... . ... .. .. .. ... .... ... . . ... . .. . .. . .. . . .. .. .. . .. . . .. . .. .. . ... .. . .. .. .. .. .. ... .. .. .. .. .. ... .. .. .. . .. . .. .. .. .. . ......... 72. 1.1 Laws, Regulations. and Acts .................................................................................................................. 7~,],~ DNFSB Documents .... ............................................................................................................................ ?2.1,3 Department qfEnerq> Docliments ........................................................................................ ................. 72,1.4 Executive Orders ................................................................................................................................. 102,1.5 State and Tribal b\t3xatld Agreemetlts ............................................................................................... 102. 1.6 Local Orditlances .................................................................. .............................................................. 10

~ ~ NoN.GoVERNMENT DOcUNIENTs .. ... .. ... .. .. .... .. .. .. .. . .. . .. . .. . .. . . . .. . . .. .. . .. .. .. . .. .. .. . ... .. .. .. .. ... .. .. .. .. .. ... .. . .. .. . .. .. .. . .. . .. . . .. 10---

2.2.1 Standards .............................................................. ............................................................................... 10

3.0 SYSTEMREQUIREMENTS........................................................................................................................... 11

3.1 SYSTEM DESCRIPTION..... .. .. .. .. ... .. .. ... .. .. . .... .. ... ... .. .. . .. .. ... . . .. . . . .. . .. .. . . .. .. . .. .. .. .. . .. .. ... .. .. ... .. .. .. .. ... .. .. .. .. . .. ............... 113.1.1 System Component.Y .......................... . .......... . . ..... .............. ........... 123.1.2 System Inte@aces .:................................................................. ............................................................. 133.1.3 97-1 ~-q~UMaterials Itl\'entories .................................... ...................................................................... 13

3.2 SYSTEM LEVEL RECX,’IREMENTS.... .. .. . . .. . . . . . . .. . .. .. .. . . .. .. .. .. .. .. .. .. . .. .. . . ... . . . . . . 177J, 1 Pe@ormance ........................................................................................................................................ 17{72..-. Furlctiottal ..... ...................................................................................................................................... 17<3j [nte,qration undltltefli~ce Cotitrol.., ..... .......................... ........ . .... ..... ... . .. . . . . ...................... .. 18.. ’-..;7..-. -1 information Sysrenl.Y ............................................................................................................................ 25,?.3.-. 5 Emergency Respott.~e .5vstenls ..............................................................................................................26{7(j..-, Environment. Safe~atld Heaitil .......................................................................................................... 29{37..-. Safegllards atld Secllrity ......................................................................................................................34i38..-. Reliabili~, Availability, atld.Vaitllalttab ility ...................................................................................... -/2

3.2.9 Human Facto rs ................................................. ...... . .............................................................. 42< ~ ]() ‘Traltlltlq ‘ljtd Qua[ificatiott.v..-. . 42

3.2.11 Design ’and Consrrucrio n............................ ............... ...................................................................... 4631]2 Lye c~cleASSer~anagement(LcA,+l)..............................................................................................48

3.2.13 Non- Federal Luit’s. .4greements. and Ordittatlces ............................................................................... 513.3 ‘lkl PROCESSINGSUBSYSTEM REQUIREMENTS... .. . .. .. . .. . . .. . .. . . .. . .. . .. . .. . ... .. . .. ... . .. .. .. ... ... .. .. ... . .. ... .. . .. .. .. .. . .. .. .. . .. . . . 51

3.3.1 Pe#ormance ........................................................................................................................................ 513.3.2 Functional .................................... . .. ........... ....... . . . ............................................................ 523.3.3 integration andlntetjace Control ........................................................................................................ 533.3.4 Information Systems ............................................... . . . . ......................................................... 533.3.5 Emergency Response Systems ............................ ........ .......... .............................................................. 533.3.6 Environment, SafeP, and Health .... .. .. ... .. .. .. . . .... ... .. ... .. ................................................ 533.3.7 Safeguards artd SecuriG ............................ ..... ... .. ........... . . . ....................................... 533.3.8 Reliabili~, Availabilip, and Maintamabili~ . ... . . . ................................................. 53~ .J.9 Human Facto as ......... . . . . .. .... . . .. ... .. ......... . .. . ..................................... 54

v

2=U Safe Storage System Revision O

System Requirements Document May 1998

3.3.10 Training and Qualification .................................................................................................................. 543.3.11 Design and Construction ..................................................................................................................... 543.3.12 Life Cycie Asset Management (LCAM) ................................................................................................ 543.3.13 NOn.Fpdera/Lgws,Agreements,andOrdinarlces ............................................................................... >-/

3.4 STORAGESUBSYSTEMREQUIREMENTS.... .. . ... . .. . ... . .. .. ... .. ... . ... ... ... ... . ... .. .. .. .. . .. .. .. . .. .. . .. .. . .. .. . .. .. .. . .. . .. .. . .. . .. ... .. .. .. . M3.4.1 Pe~ormance ..................................................................................................... ................................... 543.4.2 Funcnonal ......................................................... ............................................ .................................... 54.{.4.3 lntegt-anon andlnterjace C()rltro[........................................................................................................ .553.4.4 Information Sy.rtems ............................................................................................................................ 553.4.5 Emergency Response S}stems .............................................................................................................. 553.4.6 Environment, Safety. andHea[t h.. . ................... ............... ................... .. ..........563.-/.7 Safe,guurds and Security ...... ..... . .. . . ..... ....... . ...... .. .. ..... . .. .. ...... ................... ...... ...563.4.8 Reliabilifi, Availabili~, und Maintalllabili~ .................................................... .... ............................ 563.4.9 Human Facto rs .................................................................................................................................... 56_7.4.10 Training and Qua[l~cattotl .................................................................................................................. 56

3.4.11 Design and Construction ............................... . . .................................................................... 56j,./,/l Lye C\c[eAssetM at~agetnetlt( LCAkl) ................................................................................................ 56

.{../. ]3 Votl.FKdera[~ )vs, Agreements. ~md Orditlutlces ................................................................................. !~

3.5 TRANSPORTATION SUBSYSTE\f REQUIREMENTS .. ... .. .. .. .. ... .. ... ... .. .. ... .. ... . ... .. . .. .. . .. .. .. . . . .. . .. . . ... . .. . .. .. . .. .. . .. .. .. .. .. .. . 57

{5[. . . Peqornlcttlce ................................................................................................... ..................................... S73.5.2 Flincrtotiai ......................... ... ............................................................................................................... !?3.5.3 Integrarlon and[nteqace Cotltrol ........................................................................................................ .57.~.5.4 Injormatlon S>sret~ls. ........................................................................................................................... 573.5.5 Emergency Response Systenls .............................................................................................................. 573.5.6 Environment, Safe~, und Health ......................................................................................................... 583.5.7 Safegitards and Security ..................................................................................................................... 59

3.5.8 Reliabilip, Aiailabilip, and Maintaitlabi[ity ...................................................................................... 603.5.9 Human Factors .................................................................................................................................... 603,5.10 TraitItnq and QIta/~icafiotl ............................................................. ..................................................... 60

3.5.11 Design und Construction (Facilities) .................................................................................................. 603.5.12 Life C~cleAsset Management (L CA M) .......................................................... ...................................... 61j j,]j ,Vorl.Fe(/pr~l[~l)\,f, ,.\~t-pemcllr.Y, (old Ot-dlrlatlc’es... . . . . . . .. . . .. .. . . . . . . . . .. .. .. .. ....62

3.6 WASTE MAS,AGEX!ENT SUBSYSTEkf . .. . .. .. . .. .. .. . .. .. .. .. ... .. .. ... .. ... .. ... ... .. .. .. ... .. .. .. . .. .. . .. .. . .. . .. . . .. .. . .. .. . .. . .. .. . .. .. .. .. .. .. .. 62

3.6. I Peflormatlce ........................................................................................................................................ 62-1~~ F/ttlcrlotlal .................................................................................................. ........................................ $2.~,6.3 ltlteqratwna ndlnrequce Cotlrro[ ........................................................................................................ 5!.~.6.4 itlformaItotz S>stems. ...........................................................................................................................63!.6.5 Emercency Response Systet~ls .............................................................................................................. 633.6.6 Environment, Safe~, and Hea[tll ......................................................................................................... 63j.6,7 Safegllards arid Secltrin ........................................................... ................. ........................... 63

3.6.8 Reliabilip. At’ailabili~, ar~diWalrttaltzab i[i~ ............................................. ............ ............................ 633,6,9 Human Facto rs.,.,. . . .... .... .. . .. .... . . ... .. . . .. . .. .. . . ... ...... ................................. 633.6.10 Tralrllrlq arid QtIa[ificatiott .................................................................................................................. 633.6.11 Dest,gn and Construction (Facilities) .................................................................. ................................ 63

3.6.12 Life Cycle Asset Mana.qemerlt (L CAiV) ................................................................................................ 63.1’.6.I3 !Von-Federal Lu}vs, Agreements. and Orditlutlces ............................................................................... 63

40 QUALITYASSIJRANCEPROVISIONS........................................................................................................ 64

VI

2XU Safe Storage System Rev/s/on (JSystem l?equirements fYocument May 1998

5.0 NOTES................................................................................................................................................................ 70

5,1 TBDmBRSUMMARYLISTING .... .. .. .. . .. ... .. .. .. .. ... ... .. .... .. .. ... .. .. .. . .. . .. . .. .. . . . . .. . . .. . . .. . .. . .. .. . . . .. .. . .. .. .. .. ... .. ... .. .. .. .. .. . .... 70

GLOSSARY 4.............................................................................................................................................................73

APPENDIX~: REQUIREMENTSTRACEABILITY,~ATRIX....................................................................A-1

APPENDIXB: REQUIRENIENTSVER1FICATIONi~ATRIX..................................................................... B-1

APPENDIXC: RELATEDDOCUMENTS........................................................................................................ c-1

APPENDIXD: BASESAND~DDITIONALINFORXIATIONFOR233USAFESTORAGESYSTEMREQUIR~\lE~TS .....................................................................................................................D-1

D-1 REQLIIREWNTSBASES AN~ADDITIONALINFOR%IATION..... .. . .. . .. . .. .. . . . .. . . .. . . . .. .. . .. . . .. .. . .. . .. .. .. .. .. .. ... . ... .. .. .. . ... . D-1D-’2 SITEDescriptions ANDCApABILITIEs. ..................................................................................................... D-13

D-2.1 Oak Ridge Natiotlal tiboraton ................................................. ..................................................... D-13D-2.2 Idaho Nationai Engineering atzd Ett\tlro!tmetlta lbboraton .......................................................... D-14D-2.3 Los Alanm.~ National bboraton .............................................. ...................................................... D-15

D-3 DISPOSITION SYSTE\! CONSIDERATIONS .. .. ... .. ... ... .. .... ... . .. ... . .. .. . .. .. . .. . .. . . .. . . . . .. . .. . .. . .. . . .. .. . .. .. . ... .. .. .. .. .. ... .. .. .. .. D.l6

vii

2=(,/ Safe Storage System Revision O


ABBREVIATIONS AND ACRONYMS

ALARAANLANSANSIASTMATMS

CCBCFR

DBA

DNFSBDOEDOE-EMDOE-MDDOTDU

EISES&H

HEPAHELT

IAEAIEEEICDINEELINTEC

LANLLCiOlLLNL

Mc&iAMSRE

NDANDENEPAlNMCNPHNRC

as low as reasonably achievableArgonne National LaboratoryAmerican Nuclear SocietyAmerican National Standards InstituteAmerican Society for Testing and MaterialsAutomated Transportation Management System

Change Control BoardCode of Federal Regulations

design basis accident

Defense Nuclear Facilities Safety BoardU.S. Department of EnergyDOE Office of Environmental .ManagementDOE Office of Materials DispositionDepartment of Transportationdepleted uranium

Environmental Impact StatementEnvironment, Safety, and Health

high-efficiency particulate air (filter)

highly enriched uranium

International Atomic Energy AgencyInstitute of Electrical and Electronics EngineersInterface Control DocumentIdaho National Engineering and Environmental L~boratoryIdaho Nuclear Technology and Engineering Center

Los Alamos National LaboratoryLife Cycle Asset ManagementLawrence Livermore National Laboratory

.Materials Control and AccountabilityMolten Salt Reactor Experiment

Non-Destructive AssayNon-Destructive ExaminationNational Environmental Policy Actnuclear materials couriernatural phenomenon hazardNuclear Regulatory Commission

2ZU Safe Storage System Rewsion OSystem Requirements Document May 1998

2=U Safe Storage System Revision O


OPSECORNL

PEPppm

PuPSM

RnROD

SARSNMSRDSRRSscSTL

TBDTBRThTINT1TRANSCOMTSDTSS

uUloxU02

operations securityOak Ridge National Laboratory

Program Execution Planparts per million (grams of designated material per megagram [metric ton] ofnet representative sample)plutoniumProspective Shipments Module

RadonRecord of Decision

Safety Analysis Reportspecial nuclear materialSystem Requirements DocumentSystem Requirements Review\tructure. system. or componentSafeguards Termination Limit

IObe determinedto be resolvedThoriumTransportation Information NetworkThalliumTransportation Tracking and CommunicationsTransportation Safeguards DivisionTransportation Safeguards System

UraniumTriuranium OctoxideUranium Dioxide \

ix

2mU Safe Storage System Revision OSystem Requirements Document May 1998

1.0 INTRODUCTION

This document defines the system requirements for the ~s3USafe Storage System. Theserequirements are extracted from those documents listed in Section 2 and derived from themission. as defined in the original Defense Nuclear Facilities Safety Board (DNFSB)Recommendation 97-1: the Implementation Plan provided by the Department of Energy (DOE);and from analysis of the problem by the 233USafe Storage Technical Team, as established by theDOE for the purpose of determining the Department response to this recommendation. [DNFSBRecommendation 97-1, DNFSB TECH 13, DOE Implementation Plan for DNFSBRecommendation 97- 1]

As used in this document, the terms “shall”. “should”, and “may”’ are defined as follows:

“Shall” denotes actions that are mandatory“Should” denotes recommended actions“May” denotes that something is permitted or likely to occur

The requirements contained herein apply to the design, construction and operation of the ’33USafe Storage System. This document will be followed by a succession of system engineering,design engineering, construction and operations documents that result in the design, construction.operation, and decontamination and decommissioning (D&D) of a facility or facilities that placeand maintain the inventory of Uranium-233 (%J) materials into safe long-term storage. The fullset of engineering documents that will be developed for this program will be defined in theProgram Execution Plan.

The 97-1 Safe Storage program recognizes that a graded approach (per 10 CFR 830) is beingiipplied at DOE field sites. Variations of this graded approach include “Work Smart.”“’Necessary and Sufficient.” or ““S/RIDS. ” At the program level it is not practical to reflect thespecific approaches to be implemented at each site. However, since the program and field sitesare baslcallv driven by a common set of Luws. Regulations. Policies. DOE ond ExecutiveOrders. and other Directives. the concept of setting forth program-level requirements in thisdocument combined with a graded approach on a site basis provides a means to transition from acomplex-wide program to individual field sites. This will be accomplished through areconciliation team that will be established once specific implementing sites are selected. Thisteam will identify those System Requirements Document (SRD) requirements not beingimplemented as a result of implementing a graded approach and document the rationale. Site-specific reconciliation will be based on the tenets of DNFSB Recommendation 95-2. which startswith identification of the hazards and application of the appropriate requirements and controls toaddress those hazards.

While this document is based on the new series DOE Orders where they exist, it is alsorecognized that not all of the sites may have transitioned to the new series Orders. Any concernsresulting from an incomplete transition will also be resolved during reconciliation efforts.

1

233USafe Storage System Rev/s/on OSystem Requirements Document May 1998

Conventions followed in this document

. References contained in brackets [document section

are as follows:

] invoke the requirements contained in that document or

. References followed by {TBR} indicate that the preceding item or value is not final and shallbe reviewed and approved prior to use in design but may be temporarily used in studies oranalyses and that any results of such work will also be identified as {TBR} status as well.

. References followed by {TBD} indicate that the preceding item or value is still to bedetermmed.

This document, once approved. will be placed under program change control and the programChange Control Board (CCB) shall approve any subsequent changes before the changes can beused in design documents. A Change Control process and the charter of the CCB will beestablished for the program at the time of issuance of this document and will be extended in theProgram Execution Plan [PEP).

1.1 Purpose

The ‘~% Safe Storage Program has been undertaken by the DOE to implement the long-termstorage mission (see Section 1.3. 1). A program team involving all affected components of theDOE has been assembled to implement this mission. This program team will coordinate theinterim response by the affected tleld sites to ensure that the present inventory of ‘3% materialsis adequately safe while concurrently managing the development of a long-term ~33USafeStorage System and planning for the eventual disposition of the %J materials.

The purpose of this document is to establish the basic system requirements that the ~qsUSafe

Storage Sys[em shall meet in the long term. Interim storage issues \vill be addressed in tiseparate Interim Technical Baseline. which wdl accompany the Program Execution Plan. SRDrequirements will be considered in developing near-term responses to assessments of the currentstate of 97-1 materials at each site to ensure that near-term actions do not preclude compatiblelong-term activities.

System Requirements will include the specific techmcal requirements (capacity, throughput.form. processes. etc. ) for a system that meets the long-term storage and disposition objectives for‘33U, as well as the regulatory and institutional requirements specified by Federal, State, Tribal.and Local laws and Regulatory agencies or Boards. These requirements are intended to ensurethat ‘3%-bearing materials at DOE facilities are converted to safe and stable forms and placedinto low-maintenance storage in packages designed to maintain their integrity under anticipatedhandling, shipping, and storage conditions until disposition of the materials is implemented.

This requirementsbearing materials.

1.2 Scope

document identifies the requirements for the long-term safe storage of ’33UThe requirements define a system for the processing, storage, and transport of

2=U Safe Storage System Revision OSystem Requirements Document May 1998

materials containing ‘33U. These requirements also address the processing and interface with theEM Waste Management program for disposition of wastes generated by the activities associatedwith this system and those 97-1 materials that may be classified as wastes per the SafeguardTermination Limits (STLS) {TBD}. It is recognized the %-J is not considered transuranic wasteand, as such, it disposition is {TBD}.

These requirements are applicable to % in unirradiated forms in storage at the Idaho NationalEngineering and Environmental Laboratory (INEEL), Oak Ridge National Laboratory (ORNL)and Los Alamos National Laboratory (LANL), as well as at the sites designated herein as “smalholdings sites.” These small holdings sites include New Brunswick Laboratory, ArgonneNational Laboratory (ANL)-East and West. Brookhaven National Laborato~. the Oak Ridge Y-12 Plant, Hanford Site, Lawrence Livermore National Laboratory (LLNL), and Rocky FlatsEnvironmental Technology Site.

Material at Nuclear Regulatory Commission (NRC) -licensed facilities is not included in theinitial scope. However, this potential interface is acknowledged, and should any of this materialbe transferred to DOE. the program scope will be flexible enough to include this inventory.

Spent fuel containing 233~T,]Oca[edat~EEL,SavannahRiversite.andotherSi[es,isconsideredout of scope, since these materials are managed under the .National Spent Nuclear Fuel Program.Should any of this material be identified for integration with the ’33U safe storage program, itwill then be within scope for this program.

Similarly, the ‘~3U fuel associated with the Molten Salt Reactor Experiment (MSRE) isaddressed under the Implementation Plan for Board Recommendation 94-1. and is. therefore. anidentified integration issue for the scope of this program. Once the ~33Umaterial is removedfrom ,MSRE and stabilized (converted to oxide form). it \vill enter the scope of the 233USafeSto~age Program.

Several sites have stored potential wastes containing ~~sV. Once the waste threshold criteriahave been established it wiil be possible to determine whether any of this material comes underthe scope of this program or whether the materials will be determined to be waste and disposedunder the EM waste management programs. It must be recognized that disposition options may

~~~Uin use at the various sites for on-not exist for 1%-bearing materials in the near future.going programs is identified as potential future inventory. Should any of this material bedeclared surplus, it will be included within the scope of this program

1.3 System Overview

1.3.1 233USafe Storage System Mission

The Mission of the ’33U Safe Storage System is to safely manage 97-1 inventories of ’33Umaterial until disposition or use.

3

2=U Safe Storage System Rev/s/on OSystem Requirements Document May 1998

1.3.2 Background

On March 3, 1997, the DNFSB issued Recommendation 97-1 that deals with the safe storage ofunirradiated ‘sq~-bearing material. On April 25, 1997, the Secretary of Energy accepted theDNFSB’s Recommendation.

The Recommendation describes ~ctions that the DNFSB considers necessary to improve the safestorage of ‘3@ bearing materials in the interim and the longer term. Eight sub-recommendationsdetail those actions:

1.

-1-.

~.

4.

5.

6.

7.

s.

Establish a single line project to deal with issues attached to safe storage of %_J

Develop the standards to be used for packaging, transportation, and interim and long-termstorage

Characterize the items of ~~~Upresently in storuge in the DOE”s defense nuclear facilitiesm to material. quantitv. type and condition ot’ storuge container:

Evaluate the conditions and appropriateness of the vaults and other storage systems used.2.<for the ‘ U at the DOE-S defense nuclear facilities

Assess the state of storage of the items of ‘% in light of the standards mentioned in sub-recommendation 2 above

Initiate a program to remedy any observed shortfalls in ability to maintain the items of% in acceptable interim storage

Establish a plan for the measures that can eventually be used to place the ~% in safepermanent storage; and

LTntilthese uitimate measures are taken. ensure that the DOE’S complex retains theresidue of technical knowledge and competence needed to carry through all of themeasures needed to ensure safe storage of the ~% bearing material in the short andlong-term.

The Recommendation was preceded in February 1997. by a Board technical report entitled

the

“’Uranium-233 Storage Safety at Department of Energy Facilities” [DNFSB TECH 13]. Thereport described [he Board’s perspective of the safety of 23% stored at various sites in theDepartment’s complex. This formed the basis for the Board’s sub-recommendations. DOEaccepted these recommendations and an Implementation Plan was transmitted to the DNFSB andhas been accepted [Implementation Plan for ’33U Safe Storage]. Collectively. these documentsare the mission drivers for the 23% Safe Storage System.

The report also acknowledged the DOE”s Highly Enriched Uramum (HEU)-VulnerabilityAssessment (VA ), completed in August 1996. As a result of that assessment, the DOE was madeaware of the legacy issues surrounding the storage of ‘S3Ubearing material. and the HEU-VAfindings were subsequently incorporated into DNFSB TECH 13. At the time of issuance of

2mU Safe Storage System Revision OSvstem Requirements Document Mav 1998

Recommendation 97-1, the Office of Defense Programs had undertaken the development of aplan describing the necessary corrective actions for the most significant vulnerabilities identifiedin the HEU-VA. The HEU Vulnerability Corrective Action Plan was subsequently issued onJune 13.1997.

1.4 Document Overview

This SRD for the %J Safe Storage System consists of five major sections and four appendices.Detailed descriptions of each SRD section are as follows:

●

●

●

●

●

●

●

Section 1. Section 1 provides introductory and historical information regarding DNFSBRecommendation 97-1 and the mission of the ‘SSUSafe Storage Program, organized toaddress issues stemming from the DNFSB recommendation.

Section 2. Section 2 lists the document number and title for those government and non-govemment documents from which system requirements were extracted. Documentsidentified in Section 2 include: Laws and Acts: DNFSB Documents: DOE Order, Standards..Manuals and Guides. Xotices. and Policy Documents: Executive Orders: State md TribalLaws. Local Ordinances: md Non-Government Standards.

Sect;on 3. Section 3 contains the specific system-level and subsystem-level requirements forthe ‘?% Safe Storage System. Section 3.1 provides system description and identifies 97-1‘3SUinventories at ORJNL, INEEL, LANL. and Miscellaneous Universities and DOE sites.Section 3.2 identifies the system-level requirements imposed on the %J Safe StorageSystem, as a whole, and on each of the associated subsystem. Sections 3.3 through 3.6identify subsystem-specific requirements for the Processing Subsystem. Storage Subsystem,Transportation Subsystem. and Waste Management Subsystem. respectively.

Section 4. Section 4 contains the requirements for the ‘~qU Safe Storage System QualityAssurance Program. as well as requirements regarding system verification.

Sect/on 5. Section 5 lists those items to be determined (TBD) or to be resolved (TBR) by the‘~3USafe Storage Program. The resolution of TBD/TBR items listed herein will beaddressed in a separate TBD/TBR Resolution Plan. to be published under separate cover.

A~~endjx A, Appendix A contains the Requirements Traceability Matrix for eachrequirement identified in this SRD. In the matrix. each requirement is identified by numberand title and traced directly to its source document applicable paragraph or subsection.

Amend/x B. Appendix B contains the Requirements Verification Matrix for eachrequirement identified in this SRD. In the matrix. the verification method for eachrequirement is identified as either Not Applicable (N/A), Test (T), Demonstration (D),Analysis (A), Inspection (1), or Similarity (S). The Requirements Verification Matrix willused at a later stage of the program life-cycle to formulate a formal Test and VerificationPlan for the ‘2% Safe Storage System.

2=U Safe Storage System Rewsion OSystem Requirements Document May 1998

● Amendix C. Appendix C lists the related documents (e o.=., guides, manuals, standards, etc. )that provide additional information on how to carry out many of the requirements identifiedherein. These documents contain “how to” information rather than explicit requirements: assuch, they are listed in Appendix C rather than in the list of Applicable Document appearing

in Section 2.

● Appendix D. Appendix D contains additional information (i.e., requirement justification,Law and Policy descriptions, facility/site descriptions, etc. ) associated with many of therequirements.

This SRD, along with its supporting appendices. constitutes the system-level requirements set forthe ‘~% Safe Storage System and forms the basis for all subsequent program activities.

‘U Safe Storage System Rewsion OSystem Requirements Document Mav 1998

2.0 APPLICABLE DOCUMENTS

Section 2 identifies applicable laws, regulations, orders, and other requirement source documentscited within this SRD. The following documents form a part of this SRD to the extent specifiedherein. In the event of conflict between the requirements of this SRD and any referenceddocument. the requirements of the referenced document shall take precedence.

2.1 Government Documents

2.1.1 Laws, Regulations, and Acts

I 42 USC 6901 et seq. I RESOURCE CONSERVATION AND RECOVERY ACT (P.L. 94- ]550)

10 CFR 830.120 QUALITY ASSURANCE REQUIREMENTS10 CFR 835 OCCUPATIONAL RADIATION PROTECTION, SURFACE

RADIOACTIVITY VALUES( 29CFR 1910 OCCUPATIONAL SAFETY AND HEALTH STANDARDSi 29 CFR 1926 SAFETY AND HEALTH REGULATIONS FOR CONSTRUCTION ~

40 CFR 260-268 HAZARDOUS WASTE SYSTEM, ET AL

49 CFR 106-18049 CFR 173.7(b) SHIPPERS – GENERAL REQUIREMENTS FOR SHIPMENT AND ,

PACKAGING49 CFR 175 CARRIAGE BY AIRCRAFT

2.1.2 DNFSB Documents

DNFSB RECOMMENDATION URANIUM-233 STORAGE SAFETY AT DEPARTMENT OF97-1 ENERGY FACILITIESIMPLEMENTATION PLAN FOR IMPLEMENTATION PLAN FOR DEFENSE NUCLEAR FACILITIESDNFSB RECOMMENDATION SAFETY BOARD RECOMMENDATION 97-1, SAFE STORAGE OF97-1 URANIUM-233

2.1.3 Department of Energy Documents

2.1.3.1 Orders.

\ DOE AL 5610.14 I TRANSPORTATION SAFEGUARDS SYSTEM PROGRAMI,,. , ,V, .w

‘“ ‘e~n” ‘m’ “nr’”r”7S DOCUMENT“S DOCUMENT‘S DOCUMENT

-

I

INFORMATION

DOE O 225.1A ACCIDENT INVESTIGATIONS -

DOE 0231.1 CHG. 2 ENVIRONMENT. SAFETY( AND HEALJTH REPORTING——

‘XL) Safe Storage System Rewsion OSystem Requirements Document May 1998

DOE O 232.1A OCCURRENCE REPORTING AND PROCESSING OFOPERATIONS INFORMATION

DOE 0414.1 QUALITY ASSURANCEDOE O 420.1 CHG. 2 FACILITY SAFETY

DOE 0425.1 CHG. 2 STARTUP AND RESTART OF NUCLEAR FACILITIES

DOE 0430.1 CHG. 1 LIFE CYCLE ASSET MANAGEMENT

DOE O 440.1A WORKER PROTECTION MANUAL FOR FEDERAL FACILITIESDOE O 440.2 AVIATIONDOE O 451.1A NATIONAL ENViRONMENTAL POLICY ACT COMPLIANCEDOE O 460.1 A PACKAGING AND TRANSPORTATION SAFETY

DOE O 460.2 CHG. 1 DEPARTMENTAL MATERIALS TRANSPORTATION ANDPACKAGING MANAGEMENT

DOE 0470.1 CHG. 1 SAFEGUARDS AND SECURITY

I DOE0471.1 [ IDENTIFICATION AND PROTECTION OF UNCLASSIFIED I

i DOE 5400.1 CHG. 1- ] GENERAL ENVIRONMENTAL PROTECTION PROGRAM I/ DOE 5400.5 CHG. 2 ] RADIATION PROTECTION OF THE PUBLIC AND THE

I

ENVIRONMENTDOE 5480.8A CONTRACTOR OCCUPATIONAL MEDICAL PROGRAM1DOE 5480.19 I CONDUCT OF OPERATIONS REQUIREMENTS FOR DOE I

FACILITIESDOE 5480.20A PERSONNEL SELECTION, QUALIFICATION AND TRAINING

REQUIREMENTS FOR DOE NUCLEAR FACILITIESDOE 5480.21 UNREVIEWED SAFETY QUESTIONS

I DOE 5480.22 \ TECHNICAL SAFETY REQUIREMENTS I] DOE 5480.23 CHG1 NUCLEAR SAFETY ANALYSIS REPORTS

‘ DOE 5480.4 ENVIRONMENTAL PROTECTION. SAFETY. AND HEALTHPROTECTION STANDARDS

DOE 5481.1 B I SAFETY ANALYSIS AND REVIEW SYSTEMS (FOR NUCLEAR I\ FACILITIES)I

~ DOE 5632.7A \ PROTECTIVE FORCE PROGRAMII DOE 5633.3B CONTROL AND ACCOUNTABILITY OF NUCLEAR MATERIALS

DOE 5650.2B CHG.2 IDENTIFICATION OF CLASSIFIED INFORMATION

I DOE 5820.2A RADIOACTIVE WASTE MANAGEMENT

2.1.3.2 Standards.

DOE-SAFT-O067 CRITERIA FOR PREPARING AND PACKAGING URANlUM-233-BEARING METALS AND OXIDES FOR LONG-TERM SAFESTORAGE

DOE-STD-1020-94 (CH-1 ) NATURAL PHENOMENA HAZARDS DESIGN AND EVALUATIONCRITERIA FOR DEPARTMENT OF ENERI:Y FACILITIES

Refer to DOE O 231.1 CHG. 2 for paragraph deletions.

23U Safe Storage System Revision OSystem Requirements Document May 1998

DOE-STD-1 021 -93(CH-1 ) NATURAL PHENOMENA HAZARDS PERFORMANCECATEGORIZATION GUIDELINES FOR STRUCTURES, SYSTEMS,AND COMPONENTS

DOE-STD-1022-94 (CH-1 ) NATURAL PHENOMENA HAZARDS CHARACTERIZATIONCRITERIA

DOE-STD-1023-95 (CH-1 ) NATURAL PHENOMENA HAZARDS ASSESSMENT CRITERIA

DOE-STD-1024-92 (CH-1 ) GUIDELINES FOR USE OF PROBABILISTIC SEISMIC HAZARDCURVES AT DEPARTMENT OF ENERGY SITES FORDEPARTMENT OF ENERGY FACILITIES

DOE STD-1 027-92 ~ HAZARD CATEGORIZATION AND ACCIDENT ANALYSISTECHNIQUES FOR COMPLIANCE WITH DOE ORDER 5480.23,NUCLEAR SAFETY ANALYSIS REPORTS

DOE-STD-1O66-97 FIRE PROTECTION DESIGN CRITERIA

DOE-STD-1O82-94 PREPARATION, REVIEW, AND APPROVAL OFIMPLEMENTATION PLANS FOR NUCLEAR SAFETYREQUIREMENTS

DOE-STD-1O83-95 i REQUESTING AND GRANTING EXEMPTIONS To NUCLEAR

SAFETY RULES

DOE-STD-1 107-97 KNOWLEDGE, SKILLS, AND ABILITIES FOR KEY RADIATIONPROTECTION POSITIONS AT DOE FACILITIES

DOE-STD-3003-94 BACKUP POWER SOURCES FOR DOE FACILITIES

DOE-STD-3006-95 PLANNING AND CONDUCT OF OPERATIONAL READINESSREVIEWS (ORR)

DOE-STD-3009-94 PREPARATION GUIDE FOR U.S. DOE NONREACTOR NUCLEARFACILITY SAFETY ANALYSIS REPORTS

DOE-STD-3020-97 SPECIFICATION FOR HEPA FILTERS USED BY DOECONTRACTORS

2.1.3.3 Manuals and Guides.

DOE M 232.1-1A OCCURRENCE REPORTING AND PROCESSING OFOPERATIONS INFORMATION

DOE M 471.2-1 MANUAL FOR CLASSIFIED MATTER PROTECTION ANDCONTROL

DOE M-5639 .6A-1 MANUAL OF SECURITY REQUIREMENTS FOR THE CLASSIFIEDAUTOMATED INFORMATION SYSTEM SECURITY PROGRAM

WHC-EP-0558 TEST AND EVALUATION DOCUMENT FOR DOT SPECIFICATION7A TYPE A PACKAGING

DOE G 420.1-X IMPLEMENTATION GUIDE FOR NON-REACTOR NUCLEARFACILITY SAFETY

2.1.3.4 Notices.

] DOE N441.1 ] RADIOLOGICAL PROTECTION FOR DOE ACTIVITIES

9

2WU Safe Storage System Revision OSvstem Requirements Document Mav 1998

2.1.3.5 Policy Documents.

DOE P 441.1 DEPARTMENT OF ENERGY RADIOLOGICAL HEALTH ANDSAFETY POLICY

DOE P 450.2A IDENTIFYING, IMPLEMENTING, AND COMPLYING WITHENVIRONMENT, SAFETY, AND HEALTH REQUIREMENTS

DOE P 450.4 SAFETY MANAGEMENT SYSTEM POLICY

2.1.4 Executive Orders

——! E~e~ut[v~ order 12856

_— .——. ..—FEDERAL COMPLIANCE WITH RIGHT-TO-KNOW LAWS AND

~ POLLUTION PREVENTION REQUIREMENTS~ Executive Order 12873 FEDERAL ACQUISITION, RECYCLING, AND WASTE

I PREVENTION

2.1.5 State and Tribal Laws and Agreements

This program tvill comply \vith all applicable State and Tribal ltiws. regulations. md agreementsState and Tribal law. regulation. tind agreement applicability is site specific.

2.1.6 Local

This programregulation applicability is site specific.

Ordinances

will comply with all applicable local laws and regulations. Local law and

2.2 Non-Government Documents

2.2.1 Standards

ANS1/ANS N13,1 GUIDE TO SAMPLING AIRBORNE RADIOACTIVE MATERIALS INNUCLEAR FACILITIES

ANSl/ANS-8.10-l 983, R88 CRITERIA FOR NUCLEAR CRITICALITY SAFETY CONTROLS INOPERATIONS WITH SHIELDING AND CONFINEMENTb

ANSl/ANS-8.1 -1983, R88 ~ NUCLEAR CRITICALITY SAFETY IN OPERATIONS WITH~ FISSIONABLE MATERIALS OUTSIDE REACTORS

~ANSl/ANS-8.20-1991 ~ NUCLEAR CRITICALITY SAFETY TRAINING~ANS1/ANS-8.3-l 986

I: CRITICALITY ACCIDENT ALARM SYSTEMS

~ANS1/ANS-8.7-l 975, R87 ~GUIDE FOR NUCLEAR CRITICALITY SAFETY IN THE STORAGE: OF FISSILE MATERIALS

ANS1/lEEE C2 --——–--------+I NATIONAL ELECTRIC SAFETY CODE

NFPA 70 NATIONAL ELECTRICAL CODE

ASME NQA-1 I QUALITY ASSURANCE PROGRAM REQUIREMENTS FORI NUCLEAR FACILITIES

ASME NQA-2 QUALITY ASSURANCE REQUIREMENTS FOR NUCLEAR\ FACILITY APPLICATIONS ~


3.0 SYSTEM REQUIREMENTS

3.1 System Description

The purpose of the ‘3% Safe Storage System is to provide safe long-term storage of the existingand future 97-1 ’33U materials that are the responsibility of DOE. The ‘~%J Safe Storage Systemwill modify or replace the existing systems used m process and store 33~Umaterial as necessary.A basic system concept has been developed based on analysis by the 97-1 Technical Team of theissues associated with accomplishing this mission and the assessment of the existing facilitiesand the state of the material stored in those facilities. This %J Safe Storage System specificallyaddresses the DNFSB recommendations as well as the needs of DOE in its larger role ofmanaging the complete life cycle of the ’33U material. This system specifically addresses theissues associated with the long-term storage and interfaces with disposition alternatives of 233U.

This SRD does not address the interim storage of this material up to the time that the long-termstorage begins. Interim storage is based on existing capabilities and facilities and the resolutionof issues related to interim storage requirements is specifically addressed in the 97-1Implementation Plan. An interim storage strategy and plan will be developed from thecharacterization effort reports that are specified by the Implementation Plan. Incomplete actionsremaining from the interim actions contained in the 97-1 Implementation Plan or resulting fromthe characterization efforts will be incorporated into the long-term storage PEP at the time thatdocument is issued.

233[T Safe Storage syStCITl~-–- —- —- —- —––-—____ -–-–-—__ . ____________,

External Sourcesm!

97.]~*J~,ln\cnlOrv

W IIsRE. HEL”/D[\i.J[er,.1(pr,,’c,,e” .1 ,,[ntr .,[<,

Trim\ler ICI,Nher \IIe l(Ir \I,rJ?c.,,ptk,[,,m WJ, [C ‘dgm[ Bene: .),,

-d”.17II,

—[ ,Cl ,__

,,.[cln 1,

-

1

\,.

p“ ‘astei’’ter’a’‘+\

~, ! ,subsv\[L,lrl /

External Destinations.———..—————..--. ——-—-—-~-.. _ .-—————————-—————.

~.;.__.Y___

Shinpln7 5S5c“$~nt.iln,:! Fw[iltic.

~t,urcc~ ,.—.—- . .. .

-—_——

Figure 3-1. ~33USafe Storage System Components and InterFaces

11


3.1.1 System Components

4The ~% Safe Storage System consists of four major subsystems. as depicted in Figure -1.These are:

3.7.1.1 Processing Subsystem. Where required to meet the ’33U Safe StorageStandard [DOE-SAIT-0067], the Processing Subsystem will convert the existing materialforms to the chosen long-term storage form(s), stabilize, and place the stabilized materialin storage containers meeting the requirements of the ’33U Safe Storage Standard forlong-term storage. This subsystem may also generate radioactive wastes containing ’33Uthat will be transferred to the Waste Management Subsystem for temporary storage anddispositioning. The specific materials to be processed will be determined by analyses andtrade studies as part of the conceptual engineering for this program.

3.1.1.2 Storage Subsystem. The Storage Subsystem will safely store ~33Umaterial fortin indefinite period. with a minimum design life of 50 years. The Storage Subsystemwill monitor the status of the material and provide the capability to place the material intoand withdraw the material from storage. Additionally, the subsystem will be capable ofhandling damaged containers and safely transferring them to the TransportationSubsystem for transport to a Processing Subsystem for restabilization and repackaging.The capability to remove selected containers for visual and other non-destructiveexamination within the Storage Subsystem facilities will also be provided.

Because of the potential for beneficial uses of the ~3?_Jmaterial, it will be possible torepeatedly withdraw the material for removal of selected isotopes for medical or otherbeneficial use and to place processed and packaged material back into storage. Thissubsystem may also generate some c?~u-bearing or other hazardous \\,astes as a by-

product of handling ~33Ustorage containers or from damage to such containers. Thiswaste \vould require processing bv the Waste Management Subsystem.

3.1.1.3 Transportation Subsystem. The Transportation Subsystem will ensure thatmaterial is safely transported between the Storage, Processing, and Waste ManagementSubsystems. Responsibilities include the placement in and removal of material packagesfrom appropriate shipping containers. all necessary shipping and receiving facilities,supplying requirements to and coordinating with external supplier systems for neededshipping ser~ices and shipping containers. and the necessary logistics functions to ensuresafe, orderly and efficient transportation operations in support of the other subsystems.The Transportation Subsystem will also interface with and manage on-site transportationof ~33Umaterials and waste materials.

3.1.1.4 Waste Management Subsystem. The Waste Management Subsystem willreceive waste materials from processing operations and any other ~33USafe StorageSystem activities that generate waste material. This will include any of the 97-1inventory of materials that may be subsequent y designated as waste (i.e., those materialsbelow the STLS as defined in DOE 5633.3B and subsequent revisions. such as thatproposed in the ,Memo of July 22.1996 from Edward J. McCallum and in ORNLITM-1359 1). Where appropriate and economical, the Waste .Management Subsystem will also

2WUSafe Storage System Revision OSvstem Requirements Document Mav 1998

recover and return ’33U material to the Processing Subsystem. The Waste Managementsubsystem will package and temporarily store the waste material as required. and handlethe transfer of the material to the DOE-Office of Environmental Management (-EM) fordispositioning.

The capacity of the Waste Management Subsystem at the facility designated to processthese materials will be sized to provide the capability to process these materials in thetime frame stated in EM program requirements.

3.1.2 System Interfaces

The ‘J~U Safe Storage System includes a number of interfaces between its subsystems as well asto external systems. Figure 3-1 (above) graphically illustrates the components of the ‘3% SafeStorage System and identifies those internal and external interfaces.

3.1.2.1 External /ntetiaces. The primary external interfaces to the ‘3% Safe StorageSystem are through the Transportation Subsystem with Commercial or DOE SpecialNuclear .Materiais (SFJM) Shippers Isee FiOure 3-1 ). As shown. Commercial or DOESISLMshippers will receive and transport ‘3% materials from existing ~% storagefacilities: the MSRE at Oak Ridge: and. potentially, from natural and depleted uraniumstorage locations to the ‘SSUSafe Storage System for processing and long-term storage.Additionally, Commercial and DOE SNM shippers will provide the primary interface fortransporting ‘3% and waste materials from the ‘3% Safe Storage System to applicableDOE-Materials Disposition (-MD) and beneficial use programs and facilities. This willbe accomplished using shipping containers supplied by the designated shipping containersupply source or the shipper as appropriate. Specific requirements for each externalinterface appear in Section 3.2.3.1 of this SRD.

3.1.2.2 /nterna/ h’ttetiaces. Interfaces internal to the %_’ Safe Storage System existbet~veen each major subsystem. namely Transportation. Processing. Stora~e. and Waste.Ylanagement. As shown in Figure 3-1. these interfaces involve the transfer of ‘~sl-lmaterials and associated waste byproducts from one subsystem to another via theTransportation Subsystem. In instances where Processing. Storage, and Waste,Management Subsystems are co-located. material transfers will be made directly fromone subsystem to another without the aid of the Transportation Subsystem. Specificrequirements for each internal system interface appear in Section 3.2.3.2 of this SRD.

3.1.3 97-1 233UMaterials Inventories

Most ‘~~Umaterials under the scope of the 97-i program are located at three DOE facilities:ORNL. INEEL. and LANL. Additionally, small quantities of DOE ’33U material can be found atvarious small sites and Universities throughout the nation. Tables 3-1 through 3-4 identify theunirradiated ’33U material inventories (as of May 1998) at various sites throughout the DOE

complex. Each of these materials will be evaluated against the Waste Threshold Criteria. whenestablished, to identify which of these materials are within the scope of the ‘S3U Safe StorageProgram. Consolidation of those materials within scope may reduce risk and cost. For completeinvenrm-y information refer to ORNL/TM - 13551. Strategy ofthe Future LTseand Disposition of

13


233U:History, Inventories, Storage Facilities, and Potential Uses. For ’33U characterizationinformation refer to ORNLiT.M- 13552, Strategy of the Future Use and Disposition of 233U:Technical Irzformation.

Table 3-1. Unirradiated %J Inventory at ORNL (as of May 1998)Location Chemicaf/Physical Form *U (kg) ‘U ~r#mt Total Qty. Number of

PP u) U (kg) PackagesBldg. 3019 UOX Powder (RCP-03)

UF4 with LiF

US08 Monolith (750/0 ‘“U)

UOX powder (Mound)

U-metal & alloys

U~O* Monolith

UOZ Powder

US08 Powder (RCP-02)

U~O~ powder (RDF-OX)

ZPR packets (U~Oe powder)

Misc. oxide powders

other miscellaneous forms

61.6

2.9

101.1

3.5

17.0

60.3

15.0

10.7

91.2

44.8

10.2

8.4

220

220

140

2-16

1-70

20

6

38

5-1o

7

1-42

1-42

67.4

3.2

1042.6

3.6

17.3

65.2

15.4

11.1

96.5

45.7

10.4

8.5

140

4

403

20

31

27

27

27

142

128

44

22

Table 3-2. Unirradiated ‘3~U Inventorv at INEEL (as of Mav 1998)Location Chemical/Physical Form ‘SU, (kg) “U oontent Total Qty. Number of

ppm ‘U) U (kg) Packages

CPP-749 Containers - Fuel and 300.80 TBD 306.64 40blanket rods containingUOJThOz pellets

CPP-749 Complete assembled seed 16.56 TBD 16.84 1module

RWMC 55gal&l10ga16M 34 TBD TBD 172Containers - Fuel andblanket rods contamlngUOz/lh02 pellets

RWMC Fabrication scrap – anti C 60 TBD TBD 1697clothing, grinding sludge,polyethylene material, rags,gloves, processingequipment components

‘U Safe Storage System Revision OSystem Requirements Document May 1998

able 3-3. Unirradiated ’33U Inventory at LANL (as of M~998)Location Chemical/PhysiosI Form ‘U, (kg) u Total Qty. Number of

content u, (kg) Packages(PPm %!)

0.049C13P

C211

C213

C214

C217

C21P

C527

C807

C862

C881

C887

C88H

K150

L523

MO11

MO1E

M391

M447

M44P

M467

M46P

M745

Compound/carbide/plutonium 239

Compound/dioxide/highpurity

Oxide

Compound/source

Compound/dioxide/impure/no major contaminant

Compound/dioxide/plutonlum 239

Compound/nitrate/impure/nomajor contaminant

Compound/tetraf luoride/impuremo majorcomammant

Compound/trioxide/multiplecontaminants/see remark

Compound/U308/high purity

Compound/U308/impure/nomajor contaminant

Compound/U308/History/archival sample

Combustible/celluloserag(s) /nonspecific

Nitrate solution/standard

Metal/high purity/high purity

Metal/high purity/encapsulated

Metal/high purity turnings/high purity

Metal/impure/impure/nomajor contaminant

Metal/impure/plutonium 239

Metal/impure turnings/impure/no majorcontaminants

Metal/impureturnings/plutonium 239

Metal/spec alloy/part

0.048

0.509

0.001

0.230

1.573

0.451

0.265

0.001

0.236

0.004

0.686

0.001

0.006

0.001

0.165

0.003

0.006

2.270

0.015

0.005

0.002

0.183

5-<10

5-<10

5-<10

5-<10

5-<10

5-<10

5 --=10

5 --=10

5-<10

5-<10

5-<10

5-<10

5-<10

5-<10

5-<10

5-<10

5-<10

5-<10

5-<10

5-<10

5-<10

5-<10

0.522

0.001

0.234

1.604

0.463

0.271

0.001

0.240

0.004

0.700

0.001

0.006

0.001

0.165

0.003

0.006

2.309

0.015

0.005

0.002

0.188

3

3

1

7

29

8

2

1

3

2

3

1

2

1

20

1

1

30

2

1

1

1

15


M74E Metal/spec alloy/ 0.061 5-<10 0.062 1encapsulated

M74H Metal/spec alloy/ 0.067 5-<10 0.068 7history/archival sample

N31O Noncombustible/graphite/ 0.115 5-<10 0.118 1nonspecific

N550 Noncombustible/ non- 0.011 5-<10 0.011 1actinide/nonspecif ic

N67W Non combustible/plastics/ o 5-<10 0 1kim wipes/approveddesignated waste

R41O Process Residue/hydroxide 0.179 5-<10 0.183 2precipitate/non-specific

R412 Process Residue/hydroxide 0.004 5-<10 0.004 1precipitate /multi-contammantlremarks

R780 Process residue/sweepings/ 0.007 5-<10 0.007 3screenings/non-specific

R78P Process residue/sweepingsi 0.002 5-<10 0.002 1screenings/plutonium 239

Table 3.4. Unimadiated 23SU~vent~rv ~[ ,$mall sites and E~te~al s“~te~~ (as of May 1998)Location Chemical/Physical Form ‘U, (kg) ‘U content Total Qty. Number of

ppm ‘U) U (kg) PackagesArqonne TBD TBD TBD 0.036 TBDEa;t

Argonne TBD TBD TBD 0.15433 TBDWest

Brook- TBD TBD TBD 0.0022 TBDhaven

Bettls TBD TBD TBD 0.412 TBDAtomic

~ Power‘ Laboratory

General TBD TBD TBD 0.172 2Atomlcs

Hanford TBD TBD TBD 0.079 3

LLNL TBD TBD TBD 3.321 50

PNNL TBD TBD TBD 0.048 15

Rocky TBD TBD TBD 0.008 8Flats

Oak Ridge TBD TBD TBD 0.881 TBDY-12

Mound TBD TBD TBD <0.005 TBD——-— ——

*WUSafe Storage System Revision OSystem Requirements Document May 1998

KnollsAtomic

MSRE Fuel

SavannahRiver

BostonCollege

Fort St.Vrain

LawrenceBerkeley

San DiegoStateUniversity

SanFranciscoState Univ.

TBD

TBD

TBD

TBD

TBD

TBD

TBD

TBD

TBD

TBD

TBD

TBD

TBD

TBD

TBD

TBD

TBD

TBD

TBD

TBD

TBD

TBD

TBD

TBD

<0.010

37.000

N/A

0.001

N/A

0.031

0.001

0.001

TBD

TBD

TBD

TBD

TBD

TBD

TBD

TBD

3.2 System Level Requirements

3.2.1 Performance

Lon -term storage capacity of the entire~

?~% Safe Storage System shall accommodate {TBD}kgof ‘3-lJ material as specified in the 233UDisposition Environmental Impact Statement (EIS)Record ofllecision (ROD), with {TBD} 70 margin to accommodate future ~33Umaterials.[Derived].

3.2.2 Functional

3.2.2.1 Compatibility with 94-1 Systems. The ‘~% Safe Storage System should becompatible with and utilize to the extent possible the systems being developed for the 94-1 Program. [Derived]

3.2.2.2 General Functionality. The system shall process. transport. and store 23%material. and interface with the disposition system for final disposition of the material.[Derived]

3.2.2.3 Transfer to Waste Disposa/ Programs. The system shall manage the ~~sLTbearing wastes generated by these activities and prepare those wastes for transfer to theappropriate DOE-EM waste disposal program. [Derived]

3.2.2.4 Monitor Materia/s and System Processes. The ’33U Safe Storage Systemshall monitor the material and subsystem processes for that material under any postulatedoperating conditions, including postulated design basis accidents (DBAs), to ensurequality and safe status of the product. protect against diversion of the material. and to

17

2=LJSafe Storage System Revision OSystem Requirements Document May 1998

protect workers from potentially harmful products used by, or produced by. the operationof the facilities. [Derived]

3.2.2.5 Assure Safe Operating Conditions. Conditions to be monitored shall be thosethat provide assurance of the safe condition of the stored material and those parametersthat are necessary to indicate when automated or operator actions are required to respondto off-normal conditions. [Derived]

3.2.2.6 Provide Package Surveillance CapabWty. In accordance with DOE-SAFT-0067. Criteria for Preparing and Packaging (_.Tranium-233-Bearing Materials for SafeLong-term Storage and Section 3.2.7.4. a package surveillance program shall be providedto assess the on-going condition of the packages against the mission requirements,including integrity and Materials Control and Accountability (MC&A) requirements.[DOE-SAIT-0067, DOE 5633.3B, Ch. III. 3]

3.2.2.7 Contain MaferiaL The 25SUSafe Storage System shall safely contain storedmaterial under all postulated design conditions. [Derived]

3.2.2.8 Retrjeve klaterja/. The % Safe Storage System shall be capable of retrievingmaterial following any DBA event. [Derived]

3.2.2.9 Provide Contamination Detection Capability. The ‘5@ Safe Storage Systemshall provide capability to detect contamination. [Derived]

3.2.2.9.1 Contamination Control—In the event of contamination, the ’33U SafeStorage System shall be capable of collecting samples for analysis. [Derived]

3.2.2.9.2 Transfer Provisions—The ‘% Safe Storage System shall includeprovision for the transfer of samples for analysis. as necessary. [Derived]

3.2.3 integration and Interface Control

3.2.3.1 External Interfaces.

3.2.3.1.1 97-1 233U Inventory/Commercial or DOE SNM Shippers/ntetiace-That portion of the 97-1 %_J material at existing DOE storage sites

(see Section 3. 1.3) not designated as waste or designated to be transferred fordisposition. in accordance with {TBD}, shall be transferred to commercial orDOE SNM shippers for transport to the ‘~sl_lSafe Storage System for processingand storage as appropriate. [Derived]

(1) Earlv Disposition. 97-1 material that is determined to be excess shall betransferred to shippers for transport to DOE-MD for early disposition.[Derived]

2*U Safe Storage System Rev/s/on OSystem Requirements Document May 1998

(2) Transt)ort Requirements. The ’33U Safe Storage System shall provideschedules and requirements to existing sites for the transport of 97-1materials. [Derived]

(3) Interface Requirements. Requirements for the 97-1 ’33U Inventory tocommercial or DOE SNM shippers interface shall be defined in {TBD}Interface Control Document (ICD). [Derived]

3.2.3.1.2 Oak Ridge Molten Sa/t Reactor Experiment/Commercial or DOESNM Shippers /ntetiac+Stabilized and packaged ‘S3U materials from the 94-1Program’s MSRE shall be transferred to commercial or DOE SNM shippers fortransport to the ‘S3U Safe Storage System. [Derived]

(1) Material and Packa~ina Requirements. The ~33USafe Storage Systemshall provide material and packaging requirements to the 94-1 Program forthe MSRE materials. [Derived]

(~) Interface Requirements. Requirements for the Oak Ridge Molten SaltReactor Experiment to commercial or DOE SNM shippers interface shallbe defined in {TBD } ICD. [Derived]

3.2.3.1.3 Natural and Depleted Uranium /Commercial or DOE SNM Shippers/ntetiac+Natural and/or depleted uranium at {TBD} existing storage sites shallbe transferred to commercial or DOE SNM shippers for transport to the ~3sUSafeStorage System for blending with ‘3% materials as required. [Derived]

(1) Reauired Materials. The ’33U Safe Storage System shall provide therequired material quantities. schedules and specifications to the naturaland depleted uranium storage sites. [Derived]

(~) Material Specifications. The natural and depleted uranium storage sitesshall provide materials quantities and specifications for available materialsto the ‘~sU Safe Storage System. [Derived]

(3) Interface Requirements. Requirements for the natural and depleteduranium storage sites to commercial or DOE SNM shippers interface shallbe defined in {TBD } ICD. [Derived]

3.2.3.1.4 Commercial or DOE SNM Shippers / 233USafe Storage System/ntetiace-Commercial or DOE SNM shi ers shall transport 97-1 ’33U materialsfrom existing storage sites and stabilized

l?‘-- U from the MSRE to the ’33U Safe

Storage System for processing and long-term storage. [Derived]

(1) Transport Requirements. The ~3% Safe Storage System shall provideschedules and material quantities to the commercial and DOE SNMshippers as required to arrange for transport. [Derived]

19


(~) Transfer of 233U Materials to DOE-MD. The ~33USafe Storage Systemshall transfer packaged ~3%_Jmaterials to commercial or DOE SNMshippers for transport to DOE-MD or beneficial use facilities.

(3) Transfer of 233U Waste to DOE-EM. The ‘S3USafe Storage System shalltransfer waste materials to the shippers for transport to EM Waste,Management facilities. [Derived]

(4) Natural and DeDleted Uranium. Commercial or DOE SNM ship~ers shalltransport natural and depleted uranium from {TBD} sites to the ‘S3U SafeStorage System for processing. [Derived]

(5) Detailed Interface Requirements. Detailed requirements for thecommercial and DOE SNM shippers to ‘% Safe Storage System interfaceshall be defined in {TBD} ICD. [Derived]

3.2.3.1.5 Commercial or DOE SNM Shippers /DOE-MD Interface

Commercial or DOE SNM shippers shall transport packaged ‘3SU materials fromthe ‘s~~ Safe Storage System to {TBD} DOE-iMD for final disposition. [Derived]

(1) MD Materials and PackaQinq AccerXance Criteria. DOE-MD shallprovide materials and packaging acceptance criteria to the ’33U SafeStorage System. [Derived]

(2) Interface Requirements. Requirements for the commercial or DOE SNMshippers to DOE-MD interface shall be defined in {TBD} ICD. [Derived]

3.2.3.1.6 Commercial or DOE SNM Shippers /DOE-EM Waste Management

/nterfac~ommercial or DOE SNM shippers shall transport waste materials.packaged to meet EM Waste Acceptance Criteria. from the ‘SSLTSafe StorageSystem to {TBD} DOE-EM Waste .Management facilities l;r ~lsposition.[Derived]

(1) DOE-EM Waste Acce~tance Criteria. DOE-EM shall provide wasteacceptance criteria. including waste form and packaging criteria andsources. for waste materials to the ~33USafe Storage System. [Derived]

(~) Interface Requirements. Requirements for the commercial or DOE SNMshippers to DOE-EM Waste Management interface shall be defined in{TBD} ICD. [Derived]

3.2.3.1.7 Commercial or DOE SNM Shippers /Beneficial Use lnterface-Commercial or DOE SNM shippers shall transport packaged ’33U materialsbetween the ~qlU Safe Storage System and {TBD} beneficial use facilities andprograms. [Derived]

2=() Safe Storage System Revis/on OSystem Requirements Document May 1998

(1) Interface Rectuirements. Requirements for the commercial or DOE SNMshippers to beneficial use program interface shall be defined in {TBD }ICD. [Derived] I

3.2.3.1.8 Sites and Facilities /233U Safe Storage System lnterfac+The ~%TSafe Storage System shall be located at {TBD} sites and facilities.

(1) Site and Facilitv Services. These sites and facilities shall provide {TBD}services to the ‘3% Safe Storage System. [Derived]

(2) Interface Requirements. Requirements for the sites and facilities to 23%Safe Storage System interface shall be defined in {TBD} ICD. [Derived]

3.2.3.1.9 233USafe Storage System/External Shipping Container Sourcelntetiac+The ’33U Safe Storage System Transportation Subsystem shall acquirecertified shipping containers from external sources in quantities that ensureprogram schedules. [Derivedl

(1) Interface Requirements, Requirements for the ’33U Safe Storage Systemto external shipping container source interface shall be defined in {TBD}ICD. [Derived]

3.2.3.2 Internal Interfaces.

3.2.3.2.1 Transportation Subsystem/Processing Subsystem lnterface-The Transportation Subsystem shall transfer 97-1 ‘3% and blending materialstoand from the Processing Subsystem. [Derived]

(1) Transfer of 233U Materials. The Processing Subsystem shall provideprocessed and packaged ‘s~LTmaterials to the Transportation Subsystemfor transport to the Storage Subsystem. [Derived]

,2) Transfer of Waste. The Processing Subsystem shall provide subsystem-generated waste for transport to the Waste Management Subsystem forprocessing and packaging for transfer to E.M Waste Management.[Derived]

(3) Interface Requirements. Requirements for the TransportationSubsystem/Processing Subsystem interface shall be defined in {TBD}ICD. [Derived]

3.2.3.2.2 Transpoflation Subsystem/Storage Subsystem Interfac+ TheTransportation Subsystem shall transfer 97-1 ~s3U materials to and from theStorage Subsystem. [Derived]

21

233USafe Storage System Revision OSystem Requirements Document May 1998

(1)

(2)

(3)

(4)

Transfer of 233U Materials. The Storage Subsys~em shall provideprocessed and packaged ‘q3U materials to the Transportation Subsystem.[Derived]

Transfer of Waste. The Storage Subsystem shall provide StorageSubsystem-generated waste for transport to the Waste lManagementSubsystem. [Derived]

Transfer of Damaqed Packaqes. The Storage Subsystem shall transferdamaged pockages. or packages opened as a result of on-going verificationof package integrity, to the transportation subsystem for transport to theprocessing subsystem for packaging. [Derived]

Interface Requirements. Requirements for the TransportationSubsystem/Storage Subsystem interface shall be defined in {TBD} ICD.[Derived]

3.2.3.2.3 Transportation Subsystem / Waste Management Subsystem/ntetiac+The Transportation Subsystem shall transfer waste from the Storageand Processing Subsystems to the Waste iManagement Subsystem, if thesesubsystems are not co-located. [Derived]

(1) Transfer of Waste. The Waste .Management Subsystem shall providepackaged waste to the Transportation Subsystem for transfer to EM WasteManagement. [Derived]

(~) Internal Waste Transfer Criteria. The Waste Management Subsystemshall provide internal waste transfer criteria to the TransportationSubsystem. [Derived]

(3) Interface Requirements. Requirements for the TransportationSubsystem/Waste Management Subsystem interface shall be defined in{TBD} ICD. [Derived]

3.2.3.2.4 Processing Subsystem /Storage Subsystem Intetiace f_TBR}-Forco-located Processing and Storage Subsystems, the Subsystems shall transferpackaged 97-1 ‘JSU materials directly between the two subsystems . [Derived]

(1) Transfer of Processed Materials. When co-located, the ProcessingSubsystem shall transfer packaged 97-1 ‘q3U materials directly to theStorage Subsystem. [Derived]

(2) Transfer of Packaqes Requirinq Additional Processing and/or Packaqirq.

When co-located, the Storage Subsystem shall transfer ‘%-J packagesrequiring additional processing and/or packaging directly to the ProcessingSubsystem. [Derived]

2mUSafe Storage System Revision OSystem Requirements Document May 1998

(3) Packaaina and Material Acceptance Criteria. The Storage Subsystemshall provide packaging and material acceptance criteria to the ProcessingSubsystem. [Derived]

(4) Transfer of Damaaed or Opened Packaaes. When co-located, the

Storage Subsystem shall transfer damaged packages, or packages openeddue to on-going verification of package integrity. to the ProcessingSubsystem. [Derived]

(5) Interface Recwirements. Requirements for the co-located ProcessingSubsystem/Storage Subsystem interface shall be defined in {TBD} ICD.[Derived]

3.2.3.2.5 Processing Subsystem /Waste Management Subsystem/ntetiace-For co-located Processing and Waste Management Subsystems, theProcessing Subsystem shall transfer subsystem-generated wastes directly to theWaste Management Subsystem. [Derived]

(1) Waste Acceptance Criteria. The Waste Management Subsystem shallprovide waste acceptance criteria to the Processing Subsystem. [Derived]

(~) Interface Requirements. Requirements for the co-located ProcessingSubsystem to Waste Management Subsystem interface shall be defined in{TBD} ICD. [Derived]

3.2.3.2.6 Storage Subsystem /Waste Management Subsystem Intetiact=For co-located Storage and Waste Management Subsystems. the StorageSubsystem shall transfer subsystem-generated waste directly to the WasteManagement Subsystem. [Derived]

(1) Waste Acceptance Criteria. The Waste Management Subsystem shallprovide waste acceptance criteria to the Storage Subsystem. [Derived]

(2) Interface Reauirements. Requirements for the co-located StorageSubsystem to Waste Management Subsystem interface shall be defined in{TBD} ICD. [Derived]

3.2.4 Information Systems

’33U Safe Storage System shall include a comprehensive information management system toensure rapid access to procedures, hazards information, and process status and provide acomprehensive material control and accountability record keeping, as specified in Section3.2.7.4. [Derived]

23


3.2.4.1 General.

I3.2.4.1.7 Database-A database shall be maintained to serve as a source ofrelevant information about stored materials and containers. For completeness,MC&A documentation should be coordinated with the database. [DOE-SA~-0067,4.5. 1]

(1) Classified Data Se~aration. A separate database that contains allclassified data or data that when combined is classified shall be providedand maintained. [Derived]

(a) Classification Guide. The % Safe Storage System classifieddatabase shall be classified in accordance with CG-SS-3.Classification Guide for Safeguards and Security Information.[Derived]

(2) ComDatibilitv. Data stored m the electronic database shall be in a form thatis directly shareable between DOE sites. [Derived]

(3) Data Architecture. The database shaIl employ an open systemsarchitecture that does not employ vendor specific interfaces or systemsoftware. [Derived]

(4) Transferability. The implementation of the ’33U Safe Storage System andits database shall employ an architecture that permits the transfer of ’33USafe Storage System data to DOE complex-wide users. [Derived]

3.2.4.1.2 Data Access Control—For each facility. management shall establishcontrols that limit access to the NIC&A accounting system and nuclear materialsaccounting data. [DOE 5633.3B]

3.2.4.2 Data Storage. flBR]

3.2.4.2.1 Material Transfer—The database shall include .MC&A materialtransfer data in accordance \vith DOE 5633.3B. Chapter II. Section 5. [DOE5633.3B. Ch. II. 5]

3.2.4.2.2 Material Location—The database shall include locauons of storedmaterials. [DOE-SAIW-0067, 4.5.2.d]

3.2.4.2.3 Analysis and Separation—The database shall include dates ofanalysis and/or separation for isotopes, if available, to allow calculation of futurecomposition. [Derived]

3.2.4.2.4 Material Physjcal Form—The database shall include description ofmaterial physical form (e.g., ’33U metal. oxide powder. or ceramic monolith), ifavailable. [DOE-SAIT-0067. 4.5.2 .a.2]

24

‘af.l Safe Storage System Revision OSystem Requirements Document May 1998

3.2.4.2.5 Moisture Content—The database shall include moisture content andconditions of the tests. [Derived from DOE-SAIT-0067, 4.5.2 .a.7]

3.2.4.2.6 Stabilization Test—The database shall include all stabilization testingresults. [Derived]

3.2.4.2.7 Processing Conditions—The database shall include specificprocessing condition(s). [DOE-SAIT-0067. 4.5.2 .a.6]

(1) Processing. Process conditions shall include. but are not limited to,stabilization temperature and atmosphere. [Derived]

3.2.4.2.8 Package Configuration— The database shall include packageconfiguration and number (and type) of containers in package. DOE-S AFT-0067.4.5.~.b~]

3.2.4.2.9 Packaging Date-The database shall include the date of packaging.[DOE-SAIT-0067. 4.5.2 .b.3]

3.2.4.2.10 lnitia/ Radiation Fie/d-The database shall include initial radiationfield (gamma and neutron at contact and 30 cm. (12 in.)). [DOE-SAFT-0067,4.5.2 .b.4]

3.2.4.2.71 Chemical Composition—The database shall include chemicalcomposition. if available. [DOE-SAFT-O067, 4.5.2.a. 1]

3.2.4.2.12 Isotopic Fraction—The database shall include the fissile isotopefraction or% fraction (in ppm), if uvailable. [DOE-SAIT-0067, 4.5.2 .a.4]

3.2.4.2.13 Materia/ Source-The database shall include [he source of the storedmaterial (facility that prepared the material) in its current form. [DOE-SA~-0067. 4.5.2 .a.5]

3.2.4.2.14 Package Identification Number—The database shall include theunique package identification number associated with each container data record.[Derived]

3.2.4.2.15 Surveillance Resu/ts—The database shall include surveillance resultsfor a {TBD} period. [Derived]

3.2.4.2.76 Inspection Tests Petiormed-The database shall include records ofthe inspection tests performed. [DOE-SAIT-0067, 4.5.2.c]

3.2.4.2.77 Individuals Performing Inspections—The database shail includerecords of the names of individuals performing inspections. [DOE-SAFI’-OO67,4.5.2.c]

25


3.2.4.2.18 Inspection Dates—The database shall include records of the dates ofinspections for a {TBD} period. [Derived from DOE-SAIT-0067, 4.5.2.c]

3.2.4.2.19 Fill Gas—The data base shall include fill gas composition and

pressure {TBR}on sealing. [Derived from DOE-SAFT-0067. 4.5.2.b. 1]

3.2.4.2.20 Elemental Concentration or Mass-The database shall include thequantity (mass) of material contents. [DOE-SAIT-0067, 4.5.2 .a.3]

3.2.4.2.21 Baseline Package-The database shall include baseline package(gross) weight and dimensions. [DOE-SAFT’-OO67. 4.5.2 .b.5]

3.2.4.2.22 Container Lot Identification /Vumber-The database shall includethe manufacturer lot identification number for each container. [Derived]

3.2.4.2.23 Other Relevant Information—The database shall include othera~’ailable information relevant to the material contents (e. g., major impurities.radiation level. etc. ). [DOE-SAFT’-O067. 4.5.2 .a.8]

3.2,4.3 Historica/ Records—Historictil records on packages shall be maintained for thelife of the packages. [DOE-SAIT’-OO67. 4.5.2.c]

3.2.5 Emergency Response Systems

3.2.5.1 Communications. %J Safe Storage System sites/facilities shall comply withthe general, planning phase. preparedness phase, and response phase requirements fornotification and reporting of Operational Emergencies. Energy Emergencies. andEmergency Assistance in accordance with DOE O 151.1. Chapter VIII. [DOE O 151.1(chg. 2). Ch. VIII]

3.2.5.2 Emergency Management System. ‘S~U Safe Storage System sites/facilities>hall develop and mamtain an integrated and comprehensi~re Emergency lManagementSystem IAW DOE O 151.1 Section 4. [DOE O 151.1 (chg. ~), Sect. 4a.]

3.2.5.3 Emergency Planning and Preparedness. : ‘3U Safe Storage Systemsites/facilities shall assess their emergency management needs to plan and implement acomprehensive emergency management program commensurate with the hazards present(i.e. consistent with a graded approach). [DOE O 151.1 (chg. ~). Sect. ~b.1

3.2.5.4 Emergency Response. ’33U Safe Storage System sites/facilities shall directappropriate emergency response actions within the area under their control and at thescene of any emergency and promptly notify local. State, Tribal, DOE and other regionalFederal agencies when events categorized m Operational Emergencies occur. [DOE O151.1 (chg. 2), Sect. 4c.]


3.2.5.5 Medical Support. Medical support shall be planned in accordance with DOE5480.8A, Contractor Occupational Medical Program. (or replacement directive) forworkers contaminated by hazardous material. [DOE 5480.8A]

3.2.5.6 Emergency Transition. System operation shall transition to a safe conditionupon emergency or serious off-normal events. [Derived]

3.2.5.6.1 Operator /ntervention-Transition of system operation to a safecondition under emergency or off-normal events should require little or nooperator intervention. [Derived]

3.2.5.6.2 Econon?ic Loss—System design should be such that material oreconomic loss is minimized as a result of emergency automated or manualtransition of process operations. [Derived]

3.2.5.7 Emergency Recovery. 23% Safe Storage System site/facility mitigative.cleanup, and restoration activities may begin prior to response termination [DOE O 151.1(chg. 2), Sect. 4d.]

3.2.5.7.1 Recovery Procedures—Specific recovery requirements andprocedures shall be established on a case-by-case basis. [DOE O 151.1 (chg. 2),Sect. 4d.]

3.2.5.8 Implementation. % Safe Storage System sites/facilities shall developimplementation schedules for full compliance with DOE O 151.1 that shall be submittedto the Operations/Field Office Manager for approval with the next annual EmergencyReadiness Assurance Plan. [DOE O 151.1 (chg. Z). Sect. 6.]

3.2.5.9 Operations/Field Oflice Manager Responsibilities. 23% Safe Storage SystemOperations/Field Office managers shall implement emergency management policy andrequirements. imd maintain programs and systems consistent with policy andrequirements. [DOE O 151.1 (chg. 2). Ch. I. para.8. ]

3.2.5.10 Site/Facility Manager Responsibilities. ’33U Safe Storage SystemSite/Facility managers shall develop, implement. maintain, and update. as necessary, anemergency management program commensurate with the facility specific hazards andconsistent with DOE directives and standards of performance. [DOE 0 151.1 (chg. 2),Ch. I, para.9.]

3.2.5.11 Operational Emergency Bas-GeneraL ‘3% Safe Storage Systemsites/facilities shall have an Operational Emergency Base Program that provides theframework for response to serious events involving health and safety, the environment.safeguards, and security. [DOE O 151.1 (chg. 2). Ch. II. para. 1.]

3.2.5.12 Operational Emergency Base Related Regulations and Plans. TheOperational Emergency Base Program shall provide for compliance with the regulationscited in DOE O 151.1, Chapter III. [DOE O 151.1 (chg. 2). Ch. HI. para.2. ]

27


3.2.5.13 Operational Emergency Base Planning. ’33U Safe Storage Systemsite/facility Operational Emergency Base planning shall be integrated, incorporateexisting plans, and address those areas identified in DOE O 151.1, Ch. III. [DOE O 151.1(chg. 2), Ch. HI, para.3.]

3.2.5.14 Operational Emergency Base Preparedness. ~33USafe Storage Systemsite/facility Operational Emergency Base preparedness shall be assured through training,drills. and exercises as detailed in DOE 151.1, Chapter III. [DOE O 151.1 (chg. 2), Ch.III. para.4]

3.2.5.15 Operational Emergency Base Response. ~s3USafe Storage Systemsite/facility re-entry planning shall include contingency planning to ensure safety of re-entry personnel, such as planning for the rescue of re-entry teams, in accordance withDOE 151.1, Chapter HI. [DOE 151.1 (chg.’ 2), Ch. III. para.5.]

3.2.5.16 Operational Emergency Hazardous Material Program. %T Safe StorageSystem sites/facilities may be required to establish and maintain a quantitative hazardsassessment. to be used to detlne the provisions of the Operational Emergency HazardousMaterial Program to ensure the program is commensurate with the hazards identified.[DOE O 151.1 (chg. 2), Ch. IV]

3.2.5.17 Operational Emergency Events and Conditions. ?3% Safe Storage Systemsite/facility initiating events that warrant categorization as Operational Emergencies shallbe included in the site/facility specific procedures. [DOE O 151.1 (chg. 2), Ch. V]

3.2.5.18 Public Affairs Policy and Planning. ’33U Safe Storage System siteslfacilitiesshall comply with the general. planning phase, preparedness phase, and response phaserequirements for providing accurate. candid, and timely information to site workers andthe public during all emergencies in accordance with DOE O 151.1. Chapter IX. [DOE O151.1 (chg. 2), Ch. LX]

3.2.5.19 Evaluations and Readiness Assurance. ‘S3LTSafe Storage Systemsites/facilities shall prepare Emergency Readiness Assurance Plans (ERAPS) todocument emergency planning and preparedness activities and develop needed resourcesand improvements. [DOE O 151.1 (chg. 2), Ch. X. para.3. ]

3.2.5.20 Emergency Readiness Assurance Appraisals and Assessments. ’33U SafeStorage System sites/facilities shall conduct an annual internal readiness assuranceassessment of their emergency management programs at least once every three years.[DOE O 151.1 (chg. 2), Ch. X. para.4.]

3.2.5.21 Contractor Requirements. I% Safe Storage System site/facility contractorsshall comply with all Comprehensive Emergency Management System requirementsidentified in DOE O 151.1, Attachment 1. [DOE O 151.1 (chg. 2), Att. 1]

28


3.2.6 Environment, Safety and Health

3.2.6.1 General Directives. The design, construction, and operation of all ’33U SafeStorage System subsystems and facilities shall, at a minimum, comply with thefollowingdirectives:

A.

B.

c.

D.

E.

F.

G.

H.

I.

J.

K.

DOE P 450.2A. Identifying, implementing, and complying with environmental.safety and health requirements [DOE P 450.2A]

DOE 5400.1. DOE Environmental Protection Program [DOE 5400.1 (chg. 1)]

DOE 5480.4. Environmental protection. safety, and health protection standards[DOE 5480.4]

DOE O451. 1A, National Environmental Policy Act Compliance Program [DOE0451.lA]

DOE 0460. 1.& Packaging and transportation safety [DOE 0460. 1A]

DOE O 440.1A. Worker protection management for DOE federal and contractoremployees [DOE O 440.1A]

DOE 5480.22. Technical safety requirements [DOE 5480.22]

DOE 5480.23. Nuclear Safety Analysis Reports [DOE 5480.23 (chg. 1l]

DOE 5481. IB. Safety analysis and review systems [DOE 5481. lB]

DOE 5480.21. Unreviewed Safety Questions [DOE 5480.21]

DOE 5820.2A. Radioactive Waste Management . [DOE 5820.2.4]

3.2.6.2 Fire Protection. The % Safe Storage System shall have a comprehensive fireand related hazards protection program that is sufficient to minimize the potential for:

A. the occurrence of a fire or related event [DOE 0420.1 (chg. 2)]

B. a fire that causes an unacceptable on-site or off-site release of hazardous orradiological material that will threaten the health and safety of employees. thepublic or the environment [DOE 0420.1 (chg. 2)]

c. vital DOE programs suffering unacceptable interruptions as a result of fire andrelated hazards [DOE 0420.1 (chg. 2)]

D. property losses from a fire and reiated events exceeding defined limits establishedby the DOE [DOE 0420.1 (chg. 2)]

29

2-(,/ Safe Storage System Revision OSystem Requirements Document May 1998

E. critical process controls and safety class systems being damaged as a result of afire and related events. [DOE 0420.1 chg. 2]

F. loss through structural considerations and fire suppression systems in accordancewith DOE-STD- 1066-97. [DOE-STD- 1066-97]

3.2.6.3 Radiological Protection. Facility operations shall be conducted in accordancewith DOE P 441.1 (Sec. 3), DOE N 441.1 (Sec. 6), DOE 5400.5 (See 10), and 10 CFR835. [DOE P 441.1. DOE N 441.1. DOE 5400.5 (chg. 2), 10 CFR 835]

3.2.6.3.1 Sampling Airborne Radioactive Materials—zJ3U Safe StorageSystem sites/facilities shall perform sampling for the presence of airborneradioactive materials in accordance with the procedures specified in AmericanNational Standards Institute (ANSI) N-13. 1-1969. [Derived]

3.2.6.3.2 Radiation Shielding. The ‘~% Safe Storage System shall providesufficient radiation shielding to ensure the continued safety of workers in thefacility under all design conditions, consistent with “as-low-as-reasonably-achievable” (ALARA) objectives. [Derived]

3.2.6.3.3 ALARA—The content of each RPP shall be commensurate with thenature of the activities performed and shall include formal plans and measures forapplying the ALARA process to occupational exposure in accordance with DOE5400.5. Subsection 10.a. [DOE 5400.5 (chg. 2), Subset. 10.a]

3.2.6.3.4 Key Radiation Protection Positions—~3% Site/Facility contractorsshall comply with the detailed qualification criteria for key radiation protectionpersonnel in accordance with DOE-STD- 1107-97. [DOE-STD- 1107-97]

3.2.6.4 Worker Protection. in addition to 29 CFR 1910 and 1926. till ‘~sU Safe StorageSystem subsystems shall comply with worker protection requirements specified in DOEP 450.4 (components 2 and 4) and as amplified in DOE P 450.2A (ImplementationPlans). [29 CFR 1910.29 CFR 1926. DOE P 450.4, DOE P 450.2A]

3.2.6.4.1 Worker Protection Program —All ‘~s~USafe Storage Systemsubsystems shall implement a written worker protection program that:

A. provides a place of employment free from recognized hazards that arecausing or are likely to cause death or serious physical harm to employees[DOE 0440. 1A]

B. integrates all requirements contained in paragraphs 4a through 41 of DOE0 440.1A [DOE 0440. 1.4]

c. ensures a comprehensive, construction, fire, firearms, and explosiveprotection program exists or is implemented with the objective of


providing an acceptable level of safety from fire and related hazards forDOE Federal personnel, contractors, and for the public. [DOE 440. 1A(Att. 1, Sect. 1-4)] I

3.2.6.4.2 Industrial Hygiene Program-All %J Safe Storage Systemsubsystems shall implement a comprehensive and effective industrial hygieneprogram to reduce the risk of work-related disease or illness at affected facilities.[DOE O 440.lA (Att. 1. Sect. 5)].

3.2.6.5 Material Handling. The addition or removal of material from ’33U Safe StorageSystem equipment and storage facdities shall be accomplished using handling equipmentthat minimizes the radiation exposure (internal and external) of operating personnelconsistent with ALARA. [DOE 5400.5 (chg. 2). Subset. 10.a]

3.2.6.6 Comprehensive Monitoring. All ‘S3U Safe Storage System subsystems andfacilities shall provide a comprehensive monitoring and surveillance capability for the in-process material and the containment systems for that material under any postulatedoperating conditions. including postulated accidents. [DOE 5400.5 (chg. 2). Ch. II. Sect.6 and 7]

3.2.6.6.1 Safety and Operating Status< onditions monitored shall includeparameters that provide an indication of safety status as well as operating status.[DOE 5400.5 (chg. 2). Ch. II, Sect. 6 and 7].

3.2.6.7 Nuclear Criticality Safety. All ‘3% Safe Storage System facilities shall have anuclear criticality safety program in accordance with the requirements of DOE O 420.1(chg.~) (Subset. 4.3.2 and 4.3.3). The program shall include the following, as aminimum: [DOE O 420.1 (chg. 2)]

.A. nuclear criticality safety e~’aluations for normal and credible abnormal conditionsthat document the parameters. limits. and controls required to ensure that theanalyzed conditions are sub-critical. [DOE 0420.1 (chg. 2)]

B. implementation of limits and physical and administrative controls identified bythe nuclear criticality safety evaluations. [DOE 5480.22 (Subset. 9.b)]

c. reviews of operations to ascertain that limits and controls are being followed andthat process conditions have not been altered such that the applicability of thenuclear criticality safety evaluation has been compromised. [DOE 5480.23 (chg.2), Subsets. 8a, 8.b, and 8.c; and DOE 5481. lB]

D. assessment of the need for criticality accident detection devices and alarmsystems, and installation of such equipment where total risk to personnel will bereduced. [DOE 5480.23 (chg. 2).Subset. 8a: and DOE O 420.1 (chg. 2), Subset.4.3.2]

31

230 Safe Storage System Revision OSystem Requirements Document May 1998

3.2.6.7.1 Nuclear Criticality A/arms-Existing ’33USafe Storage Systemsite/facility criticality alarm systems shall comply with existing ANSIrequirements. [DOE O 420.1 (chg. 2)]

3.2.6.7.2 New Facilities Design—New facilities to be used for ~33USafe StorageSystem shall be designed and tested in accordance with ANSI requirements.[DOE 0420.1 (chg. 2)]

3.2.6.7.3 Nuclear Criticality Safety in 0perations—L33U Safe Storage Systemsites/facilities shall conduct operations with fissile materials in compliance withthe criticality safety requirements of ANSVAmerican Nuclear Society (ANS) 8.1-1983 [DOE 0420.1 (chg. 2)]

3.2.6.7.4 Nuclear Criticality Safety Training—:33U Safe Storage Systemsites/facilities shall plan. conduct. and document Nuclear Criticality SafetyTraining in compliance with0420.1 (chg. 2)]

3.2.6.8 Pressure Safety, The ~~~~requirements of DOE O 440.2 chg.~440. 1A, Att. 1 (Sect. 6)]

the requirements of ANSI/ANS-8.20- 1991. [DOE

Safe Storage System shall comply with theregarding pressure safety requirements. [DOE

3.2.6.9 Hazard Prevention. The constructors and operators of the ‘?% Safe StorageSystem shall. in accordance with DOE 0440. 1A implement a hazardprevention/abatement process to ensure that all identified hazards are managed throughfinal abatement or control. [DOE 0440. 1A].

3.2.6.10 Performance Indicators and Analysis of Operations Information.

3.2.6.10.1 Performance Indicator Program— ‘3SU Safe Storage Systemsites/facilities shall establish a program that identifies, gathers. lerlfies. analyzestrends. disseminates, imd makes use of environment, safety. and health (ES&H)performance indicators to Improve the performance of DOE facilities, programs,and organizations. [DOE O 210.1]

3.2.6.10.2 Root Cause Analyses—~s~ ~L Safe Storage System sites/facilitiesshall gather. verify, analyze. trend, and disseminate ES&H performance indicatordata, including narrative data that can help assess performance. and whereappropriate perform root cause analyses. [DOE O 210.1]

3.2.6.10.3 Feedback Mechanisms—:3~ U Safe Storage System sites/facilitiesshall implement feedback mechanisms for identification and communication ofES&H good practices, lessons learned, and corrective actions. [DOE O 210.1]

3.2.6.10.4 Management Information Systen?-z33U Safe Storage Systemsites/facilities shall maintain a management information system containing

2mUSafe Storage System Revision OSystem Requirements Document May 1998

appropriate ES&H performance indicator data for historical reference. [DOE O210.1]

3.2.6.10.5 Program Assessments—~33 U Safe Storage System sites/facilitiesshall periodically assess ES&H performance indicator programs to verify thatindicators are accurately measuring performance and are resulting in improvedperformance. [DOE O 210.1]

3.2.6.10.6 Analytical Data-z3qU Safe Storage System site/facility contractorsshall comply with all of the above and use analytical ES&H data to basedecisions. establish goals, identify performance trends, provide earlyidentification of potential problems. and apply lessons learned and good practices.[DOE 0210. I]

3.2.6.11 Accident Investigations.

3.2.6.11.1 Investigation Procedures—zss U Safe Storage System sites/facilitiesshall conduct accident investigations in accordance with the practices andprocedures prescribed in DOE O 225. 1A [DOE 0225. 1A]

3.2.6.11.2 Type A /Type B investigations—z33U Safe Storage Systemsite/facility contractors shall support Type A and Type B investigations of”accidents at sites under their cognizance in accordance with DOE O 225.1A,Attachment 1. [DOE 0225. 1A. Att. 1]

3.2.6.72 Nuclear Safety Implementation Plan. Any determination by the ’33U SafeStorage System implementing organization that a specific requirement is not applicableto the facilities or activities addressed in the implementation pian for nuclear safetyrequirements shall be documented in the Nuclear Safety Implementation Plan to ensurethat the determination is clearly communicated. [DOE- STD- 1082-94]

3.2.6.12.1 Relief from Nuclear Safety Requirements—Relief fromrequirements that are clearly applicable shall be granted by an approvedexemption as discussed in Section 3.11 of DOE-STD- 1082-94. [DOE-STD- 1082-94]

3.2.6.12.2 Exemptions—The Nuclear Safety Implementation plan shall clearlyidentify any exemptions that have been approved or are being requested from thesubject requirements. [DOE-STD- 1082-94]

(1) Reauestina and Grantina DOE Nuclear Safetv Rules Exem@ions.

Requesting and granting exemptions to DOE nuclear safety rules shall beaccomplished in accordance with the procedures of DOE-STD- 1083-95.[DOE-STD-1O83-95]

33

*3U Safe Storage System Revsion 0System Requirements Document May 1998

3.2.6.13 National Environmental Policy Act (NEPA) Implementing Procedures.Exemptions to environmental regulations shall be evaluated in accordance with the DOENEPA Implementing Procedures (10 CFR Part 1021) whenever they will have asignificant environmental impact that has not been previously considered in a NEPAanalysis. [DOE-STD- 1083-95]

3.2.6.14 Planning and Conduct of Operational Readiness Reviews. ’33USites/Facilities shall implement the planning and conduct of Operational ReadinessReviews in accordance with DOE-STD-3006-93. [DOE-STD-3006-93]

3.2.6.15 Safety Analysis Reporting Implementation. ’33U Sites/Facilities shallimplement the Safety Analysis Reporting requirements of DOE 5480.23 in accordancewith DOE-STD-3009-94. [DOE-STD-3003-94]

3.2.7 Safeguards and Security

3.2.7.7 Safeguards and Security Program. The ‘3% Safe Storage System safeguardsand security program shall deter, prevent. detect. and respond to unauthorized possession.use. or sabotage of special nuclear materials trans orted. processed. or stored by the

?system in accordance with DOE O 470.1. This ‘q-U Safeguards and Security Programmay be part of the overall site Safeguards and Security Program. [DOE O 470.1 (chg. 1),Sect. 1]

3.2.7.2 Personnel Security. %J Safe Storage System sites/facilities shall ensure thatindividuals are processed for, granted, and retain a DOE access authorization only whentheir official duties require such access and that facility designs and procedures complywith the personnel security activity requirements of DOE O 472. lB. [DOE O 472. IB]

3.2.7.3 Review of Sensitive Activities. All 2% Safe Storage System facilities shallconduct an Operations Security (OPSEC ) review of sensitive activities and facilitieswhene~’er new construction is planned. [DOE O 470.1 (chg. 1). DOE O 47 1.2.4]

3.2.7.4 Materials Control and Accountability. All ~% Safe Storage Systemsubsystems shall include a materials control and accountability system to manage theinventory of ‘% material in accordance with the requirements of DOE 5633.3B. [DOE5633.3B]

3.2.7.4.1 Basic Requirements—

(1) General.

(a) Materia/s Contro/ and Accountability P/an. A Materials Control andAccountability (MC&A ) Plan shall be developed in accordancewith the requirements of DOE 5633.3B, Chapter I, Section 1 foreach ’33U Safe Storage System fkcility possessing nuclearmaterials [DOE 5633.3B. Ch. I. 1.el]

2=(J Safe Storage System Revision OSvstem Recwirements Document Mav 1998

(~)

(3)

(4)

(b) Marrauernent Approva/. The MC&A Plan, which includes the’33U Safe Storage System. shall be approved by the cognizantManager/Operations Office. [DOE 5633.3B. Ch. L 1e.]

(c) Minimum F?eauirements. The MC&A system for each ’33U SafeStorage System facility shall comply with the minimumrequirements for the control and accountability of nuclear materialsas specified in DOE 5633.3B, Chapter I, Section 1. [DOE 5633.3B.Ch. I, 1]

(d) /nternafiona/ Atomic Enerav Auencv (/AEA) and NRC Standards.

When appropriate and consistent with DOE regulatory goals, the’33U Safe Storage System shall use procedures, techniques. andstandards as promulgated by the IAEA and the NRC, in developingthe basis for nuclear material control. measurements. andmeasurement control. accounting, and statistical methods. [DOE5633.3B. Ch. 1. 1.0]

(e) American Societv for Testina and Measures (ASTM) and ANSIStandards. The ~33USafe Storage System shall use procedures.techniques. and standards as promulgated by ASTIM and ANSI,when such standards exist. in developing the basis for nuclearmaterial control, measurements. and measurement control,accounting, and statistical methods that are employed forsafeguarding of nuclear materials, unless otherwise directed byDOE directives. [DOE 5633.3B, Ch. I. 1.0]

Graded Safeguards. Each ‘1% Safe Storage System facility shall have agraded safeguards program in accordance with the requirements of DOE5633.3B. Chapter I. Section 2.. [DOE 5633.3B. Ch. L J.1

Materials Control and Accountability Requirements for Source and Other

Nuclear Materials. The materials control and accountability requirementsfor depleted uranium. source and other nuclear materials shall be asspecified in DOE 5633.3B, Chapter I. Section 3. [DOE 5633.3B. Ch. I, 3.]

Loss Detection Element Evaluation.

(a) Vu/nerabi/itv Assessment. .A vulnerability assessment shall beperformed for each ’33U Safe Storage System facility inaccordance with DOE 5633.3B. Chapter I, Section 4a. [DOE5633.3B, Ch. I, 4a.]

(b) Performance Testinq Each %’ Safe Storage System facility shallestablish and implement a documented testing program to verifymaterials control and accountability procedures and practices andto demonstrate that material controls are effective as specified in

35


DOE 5633.3B, Chapter I, sections 4.b.-4.d . [DOE 5633.3B, Ch. I,4.b.-4.d.] I

(5) Monitoring Proaram. Each ’33U Safe Storage System facility shallestablish a monitoring program to determine the status of nuclear materialinventories in accordance with the occurrence investigation and reportingrequirements specified in DOE 5633.3B, Chapter I, Section 5. [DOE5633.3B, Ch. I, 5.]

(6) Administrative Controls. For each ‘3SU Safe Storage System facility,management shall establish a graded program to ensure the integrity andquality of materials control and accountability systems and procedures,and to periodically review and evaluate these systems as specified in DOE5633.3B, Chapter I. Section 6. [DOE 5633.3B. Ch. 16.]

3.2.7.4.2 Materials Accountabi/ity—

(1) Accounting Svstems. Each % Safe Storage System facility shallestablish an accounting system in accordance with the requirements ofDOE 5633.3B, Chapter 11.Section 2. [DOE 5633.3B, Ch. H, 2]

(a) Materkd /nvenfories and Data. The accounting system shall tracknuclear material inventories, document nuclear materialtransactions. issue periodic reports, and assist with the detection ofunauthorized system access, data falsification. and material gainsor losses. [DOE 5633.3B, Ch. II, 2.]

(2) Physical Inventories. Each ~3sUSafe Storage System facility shallestablish a physical inventory program for nuclear materials in accordancewith DOE 5633.3B. Chapter II. Section 3. [DOE 5633.3B. Ch. II 3.]

(a)

(b)

(c)

Proqram Como/iance. Stored materials shall be inventoried inaccordance with the facility physical inventory program asspecified in DOE 5633.3B, Chapter H Section 3. [DOE 5633.3B.Ch. II, 3.]

Res~onskvWes. For each facility, there shall be documentedplans and procedures defining responsibilities for performinginventories and specifying criteria for conducting, verifying, andreconciling inventories of nuclear material. as specified in DOE5633.3B, Chapter II. Section 3a.(2). [DOE 5633.3B. Ch. II, 3.a.2]

Freauencv. For each facility, the frequency of physical inventoriesfor Category I and II Materials Balance Areas shall be inaccordance with DOE 5633.3B. Chapter II, Section 3.a.4 and 3.a.5.The inventory frequency may be reduced in accordance with the

*SU Safe Storage System Revision OSvstem Requirements Document Mav 1998

(3)

(4)

(5)

(6)

guidance in DOE G 5633.3B. Chapter VI. [DOE 5633.3B. Ch. II.3.a.4 and 3.a.5.]

Measurements and Measurement Control. Each ’33U Safe Storage Systemfacility shall implement a measurement and measurement control programfor nuclear materials in accordance with DOE 5633.3B. Chapter II.Section 4. [DOE 5633.3B, Ch. II. 4.]

Material Transfers. Each 2%-J Safe Storage System facility shall establisha program to account for internal and external facility transfers of nuclearmaterials in accordance with DOE 5633.3B. Chapter II. Section 5. [DOE5633.3B, Ch. II, 5.]

Material Control Indicators. Each ’33U Safe Storage System facility shallestablish a program to assess the material control indicators. as specifiedin DOE 5633.3B, Chapter II. Section 6, to assure detection of losses andunauthorized removals of nuclear materials. [DOE 5633.3B, Ch. II. 6.]

Documentation and Re~ortinq. Each ~ssU Safe Storage System facilityshall comply with the documentation and reporting requirements fornuclear materials as specified in DOE 5633.3B, Chapter II, Section 7.[DOE 5633.3B, Ch. H, 7.]

3.2.7.4.3 Materials Control—

(1)

(2)

(3)

(4)

(5)

General. Each %J Safe Storage System facility shall establish a gradedmaterials control program for access controls. material surveillance.material containment and detection in accordance with the requirements ofDOE 5633.3B, Chapter 111. [DOE 5633.3B. Ch. HI. 1.]

Plan Documentation. The materials control program shall be formallydocumented in the MC&A Plan. [DOE 5633.3B. Ch HI. 1.]

Access. Each ‘%-J Safe Storage System facility shall establish a gradedprogram for controlling personnel access to SNM areas and materials inaccordance with the requirements of DOE 5633.3B. Chapter 111.Section2. [DOE 5633.3B, Ch. HI. 2.]

Surveillance. Each ‘~% Safe Storage System facility shall establish agraded surveillance program for monitoring nuclear materials anddetecting unauthorized activities or anomalous conditions and forreporting material and facility status in accordance with the requirementsof DOE 5633.3B, Chapter III. Section 3. [DOE 5633.3B, Ch. III, 3.]

Controls Proctram. Each ‘3% Safe Storage System facility shall have adocumented program to provide controls for nuclear materials operationsrelative to Materials Access Areas, Protected Areas, Materials Balance

37

*WU Safe Storage System Revision OSystem Requirements Document May 1998

Areas, other authorized storage repositories, and processing areas inaccordance with the requirements of DOE 5633.3B. Chapter HI, Section 4.[DOE 5633.3B, Ch. III 4.]

(6) Detection/Assessment. Each ‘3% Safe Storage System facility shall havethe capability to detect and assess the unauthorized removal of nuclearmaterials in accordance with the requirements of DOE 5633.3B, ChapterIII, Section 5. [DOE 5633.3B. Ch. III 5.]

3.2.7.5 information Security. Each ‘3:U Safe Storage System site/facility shallestablish an Information Security Program for the protection and control of classified andsensitive information in accordance with DOE O 47 1.2A, and its associated “need-to-know” policy. [DOE 047 1.2A]

3.2.7.5.1 Access to Classified and Sensitive Unclassified lnformation—Each ‘3% Safe Storage System site/facility shall comply with the requirements ofDOE O 471 .2A. Section 4.a for access to classified and sensitive unclassifiedinformation. [DOE O 47 1.2A. Sect. 4a.]

3.2.7.5.2 Classified Information Systems-Classified information systemsshall comply with the requirements of DOE O 47 1.2A and DOE M 5639.6A-1.[DOE O 471.2A, Sect. 4.b.]

3.2.7.5.3 Deviations—Unless otherwise stated in DOE O 47 1.2A, deviationsfrom the requirements in DOEO471.2A shall be processed according to DOE O470.1, Safeguards and Security Program. [DOEO471.2.4, Sect. 4.d.]

3.2.7.5.4 Supplementary Directives—The following .Manuals supplement DOE047 1.2A and contain non-discretionary. mandatory Information SecurityProgram requirements. standards. ~nd procedures:

A. DOE M 471.2-1. Classified Matter ProtectIon And Control [DOE O471.2A, Sect. 4.e]

B. DOE JM5639.6A-1, .Manual Of Security Requirements For The ClassifiedAutomated Information System Security Program [DOE O 47 1.2A, Sect.4.e]

c. DOE “Technical Surveillance Countermeasures Procedural Manual,”(classified). [DOE 047 1.2A. Sect. 4.e]

3.2.7.5.5 Guides—The following Guides shall be used for discretionary, non-mandatory assistance in implementing the requirements of the above Manuals andDOE 0471 .2A.

A. DOE G 471.2-1, Classified .Matter Protection And Control [DOE O471.2A. Sect. 4.fl


B. “DOE OPSEC Procedural Guide.” [DOEO471.2A, Sect. 4.fl

3.2.7.5.6 Responsibilities and Authorities— Each %-J Safe Storage SystemInformation Security Program shall comply with the responsibility and authorityrequirements of DOE 047 1.2A, Section 5. [DOE 047 1.2A. Sect. 5.]

3.2.7.5.7 Program Management— Each %? Safe Storage System InformationSecurity Program shall comply with the program management requirements ofDOE O 471.2A, Chapter I. [DOE O 471.2A, Ch. 1]

3.2.7.5.$ Operations Security Program-Each ’33U Safe Storage System shallestablish an Operations Security (OPSEC) Program in accordance with therequirements of DOEO471.2A. Chapter II. [DOE 047 1.2A, Ch. II]

3.2.7.5.9 Classified Information Systems Security—Each ~s3U Safe StorageSystem Information Security Program shall protect classified information andunclassified information processed on classified systems against unauthorizeddisclosure or compromise in accordance with the requirements of DOE 047 1.2A.Chapter III and DOE M 5639.6A-1. [DOEO471.2A. Ch. III]

3.2.7.5.10 Protection and Control of Classified Matter-Each ’33U Safe

Storage System Information Security Program shall include procedures, facilities.and equipment to protect and control classified matter that is being generated.received. transmitted, used, stored, reproduced, or destroyed in accordance withthe requirements of DOE O 47 1.2A. Chapter IV and DOE M 471.2-1. [DOE O47 1.2A, Ch. IV]

3.2.7.5.11 Identification of Classified Information. Each ‘~~U Safe StorageSystem site/facility contractor shall identify classified information. documents ormaterial in accordance with the policy, responsibilities. authorities and proceduresspecified in DOE 5650.2B. [DOE 5650.2B (chg. 2). Section 3.]

3.2.7.5.12 Contractor Information Security Program-Each ’31J Safe StorageSystem site/facility contractor shall comply with the above information securityrequirements and the Contractor Requirements Document, Attachment 1 to DOEO 471.2A. [DOE O 471.2A. Att. I]

3.2.7.6 Unclassified Computer Security Program. Each ’33U Safe Storage Systemsite/facility shall establish an Unclassified Computer Security Program to protectunclassified computer systems and sensitive unclassified automated information inaccordance with the requirements of DOE 1360.2B. [DOE 1360.2B]

3.2.7.7 Risk Management. ’33U Safe Storage System sites/facilities shall base their

safeguards and security programs on vulnerability/risk analyses designed to providegraded protection in accordance with the asset’s importance or the impact of its loss,

39

2mLJSafe Storage System Rewsion OSvstem Requirements Document Mav 1998

destruction, or misuse. Risks to be accepted shall be identified and documented. [DOE O470.1 (chg. 1)]

3.2.7.8 Site Specific Characteristics. ‘3%-JSafe Storage System site/facility safeguardsand security protection programs shall be tailored to address site-specific characteristicsand requirements, current technology, ongoing programs, and operational needs. and toachieve protection levels that reduce inherent risk on a cost-effective basis. [DOE O470.1 (chg. 1), Ch. 1, para. 3]

3.2.7.9 Deviations Requirements. ‘7~USafe Storage System sites/facilities shall followthe procedures of DOE O 470.0. Section 4f for all deviations from Safeguards andSecurity Program directives. [DOE 0470.1 (chg. 1), Sect. 4fl

3.2.7.10 Standardization. New ’23U Safe Storage System facilit y designs shallincorporate the use of standardized safeguards and security equipment and systems wherepossible without compromising design flexibility or adherence to performance criteria.[DOE 0470.1 (chg. 1), Sect. 4:]

3.2.7.11 Threat. ~~% Safe Storage System sites/facilities shall use the “’Design BasisThreat Policy for the Department of Energy Programs and Facilities” with local threatguidance and vulnerability assessments for protection and control program planning.[DOE 0470.1 (chg. 1), Ch.1, para. 3]

3.2.7.12 Site Safeguards and Security Plan. ~33USafe Storage System SiteSafeguards and Security Pkm(s) shall depict the existing condition of safeguards andsecurity sitewide and by facility. establishing improvement priorities and resourcerequirements for necessary improvements. [DOE O 470.1 (chg. 1), Ch. 1. para. 4]

3.2.7.12.1 Plan Contents—Plans shall contain. as a minimum. the items outlinedin DOE O 470.1, Chapter. i. para.-l. [DOE O 470.1 (chg. 1). Ch. 1. para. 4]

3.2.7.13 Security Plan. ‘J3U Safe Storage System sites not requiring a Safeguards andsecurity Plan due to the limited scope of safeguards and security interests shall develop asecurity plan to describe the protection program in place. [DOE O 470.1 (chg. 1). Ch. 1.para. 4]

3.2.7.14 Plan Review. ‘3%J Safe Storage System site Safeguards and Security plansshall be reviewed and updated annually. [DOE O 470.1 (chg. 1). Ch. 1, para. 4]

3.2.7.15 Training Program. ~%1 Safe Storage System site/facility Safeguards andsecurity Training Programs shall encompass training in ( 1) Program Management. (2)Personnel security, (3) Protection Operations, (4) Materials Control and Accountability,and (5) Information Security. [DOE O 470.1 (chg. 1). Ch. 2, para. 3]

3.2.7.16 Training Standardization. ’33U Safe Storage System site/facility trainingmethodology and courses shall be standardized with the scope and level of training

2XU Safe Storage System Revision OSystem Requirements Document May 1998

provided to individuals tailored to their assigned duties and responsibilities and basedupon their prior safeguards and security experience and training. [DOE O 470.1 (chg. 1),Ch. 2, para. 3]

3.2.7.17 Unclassified Controlled Nuclear Information. ~33USafe Storage Systemsites/facilities shall ensure that unclassified controlled nuclear information is reviewed.marked, and protected. and that violations and infractions are identified and processed inaccordance with DOE O 471.1. [DOE O 471.1]

3.2.7.18 Training Records. %? Safe Storage Svstem sites/facilities shall implement astandardized training records management system for Safeguards and Security asdescribed in DOE 0470.1. Section 2, paragraph 31. [DOE 0470.1 (chg. 1), Ch. 2. para.31]

3.2.7.19 Safeguards and Security Awareness. ~31J Safe Storage System site/facilitysafeguards and security awareness programs shall incorporate site-specific safeguardstind security policies. procedures, and requirements. [DOE O 470.1 (chg. 1), Ch. 4]

3.2.7.20 Self-Assessment. ~ssU Safe Storage System sites/facilities shall performsafeguards and security self-assessments in accordance with DOE O 470.1, Chapter 10.[DOE 0470.1 (chg. 1), Ch. 10]

3.2.7.21 Performance Assurance. ’33U Safe Storage System sites/facilities shallassure performance of safeguards and security systems ancUor system components forthose systems providing essential protection for Category I and Category II specialnuclear material through performance assurance programs that provide for operabilityand effectiveness tests. [DOE O 470.1 (chg. 1). Ch. 3, para. 3]

3.2.7.22 Documentation. ’33U Safe Storage System sites/facilities shall documentsafeguards and security performance assurance through plans and PerformanceAssurance Reports in accordance with DOE 0.470.1. Chapter 3. paragraph 4. [DOE O470.1 (chg. 1), Ch. 3, P=d. 4]

3.2.7.23 Contractor Requirements. ’33U Safe Storage System site/facility contractorsadhere to the same standards for protection of materials, information. and other propertyof interest to the DOE Safeguards and security Program against loss. theft, sabotage, orother hostile acts, as those required of DOE elements and their personnel. [DOE O 470.1(chg. 1), Att. 1]

3.2.7.24 Protective Force Program. Each ’33U Safe Storage System site/facility shallestablish and implement a Protective Force Program in accordance with the policy,responsibilities and requirements specified in DOE 5632.7A. [DOE 5632.7A, Section 3.]

41

2=U Safe Storage System Revision OSvstem Requirements Document Mav 1998

3.2.8 Reliability, Availability, and Maintainability

3.2.8.1 Reliability. All ~q3USafe Storage System subsystems shall be designed with{TBD}% reliability to ensure the safe operation of all facilities and equipment.[Derived]

3.2.8.1.1 Re/iabi/ify A//ocatior?s-Rel iability allocations shall be distributed tosystem elements . [Derived]

3.2.8.2 Availability. All ‘S3(J Safe Storage System subsystems shall be designed toensure {TBD}% availability of equipment, replacements, and upgrades throughout allphases of the life cycle. [Derived]

3.2.8.3 Maintainability. The ’33U Safe Storage System shall be designed to ensuremaintainability of facilities and equipment throughout all phases of the life cycle.[Derived]

3.2.9 Human Factors

Operating facility. equipment control systems and emergency systems should be designed tocurrent human factors industry standards that have been approved by human factors specialists.[Derived]

3.2.10 Training

3.2.10.1

and Qualifications

Organization. Each ‘3% Safe Storage System operating contractor shallestablish one or more organizations to be responsible for the training of operatingorganization personnel. [ DOE 5480.20A, Ch. I. 2]

3.2.10.2 Organization/ Responsibilities. The training organizations) shall beresponsible for providing facility line management with the support necessary to ensure

that personnel in the operating organization are qualified to safely and effectively meetjob requirements. [DOE 5480.20A, Ch. I, 2]

3.2.10.2.7 Llocwnentation-The responsibilities, qualifications. and authority oftraining organization personnel shall be documented, and managerialresponsibilities and authority clearly defined as specified in DOE 5480.20A.Chapter 1, Section 2. [DOE 5480.20A. Ch. 1. 2.]

3.2.10.3 Subcontractor PersonneL Subcontractor personnelshall meet the qualification requirements for the job function to be performed as definedin DOE 5480.20A, Chapter I. Section 3. [DOE 5480.20A, Ch. I, 3.]

3.2.10.4 Personne/ Se/ection. Each ‘~% Safe Storage System operating organizationshall establish a process for selection and assignment of personnel into the operatingorganizationChapter IV.

in accordance with the requirements of DOE 5480.20A. Chapter I and[DOE 5480.20A. Ch. 1,4.. Ch. IV]

23U Safe Storage System Rewsion OSystem Requirements Document May 7998

3.2.10.5 Process. Each ’33U Safe Storage System operating organization shall definequalification requirements for personnel in each functional level based on the criteriacontained in DOE 5480.20A, Chapter I and Chapter IV. [DOE 5480.20A, Ch. I, 51]

3.2.10.6 Cetiification. Each %-J Safe Storage System operating contractor shallestablish a certification program whereby contractor nuclear facility managementendorses and documents, in writing, the satisfactory achievement of qualification ofpersonnel for key operations positions as specified in DOE 5480.20A. Chapter 1, Section6. [DOE 5480.20A, Ch. I, 6.]

3.2.10.7 Training. Each ‘3%.JSafe Storage System operating contractor shall providetraining to support qualification arid certification programs in accordance with therequirements of DOE 5480.20A. Chapter I, Section 7. [DOE 5480.20A. Ch. I, 7.]

3.2.10.7.1 Graded Approach—A graded approach shall be used to establish thesystematic approach to training for operations personnel, maintenance personnel,technicians. and the technical staff. [DOE 5480.20A. Ch. 1, 7.]

3.2.10.7.2 hnplementation #fatrix-A Training Implementation Matrix whichdefines and describes the application of the selection, qualification, certificationand training requirements of DOE 5480.20A shall be prepared by the contractoroperating organization. [DOE 5480.20A. Ch. I, 7.a.( 1)]

(1)

(~)

(3)

Trainin~ Res~onsibilitV. The Matrix shall clearly define the organization,planning, and administration of the qualification program and set forththe responsibility, authority, and methods for conducting training. [DOE5480.20A Ch. I, 7.a.( 1)]

Justification for Excet)tions. Suitable justification for exceptions shall beincluded in the .Matrix for any requirement not implemented. [DOE5480.20A Ch. 1. 7.a.( 1)]

Matrix Substitution. At some sites with several facilities. a combinedTraining Implementation Matrix may be submitted. [DOE 5480.20A. Ch.I, 7a.(l)]

3.2.10.7.3 Program Basis—The training and qualification program for nuclearfacilities should be developed on the basis of the hazards involved and riskassociated with the operation of the facility or activity. [DOE W80.20A. Ch. I7a.(2)]

3.2.10.7.4 Training and Qualification Neecfs-The level of detail of andcontent of the Training Implementation Matrix and content of the trainingprograms should reflect the training and qualification needs of these facilities toassure personnel are qualified to carry out their assigned responsibilities. [DOE5480.20A, Ch. 17a.(2)]

43


3.2.10.8 Operator and Supervisor Examination. Comprehensive written and oralexaminations and operational evaluations shall be prepared and administered, as specifiedin DOE 5480.20A, Chapter I, Section 8. to demonstrate that certified operator andcertified supervisor candidates possess the required knowledge and skills. [DOE5480.20A, Ch. 18.]

3.2.10.9 Operator and Supervisor Reexamination. Each ’33U Safe Storage Systemoperating contractor shall administer reexamination of certified and qualified operatorsand supervisors in accordance with the requirements of DOE 5480.20A. Chapter I,Section 9. [DOE 5480.20A, Ch. 19.]

3.2.10.10 Requalification. Operators and their immediate supervisors shall not beallowed to continue to function in qualified or certified positions if they have notcompleted all of the requalification or recertification program elements within the two-year continuing training cycle. [DOE 5480.20A, Ch. I, 10]

3.2.10.10.7 Administration-Regaining qualification or certification shall beadministered in accordance with the requirements of DOE 5480.20A, Chapter 1.Section 10. [DOE 5480.20A. Ch. I 10.]

3.2.10.11 Exceptions to Training Requirements. Exceptions to the trainingrequirements of DOE 5480.20A shall be permitted as defined in DOE 5480.20A, ChapterI, Section 11. [DOE 5480.20A, Ch. I 11.]

3.2.10.12 Extensions. An extension of qualification or certification may be granted topersons on a case-by-case basis in order to support operational and schedulecommitments in accordance with DOE 5480.20A. Chapter I, Section 12. [DOE5480.20A. Ch. I 12.]

3.2.10.13 Alternatives to Education and Experience Requirements. Workexperience may be substituted for education requirements and education and training maybe substituted for experience requirements in specific cases as defined in DOE 5480.20A.Chapter I, Section 13. [DOE 5480.20A. Ch. I 13.]

3.2.10.14 Record Requirements. Each %-J Safe Storage System operating contractorshall develop and implement administrative procedures that specify requirements for themaintenance of training, qualification, and certification records for operating organizationpersonnel. [DOE 5480.20A. Ch. I. 15]

3.2.10.14.1 Standardization of Training Records-The guidance in theNuclear Information and Records Management Association Guidelines forManagement of Nuclear Related Training Records, TG- 17 should be used to helpstandardize identification, handling, and storage of training records. [DOE5480.20A. Ch. I 15.1

3.2.10.14.2 Personnel Qualification and Certification Records+ualificationand certification of personnel shall be documented in an easily auditable format.

‘ml./ Safe Storage System Revision OSystem Requirements Document May 1998

At a minimum, individual record documentation shall include the data specified inDOE 5480.20A, Chapter I. Section 15 a. [DOE 5480.20A, Ch. I 15 a.]

3.2.10.15 Worker Protection Training. The constructors and operators of the ’33U SafeStorage System shall, in accordance with DOE O 440.1A, provide workers, supervisors,mmagers,VISltOrS,andworker protection professionals with worker protection training.[DOE O 440.lA]

3.2.10.16 Measurement Training Plan. Each facility shall have a documented plan forthe training of personnel who perform ’33U Safe Storage System measurements. [DOE5633.3B. Ch. II 4.c.( 1)]

3.2.10.16.7 Measurement—Each ~33USafe Storage System facility training

plan shall specify training, qualification, and requalification requirements foreach measurement method. [DOE 5633.3B, Ch. 114.c.( 1)]

3.2.10.16.2 Proficiency Demonstration—Each ~33USafe Storage Systemfacility shall have a documented qualification program that ensures thatmeasurement personnel demonstrate acceptable levels of proficiency beforeperforming measurements. [DOE 5633.3B. Ch. II ~.c.f~Jl

3.2.10.16.3 /?equa/Nication-Each % Safe Storage System facilityqualification program shall ensure that measurement personnel are requalifiedaccording to the requirements of the facility training plan. [DOE 5633.3B, Ch. II4.C.(2)]

3.2.10.77 Contractor Requirements Document. In addition to compl ying with theabove training requirements, each ’33U Safe Storage System management and operatingcontractor shall:

A.

B.

c.

D.

E.

Implement the requirements of DOE 5480.20A as they apply to the ilcility andthe position [DOE 5480.20A. Att. I.]

Prepare and submit a Training Implementation Matrix to the Operations Office.Manager for review and approval [DOE 5480.20A. Att. I.]

Prepare and submit procedures that establish the requirements for grantingexceptions to specific training or qualification requirements for an individual tothe Operations Office Manager for review and approval [DOE 5480.20A, Att. I.]

Provide written requests for certification extensions to the Operations OfficeManager for approval [DOE 5480.20A, Att. I.]

Perform periodic systematic evaluations of training and qualification programs.[DOE 5480.20A, Att. 1.]

45

2WUSafe Storage System Rewsion OSystem Requirements Document May 1998

3.2.11 Design and Construction

103.2.11.1 Operations Design. The ‘3% Safe Storage System shall be designed toperate in a manner coincident with the number of hours per day that the equipment is tobe used and to ensure that unattended equipment and any associated materials aremaintained in a safe and secure condition. [Derived]

3.2.11.2 Design Modifications. Modifications to facility design and constructionduring the design and construction phase shall conform to the requirements for new DOEfacilities in accordance with DOE 0420.1. [DOE 0420.1 (chg. 2)]

3.2.11.2.1 Design and Analysis—Facility and component design and associatedsafety analysis shall be conducted according to the requirements of the currentrelease of DOE 0420.1. [DOE 0420.1 (chg. 2)]

3.2.11.3 Natural Phenomena Hazards Mitigation. ‘3% Safe Storage System facilitiesshall be designed, constructed. and operated in accordance with DOE O 420.1 so that thegeneral public. workers. i.mdthe environment are protected from the impact of NaturalPhenomena Hazards (NPHs ), including hazards such as seismic. wind, flood. andlightning. [DOE 0420.1 (chg. 2)].

3.2.11.3.1 Natural Phenomena Hazards Approach—The overall ’33U SafeStorage System approach for NPH mitigation shall be consistent with the gradedapproach embodied in the Safety Analysis Reports (SARS). [DOE-STD- 1020-94(CH-1)]

3.2.11.3.2 Saf’ety C/assitications—The tipplication of NPH design requirementsto % Safe Storage System structures. systems. and components (SSCS) shall bebased on the life-safety or the safety classifications for the SSCS as established bysafety analysis. [DOE-STD- 1020-94 ~CH- 1)]

3.2.11.3.3 Safety Class SSCS—.A ‘s~U Safe Storage System site/facility SSC,failure of which may impair or adversely affect an operator action that is requiredfor safety during and following an NPH event. shall also be stabilized as a Safety-Class or Safety-Significant SSC for the purpose of selecting performance categoryin accordance with DOE-STD- 1021.93 [DOE-STD- 1021-93]

3.2.11.3.4 Win&Tornado Hazard Data—~’~ ~1Safe Storage System site/facility

windltornado hazard data shall be determined in accordance with DOE-STD-1023. [DOE-STD- 1020-94 (CH- 1)]

3.2.11.3.5 Flood Protection and Emergency Operations Plans—The designof ’33U Safe Storage System site/facility structural systems (i.e. exterior buildingwalls) shall be developed in accordance with DOE-STD- 1020-94 and otherapplicable regulations. [DOE-STD- 1020-94 (CH- 1)]

‘U Safe Storage System Rewsion OSystem Requirements Document May 1998

3.2.11.3.6 Site Investigations-The meteorologic, hydrologic, geologic,seismological and geotechnical characteristics of a 233USafe Storage Systemsite/facility and its environs shall be investigated in sufficient scope and detail toprovide reasonable assurance that they are sufficiently well understood to permitan adequate evaluation of the proposed or existing site, and to provide sufficientinformation to support the evaluations required by other DOE standards (e.g.DOE-STD- 1023 and DOE-STD- 1020, etc.,) for implementation of NPHmitigation requirements specified in DOE 5480.28. [DOE-STD- 1022-94]

3.2.11.3.7 Other Considerations—Mission im ortance and economic?considerations should also be used to categorize ‘3SU Safe Storage Systemsite/facility SSCS which require NPH. [DOE-STD- 1020-94 (CH- 1)]

3.2.11.4 Industry Codes and Standards. Where no specific requirements arespecified, model building codes or national consensus industry standards shall be used.[DOE 0420.1 (chg. 2)]

3.2.11.5 Minimization of Economic Loss. System design should be such that materialor economic loss should be minimal as a result of automated or manual termination ofprocess operations. [Derived]

3.2.11.6 Construction Materials. The ‘% Safe Storage System should be constructedof materials that retain their design performance for the life of the system. [Derived]

3.2. f 1.6.1 Work Area Coatings—Work area coatings should be designed tofacilitate decontamination. [Derived]

3.2.11.6.2 Industry Standards—Accepted industry design standards {TBD}should be followed in facility design. [Derived]

3.2.11.7 Design Requirements Application. The application of the most rigorousdesign requirements should be limited to those SSCS classified by safety analysis asSafety-Class or Safety-Significant consistent with DOE-STD-3009-94. [DOE-STD- 1021-93]

3.2.71.8 Applicability. The safety classification should be applied to specific ’33U SafeStorage System site/facility SSCS on a case-by-case basis and need not apply to an entirefacility. [DOE-STD-1O2O-94 (CH- 1)]

3.2.11.9 Existing Facilities. For existing facilities to be used for the ’33U Safe StorageSystem, evaluations (including aging assessments) of existing SSCS shall follow, or atleast be measured against the criteria provided in DOE-STD- 1010-94 and DOE-STD-1073-93, Chapter 4. [DOE-STD- 1020-94 (CH-1 ), DOE-STD-1O73-93 (Ch. 4)]

47

2=(J Safe Storage System Revision OSystem Requirements Document May 1998

3.2.77.70 Site hwestigation Program. An appropriate site investigation program shallbe developed in consultation with the geotechnical engineering representative of theproject team. [DOE-STD- 1022-94]

3.2.11.11 Analysis Techniques. ~33USafe Storage System sites/facilities shall followthe guidelines for a graded approach proportional to the complexity of the facility and thesafety systems relied on to maintain an acceptable level of risk in accordance with DOE-STD- 1027-92. [DOE-STD- 1027-92]

3.2.11.12 Part-time /nventory. ‘S?LTSafe Storage System sites/facilities that areinvolved with an inventory of hazardous materials that varies with time shall becategorized on the basis of their maximum inventory of hazardous materials. [DOE-STD-1027-92]

3.2.11.13 Electrical Design. ‘% Safe Storage System site/facility designs shallcomply with ANSI/IEEE C2. ,National Electric Safety Code. and NFPA 70. NationalElectrical Code. u tippropriate. [Derived from DOE 0420.1 (chg. 2)].

3.2.17 .13.1 Facility Safety C/ass E/ectrica/ Systems—Facility safety classelectrical systems shall be designed to the basic approach outlined in Section5.2.3 (Electrical) of DOE G 420.1-X, Implementation Guide for NonreactorNuclear Safety Design Criteria and Explosives Safety Criteria. [DOE 0420.1(chg. 2), 4.1.1.2]

3.2.11.14 Backup Power Sources. ‘S2USites/Facilities shall determine therequirements for, justify, acquire. and maintain backup power sources for Safe StorageSystem components and subsystems. where necessary. in accordance with DOE-STD-3003-94. [DOE-STD-3003-94]

3.2.11.15 Ventilation Systems. All ~7sU Safe Storage System facility ventilationsystems shall address control of 12r)Rnto allow sufficient time for its decay to a filterableisotope to prevent release to the environment. [Derived]

3.2.11 .15.1 Procurement and Testing of HEPA Fi/ters—Procurement andTesting of HEPA Filters for 2:~U Sites/Facilities shall be accomplished inaccordance with DOE-STD-3020-97. [DOE-STD-3020-97]

3.2.12 Life Cycle Asset Management (LCAM)

3.2.12.1 LCAM Approach. ’33U Safe Storage System sites/facilities shall use a value--added, quality driven, graded approach to life cycle asset management. [DOE 0430.1(chg. 1)]

3.2.12.2 LCAM Practice(s). ‘~% Safe Storage System site/facility assets managementshall be based upon best industry practice and shall be commenimportance of the tisset using a graded approach. [DOE O 430.

urate with the value and

(chg. 1)]

2MUSafe Storage System Rewsion OSystem Requirements Document May 1998

3.2.12.3 Performance Measures. ’33U Safe Storage System site/facility assetmanagement performance measures shall ensure formal. comprehensive, integrated.documented planning and control methods for the acquisition, use. maintenance, anddisposal of physical assets. including real estate. energy, and utilities. [DOE 0430.1

(chg. 1)]

3.2.12.4 Acquisition Approach. ’33U Safe Storage System sitesifacilities shall utilizean integrated. systematic approach to physical asset acquisition. [DOE O 430.1 (chg. 1)]

3.2.12.5 Project Management System. 7S3USafe Storage System sites/facilities shalluse a project management system based on effective management practices that issufficiently flexible [o Mow for the size and complexity of the project. [DOE O 430.1(chg. 1)]

3.2.12.5.1 Conceptual Design—:33 U Safe Storage System site/facility projectmanagement shall. prior to the commencement of conceptual design. include thefollowlng in project planning for approval:

A. mission need [DOE O 430.1 (chg. I )]

B. minimum technical functional requirements [DOE 0430.1 (chg. 1)]

c. proposed cost and schedule ranges [DOE 0430.1 (chg. 1)]

D. preliminary environmental strategy [DOE 0430.1 (chg. 1)]

E. identification of project technical and organizational interfaces [DOE O430.1 (chg. 1)]

F. integrauon \vith other proiects and wgencies. [DOE O 430.1 Ichg. 1)]

3.2.12.5.2 Execution—:77 L’ Safe Storage System site/facility projectmanagement shall. prior to the commencement of execution. include thefollowing in project planning for approval:

.4. project objectives [DOE O 430.1 ich:. 1)]

B. scope. schedule, and cost baselines. including contingencies [DOE O430.1 (chg. 1)]

c. life cycle cost analysis [DOE 0430.1 (chg. 1)]

D. preliminary safety assessment [DOE 0430.1 (chg. 1)]

E. project controls. including baseline change control, change controlthresholds. and statusing [DOE 0430.1 (chg. 1)]

49


F. completion of National Environmental Protection Act documentation priorto final commitment to an alternative [DOE O 430.1 (chg. 1)]

G. verification of performance criteria through test and evaluation [DOE O430.1 (chg. 1)]

H. design tilternatives. [DOE 0430.1 (chg. 1)]

3.2.12.5.3 Operation—:~7 U Safe Storage System site/facility projectmanagement shall. prior to opermon:

A. prepare a plan for turnover of a Facility [DOE 0430.1 (chg. 1)]

B. accomplish veritlcation of performtince criteria through test and evaluation[DOE 04.30.1 (chg. 1)]

3.2.12.5.4 Conduct of Operations— illrectl~es. plans. red/or procedures

relating to the conduct of operations ut DOE ti~cilities shall be developed inaccordance with DOE 5480.19. [DOE 5480. 19]

3.2.12.6 Operation and Maintenance Process. ~~~~1safe storage system siLe/facility

project management shall ensure that the process for the operation ~nd maintenance ofphysical assets meets the minimum requirements of DOE 0430.1. para. f. [DOE 0430.1(chg. 1J, pm. t]

3.2.12.7 Disposition Process. ‘;’ 1.’Safe S(orage System site/faciiit~ proiectmanagemen[ >nali ensure ~ha[ the Proce>> ror [ne disposition ot’ ph~~lc~l wsets meets themmimum reaulrements ~-It DOE O -H). 1. uml. :. \DOE O 430.1 \cnc. i 1.pwa. c)

3.2.12.8 Utility Services. ‘:; L’ SaI’e Storage Sysrem site/facility project management~hall ensure [hat u[ilit> wrvlces tire acquired md disposed of ~hrough J DOE primecontract. [DOE O 430.1 ichg. 1). pm-a. HI

.::3.2.72.9 Asset Database. ‘-- L’ Sd’e Storage System site/faclii~y prolec[ mmugementshall ensure that the corporate physical assets database is maintained m a completeinventory of DOE physical usets ~t the si~e/facility. [DOE O 430.1 (chg. 1). para. i]

3.2.12.10 Compliance. ’77U S~fe Storage System site/faciiity project management shallensure that all applicable Federal. state, and local laws and regulations are followed in theacquisition. operation. maintenance. and disposition of phvsical assets at the site/facilitv.[DOE 0430.1 (chg. 11.para. j]

3.2.72.11 Logistics. Each “~LTSafe Storage System site/facility shall provide logisticsSupport for its respective operations, [Derived].

50

2-USafe Storage System Revision OSystem Requirements Document May 1998

3.2.13

3.3.1

3.2.12.12 Decontamination and Decommissioning.

3.2.12.12.1 Component Decontamination—System components should bedesigned to be decontaminated with minimal generation of hazardous andradioactive wastes. [Der~veal]

3.2.12.12.2 Decontamination So/utions—Decontamination solutions should berecycled to reduce waste generation. [Derived]

3.2.12.12.3 Minimal EffoR to D&D-The ~33LTSafe Storage System should bedesigned to be decontaminated and decommissioned with the least possible effortand cost at the end of its operational life. [Derived]

3.2.12.72.4 Federal Requirements and Orders—.Any planned action ofdecontamination and decommissioning shall adhere. if applicable. to requirementsof the Part B Permit issued by the host state under provisions of 40 CFR 260-268and Executive Orders+ specially 12856. Federal Compliance \vith Right-to-Know-Luws and Pollu[ion Prevention Requirements (3 August 1993). and 12873.Acquisition. Recycling. and Waste Prevention (20 October 1993). [40 CFR 260-268. Executive Order 1X56. Executive Order 12873]

Non-Federal Laws, Agreements, and Ordinances

3.2.13.1 State and Tribal Laws and Agreements. The ’33U Safe Storage System shallcomply with all applicable State and Tribal laws, regulations. and agreements. [Derived]

3.2.13.2 Loca/ Ordinances. The ’33U Safe Storage System shall comply with allapplicable local laws and regulations.

3.3 233UProcessing Subsystem

Performance

3.3.1.1 Processing Capacity and Capability. Thethe 97-1 material at a rate of {TBD} to the final form

public safety are not compromised. [Derived]

Requirements

Processing Subsystem shall processwhile ensuring that personnel and

3.3.7.7.1 Isotope Separation for Beneficial Use. The 233U Safe StorageSystem shall have {TBD} capability for isotope separation for beneficial use.[Derived]

3.3.7.1.2 Duration of Processing Capability—The capability to processmaterial that is not in a form compatible with the ’33U Safe Storage Standard shall

be required only until the material is processed and maybe decommissioned onceprocessing is complete. [Derived]

51

233USafe Storage System ,:ewsion OSystem Requirements Document May 1998

3.3.7.2 Stabilization Capability. The Processing Subsystem shall be capable ofstabilizing stored materials and repackaging damaged or opened storage containersduring the entire ‘s~U Safe Storage System 50 year operating life. [Deri\’ed]

3.3.1.3 Variant Materials Processing. The Processing Subsystem shall process materialvariants as defined in Section 3.1. [Derived]

3.3.2 Functional

3.3.2.1 Receive Materia/s. ,Materlals shall be received from existing interim storage forprocessing via the Transportation Subsystem. [Derived]

3.3.2.2 Transfer to External Systems. Llpon completion of processil ~ged

materiuls shall be ~ransferred to the Transportauon Subsystem for transpc.. ..J one of theexternal systems identified in SectIon 3.1. [Deri\ed]

3.3.2.3 Remove from Packaging Containers. “The Processing Subs} \tem shall open[he packaging containers that do not meet the reqwements of the Storage Standard[SAIT-0067] ~nci place the material contents into \uitable containers. [Derived]

3.3.2.4 Convert to Stable Long-term Forms. \Vhere the materiul does t meet therequirements of the ~~q~Storage Standard (DOE- SA~-0067’). the Processing Subsystemshall convert 97-1 material from its present form to J stable form that meets the criteria ofthe Storage Standard. [I)OE-SAIT-0067]

3.3.2.5 Stabi/ize for Packaging. The Processing Subsystem shall perform anynecessw~’ ~t~bl]iztition for the pre-trexmevr ot mmerial prior to paciwglng to ensure [htit(he mxerid meets DOE-SAFT-006- .J from DOE-SA~-0067]

3.3.2.6 Packageg to 233LJSafe S:-, dge Standard. Packayng shall ccmpi: Ivith therequirements ~pecItleu in DOE-S .+fl-0067. [Derllea]

3.3.2.6.1 Package Labe/ing—Ewh storage conmmer shall be permanently mduniquel: labeled in ~ccordmce ~vlth DOE-S .MT-0067 [DerlIeci]

3.3.2.7 Handle Packages. The Prwesslng Sub~: ~tenl ~n~d hunaie :nawrld pxlwges .I>received from the 97-1 inventory. md the packaging resulting from processing activities.[Derived]

3.3.2.8 Stage MateriaL The Processing :.ubsystem shall provide temporary storage forreceived materials. in-process materiais. and products of the process. [Derived]

3.3.2.9 Collect Waste Byproducts. The Processing Subsystem shall collect byproductsfrom waste processing. [Derived]

3.3.2.9.1 Segregate, Pretreat, and Transfer Wastes—The ProcessingSubsystem should segregate hazardous and radioactive wastes received from

2aU Safe Storage System Rev/s/on OSystem Requirements Document May 1998

waste processing by type. pre-treat as necessary, artd transfer these wastes to a co-Iocated Waste Management Subsystem or to the Transportation Subsystem fortransport to the Waste .Management Subsystem. [Derived]

3.3.2.10 Characterize /l#ateria/s. The Processing Subsystem shall examine materialdocumentation to confirm that materials received from existing storage facilities meetmaterial acceptance criteria. [Derived]

3.3.2.10.1 Sampling Capability—Process ing and characterization activities shallinclude sampling capabilities to verify the state of materials. M required.[Derived]

3.3.2.10.2 Non-Destructive Assay (NDA) Capabilities—NDA capabilities shallbe provided to verify the integrity of the packaged materials. [Derived]

3.3.2.10.3 Transfer l%ovisions—Provi sions shall be made to transfer samples~or~dditiontil analyses. M necessxy. [Deri\red]

3.3.2.11 Open Containers. The Processing Subsystem shall open container puckageswhen \varran[ed. as specified in DOE-SMT-0067. [Derived]

3.3.2.12 Provide Blending Capabilities. The Processing Subsystem should include thecapability to blend materials. as required. {TBR} [Derived]

3.3.3 Integration and Interface Control

See System-level Requirements (Section 3.2.3).


See S:\tem-ie\el Requirements (. Section 3.2.-!)


See System-Le\el Requirements (Section 3.2.5’).

3.3.6 Environment, Safety, and Health






53

233USafe Storage System Rev/s/on OSystem Requirements Document Mav 1998

3.3.9 Human Factors

See System-Level Requirements (Section 3.2.9)

3.3.10 Training and Qualification

See System-1evel Requirements tSection 3.2. 10).


In adciitlon to System-le\rel Requirements lden~ltied in Section 3.2.11. the following Design ~..dConstructIon requirements tipply [o the Processing Subsystem.

3.3.11.1 Design Life. The design life ot’ the storage containers to be used by the ‘SSL’Processing Subsystem shall meet the requirements of the DOE-S. MT-0067. [Derived]

3.3.12 Life Cycie Asset Management (LCAM)

See S\stem-le\’el Requirements (Section 3.2. l:).

3.3.13 Non-Federai Laws, Agreements, and Ordinances

See System Level Requirements (Section 2.2. 13)

3.4 Storage Subsystem Requirements

3.4.1 Performance

3.4.1.2 Temporary Storage Capacity. The Storage Subsystem shall hti~e {TBD} 7C

c~pxity for temporm-y s~orage. [Derived]

3.4.1.3 Package Handling Throughput. The - ‘U Storage Subs>>[em snail be cdp~bie. . .

of emplacing and retrie~lng {TBD} packages of materials within {TBD timeframe}.[Derived]

3.4.2 Functional

3.4.2.1 Receive Packaged /14ateria/s. The Storage Subsystem shall receive ~33LTpackages for storage tl-om the Transportation Subsystem or a co-located processingsubsystem. [Deri\red]

‘U Safe Storage System Rev/s/on OSystem Requirements Document May 1998

3.4.2.2 Identify Packaged Materials. The Storage Subsystem shall identi@ ’33Upackages that are permanently and uniquely labeled in accordance with DOE-SAFT-0067. [Derived] I

3.4.2.3 Transfer Packaged Materials. The Storage Subsystem shall be capable oftransferring packaged materials to the Transportation Subsystem. [Derived]

3.4.2.4 Safely Store Packaged 233U /l#ateria/s. The Storage Subsystem shall ensure thesafe condition of the materials in accordance with the surveillance requirements ofSection 3.2.2. [Derived]

3.4.2.5 Retrieve 233UPackages from Storage. The Storage Subsystem shall remove~33Ustorage packages from storage for periodic inspection. transfer to beneficial use ordisposition or return to a processing facility. [Derived]

3.4.2.6 Collect, Segregate, Package, and Transfer Waste. The Storage Subsystemshould collect. segregate. and package wastes generated from storage operations andtransfer these wastes to a co-located Waste Management Subsystem or to theTranspommon Subsystem for transport to the Waste >Ianagement Subsystem. [Derived]

3.4.2.7 Handle Damaged Packages. The Storage Subsystem shall be capable ofhandling \including overpacking and decontaminating Jdamaged or leaking packages.[Derived]

3.4.2.8 Provide Surveillance Capability. The Storage Subsystem shall provide apackage sumeillance program in accordance with the requirements of Section 3.2.2.6[DOE-SAn-0067]

3.4.2.9 Transfer of Materials to Staging Area. The Storage Subsystem shall transfer23~Ucontainers from [he mrmsportatlon shipping recel~ing area to d staging ~re~. asnecessary. ~Derlved]


See System-le\rel Requirements (Section 3.2.3).


See System-level Requirements [Section 3.2.4).


See System-1evel Requirements (Section 3.2.5).

55

233USafe Storage System Rev/s/on OSvstem Requirements Document Mav 19!?8


In addition to System-1evel Requirements Identified in Section 3.2.6, the following requlremen~sapply to the 2~sLTStorage Subsystem.

3.4.6.1 Critically Safe Storage Arrays. 131USufe Storage System sites/facilities sha!.store tissile materials in critically safe stori.ige w-rays. in accordance with therequirements of ANSI N 16.5-1987. [DOE O 420.1 (chg. 2)]

3.4.6.2 Radiation Shie/ding. The effects of radiation shielding within the critically sat’e~tora~e arrays shall be considered. [DOE O 420.1 (chg. J )]


See Sy~tem-le\ei Requirements tSectIon 3.J.71.


See S~\tem-ie\el Requirements (Section 3.G.S ).

3.4.9 Human Factors

In addition to System-le\el Requirements identified in Section 3.2.9. the following HumanFactors requirements apply to the Storage Subsystem.

3.4.10

See S!

3.4.11

3.4.9.1 Operator Intervention. The Storage Subsystem should require no operator!nter\ention during normtil o~eratlon t~[her thun routine monitoring. except \vhen addingor removing materi~l from \toruge or \\”hen mwntalning storage system equipment.

(Derllecil

Training and Qualification

\tem-ie\el Requirements (. Section 5.J. !0).

Design and Construction

See System-le\el Requirements iSection 5.2. ! 1i.


See System-level Requirements (Section 5.2. 12).

3.4.13 Non-Federal Laws, Agreements, and Ordinances


2XU Safe Storage System Rewsion OSystem Requirements Document May 1998

3.5 Transportation Subsystem Requirements

3.5.1 Performance

The Transportation Subsystem shall have an operating life of not less than 50 years. [Derived]

3.5.2 Functional

3.5.2.1 Receive Materials. The Transportation Subsystem shall receive materialspackages from external shippers and internal ‘3SU Safe Storage System subsystems.[Derivedl

3.5.2.2 /derWfy Materials. The Transportation Subsystem shall identify ’33U packagesthat are permanently and uniquely labeled in accordance with DOE-SAIT-0067.[Derivedl

3.5.2.3 Transfer Materials between Subsystems. The Transportation Subsystem shalltransfer materials between subsystems. including handling and logistics. except whenexternal transfer is required. [Derived]

3.5.2.4 Coordinate External Shipping. The Transportation Subsystem shall coordinateexternal shipping and ensure that packages meet all regulatory requirements. [Derived]

3.5.2.5 Overpack for Shipment. The Transportation Subsystem shall place materialcontainers received from other subsystems into proper transport overpacks for shipmenttind remove these overpacks at the destination. as necessary. [Derived]

3.5.2.6 Provide Temporary Storage. The Transportation Subsystem shall provide thecapability to temporarily <tore material packages prior to shipping and on receipt.[Derived]

3.5.2.7 Acquire Shipping Containers. The Transportation Subsystem shall acquireneeded shipping containers that meet all requirements for shipping 97-1 materials.[Derived]


See System-level Requirements (Section 3.2.3)




In addition to System-level requirements identified in Section 3.2.5, the following EmergencyResponse requirements apply to the Transportation Subsystem.

57

233USafe Storage System Rev/s/on OSvstem I?eauirements Document Mav 1998

3.5.5.1 Regulatory Compliance. ‘3~U Safe Storage transportation systems shall bedesigned to facilitate the implementation of the objectives of DOE O 151.1 chg.~ 1regarding DOE transportation systems emergency response capabilities. [DOE O 151.1(chg. 2) chg.~]

3.5.5.2 Medical Resources. The Transportation Subsystem shun have uccess to medicdresources to support regultir physlcds and drug testing for DOT drivers. [Derived fromDOEO 151.1 (chg. 2)]


in addition to System-level requirements (see Section 3.2. 6 J. the following Safety md Heulthrequirements appiy to the ‘s~ll Transportation Subsystem.

3.5.6.7 Confinement. P!acement or removal of”- U storage canisters into and from.:2

[ransport contwners ~hould be xcompilsheci In J controlled en~lronment to Iimlt thereieose 01 materl~l. [Derl\eu]

3.5.6.2 Off-site Transfers. Ex-h oif-.l[e package und shipment of hazardous materialsshall be preptired in complimce with DOE O 460. 1.A[Subsets. 4.J. ( 1) und (4)] ondapplicable tribal. state. tind local regukttions not otherwise preempted by DOT. [DOE O460.1,4. -1.a.(1)]

3.5.6.3 Type A Radioactive Material Packaging. In addition to packaging authorizedby the H~zardous Materiels Regulations. each person who offers for transportation aType .+ quantity of radioactive mtiterlds LAOmay use u commercially procured Type .4packagn:. J pxhge quditied M LL:enerd T) pc ,3 md listed in \VHC-EP-0558 ( ‘Testmd e~oluxlon of document for DOT Specification ‘.A Type .+ Packaging” ). or a T>pe Bpacka:lng cemfied by the Headquwters Ccr~lt}lng Officifii ~>rXRC. {DOE O 460. 1.+.4 LA. (41(J): i\ ’HC-EP-055S. .Jitt. I IS LI’Dsec. ~,JI]

3.5.6.3.7 Retesting—Packaging [ested by and purchused from commercial~ources do not require re-(estln: by DOE contractors: ho~ve~’er. the requiredJocumenu.mon on design. testing. ~nd use shall be in the possession of the user.iDOE O 46(1.}.4. J u.~-l)(a): WHC-EP-055S. .\[t. 1 ISubsec. .:.J}]

3.5.6.4 Type B or Fissiie Radioactive Material Packaging. In addition to packa~ingauthorized by the Hazardous iMatermls Regulations. each person \vho offers fortransportation a T}pe B red/or iisslie quimtlty 01 L-adioi.wtlte materials also m~y use apackaging certified by Headquarters Certifying Official or NRC. [DOE 0460. 1A.4.a.(4)(b}: WHC-EP-0558. Att. 1 (Subset. 3.b J]

3.5.6.4.1 Use of /VRC-Certified Packaging—NRC-certified Type B and fissilepackaging that have a current Certificate of Compliance may be used by DOE andDOE contractors only under the conditions specified in the Certificate. and onlyafter DOE is registered with NRC M a user. [DOE O 460.1,4. 4a.(4)(b); WHC-EP-055S. .\tt. 1 (Subset. ~.b~]

‘U Safe Storage System Rewsion OSystem Requirements Document May 1998

3.5.6.4.2 Use of DOE-HQ CeHified Packaging-Packaging that have a currentDOE Certificate of Compliance issued by the Headquarters Certifying Officialmay be used by DOE and DOE contractors only under the conditions specified inthe Certificate. [DOE O 460.1A. 4a.(4)(b); WHC-EP-0558, Att. 1 (Subset. 3.b’)]

3.5.6.5 On-site Transfers. On-site transfers of hazardous materials shall comply withTransportation Safety Document approved by the cognizant Operations or Field Office[DOE 0460. 1A, 4.b]

3.5.6.5.1 Methodology and Compliance Process-The Transportation SafetyDocument shall describe the methodology and compliance process to meetequivalent safety for any deviation from the Hazardous Materials Regulations.[DOE 0460. 1A. 4.b]

3.5.6.6 Safety Documents. For multiple-tenant DOE sites, safety documents for>everal contractor organizations may be combined into a single document. DOE-operated~ites may approve their own Transportation %fetv Documents. [DOE O -MO.1A. -+.b]

3.5.6.6.1 Effective Date-.Approved Transportation Safety Documents shall bein effect no later than 1 year from incorporation of this Order into [he contractorscontracts. [DOE 0460. 1A. 4.b]

3.5.6.7 Contractor Motor Carrier Safety Regulations. Each contractor who is a DOT-registered carrier and who operates a Government-owned or commercial motor vehicleoffsite shall comply with Federal iMotor Carrier Safety Regulations (49 CFR Parts 350-399) and applicable tribal. State, und local regulations not otherwise preempted by DOT.[DOE 0460. 1A. .Att. 1 (Sect. 5)]

3.5.6.8 DOE Employee Motor Carrier Safety Regulations. DOE employees andemployees of DOE contractors that are State agencies (nor othenvise subject to DOTjurisdiction J shall also comply with Federal .Motor Carrier Safety Regukmons (49 CFRPans 350-399) und applicable tribal. State. tind local regulations not otherwise preemptedby the Department of Transportation [DOE 0460. 1A. Att. 1 (Sect. 6)]

3.5.6.9 Transpofiation by Aircraft. In addition to the Hazardous iMatermls Regulationsfor “Carriage by Aircraft.” 49 CFR Part 175. all DOE transportation operations byaircraft shall follow the requirements of DOE O 440.2, Aviation. [DOE O 460.1A, 4.d]


In addition to System-1evel Requirements (see Section 3.2.7), the following Safeguards andSecurity requirements apply to the ’33U Transportation Subsystem.

3.5.7.1 Safeguard Termination Limits. Itshould be possible to transport ~33Umaterialsbelow STLS using normal truck or rail equipment without modification. [Derived]

59

233USafe Storage System Rev/s/on OSvstem Requirements Document Mav 1998

3.5.7.2 Materials in Excess of STLS. .Nlaterial that exceeds the STLS shall requiretransport by approved DOE shippers for SNM class materials. [Derived]

3.5.6.3 Use of Transpotiation Safeguards System (TSS) Services—:3sU inquantities of 2 kg or more shall be transported by Transportation Safeguards DivisionITSD) Nuclear .Materlals Couriers (NMCSJ in the TSS in accord. ;e with therequirements of DOE AL 5610.14. Chapter III. [DOE AL 5610. i+, Ch. HI. 1a.]

3.5.6.3.1 Request for TSS Services—Requests for TSS services shall besubmitted in ticcordance with the requirements of DOE AL 5610.14. Chapter III.SectIon 2. [DOE .+L 5610.14. Ch. III. 2.]

3.5.6.3.2 TSS Packaging Requirements and Criteria-Eoch ~~sL.lSafe StorageSystem contractor shall ensure that appropriate packaging md tie-downs areutdized for the >hlpment w specified in DOE .AL 5610.14. Chapter III. Section -!,[DOE .\L 5610, !4. Ch. III. 4.]


In addition to System-le\el Requirements idenufied in Section 5.2. S. the following Reliability\..Availability. und Maintainability requirements ~ppiy to the Transportation Subsystem.

3.5.8.1 Subsystem Re/iabi/ity. {TBD}

3.5.8.2 Reuse and Availability. Transportation p~ckages should be reusable and have{TBD}W fivailabiiity, including turnaround time after e~ch use. [Derived]

3.5.8.3 /mpact on Shipping Schedu/es. Sutficlent shipping containers should be..~l~vailable at ‘“ L_>hipplno tind receltlng >I[es such (hat m~terial can be >tored ~emporarll>..-[Derl\ed]

3.5.8.4 System Capacity. The >ubs}stern shouid handle required transfers \vithoutundue delays due [o IXK of’subsys~em c~pwlt}. [Deri\ed]

3.5.9 Human Factors

See System-level Requirements (Section 3.2.9)


See System-level Requirements tSection 3.2.10

3.5.11 Design and Construction (Facilities)

See System-1evel Requirements {Section 3.2.11).

2aU Safe Storage System Revision OSystem Requirements Document May 1998


In addition to System-1evel Requirements identified in Section 3.2.12, the following managementand planning requirements apply to the Transportation Subsystem.

3.5.12.1 Departmental Materials Transpotiation and Packaging Management. Each~33USafe Storage System contractor shall conduct its operations in compliance with allapplicable international, Federal, State, local. and tribal requirements governing materialstransportation unless exemptions or alternatives are approved in accordance with DOE O460.1. Notwithstanding the exemption available through the National Security Provision,49 CFR 173.7(b), shipments under this provision will comply with the 49 CFR 106-180requirements except those that infringe upon maintenance of classified information.[DOE C 460.2, 1]

3.5.72.2 Materials Transportation Plan. A Transportation Plan shall be prepared byeach ’33U Safe Storage System contractor and submitted to the appropriate Field Elementwith information on shipments of spent nuclear fuel. high-level waste. and high-visibilityshipments and campaigns as determined by the cognizant Program Office (pO). [DOE C460.2. 2.]

3.5.12.2.1 Materials Transpofiation Plan Content—The plan shall consist ofinformation describing material type. shipping dates, estimated number andweight of shipments, mode of transport. carrier proposed route, packagingdescription, and cargo security arrangements, if required. [DOE C 460.2, 2.]

3.5.12.2.2 Transportation Information Network (TIN) —The contractor, whenpreparing a Transportation Plan, shall use the Prospective Shipments Module(PSM) of the Transportation Information Network (TIN) in the development ofthe Plan. [DOE C 460.2. 2.]

3.5.12.3 Transpotiation Tracking and Communications (TRANSCOM) System. TheDOE Transportation Tracking and Communications (TRANSCOM) System shall be usedby the contractor. in accordance with the TRANSCOM operations system manuals(controlled documents ) for tracking and monitoring the following categories of shipments[DOE C 460.2. 3.]:

A. Spent nuclear fuel (Reference DOE .34S632.lC-1, Chapter IV) [DOE C 460.2, 3]

B. High-level waste [DOE C 460.2. 3]

c. High-visibility shipments and campaigns as determined by the cognizant DOEPOS. [DOE C 460.2, 3]

3.5.72.4 Automated Transportation Management System (A TMS). To the maximumextent practicable, the contractor shall utilize the Automated Transportation ManagementSystem (ATMS) to perfotm transportation tasks. [DOE C 460.2, 4a.]

61

233USafe Storage System Rewsion OSystem Requirements Document May 1998

3.5.12.5 Contractor Requirements Document for Depatimental Materials

Transportation and Packaging Management. In addition to the above requirements.each ’33U Safe Storage Svstem contractor shall comply with the requirements of DOE O460.2. Contractor Requi- nents Document, Attachment I. [DOE C 460.2]


See System-1evel Requirements (Section 3.2. 13).

3.6 Waste Management Subsystem

3.6.1 Performance

3.6.1.1 Receipt Capacity. The Waste Management Subsystem shall have {TBD}%capacity to receive wastes from other subsystem operations. [Derived]

3.6.1,2 Waste Hand/ing. The Waste Management Subsystem shall perform mynecessary treatment in accordance with the E.M Waste .Management acceptancestandards. [Derived]

3.6.1.3 Operating Life. The Waste Managementoperating life of not less that 50 years. [Derived]

3.6.2 Functional

Subsystem shall be designed for an

3.6.2.1 Receive Waste. The Waste .Management Subsystem shall receive waste from‘sqU Safe Storage System subsystems and from existing storage. [Derived]

3.6.2.2 Recover Waste. The system should recover and return ‘7SLTmaterial to theProcessing Subsystem. [Derived]

3.6.2.3 Collect Waste. The Waste Management Subsystem shall collect designatedwastes according to type.

3.6.2.4 Segregate and Treat Waste. The Waste Management Subsystem shouldprovide any necessary segregation and treatment to stabilize the waste material in a formacceptable to EM waste disposition operations. [Derived]

3.6.2.5 Package Waste. The Waste Management Subsystem shall have the capabilityto package waste in accordance with EM waste acceptance criteria. [Derived]

3.6.2.6 Provide Temporary Storage. The Waste Management Subsystem should placereceived materials into temporary storage until sufficient material is accumulated that itcan be transferred to the responsibility of EM Waste Management Operations. [Derived]

3.6.2.7 Transfer Materials. The Waste Management Subsystem shall transfer materialto DOE-EM via the ‘Transportation Subsystem. [Derived]

2=U Safe Storage System Revision OSystem Requirements Document Mav 1998






See System-1evel Requirements (Section 3.2.5).






See System-level Requirements

3.6.9 Human Factors

See System-level Requirements

Section 3.2.8).

Section 3.2.9).


See System-1evel Requirements (Section 5.2. 10).

3.6.11 Design and Construction (Facilities)






63

233(JSafe Storage System Rev/s/on OSystem Requirements Document May 1998

4.0 QUALITY ASSURANCE PROVISIONS

4.1 Quality Requirements

The design and development process for the ~~~1)Safe Storage System shall incorporate a qualityassurance program which complies with DOE O414.1 (Sect. 2.3, and 6) and complies with thedefinition of ‘graded approach’ in Subsection 5.b. [DOE O 414.1]

4.1.1 Quality Assurance Program

4.1.1.1 General Rule. Contractors responsible for DOE nuclear facilities shall:

A. Develop and submit for approval by DOE a Quality Assurance Program (QAP)for the work in accordance with 10 CFR 830.120. [10 CFR 830.120. DOE O414.1 (Sect. 2)]

B. Implement the QAP. as approved and modified by DOE [DOE O 414.1 (Sect. 2)].

4.1.1.2 Quality Assurance Program (QAP).

4.1.1.2.1 Quality Assurance Criteria—A contractor shall develop a QAP inaccordance with DOE O 414.1 and the quality assurance criteria specified inparagraph 4.1.2 of this Section. [DOE 0414. 1]

(1) Criteria Satisfaction. The QAP shall include a discussion of how criteriashall be satistied. [DOE O 414.1 (Subset. 5.b)].

(2) Graded A~proach. Criteria shall be applied using a graded approach[DOE () 414.1 (Subset. 5.b)].

4.1.1.2.2 Qua/ity Assurance Program /mp/ementation—The contractor shalluse ASME NQA- 1 to develop and implement the QAP. [DOE O 414.1 (Sect. 2)]

4.1.1.2.3 QAP Motlifications—

(1) Contractor Chanqes. A contractor may, at any time. make changes to anapproved QAP. [10 CFR 830. 120]

(2’

(3’

Chanae Submittal. Changes shall be submitted annually to DOE forreview. [10 CFR 830.1201

Submittal Contents. A submittal shall identify changes. pages affected,reason for changes. and basis for revisions. [10 CFR 830. 1~0]

(4) Editorial Chan~es. Changes made to correct spelling. punctuation, orother editorial items do not require explanation, [10 CFR 830. 120]

64

‘U Safe Storage System Rev/s/on OSvstem Requirements Document Mav 1998

4.1.1.2.4 DOE Approva/—Implementation plans and QAPs shall be regarded asapproved by DOE 90 days after submittal. unless approved or rejected by DOE atan earlier date, and shall include any modification made or directed by DOE [10CFR 830. 120].

4.1.2 Quality Assurance Criteria

4.7.2.7 Management.

4.1.2.1.1 Program—

(1) Proqram Develo~ment. Contractor and DOE organizations shall develop,implement. and maintain a written Quality Assurance Program. [Derived]

(~) Orctanizational Structure and Responsibilities. The QAP shall describethe organizational structure, functional responsibilities, levels of authority.and interfaces for those managing, performing, and assessing adequacy ofwork. [Derived]

(3) Manacjement Svstem. The QAP shall describe the management system.including planning, scheduling, and cost control considerations. [Derived]

4.1.2.1.2 Quality lmprovement—

(1) Quality improvement Processes. Contractor and DOE organizations shallestablish and implement processes to detect and prevent quality problemsand ensure quality improvement. [Derived]

(2) Identification and Control of Problems. Items and processes that do notmeet established requirements shall be identified. controlled. andcorrected. [Derived]

i?) Corrective Action. Correction shall include identifying the causes ofproblems and preventing recurrence. [Derived]

(-l) Review and Analvsis. Item reliability, process implementation. and otherquality-related information shall be reviewed and the data analyzed toidentify items and processes needing improvement. [Derived]

4.1.2.1.3 Documents and Records—

(1) Document Preparation and APRroval. Documents shall be prepared.reviewed, approved, issued, used, and revised to prescribe processes.specify requirements, or establish design. [Derived]

(2) Record Maintenance. Records shall be specified, prepared, reviewed.approved. and maintained. [Derived]

65


4.1.2.2 Petiormance.

4.1.2.2.1 Standards and Administrative Controls-

(1) Controlled Conditions. Work shall be performed under controlledconditions using approved instructions, procedures, or other appropriatemeans. [Derived]

(~) Identification and Control. Items shall be identified and controlled toensure their proper use. [Derived]

(3) Maintenance. Items shall be maintained to prevent their damage,unavailability, or deterioration. [Derived]

(4) Monitoring and Data Collection Equipment. Equipment used for processmonitoring or data collection shall be calibrated and maintained. [Derived]

(5) ProRertV Control. Items shell be controlled to prevent their loss.[Derived]

4.1.2.2.2 Design—

Princi~les and Standards. Items and processes shall be designed usingsound engineering/scientific principles and appropriate standards.[Derived]

Incorporation of Desictn Bases. Design work. including changes. shallincorporate applicable requirements and design bases. [Derived]

Desmn Interfaces. Design lnterti~ces shall be identified and controlled.[Derived]

Verification and Validation. The adequacy of design products shall beverified or validated by individuals or groups other than those whoperformed the work. [Derived]

Verification Timinq. Verification and validation of design work shall becompleted before approval and implementation of the design. [Derived]

4.1.2.2.3 Procurement—

(1) Performance Qualitv. Contractor and DOE organizations shall ensure thatprocured items and services meet established requirements and perform asspecified. [Derived]

(~) Evaluation of Surwliers. Prospective suppliers shall be evaluated andselected on the basis of specified criteria. [Derived]


(3) Sumlier Reiiabilitv. Contractor and DOE organizations should ensure thatapproved suppliers can continue to provide acceptable items and services.[Derived]

(4) Suspect/Counterfeit Items (S/Cl) Controls.(S/CI) controls shall be in accordance with440. 1A]

ISuspect/Counterfeit Items

DOE 0440. 1A. [DOE O

4.1.2.2.4 Inspection and Acceptance Testing-

(1) Acceptance and Performance Criteria. Inspection and acceptance testingof specified items and processes shall be conducted using establishedacceptance and performance criteria. [Derived]

(2) Equipment Maintenance. Equipment used for inspections and tests shallbe calibrated and maintained. [Derived]

4.1.2.3 Assessment.

4.1.2.3.1 Management Assessment—

(1) QAP Assessments. Management shall periodically assess the integratedquality assurance program and its performance. [Derived]

(2) Corrective Action. Problems that hinder contractor and DOEorganizations from achieving their objectives shall be identified andcorrected. [Derived]

4.1.2.3.2 Independent Assessment—

(1) Conduct of Assessments. Planned and periodic independent assessmentsshall be conducted to measure item quality and process effectiveness andto promote improvement. [Derived]

(~) Assessment Authoritv. Personnel performing independent assessmentsshall have the authority and freedom from the line organization to carryout their responsibilities. [Derived]

(3) Technical Qualification. Personnel performing independent assessmentsshall be technically qualified and knowledgeable in the areas assessed perNQA- 1 and applicable ANSI standards. [Derived]

67

23(J Safe Storage System Revision OSystem Requirements Document May 1998

4.2 Verification

4.2.1 Program

4.2.1.1 Conformance. ~33USafe Storage System contractors shall verify conformancewith the requirements of Section 3 of this SRD at appropriate locations and levels ofassembly up to and including the total system. [Derived]

4.2.7.2 Resources and Personne/. The contractors shall provide all personnel,facilities, test equipment. spares and expendable required for the verification program.[Derived]

4.2.2 Interfaces

4.2.2.1 Intetiace Veri~ication. The verification program shall incorporate interfaceverification as part of the design and development process. [Derived]

4.2.2.2 Functionality and Performance. The verification program shall incorporatetests or other verification methods that specifically verify the functionality andperformance of the internal and external interfaces. [Derived]

4.2.3 Methods

To verify compliance with the requirements of Section 3. the 23% Safe Storage System shall besubjected to verification as defined in Section 4.2.4. [Derived] The methods of verification aredefined as follows:

A.

B.

c.

D.

Test. An action by which the operability, supportability, performance capability or otherspecified qualities of an i~em are \erified when subjected to controlled conditions that arereal or simulated. These ~erifications may require use of special test equipment undinstrumentation to obtain quanutatlve data for analysis as well as qualitative data derivedfrom displays and indicators inherent in the item(s) for monitor and control.

Demonstration. An exhibition of the operability} or supportability of an item underintended service/use conditions. These verifications are usually non-repetitive and areoriented almost exclusively toward acquiring qualitative data. Demonstrations may beaccomplished by computer simulation.

Analvsis. A process used in lieu of or in addition to other verification methods to verifycompliance with requirements. The techniques typically include an interpretation orinterpolation/extrap~l ;ation of analytical or empirical data under defined conditions orreasoning to show theoretical compliance with stated requirements. Analysis may includecomputer modeling or simulation.

Inspection. An observation or examination of the product characteristics, or the review ofapplicable documentation to determine compliance with requirements.

2WUSafe Storage System Revision OSystem Requirements Document May 1998

E. ~ The PrOCeSSOf comparing a cu~ent item with a PreViOUSlyverified item,taking into consideration configuration, test data. application and/or environment. Theevaluation must be documented and shall include: the test procedures/reports of the itemto which similarity is claimed; a description of the difference(s) between the items: andthe rationale for verification by similarity.

4.2.4 Requirements Matrix

Requirements of Section 3 shall be verified using the method specified for each requirement asshown in Appendix B, Requirements Verification Matrix. [Derived]

69

2=U Safe Storage System Rev/s/on OSystem Requirements Document . May 1998

5.0 NOTESI

5.1 TBD/TBR Summary listing

rable 5-1. TBD ListingTBD Number I Source Paragraph RequiremenVTitle TextTBD-1 These requirements also address the processing and interface

i ‘ “2’ ‘ara” ‘ with the EM Waste Management program for disposition ofwastes generated by the activities associated with this system

I and those 97-1 materials that mav be classified as wastes Der the~ Safeguard Termination Limits (S~Ls) ~ BD}.

TBD-2 1.2, para. 1——

I It is recognized the 2‘3U is not considered transuranic–waste and,as such. it disposition is ~BD}.

TBD-3 Table 3-2 Various FieldsTBD-4 Table 3-4 , Various FieldsTBD-5 3.2.1 I Long-term storage capacity of the entire ’33U Safe Storage

1 System-shall accommodate ~BD}kg of 233Umaterial as specified~ in the ‘“U Dis~osltion Environmental lm~act Statement (EIS)

, Record of Decision (ROD), with ~BD]O/~ margin to accommodate~future ‘2W materials.

TBD-6 3.2.3.1.1 That portion of the 97-1 “3 U material at existing DOE storagesites (see Section 3.1.3) not designated as waste or designatedto be transferred for disposition, in accordance with ~BD}, shallbe transferred to commercial or DOE SNM shippers for transport

, to the 233USafe Storage System for processing and storage as1appropriate.

TBD-7 3.2.3.1.1 (3) ~ Requirements for the 97-1233 U Inventory to commercial or DOEI SNM shippers interface shall be defined in nBD} Interface

Control Document (lCD).TBD-8 3.2.3.1.2 (2) ~ Requirement s for the Oak Ridge Molten Salt Reactor Expe’ - mt

, to commercial or DOE SNM shimers interface shall be clef,, ~ci in,,flBD} ICD.

TBD-9 3.2.3.1.3 Natural and/or depleted uranium at {TBD} existing storage sitesshall be transferred to commercial or DOE SNM s-hippers fortranspon to the 233USafe Storage System for blenaing with ‘S3U

~ materials as required. ITBD-10 3.2.3.1.3 (3) ~ Requirements for the natural and depleted uranium storage sites

I to commercial or DOE SNM shippers interface shall be defined in i

t 1~BD} ICD. (i TBD-1 1 3.2.3.1.4 (4) ~Commercial or DOE SNM shirmers shall trans~ort natural and ~

I depleted uranium from mBD} sites to the ‘33U”Safe StorageSystem fc- >cessing. - -

TBD-12 , 3.2.3.1.4 (5) Requirement ,.s for the commercial and DOE SNM shippers to ‘S3UI Safe Storage System interface shall be defined in (TBD} ICD.

TBD-13 I 3.2.3.1.5 Commercial or DOE SNM shippers shall transporl packaged ‘“Umaterials f- -n the 233USafe Storage System to ~BD} DOE-MT ~for final di: sition.

TBD-14 : 3.2.3.1.5 (2) Requireme s for the commercial or DOE SNM shippers to DOE- “~] MD”interface shall be defined in ~BD} ICD.

TBD-15 3.2.3.1.6 : Commercial or DOE SNM shippers shall transport waste~

\ materials, packaged to meet EM Waste Acceptance Criteria, from 1Ithe 233USafe Storage System to ~BD} DOE-EM Waste

._.._._—.w5!TEnt facilities for disposition ___—_---J

2=U Safe Storage System Revis/on OSvstem Requirements Document Mav 1998

TBD-16 3.2.3.1.6 (2) Requirements for the commercial or DOE SNM shippers t;DOE-EM Waste Management interface shall be defined in flBD} ICD.

TBD-17 3.2.3.1.7 Commercial or DOE SNM shippers shall transpofi packaged ’33Umaterials between the 233USafe Storage System and OBD}beneficial use facilities and programs.

i TBD-18 3.2.3.1.7 (1) [ Requirements for the commercial or DOE SNM shippers to[ beneficial use program interfaceshallbe defined in ~BD} ICD.

TBD-19 3.2.3.1.8 The ‘JJU Safe Storage System shall be located at rBD} sitesand facilities.

TBD-20 3.2.3.1.8 (2) Requirements for the sites and ~I System interface shall be defined in ~BD} ICD.

TBD-21 3.2.3.1.9 (1) Requirements for the z33U Safe Storage System to external~~~~ping container source interface shall be defined in ~BD}I Ibu.

TBD-22 3.2.3.2.1 (3) Requirements for the Transportation Subsystem/ProcessingSubsystem interface shall be defined in ~BD} ICD.

i TBD-23 3.2.3.2.2 (4) Requirements for the Transportation Subsystem/StorageSubsystem interface shall be defined in ~BD} ICD.

TBD-24 3.2.3.2.3 (3) Requirements for the Transportation SubsystemNVaste~ Management Subsystem interface shall be defined in ~BD} ICD. ~

TBD-25 3.2.3.2.4 (5) I Requirements for the co-located Processing Subsystem/Storage‘ Subsystem interface shall be defined in flBD} ICD. I

; TBD-26 3.2.3.2.5 (2) Requirements for the co-located Processing Subsystem to Waste IManagement Subsystem interface shall be defined in ~BD} ICD.

TBD-27 3.2.3.2.6 (2) Requirements for the co-located Storage Subsystem to Waste

I Management Subsystem interface shall be defined in ~BD} ICD.TBD-28 I 3.2.4.2.15 The database shall include surveillance results for a ~BD}

~ I period.! TBD-29 I 3.2.4.2.18 I The database shall include records of the dates of inspections for

a ~BD} period.TBD-30 3.2.8.1 All ’33U Safe Storage System subsystems shall be designed with

~BD}% reliability to ensure the safe operation of all facdities and ,e ui ment. I

~TBD-31 3.2.8.2 A~U Safe Storage System subsystems shall be designed to ]I ensure mBD}04 availability of equipment, replacements. andI

Upgrades throughout all phases of the life cycle.TBD-32 , 3.2.11 .6.2 ~Accepted industry design standards ~BD} should be followed in

I ! facility design. I

I TBD-33 3.3.1.1 The Processing Subsystem shall process the 97-1 material at arate of ~BD} to the final form while ensuring that personnel and !

I public safety are not compromised.I TBD-34 i 3.3.1 .1.1 The 233U Safe Storage System shall have UBD} capability for ~

isotope separation for-beneficial use.TBD-35 3.4.1.1 The Storage Subsystem shall place ~BD quantity} of DOE-

SAFT-0067 compliant 233Ustorage packages into safe storage fora period of at least 50 years.

TBD-36 3.4.1.2 The Storage Subsystem shall have ~BD}O/O capacity fortemporary storage.

TBD-37 3.4.1.3 The ‘J3U Storage Subsystem shall be capable of emplacing andretrieving ~BD} packages of materials within CBD timeframe}.

TBD-38 3.5.8.1 Subsystem Reliability. UBD}TBD-39 3.5.8.2 Transportation packages should be reusable and have flBD}O/O

availability, including turnaround time after each use.TBD-40 3.6.1.1 The Waste Management Subsystem shall have ~BD}O/O capacity

1 - to receive wastes from other subsystem operations.

71

23U Safe Storage System Rev/s/on OSystem Requirements Document Mav 1998

Table 5-2. TBR ListingTBR Number I Source Paragraph RequirementKiile Test 1

i TBR-1 I 3.2.3.2.4 Processing Subsystem / Storage Subsystem Interface ~BR}~TBR-2 ~3.2.4.2 Data Storage. ~BR}; TBR-3 ~3.2.4.2.19 The data base shall include fill gas composition and pressure

flBR} on sealing.1TBR-4 3.3.2.12 ~The Processing Subsvstem should-include the capability to blend

2-U Safe Storage System Revision OSystem Requirements Document May 1998

GLOSSARY

Acceptable

Accounting

ALARA (As 10W 6’S

reasonablyachievable )

Alloy

Application oj’Safeguards (toMaterials or Facilities)

Approved

Authority HavingJurisdiction

Barrier

Blendin q

Ceramic

Certification

Combustible

Conversion

Conforming with requirements, directives. or regulations.

That part of Safeguards and Materials Management that encompassesthe management system and records and reports to account for sourceand special nuclear material to minimize the possibility of diversionand to detect diversion promptly should it occur. Accounting doesnot include physical protection.

The implementation of good radiation-protection programs andpractices that traditionally have been effective in keeping the averageand individual exposures for monitored workers well below thelimits.

A solid solution of two or more metals united by being fused togetherand dissolving in each other when molten.

The implementation of appropriate safeguards system under theNonproliferation Treaty with a view of preventing diversion ofnuclear energy from peaceful use to nuclear weapons or otherexplosive devices.

Acceptable to the “authority having jurisdiction.”

The organization, office, or individual responsible for approvingequipment, installation. or procedure.

A protective system that prevents undesired reactions or containment.

See Dilution.

A class of inorganic. nonmetallic solids that are subjected to hightemperature (> 1000”C) during manufacture or use.

The process by which contractor nuclear facility managementprovides written endorsement of the satisfactory achievement ofqualification of a person for a position.

In the form used and under the conditions anticipated, will ignite,bum, support combustion, or release flammable vapors whensubjected to fire or heat.

An operation for changing from one material form, use, or purpose toanother.

73


Database

Dilution

Effecti~’e NeutronMultiplication Factor

(Ltt)

Enclosure

Engineered SafetyFeat[ire

Grade~i .4pproac11

Handling Enclosure

H[cwr[i Cliteqot-ies

Hot Ceil

Inert Gas

A large collection of data in a computer. organized so that it can beexpanded, updated, and reviewed rapidly for various uses.

In general the addition of inert material or solvent with the result thatthe concentration of the material of interest is reduced.

The ratio of the total number of neutrons produced during a timeinterval (excluding neutrons produced by sources whose strengths ar~not a function of fission rate) to the total number of neutrons lost byabsorption and leakage during the same time interval.

A physical structure that provides a barrier between the internallycontaminated package and the worker, facility, and environment.

Systems. components. or structures that prevent and/or mitigate theconsequences of potential accidents including the bounding designbasis .ccidents.

A process by which the level of analysis. documentation, and actionsnecessary to comply with a requirement are commensurate with: ( 1)the relative importance to safety, safeguards, and security; (2) themagnitude of any hazard involved; (3) the life cycle stage of afacility; (4) the programmatic mission of a facility; (5) the particularcharacteristics of a facility; and (6) any other relevant factor.

A glove box line or similar equipment tha~ isolates 133U-bearingmaterials from the worker”s environment while allowing the materialto be handled or processed.

The consequences of unmitigated releases of radioactive and/orhtizardous material are evaluated as required by DOE 5480.23 andclassified by the following hazard categories: Ctitegory 1. The hazardanalysis shows the potential for significant offsite consequences.Category 2. The hazard analysis shows the potential for significantonsite consequences. Category 3. The hazard ana~ysls shows thepotential for only sigmficant

A heavily shielded enclosure in which radioactive materials can behandled by persons using remotely operated manipulators whileviewing the materials through shielded windows or periscopes.

A non-reactive gas or combination of gases appropriate to thematerial being stored that will not support corrosion of the containeror oxidation of its contents.

‘mu Safe Storage System Revision OSystem Requirements Document May 1998

Material Container

Non-Destructive Assav(NDA )

Non-DestructiveExamination (NDE)

Nuclear CriticalitySaj@

Packaging

Process

Pyrophoric

Qualification

Qualip Assurance(QA~

Residue

Sealed

Shall. Should,and May

Storage

Storage Faciliy

The container that is in contact with the uranium material beingstored. If structurally adequate and sealed, the material containerprovides one barrier.

A procedure (e.g., calorimetric or radiometric measurement) fordetermining the amount of fissionable uranium in a container withoutphysically sampling the material.

A procedure (e.g., radiography) for examining the contents of acontainer without opening the container.

A method used to prevent nuclear criticality and protection againstinjury or damage due to an accidental nuclear criticality.

The assembly of materials and components in compliance withstorage/shipment requirements.

To extract. separate. purify, or fabricate a material by physical.chemical. or mechanical means.

Capable of igniting spontaneously when exposed to air.

Education, experience. training, examination, and any specialrequirements necessary for performance of assigned responsibilities.

All planned and systematic actions necessary to provide adequateconfidence that a structure, system, or component will performsatisfactorily in service.

Process-generated uranium-bearing materials not classified asstorable metal or stabilized oxide that contain a non-discardablequantity of uranium.

Sealed means that a container has been closed (e.g., welded) andcertified to be leak-tight in accordance with ANSI Ni4.5- 1987standard.

“’Shall” denotes that something is required. “’Should” denotes thatsomething is recommended but is not required. “May” denotes thatsomethingis permitted but is neither a requirement nor arecommendation.

Any method for safely maintaining items in a retrievable form forsubsequent use or disposition.

The building structure and other confinement systems that housestorage containers.

75

2=USafe Storage System Revision O


Stora,qe Package A configuration of nested containers including package content.

Thermal Stabilization A process that exposes a uranium-bearing material in air to anelevated temperature for the duration required to convert reactiveconstituents present to an oxide (usually U30S) and to removeadsorbed moisture and other volatile species.

Tube Vaults Tubular storage devices (steel lined and encased in concrete) used forthe storage of packages containing ‘33U.

Unirrm.iiated Material Material that does not contain fission products or undesired activationproducts resulting from residence in a nuclear reactor core.

76

2mU Safe Storage System Revision OSystem Requirements Document May 1998

APPENDIX A: REQUIREMENTS TRACEABILITY MATRIX

Requirement No. Requirement Title Requirement Source Source Pamgraph3.2.1 Performance Derived

3.2.2.1 Compatibility with 94-1 Derived\ Systems

3.2.2.2 ; General Functionality Denved

3.2.2.3 ] Transfer to Waste Disposal Derived1 Programs

3.2.2.4 I Monitor Materials and System I DerivedI Processes——-- ——

3.2.2.5—

Assure Safe Operating ~Derived~Conditions

3.2.2.6 Provide Package Surveillance DOE-SAFT-O067Capability DOE 5633.3B Ch. Ill, 3

3.2.2.7 I Contain Material Derived

3.2.2.8 I Retrieve Material Derived

3.2.2.9 ) Provide Containment ~DerwedDetection Capability

3.2.2.9.1 ~Containment Control Derived

3.2.2.9.2 Transfer Provisions , Derived

3.2.3.1.1 I 97-1 33U Storage/ ; Derived! Commercial or DOE SNM ~! Shippers Interface

3.2.3.1.1 (1) Early Disposition Derived

3.2.3.1.1 (2) Transport Requirements Derived

3.2.3.1.1 (3) Interface Requirements Derived

3.2.3.1.2 Oak Ridge Molten Salt Derived

~ Reactor Experiment/Commercial or DOE SNMShippers Interface

3.2.i.i.2 (1) ~Material and Packaging! Requirements

I Derived

i3.2.3.1.2 (2) I Intenface Requirements I Derived

3.2.3.1.3 ~Natural and Depleted Uranium i Derived/ Commercial or DOE SNMShip pers Interface 1

3.2.3.1.3 (1) Required Materials Derived

3.2.3.1.3 (2) Material Specifications Derived


3.2.3.1.4 Commercial or DOE SNM DerivedShippers / 233USafe Storage ISystem Interface

3.2.3.1.4 (1) Transport Requirements ] Derived

3.2.3.1.4 (2) Transfer of 233UMaterials to i DerivedDOE-MD

3.2.3.1.4 (3) Transfer of ’33U Materials to Derived

DOE-EM

3.2.3.1.4 (4) Natural and Depleted Uranium Derived


3.2.3.1.5 Commercial or DOE SNM Derived

Shippers / DOE-MD Interface3.2.3.1.5 (1) MD Materials and Packaging Derived

Acceptance Criteria_. . .......— ._— .—— .,—.—. —

A-1


Requirement No. Requirement Title ] Requirement Source Source Paragraph3.2.3.1.5 (2) Interface Requirements i Derived

~3.2.3.1.6 Commercial or DOE SNM I DerivedShippers / DOE-EM Waste !Management Interface !

~3.2.3.1.6 (1) DOE-EM Waste Acceptance Derived -) Criteria~3.2.3.1.6 (2) Interface Requirements Derived I~3.2.3.1.7 Commercial or DOE SNM ~ Derived I

I Shippers/ Beneficial Use I

1 Storage System Interface I I

~ 3.2.3.1.8 (1) Site and Facility Requirements I Derived~3.2.3.1.8 (2) Interface Requirements I Derived: 3.2.3.1.9 33U Safe Storage System/ : Derived

I External Shippi;g ContainerI Source lnterface-

3.2.3.1.9 (1) Interface Requirements Derived3.2.3.2.1 i Transportation Subsvstem / Derived

Processing SubsystemInterface

; 3.2.3.2.1 (1) Transfer of ’33U Materials i Derived‘ 3.2.3.2.1 (2) Transfer of Waste t Derived

I

3.2.3.2.1 (3) Interface Requirements I Derived .~, 3.2.3.2.2 Transportation Subsystem / Derived! ‘ Storage Subsystem Interface

I

——.—.—

I 3.2.3.2.2 (1 ) Transfer of ’33—.—..__

U materials Derwed——

I 3.2.3.2.2 (2) Transfer of Waste DerivedI

3.2.3.2.2 (3) Transfer of Damaged DerivedPackages !

t 3.2.3.2.2 (4) Interface Requirements Derived3.2.3.2.3 I Transpoctatlon Subsystem 1 Derwed

~Waste Management-~Subsyslem Interface

3.2.3.2.3 (1) ‘ Transfer of Waste Derived I

3.2.3.2.3 (2) Internal Waste Acceptance Derived ~

Criteria (~3.2.3.2.3 (3) Interface Requirements Derwed d

3.2.3.2.4 I Processing Subsystem / DerwedStorage Subsystem Interface

1

{TBR} If‘3.2.3.2.4 (1) Transfer of Processed Derwed 1

Materials

~3.2.3.2.4 (2) Transfer of Packages i DerivedRequiring AdditionalProcessing and/or Packaging

3.2.3.2.4 (3) Packaging and Acceptance , DerivedCriteria I 1

3.2.3.2.4 (4) Transfer of Damaged or Derived —Opened Packages

I

I 3.2.3.2.4 (5)~

Interface Requirements Derwed——-

A 2

*SU Safe Storage System Revision OSvstem Requirements Document Mav 1998

Requirement No. I Requirement Titie I Requirement Source ] Source Paragraph3.2.3.2.5 I Processing Subsystem/ I Derived

Waste ManagementSubsvstem Interface

3.2.3.2.5 (1) Waste Acceptance Criteria Derived I

3.2.3.2.5 (2) Interface Requirements I Derived3.2.3.2.6 Storage Subsystem / Waste Derived

I Management Subsystem

I1

] Interface3.2.3.2.6 (1) I Waste Acceptance Criteria I Derived

\ 3.2.3.2.6 (2) I Interface Requirements Derived I3.2.4 I Information Systems Derived I———-. —_-—-— ———.——. -.——— ....—-...- .——

I Database—- .--—--— ——---.——-+———---————4

3.2.4.1 ~___c DO E-SAFT-0067 I 4.5.1~—..—. .—.-.—3.2.4.1.1 (1) I Classified Data Separation

.—— —-.-—. .—-—Derived

--d

3.2.4.1.1 (l)(a)——

~Classification Guide Derived II3.2.4.1.2 (2) Compatibility ~ Derwed

I

3.2.4.1.1 (3) Data Architecture 1 Derived 1

3.2.4.1.1 (4) Transferability I Derived 1I 3.2.4.1.2 I Data Access Control DOE 5633.3B I: 3.2.4.2.1 ~ Material Transfer DOE 5633.3B : Ch. 11,5

\ 3.2.4.2.2 1 Material Location DOE-SAFT-0067 4.5.2.d

i 3.2.4.2.3 I Analysis and Separation Derived I

I 3.2.4.2.4 Material Physical Form I DOE-SAFT-O067 \ 4.5.2.a.2 (,

3.2.4.2.5 Moisture Content I DOE-SAFT-0067 4.5.2.a.73.2.4.2.6 Stabilization Test ~ Derived

3.2.4.2.7 Processing Conditions ‘ DOE-SAH-0067 4.5.2.a.6—--2.7 (1) ‘ Processing , Derwed

3.2.4.2.8 Package Configuration - I DOE-SA17-0067 4.5.2.b.2

[ 3.2.4.2.9 Packaging Date DOE-SA~-0067 4.5.2.b.3

[ 3.2.4.2.10 Initial Radiation Field DOE-SAFT-0067 4.5.2.b.457 4.5.2.a.l3.2.4.2.11 Chemical Composition , DOE-SAFT-00~—.

3.2.4.2.12 Isotopic Fraction . DOE-SAFT-0067 – j 4.5.2.a.4 I

%2.4.2.13 Material Source ~ DOE-SAFT-0067 I 4.5.2.a.5 I

~ 3.2.4.2.14 Package Identification Number Derived3.2.4.2.15 Surveillance Results Denved

3.2.4.2.16 Inspection Tests Performed DOE-SAFT-O067 4.5.2.c

; 3.2.4.2.17 Individuals Performing DOE-SAFT-0067 ~4.5.2.cInspections I

3.2.4.2.18 Inspection Dates I Derived from DOE-SAFT- I 4.5.2.c II ~0067 I

3.2.4.2.19 I Fill Gas Derived from DOE-SAFT- I 4.5.2.b.l I,0067 I

3.2.4.2.20 [ Elemental Concentration or ! DOE-SAFT-0067 I 4.5.2.a.3

Mass3.2.4.2.21 Baseline Package ~ DOE-SAFT-0067 4.5.2.b.5

3.2.4.2.22 Container Lot Identification ] Derived

1=3.2.4.23.2.4.33.2.5.1

I 3.2.5.2

.23I ‘ Number 1 I I

Other Relevant Information -Historical RecordsCommunications

[

Emergency Management

DOE-SAFT-0067 ‘ 4.5.2.a.8

DOE-SAFT-0067 4.5.2.c

DOE O 151.1 (chg. 2) Ch. VlllDOEO 151.1 (chg. 2) , Sect. 4a. ,

System

3.2.5.3 Emergency Planning and ~ DOE O 151.1 (chg. 2) Sect. 4b.Preparedness.—— ..- .-...-—.——.. ..—-—..——-.. ..--————— ———

A-3

2SU Safe Storage System Revkion OSystem Requirements Document May 1998

Requirement No. \ Requirement Title ] Requirement Source Source ParagraphI 3.2.5.4 j Emergency Response : DOE O 151.1 (chg. 2) Sect. 4c.I 3.2.5.5 “— / Medical Support I DOE 5480.8A~3.2.5.6 1 Emergency Transition ] Derived

3.2.5.6.1 I Operator Intervention I Derived3.2.5.6.2 I Economic Loss ~ Derived

~3.2.5.”7 ! Emergency Recovery———

I DOEO 151.1 (chg.2) _ =ect. 4d.

1 3.2.5.7.1 I Recovery Procedures [ DOE O 151.1 (chg. 2) Sect. 4d. ‘“—

3.2.5.8 ~ Implementation I DOE O 151.1 (chg. 2) Sect. 6.

~ 3.2.5.9 I Operations/Field Office I DOE O 151.1 (chg. 2) Ch. 1,para.8.

I ! Manager Responsibilities ;_ __I

—- .-—i 3.2.5.10 ‘Site/Facility Manager

~ResponsibilitiesI DOE O 151.1 (chg~Z---–--~a=;-~a=.9. ;I

3.2.5.11 ~Operational Emergency I DOE O 151.1 (chg. 2) Ch. 11,para.1. I

I BaseGeneral I

I 3.2.5.12 1Operational Emergency Base ~ DOE O 151.1 (chg. 2) Ch. Ill, para.2. II Related Regulations and Plans ;

3.2.5.13 ~Operational Emergency Base ~ DOE O 151.1 (chg. 2) Ch. Ill, para.3.Planning I

3.2.5.14 Operational Emergency Base ~ DOE O 151.1 (chg. 2) ~Ch. ill, para.4: Preparedness !

II 3.2.5.15 , Operational Emergency Base DOE O 151.1 (chg. 2) ] Ch. Ill, para.5.

I Response3.2.5.16 ! Operational Emergency ] DOE O 151.1 (chg. 2) Ch. IV

i Hazardous Material Program !I

3.2.5.17 Operational Emergency ~ DOE O 151.1 (chg. 2) ] Ch. V1

,.! Events and Condi~ons”

I

3.2.5.18 Public Affairs Policy and DOE O 151.1 (chg. 2) Ch. IXPlanning I

3.2.5.19 Evaluations and Readiness DOE O 151.1 (chg. 2) Ch. X, para.3.Assurance

I

~5.20J

1 Emergency Readiness I DOE O 151.1 (chg. 2) Ch. X, para.4.~Assurance Appraisals and :

Assessments

3.2.5.21 Contractor Requirements DOE O 151.1 (chg. 2) Att. 1

3.2.6.1, Item A Regulatory Compliance DOE P 450.2A I; 3.2.6.1, Item B ~Regulatory Compliance DOE 5400.1 (chg. 1)~3.2.6.1, Item C Regulatory Compliance : DOE 5480.4 I

I 3.2.6.1, Item D I Regulatory Compliance : DOEO 451.1A

3.2.6.1J Item E ; Reguia~orY Compliance _ I DOE0460.1 AI 3.2.6.1, Item F

—-. — .,. . ——-— -—--.-—i Regulato~ Compliance ~ DOE O 440.1 A ‘-- ~

3.2.6.1, Item G Regulatory Compliance I DOE 5480.22 1

3.2.6.1, Item H Regulatory Compliance DOE 5480.23 (chg. 1)

3.2.6.1, Item I Regulatory Compliance DOE 5481 .lB

3.2.6.1, Item J Regulatory Compliance DOE 5480.21i\

3.2.6.1, Item K Regulatory Compliance \ DOE 5820.2A (3.2.6.2 Fire Protection DOE 0420.1 (chg. 2)

3.2.6.2, Item A Fire Protection DOE 0420.1 (chg. 2) ),3.2.6.2, Item B Fire Protection DOE 0420.1 (chg. 2) J3.2.6.2, Item C Fire Protection \ DOE O 420.1 (chg. 2)

3.2.6.2, Item D Fire Protection DOE 0420.1 (chg. 2) -3.2.6.2, Item E Fire Protection DOE 0420.1 (chg. 2)

3.2.6.2 Item FI

Fire Protection --- DOE-STD-1 066-97.———..—..J_—- —-— ——..——..— —....-—-

2mLJSafe Storage System Rewsion OSystem Requirements Document May 1998

Requirement No. Requirement T’itie Requirement Source Source Paragraph3.2.6.3 Radiological Protection DOE P 441.1 Sect. 3

I DOE N 441.1 Sect. 6DOE 5400.5 (chg. 2) Sect. 10 1

3.2.6.3.1 I Sampling Airborne Radioactive Derived~Materials

3.2.6.3.2 ! Radiation Shielding Derived3.2.6.3.3 \ ALARA DOE 5400.5 (chg. 2) Subset. 10.a ~—..3.2.6.3.4 i Kev Radiation Protection DOE-STD-1 107-97 I

I PositionsI

, 3.2.6.4 ! Worker Protection 29 CFR 1910I 29 CFR 1926

Ii DOE P 450.4 ] Comp. 2 and 4

[I DOE P 450.2AI 3.2.6.4.1, Item A : Worker Protection Program DOE O 440.1 A

3.2.6.4.1, Item B I Worker Protection Program DOE O 440.1 A3.2.6.4.1, Item C ~Worker Protection Program DOE 440.1 A Att. 1, Sect. 1-4 ~

I 3.2.6.4.2 Industrial Hygiene Program DOE O 440.1 A Att. 1, Sect. 5

~3.2.6.5 Material Handling I DOE 5400.5 (chg. 2) Subset. 10.aO3.2.6.6 Comprehensive Monltonng : DOE 5400.5 (chg. 2) ~ Ch. 11,Sect. 6 and 7

Derwed I

13.2.6.6.1 Safety and Operating Status ] DOE 5400.5 (chg. 2) Ch. 11,Sect. 6 and 7I 3.2.6.7 Nuclear Criticality Safety ] DOE 0420.1 (chg.2) Subset. 4.3.2-

4.3.3.

3.2.6.7, Item A Nuclear Criticality Safety DOE O 420.1 (chg. 2)3.2.6.7, Item B j Nuclear Criticality Safety DOE 5480.22 Subset. 9.b I

3.2.6.7, Item C ~ Nuclear Criticality Safety DOE 5480.23 (chg. 1) Subsets. 8a, 8.b.! DOE 5481.1 B [ 8.c

I 3.2.6.7, Item D Nuclear Criticality Safety ! DOE 5480.23 (chg. 1) \ Subset. 8.aI ~ DOE 0420.1 (chg. 2) ] Subset. 4.3.2

3.2.6.7.1 1 Nuclear Criticality Alarms ~ DOE O 420.1 (chg. 2) I

I 3.2.6.7.2 ~New Facilities Design ~ DOE 0420.1 (chg. 2) II 3.2.6.7.3 ~Nuclear Criticality Safety In ! DOE 0420.1 (chg. 2)

1Operations3.2.6.7.4 Nuclear Criticality Safety DOE O 420.1 (chg. 2)

Tralnlng

I 3.2.6.8 Pressure Safety DOE O 440.1 A i Att. 1, Sect. 6

~3.2.6.9 Hazard Prevention ~ DOE O 440.1 A

i 3.2.6 .10.1 i Performance Indicator DOE 0210.1I

I ~ Program I

I 3.2.6 .10.2 \ Root Cause AnalysesIDOE O 210.1 I_

TIE1O.3 Feedback Mechanisms ~ DOE O 210.1

I 3.2.6 .10.4 ~Management Information ~ DOE O21O.11

System

3.2.6 .10.5 Program Assessments DOE 0210.1

3.2.6 .10.6 Analytical Data DOE 0210.1

3.2.6 .11.1 Investigation Procedures DOE O 225.1A

3.2.6 .11.2 Type A I Type B Investigations DOE O 225.1A Att. 1

3.2.6.12 Nuclear Safety Implementation DOE-STD-1 082-94I Plan I

\ 3.2.6 .12.1 ~ Relief from Nuclear Safety DOE-STD-1 082-94 ~I Requirements

I 3.2.6 .12.2I I

] Exemptions I DOE-STD-1 082-94

A-5

2W()Safe Storage System Revision OSystem Requirements Document May 1998

i Requirement No. ~Requirement Title I Requirement Source \ Source Paragraph; 3.2.6 .12.2 (1) I Requesting and Granting DOE ; DO E-STD-1 083-95 I I

3.2.6.13 National Environmental Policy ~ DOE-STD-1 083-95Act (NEPA) Implementing

!-ii%::%:; ‘DOE-sT=6-’3iReviews I

3.2.6.15 Safety Analysis Reporting ! DOE-STD-3003-94

Program !—— —..

~3.2.7.21

Personnel Security H DOE O 472.1 B I

~3.2.7.3 Review of Sensitive Activities I DOE O 470.1 (cha. 1)! DOE O 471.2A -

\ 3.2.7.4 I Materials Control and ! DOE 5633.3B 1!

Accountability/

3.2.7.4.1 (l)(a) Materials Control and DOE 5633.3B Ch. 1, l.eI

~Accountability Plan3.2.7.4.1 (1) (b) Management Approval DOE 5633.36 , Ch. I I.e.

; 3.2.7.4.1 (1)(c) Minimum Requirements DOE 5633.3B I Ch. 1, 1~3.2.7.4.1 (l)(d) International Atomic Energy DOE 5633.3B I Ch. i, 1.0

I \ Agency (IAEA) and NRC I] Standards

I

~3.2.7.4.1 (l)(e)I

I American Society for Testing DOE 5633.3B I Ch. 1, 1.0

I and Measures (ASTM) and IANSI Standards ‘

3.2.7.4.1 (2) Graded Safeguards DOE 5633.3B Ch. 1,23.2.7.4.1 (3) Materials Control and DOE 5633.3B Ch. 1,3I ‘ Accountability Requirements

i for Source and Other NuclearMaterials I

3.2.7.4.1 (4)(a) Vulnerability Assessment DOE 5633.3B Ch. 1.4.a3.2.7.4.1 (4)(b) I Performance Testing DOE 5633.3B : Ch. 1,4.b - 4.d3.2.7.4.1 (5) I Monitoring Programs DOE 5633.3B Ch. 1,53.2.7.4.1 (6) I Administrative Controls DOE 5633.3B ~Ch. 1,63.2.7.4.2 (1) I Accounting Systems DOE 5633.3B

I: Ch. 11,2

; 3.2.7.4.2 (1) (a) Material Inventories and Data DOE 5633.3B \ Ch. 11,2.i 3.2.7.4.2 2 Physical Inventories DOE 5633.3B I Ch. 11,3.~3.2.7,4.2 (2)(a) Program Compliance DOE 5633.3B——— Ch. 11,3.I 3.2.7.4.2 (2)(b) Responsibilities DOE 5633.36 ~Ch. 11,3.a.2

3.2.7.4.2 (2)(c) Frequency : DOE 5633.3B \ Ch. 11,3.a.4 - 3.a.5.I 3.2.7.4.2 (3) Measurements and ~ DOE 5633.3B I Ch. 11,4

I 3.2.7.4.2 (5)

m

I 3.2.7.4.3 (4)

3.36

Measurement Control I, 3.2.7.4.2 (4) Material Transfers I DOE 5633*3B Ch. 11,5

Material Control Indicators ! DOE 5633.36 \ Ch. Ii, 6Documentation and Reporting– i DOE 563: I Ch. Il. 7General 1 DOE 5633.3B _I

! 3.2.7.4.3 (2) Plan Documentation DOE 5633.3B\ 3.2.7.4.3 (3) Access DOE 5633.3B ~Ch. Ill, 2—.——

——---- .-— I Ch. Ill, 33.2.7.4.3 (5) I Containment ~ DOE 5633.3 B- I Ch. Ill, 4.-—..-

_- DOE 5633.3B : Ch ill G—- ---—

I Surveillance ! DOE 5633. N3

~3.2.7.4.3 (6) ~ Detection/Assessment—.—

I Ch. Ill, 1~Ch Ill, 1.

w,, . ,,, , “

A 6


Requirement No. Requirement Title I Requirement Source Source Paragraph3.2.7.5 InformationSecurity ] DOE 0471 .2A3.2.7.5.1 Access to Classified and ; DOE 0471 .2A Sect. 4.a

ISensitive UnclassifiedInformation~

! 3.2.7.5.2 ----aClassified Information Systems I DOE 0471 .2A

~3.2.7.5.3 Deviations DOE 0471 .2A f Sect. 4.d3.2.7.5.4, Item A Supplementary Directives

--..,.—I DOE O 471 .2A ~Sect. 4.e ,

3.2.7.5.4, Item B-—- ———..—-—

Supplementary Directives ~ DOE O 471 .2A / Sect. 4.e3.2.7.5.4, Item C Supplementary Directives ] DOE 0471 .2A I Sect. 4.e

II

3.2.7.5.5, Item A Guides I DOE O 471 .2A ] Sect. 4.f, 3.2.7.5.5, Item B Guides DOE O 471 .2A I Sect. 4.f———..——... —.-.,-.13.2.7.5.6 Responsibilities and ‘ DOE O 471 .2A --–----’-----~ I

I Authorities I I43.2.7.5.7 I Program Management ~ DOE 0471 .2A j Ch. I !

3.2.7.5.8 ] Operations Security Program DOE O 471.2A I Ch. II ,), 3.2.7.5.9 I Classified Information Systems I DOE O 471 .2A \ Ch. Ill

~Security I3.2.7.5.10 : Protection and Control of DOE O 471 .2A Ch. IV

Classified Matter3.2.7.5.11 ~ Identification of Classified DOE 5650.26 (chg. 2) Sect. 3

; information I !3.2.7.5.12 ! Cent ractor Information DOE O 471 .2A I Att. 1

1-

Security ProgramI I

I

, 3.2.7.6 Unclassified Computer ; DOE 1360.2BSecurity Program I,

3.2.7.7 Risk Management 1 DOE O 470.1 (chg. 1)

i 3.2.7.8 Site Specific Characteristics ~ DOE O 470.1 (chg. 1) Ch. 1, para. 3

3.2.7.9 Deviations Requirements I DOE O 470.1 (chg. 1) , Sect. 4 f i3.2.7.10 Standardization ‘= O 470.1 (chg. 1) ‘ Sect. 4g (3.2.7.11 Threat ‘ DOE O 470.1 (chg. 1) Ch. 1, para 3 I

I 3.2.712 Site Safeguards and Security DOE O 470.1 (chg. 1) , Ch. 1, para. 4~ PlanI I

3.2.7 .12.1 ! Plan Contents DOE O 470.1 (chg. 1) I Ch. 1. para. 4

3.2.7.13 Security Plan DOE O 470,1 (chg. 1) Ch. 1, para. 4

3.2.7.14 Plan Review DOE O 470.1 (chg. 1) Ch. 1. para. 4

13.2.7.15 I Training Program DOE O 470.1 (chg. 1) ~Ch. 2, para. 3

! 3.2.7.16 ! Training Standardization DOE O 470.1 (chg. 1) Ch. 2, para. 3

] 3.2.7.17 ] Unclassified Controlled ~ DOE O 471.1Nuclear Information

3.2.7.18 Training Records DOE O 470.1 (chg. 1) I Ch. 2, para. 31 !—.—.3.2.7.19 I Safeguards and Security - ‘=E O 470.1 (chg. 1)

——Ch. 4

Awareness I I

3.2.7.20 Self-Assessment ~ DOE O 470.1 (chg. 1) Ch. 10

3.2.7.21 Performance Assurance 1 DOE O 470.1 (chg. 1) Ch. 3, para. 3

3.2.7.22 Documentation I DOE O 470.1 (chg. 1) Ch. 3, para. 4

3.2.7.23 Contractor Requirements ] DOE O 470.1 (chg. 1) Att. 1

3.2.7.24 Protective Force Program ~ DOE 5632.7A Sect. 3.

3.2.8.1 Reliability \ Derived

3.2.8.2 Availability I Derived

3.2.8.3 Maintainability Derived I—._.._.—— —.——. . ..— .—+3.2.9 Human Factors I Derwed _

3.2.10.1 Organization ! Derived ——-3.2.10.2 Organizational Responsibilities ~ DOE 5480.20A .._ . gk 1!2.~-.. ————— — -..————..—-...--—.... —.

A-7

2UU Safe Storage System Revis/on OSystem Requirements Document Mav 1998

Requirement No. Requirement Title \ Requirement Source \ Source Paragraph

m“ :::~~~pf=nnel

/ DOE 5480.20A I Ch. 1,2.

K

I DOE 5480.20A ! Ch. 1,3.3.2.10.4 1 Personnel Selection DOE 5480.20A Ch. 1,4.: Ch. IV3.2.10.5

F

I Process DOE 5480.20A I Ch. 1,5.3.2.10.6 ! Certification “’ DOE 5480.20A—. ‘ Ch. 1.6.3.2.10.7 - I Training DOE 5480.20A—.. : Ch. 1,7.3.2.10.7.1 — ] Graded Approach—

———DOE 5480.20A ‘-Ch. 1,7. “–

3.2.10.7.2 Implementation Matrix / DOE 5480.20A i Ch. 1,7a.(l) ‘3.2.~0.7.2 (1) Training Responsibility \ DOE 5480.20A——..——.- 1 Ch. 1,7a.(l)—. —

13.2.10.7.2 (2) i Justification for ExceptIons I DOE 5480.20A ___Ch. I_7~______----.——— -.—. ..—.3.2.10 .7.2~ I Matrix Substitution DOE 5480.20A ~Ch. 1,7a.(l)3.2.10.7.3 Program Basis DOE 5480.20A ~Ch. 1,7a.(2)3.2.10.7.4 Training and Qualification DOE 5480.20A ~Ch. I 7a.(2)

Needs3.2.10.8 Operator and Supervisor I DOE 5480.20A i Ch. 1,8. I

I ~ ExaminationI

~3.2.10.9 I Operator and Superwsor ~ DOE 5480.20A Ch. 1.9.I : Reexamination !! 3.2.10.10 Requalification ~ DOE 5480.20A Ch. 1,10.I 3.2.10 .10.1 I Administration ~ DOE 5480.20A ] Ch. 110.I 3.2.10.11 I Exceptions to Training ] DOE 5480.20A Ch. 1,11. I

Requirements -3.2.10.12 Extensions DOE 5480.20A ~Ch. 1, 12.3.2.10.13 Alternatives to Education and DOE 5480.20A \ Ch. 1, 13.

Experience Requirements3.2.10.14 Record Requirements DOE 5480.20A ~Ch. 1,15.3.2.10 .14.1 Standardization of Tralnmg / DOE 5480.20A 1 Ch. I 15.

Records 1 I

, 3.2.10 .14.2 Personnel Qualification and ~ DOE 5480.20A I Ch. l,15a.I I Certification RecordsL —-— I[ 3.2.10.15 \ Worker Protection Training” ] DOE O 440.1 Ai 3.2.10.16 i Measurement Tralnlng Plan ~ DOE 5633.3B Ch. 11,4.c.(1) ~~3.2.10 .16.1 ~ Measurement ~ DOE 5633.3B Ch. 11,4.c. (1)

3.2.10 .16.2 Proficiency Demonstration DOE 5633.3B Ch. 11,4.c.(2)3.2.10 .16.3 , Requalification i DOE 5633.3B Ch. 11,4.c.(2) ~

~3.2.10.17 ~ Contractor Requirements ~ DOE 5480.20A Att. 1.~ Document II 1

3.2.10.17. Item A I Contractor Requirements : DOE 5480.20A1 I%cllment

Att. 1.1

I 3.2.10.17, Item B

p

~ Contractor Requirements ! DOE 5480.20A Att. 1.I Document ,

3.2.10.17, Item C ~ Contractor Requirements DOE 5480.20A i Att. 1. IDocument

3.2.10.17, Item D Contractor Requirements DOE 5480.20A Att. 1.Document

, 3.2.10.17, Item E Contractor Recwirements i DOE 5480.20A I Att. 1.Document

3.2.11.1 Operations Design Derived3.2.11.2 \ Design Modifications DOE O 420.1 (chg. 2)

! 3.2.11 .2.1—

1----

] Design and Analysis j DOE O 420.1 (chg. 2) I3.2.11.3 – ~ Natural Phenomena Hazards I DOE 0420.1 (chg. 2). ~

\ .. .... .. . . . . ..._..____. ~MjUWn_..._.. __!__)

—. ——-. —-- .-. . ..— — .—_— —. —.—. — ——.

2=(./ Safe Storage System Revision OSystem Requirements Document May 1998

Requirement No. I Requirement Title I Requirement Source I Source Paragnph3.2.11 .3.1 I Natural Phenomena Hazards \ DO E-STD-I 020-94 (CH-1 ) ~

1I Emergency Operations Plans 1—.—.. .+_._._—~~2.11 .3.6 Site Investigations DOE-STD-1O22-94 I

3.2.11 .3.7 Other Considerations DOE-STD-1 020-94 (CH-1 ) jI

I 3.2.11.4 Industry Codes and Standards ! DOE O 420.1 (chg. 2) ~3.2.11.5

—+I Minimization of Economic ; Derived

I

}

; Loss.—...——I 3.2.11.6 Construction Materials I Derwed

I 3.2.11 .6.1 Work Area Coatings \ Derived

~3.2.11 .6.2 Industry Standards I Derived

~3.2.11.7 Design RequirementsI Application

j DOE-STD-1O21-93

I)-94 (CH-1 )3.2.11.8 ~Applicability ; DOE-STD-102C

1.2.11.9 1 Existina Facilities ! DOE- STD-1O2C3.- )-94 (CH-1 )

3.2.11.10 I Site Investigation Program ~ DOE-STD-1 022-94

3.2.11.11 I Analysis Techniques ~ DOE-STD-1 027-92

3.2.11.12 I Part-time Inventory ! DOE-STD-1O22

i 3.2.11.13 i Electrical Design I ANSIAEEE C2

7-92I

I Nf=pA 7(3 1I\ 3.2.11 .13.1 Facility Safety Class Electrical DOE O 420.1 (chg. 2) I 4.1.1.2.

Systems] 3.2.11.14 Backup Power Sources DOE-STD-3003-94

-1.15 Ventilation Systems Derived

i 3.2.11 .15.1 Procurement and Testing of DOE-STD-3020-97 \ II HEPA Filters

,I

/

3.2.12.1 LCAM Approach I DOE O 430.1 (chg. 1) I

3.2.12.2 LCAM Practice(s) I DOE O 430.1 (chg. 1) : I1

3.2.12.3 Performance Measures ~ DOE O 430.1 (chg. 1)

3.2.12.4 I Acquisition Approach ! DOE O 430.1 (chg. 1)

3.2.12.5 Project Management Svstem DOE O 430.1 (chg. 1)

3.2.12.5.1 ! Conceptual Design I DOE O 430.1 (chg. 1)

3.2.12.5.1, Item A ~ Mission Need ~ DOE 0430.1 (chg. 1) I3.2.12.5.1, Item B I Minimum Technical Functional I DOE 0430.1 (chg. 1)

~ Requirements I I

~ 3.2.12.5.1, Item C Proposed Cost and Schedule j DOE O 430.1 (chg. 1) !Ranges I

I 3.2.12.5.1, Item D Preliminary Environmental DOE O 430.1 (chg. 1) ~Strategy

3.2.12.5.1, Item E Project Technical and DOE 0430.1 (chg. 1)Organizational Interfaces

I 3.2.12.5.1, Item F Integration With Other Projects DOE O 430.1 (chg. 1)and Agencies

3.2.12.5.2 Execution DOE 0430.1 (chg. 1)

3.2.12.5.2, Item A Project Objectives DOE O 430.1 (chg. 1)

3.2.12.5.2, Item B I Scope, Schedule, and Cost DOE O 430.1 (chg. 1) 1Baselines

I 3.2.12.5.2, Item C Life Cycle Cost Analysis DOE 0430.1 (chg. 1) !

A-9

2=(.) Safe Storage System Rev/s/on OSvstem Requirements Document Mav 1998

, Requirement No. ] Requirement Title I Requirement Source Source Paragraph3.2.12.5.2, Item D ~ Preliminary Safety ~ DOE O 430.1 (chg. 1) I

\ Assessment [ I I,3.2.12.5.2, Item E Project Controls ~ DOE O 430.1 (chg. 1)3.2.12.5.2, Item F NEPA Documentation I DOE 0430.1 (chg. 1)3.2.12.5.2, Item G Verification Of Performance – ~ DOE O 430.1 (chg. 1)

I Criterial——— ——i 3.2.12.5.2, Item H

————-—..—Design Alternatives -0430.1 (chg. 1)

I 3.2.12.5.3 Operation ~ DOE O 430.1 (chg. 1)i 3.2.12.5.3, Item A Turnover Plan ] DOE O 430.1 (chg. 1)~3.212.5.3. Item B Verification Of Performance ‘ DOE O 430.1 (chg. 1) I

ICriteria

I.—. - ..-. .—— —.———— .—..—-. .._1 3.2.12.5.3, Item C

———-— —.—I Operational Readiness

..-. —‘-~0=-0~3b.l (chg. 1) ~

3.2.12.5.4 I Conduct of Operations DOE-5480.193.2.12.6 I Operation and Maintenance DOE 0430.1 (chg. 1) para. f

I Process II 3.2.12.7 ~ Disposition Process DOE O 430.1 (chg. 1) para. g~ 3.2.12.8 I Utility Services DOE O 430.1 (chg. 1) para. H

3.2.12.9 Asset Database _ ‘ DOE O 430.1 (chg.~ i para. i3.2.12.10 Compliance : DOE O 430.1 (chg. 1) 1 para. j3.2.12.11 : Logistics \ Derived

\ 3.2.12 .12.1 i Component Decontamination \ Derived! 3.2.12 .12.2 Decontamination Solutions —–—~——Derwed I

3.2.12 .12.3 Minimal Effort to D&D Derived3.2.12 .12.4 Federal Requirements and RCRA Part C Sect. 3005

Orders Executive Order 12856Executive Order 12873

3.2.13.1 State and Tribal Laws and \ DerivedAgreements —.

, 3.2.13.2 Local Ordinances; 3.3.1.1 –-*Processing Capacity and

Capability~ 3.3.1 .1.1 ! Isotope Separation for ‘ Derwed

Beneficial Use1

3.3.1 .1.2 Duration of Processmq Derwed! capability

3.3.1.2 I Stabilization Capability i Derived I

~3.3.1.3 I Variant Materials Processing I Denveci 1

I 3.3.2.1 Receive Materials I Derived II 3.3.2.2 _ Transfer to External Systems ~ Derived I

3.3.2.3-.— .——.-—. —.. 4——.———— —

, Remove from Packaging ~ DerivedI Containers

~3.3.2.4

I

I Convert to Stable Long-term +------–— II Forms, 3.3.2.5 Stabilize for Packaging Derived

DOE-SAFT-0067

~3.3.2.6 Package to ’33U Safe Storage DerivedStandard I

3.3.2.6.1 Package Labeling Derived - - I3.3.2.7 Handle Packages __ Derived——

‘ 3.3.2.8 Stage Materials..— —._

i Derived3.3.2.9 Collect Waste Byproducts3.3.2.9.1 Segregate, Pretreat, and w=== ;’

Transfer Wastes__ ——- .——. —. .—

‘U Safe Storage System Revision OSystem Requirements Document May 1998

Requirement No. Requirement Title \ Requirement Source Source Peragreph3.3.2.10 Characterize Materials I Derived3.3.2 .10.1 Sampling Capability ! Derived—— —.....—3.3.2 .10.2 Non-Destructive Assay (NDA) ! Derived

Capabilities3.3.2 .10.3 Transfer Provisions

----+; Derived

3.3.2.11 I Open Containers Derived _—_. —3.3.2.12 ] Provide Blending Capabil~ies Derived3.3.11.1 ‘ Design Life

——. .——i Denved

3.3.11.2 Housing Facility ! Derived3.4.1.1 50 Year Storage Capability ! Derived

I Temporary Storage Capacity m

l%%

_A_Derived -..—...-. -—. ——— .+—.“! Package Handling Throughput i Denved

-—

3.4.2.1———-.— ------

~ Receive Packaged Materials \ Derived3.4.2.2 I Identify Package Materials I Derived3.4.2.3 Transfer Packaged Materials I Derived3.4.2.4 Safely Store Packaged ‘“U i Derived

Materials ~

~3.4.2.5 : Retrieve ‘3JU Packages from DerivedStorage,

13.4.2.6 Collect, Segregate, Package, Derived, and Transfer Waste I

3.4.2.7 ~Handle Damaged Packages Derived !

3.4.2.8 ‘ Provide Surveillance , SAFT-0067Capability (

3.4.2.9 I Transfer Materials to Staging ~ DerivedI Area

3.4.6.1 ] Critically Safe Storage Arrays ] DOE 0420.1 (chg. 2)3.4.6.2 I Radiation Shielding i DOE O 420.1 (chg. 2)3.4.9.1 i Operator Intervention ; Derived

11

3.5.1 \ Performance : Derived———3.5.2.1 i Receive Materials _ ~ Derived

3.5.2.2 ~ Identify Materials ~Derived3.5.2.3 I Transfer Materials Between Derived

Subsystems3.5.2.4 Coordinate External Shipping Derived

I 3.5.2.5 i Overpack for Shipment Derived

; 3.5.2.6 , Provide Temporary Storage Derived

I 3.5.2.7 I Acquire Shipping Containers Derived I

i 3.5.5.1 ! Regulatory Compliance I DOE O 151.1 (chg.2) J3.5.5.2 ~ Medical Resources ~ Derived from DOE O ~

; 151.1 (chg. 2)

3.5.6.1 Confinement Derived

3.5.6.2 Off-site Transfers DOE O 460.1 A 4.a.(1 ) 1

3.5.6.3 Type A Radioactive Matenai DOE O 460.1 A Sect. 4a.(4)(a)Packaging WHC-EP-0558 Att. 1 (Subset. 3a)

3.5.6.3.1 Retesting DOE O 460.1 A 4a.(4)(a)WHC-EP-0558 Att. 1, Subset. 3.a

3.5.6.4 Type B or Fissile Radioactive DOE O 460.1 A Sect. 4a.(4)(b)Material Packaging WHC-EP-0558 _ Att. 1 (Subset. 3.b)

I 3.5.6.4.1 Use of NRC-Certified DOE O 460.1 A 4a.(4)(b)Packaging ! WHC-EP-0558 Att. 1, Subset. 3.b ~

3.5.6.4.2 Use of DOE-HQ Cetlified—.-—

I DOE O 460.1 A 4a.(4)(b)Packaging I wHc-EP-0558!_.. --- Att. 1, Subset. 3.b I.__. -_—-— —. .—

A-1 1

2mUSafe Storage System Rewsion OSystem Requirements Document May 1998

Requirement No. Requirement Title Requirement Source Source Paragraph3.5.6.5 On-site Transfers DOE O 460.1 A Sect. 4.b3.5.6.5.1 Methodology and Compliance DOE O 460.1 A Sect. 4.b

Process3.5.6.6 Safety Documents DOE O 460.1A Sect. 4.b3.5.6.6.1 Effective Date DOE O 460.1 A Sect. 4.b

~3.5.6.7 , Contractor Motor Carrier DOE O 460.1 A Att. 1 (Sect. 5) !

~Safety Regulations3.5.6.8 DOE Employee Motor Carrier DOE O 460.1A Att. 1 (Sect. 6)

Safety Regulations356.9 ~Transportation by Aircraft.~—.. _ DOE O 460.1 A ~ Sect. 4.d I3.5.7.1

——--—-—--—— .— .——i Safeguard Termination Limits Derived

3.5.7.2 I Materials in Excess of STLS Derived——

3.5.7.3 I Use of Transportation DOE AL 5610.14 I Ch. Ill, l.a

I I Safeguards System (TSS) \ I\ Services I

3.5.7.3.1 1 Request for TSS Services \ DOE AL 5610.14 Ch. Ill. 2 ,

t 3.5.7.3.2 ! TSS Packaging Requirements ~ DOE AL 5610.14 Ch. Ill, 4and Criteria I

; 3.5.8.1 Subsystem Reliability {TBD}I 3.5.8.2 ~ Reuse and Availability ~ Derived I

~ Impact on Shipping Schedules ~ Derived _j System Capacity \ DerivedI Departmental Materials ~ DOE C 460.2 Sect. 1 I

I I Transportation and Packaging ~ I II Management I ~

3.5.12.2 ] Materials Transportation Plan i DOE C 460.2 Sect. 2 II 3.5.12.2.1 I Materials Transportation Plan i DOE C 460.2 Sect. 2 I

L- 1 Content I~3.5.12.2.2 Transportation Information ~ DOE C 460.2 Sect. 2

, Network (TIN) II—-! 3.5.12.3 ~Transportation Tracking and ; DOE C 460.2

I ~Communications *-~ (TRANSCOM) System

13.5.12.3. Item A Spent nuclear fuel DOE C 460.2 ‘ Sect. 3

I 3.5.12.3, Item B , High-level waste DOE C 460.2 ~ Sect. 3I 3.5.12.3, Item C 1 High-visibility shipments and DOE C 460.2 I Sect. 3

I campaigns I

3.5.12.4 ] Shipment Procedures[~ DOE C 460.2 Sect. 4.a ,

I 3.5.12.5 I Contractor Requirements I DOE C 460.2 I

I Document for Departmental i~Materials Transportation and ~ I

Packaging Management I I3.6.1.1 Receipt Capacity ] Derived3.6.1.2 Waste Handling Derived I3.6.1.3 Operating Life Derived (3.6.2.1 Receive Waste Derived I3.6.2.2 Recover Waste Derived I

3.6.2.3 Collect Wastes ] Derived I3.6.2.4 Segregate and Treat Waste ] Derived3.6.2.5 Package Waste Derived3.6.2.6 Provide Temporary Storage Derived

------+I

3.6.2.7 Transfer Materials Derived, 4.1 Quality Requirements _ : DOE 0414,1

—--+-——. .—...——____ .—-———. -.

A 12

2*U Safe Storage System Revision OSystem Requirements Document May 1998

[ Requirement No, Requirement Title Requirement Source Source Paragraph! 4.1.1.1, Item A General Rule DOE O 414.1 Sect. 2

~4.1.1.1, Item B Implement the QAP DOE 0414.1 Sect. 2_ ..—, 4.1.1 .2.1 Quality Assurance Criteria DOE0414.1

4.1.1 .2.1 (1) Cflteria Satisfaction ~ DOE0414.1 Subset. 5.b—.—I 4.1.1 .2.1 (2) G ~ded Approach i DOE 0414.1 Subset. 5.b

14.1.1 .2.2 Quality Assurance Program : DOE0414.1 Sect. 2Implementation ———. _.—. —.. —-

4.1.1 .2.3 (1) Contractor Changes 10 CFR 830.120

i 4.1.1 .2.3 (2) Change Submittal 10 CFR 830.120

t 4.1.1 .2.3 (3) Submittal Contents I 10 CFR83O.12O ,—-,-.——....—.- —————‘ 4.1.1.2~ (4) Editorial Changes ?-10 CFR 830.120

II

—— --- .—— —— —-———

;4.1.1 .2.4 DOE Approval I 10 CFR 830.120 ‘---

~4.1.2.1.1 (1) Program Development \ Derwed

~4.1.2.1.1 (2) Organizational Structure and \ DerivedResponsibilities

‘4.1.2.1.1 (3)1

Management System I Derived

4.1.2.1.2 (1) Quality Improvement ] Derived I

Processes4.1.2.1.2 (2) I Identification and Control of Derwed

Problems I4.1.2.1.2 (3) Corrective Action I Derwed I

! 1

4.1.2.1.2 (4) Review and Analysis ] Derived

; 4.1.2.1.3 (1) Document Preparation and I Derived~

Approval

j 4.1.2.1.3 (2) Record Maintenance Derived _

4.1.2.2.1 (1) Controlled Conditions Derived

! 4.1.2.2.1 (2) Identification and Control I Derived .—I 4.1.2.2.1 (3) Maintenance ‘—1===~

4.1 .2.2.1 (4) Monitoring and Data Collection ~ DerivedEquipment——

~4.1.2.2.1 (5) Property Control-–-:*“-—-----=-——

4.1.2.2.2 (1) Principles and Standards I Derived

4.1.2.2.2 (2) Incorporation of Design Bases I Deflyed_-. —.——4.1.2.2.2 (3) I Design Interfaces Derwed

4.1.2.2.2 (4) \ Verification and Validation Derived

4.1.2.2.2 (5) ] Verification Timing I Derived

4.1.2.2.3 (1) I Performance Quality I Derived I~4.1.2.2.3 (2) Evaluation of Suppliers I Derived I

\ 4.1.2.2.3 (3) Supplier Reliability ] Derived I

14.1 .2.2.3 (4) Suspect/Counterfeit Items ~ DOE O 440.1A 1(S/CI) ControlsI

I 4.1.2.2.4 (1) Acceptance and Performance ~ Derwed 1

CriteriaI

4.1.2.2.4 (2) Equipment Maintenance Derived

4.1.2.3.1 (1) QAP Assessments Derived

4.1.2.3.1 (2) Corrective Action Derived .—4.1.2.3.2 (1) Conduct of Assessments Derived

4.1.2.3.2 (2) Assessment Authority Derived

4.1.2.3.2 (3) Technical Qualification Derived _

4.2.1.1 Conformance I Derived

Resources and Personne~—-....—.——.—

4.2.1.2 I Derived

4.2.2.1 Interface Verification =1=====-+–————; 4.2.2.2 ~tIo@wd~mmafl%.! Derived .._ __...d--d—~_.~

A-13

2=U Safe Storage System Revis/on OSystem Requirements Document May 1998

1I Requirement No. ] Requirement Title Requirement Source I Source Paragraph

4.2.3 ~Methods Derived! 4.2.4 , Requirements Matrix Derived

A-14

2SU Safe Storage System Revision OSvstem Requirements Document Mav 1998

APPENDIX B: REQUIREMENTS VERIFICATION MATRIX

Verification MethodRequirement Requirement Title N/A\TID All s3.2.1 Performance lx

3.2.2.1 Compatibility with 94-1 Systems3.2.2.2 General Functionality

—--++ ~ ,.- ...=— .—

xl

3.2.2.3 Transfer to Waste Disposal Programs \ H ,x I3.2.2.4 Monitor Materials and System Processes 1 ix3.2.2.5 Assure Safe Operating Conditions ! x3.2.2.6 Provide Package Surveillance Ca~abil~

)Ixi_...L_.. ———_.l——-...----.. — !

13.2.2.7 I Contain Material

I 3.2.2.8““--’---~- ~–’ : ~-;--i+==l+

- ...-..4..—--——-—Retrieve Material

3.2.2.9 Provide Containment Detection Capabilit i3.2.2.9.1 Containment Control x

3.2.2.9.2 Transfer Prowsions ix~3.2.3.1.1 97-1 33U Storage/ Commercial or DOE

!jxl il,

j] SNM Shippers Interface

I I I ( !3.2.3.1.1 (1) I Early Disposition x

3.2.3.1.1 (2) I Transport Requirements , x:I 3.2.3.1.1 (3) I Interface Requirements x

~3.2.3.1.2 ~Oak Ridge Molten Salt Reactor I :x:;Experiment I Commercial or DOE SNM ‘“ I

Shippers Interface I i!3.2.3.1.2 (1) Material and Packaging Requirements I I ‘x

I 3.2.3.1.2 (2) Interface Requirements !! x

3.2.3.1.3 Natural and Depleted Uranium / lx

Commercial or DOE SNM Shippers I1

InterfaceII

13.2.3.1.3 (1) Required Materlais I I x

3.2.3.1.3 (2) Material Specifications xl,——.._...._——! 3.2.3.1.3 (3) I Interface Requirements :x!’

! 3.2.3.1.4 [ Commercial or DOE SNM Shippers/ 233U I ;x~ I

i Safe Storage System Interface3.2.3.1.4 (1)

.—Transpon Reaulrements x

3.2.3.1.4 (2) I Transfer of ‘S3U Materials to DOE-MD ; x,,

: 3.2.3.1.4 (3) I Transfer of ‘J3U Materials to DOE-EM ! lx:! I. -.. .,

3.2.3.1.4 (4) ‘ Natural and Depleted Uranium I x!’

3.2.3.1.4 (5) Interface Requirements! :x

3.2.3.1.5I

Commercial or DOE SNM Shippers/ I Ixl[I DOE-MD Interface

I——

3.2.3.1.5 (1).——.——..———— -.

MD Materials and Packaging Acceptance I I ICriteria

3.2.3.1.5 (2) Interface Requirements 13.2.3.1.6 Commercial or DOE SNM Shippers/ I x

DOE-EM Waste Management Interface

3.2.3.1.6 (1) DOE-EM Waste Acceptance Criteria I3.2.3.1.6 (2) Interface Requirements

3.2.3.1.7 Commercial or DOE SNM Shippers / ! xBeneficial Use Interface _

3.2.3.1.7 (1) Interface Requirements

3.2.3.1.8 Sites and Facilities / ’33U Safe Storage-- +

-——~——

I---I System Interface 111—— -— .—.——.——.-... ..-... ——----

4=++x

x

+!+x

x’,&x’

B-1

2aU Safe Storage System Rev/s/on OSystem Requirements Document May 1998

Verification MethodRequirement Requirement Title I WA TIDIA II s

I 3.2.3.1.8 (1) Site and Facility Requirements 1 xl:

I 3.2.3.1.8 (2) Interface Requirements I ,t x

k

3.2.3.1.9 33U Safe Storage System/ External Ixl

Shipping Container Source Interface !3.2.3.1.9 (T Interface Requirements

—, lx

3.2.3.2.1 Transportation Subsystem / Processing ~ lx~’

Subsystem Interface \3.2.3.2.1 (1) Transfer of ’33U Materials3.2.3.2.1 (2) _ Transfer of Waste—— .— .— .——— ... ———.. . $ ~ ‘ +-x- ,- ,

-3.2.3.2.1 (3)——__+——

Interface Requirements--———.

3.2.3.2.2 Transportation Subsystem / Storage ~ - x :-~Subsystem Interface I j’

3.2.3.2.2 (1) Transfer of ’33U materials 1 X,13.2.3.2.2 (2) Transfer of Waste lx’

3.2.3.2.2 (3) Transfer of Damaged Packages lx

! 3.2.3.2.2 (4) I Interface Requirements I lx]

3.2.3.2.3 I Transportation Subsystem / Waste x 1:

1 Management Subsystem Interface iI113.2.3.2.3(1) Transfer of Waste I /Xi, 3.2.3.2.3 (2) Internal Waste Acceptance Criteria I x

1 3.2.3.2.3 (3) Interface Requirements lx3.2.3.2.4 Processing Subsystem / Storage x

Subsystem Interface {TBR} I3.2.3.2.4 (1) Transfer of Processed Materials lx’

3.2.3.2.4 (2) Transfer of Packages Requiring xAdditional Processing and/or Packaging

3.2.3.2.4 (3) Packaging and Acceptance Criteria ~x ‘i 3.2.3.2.4 (4) Transfer of Damaged or Opened x

Packages I— —— .-L__l__J: 3.2.3.2.4 (5) Interface Requirements I ! x

I 3.2.3.2.5 Processing Subsystem / Waste I lx: Management Subsystem Interface

3.2.3.2.5 (1) ~Waste Acceptance Criteria x

3.2.3.2.5 (2) ; Interface Requirements x; I~3.2.3.2.6 Storage Subsystem / Waste Management I x;

Subsystem Interface II; 3.2.3.2.6 (1) Waste Acceptance Criteria I I ‘x

~3.2.3 .2.6 (2) Interface Requirements I I x

‘ 3.2.4— -———+——–-—— -----

Information Systems 1 x’

3.2.4.1.1 DatabaseI x

I 3.2.4.1.1 (1) Classified Data Separation Ii \x

3.2.4.1.1 (l)(a) Classification Guide I x

3.2.4.1.2 (2) Compatibility x;

3.2.4.1.1 (3) Data Architecture lx

i 3.2.4.1.1 (4) Transferability x

3.2.4.1.2 Data Access Control ! xl

3.2.4.2.1 Material Transfer x

3.2.4.2.2 Material Location x ‘ ‘

3.2.4.2.3 Analysis and Separation I IX 43.2.4.2.4 Material Physical Form I lx3.2.4.2.5 Moisture Content --- ! x !

: 3.2.4.2.6 \ Stabilization Test–—-—----i——— _.. .—~ . —.,

1 x I

2SU Safe Storage System Revision OSystem Requirements Document May 1998

Verification MethodRequirement Requirement Titie N/A T D] AI s3.2.4.2.7 Processing Conditions x,—.3.2.4.2.7 (1) Processing ( xl ;

\ 3.2.4.2.8 Package Configuration I \x

3.2.4.2.9 Packaging Date 1 I x3.2.4.2.10 Initial Radiation Field

I1 lx

~2.4.2.11 Chemical Composition I [x—.. .—.—-— .—— —. . —I 3.2.4.2.12 Isotopic Fraction \:–\x

3.2.4.2.13 Material Source I x

3.2.4.2.14 IPackage Identification Number ix~.15 ___ ~

?sw~~~~nc~e~~~e~~~e>---”””—--—”---—-+— -–--—

.— ——xii

~3.2.42.16 P x.—.. —3.2.4.2.17 Individuals Performing Inspections [

.. —.-—.— —-. —ix

3.2.4.2.18 Inspection Dates ix

3.2.4.2.19 Fill Gas 1 x

3.2.4.2.20 Elemental Concentration or Mass lx

~3.2.4.2.21 Baseline Package I!i :x

t 3.2.4.2.22 ~ Container Lot Identification Number I xl I3.2.4.2.23 ~Other Relevant Information I xl

~3.2.4.3 Historical Records x: 1~3.2.5.1 Communications xl

t 3.2.5.2I

Emergency Management System I x’i 3.2.5.3 Emergency Planning and Preparedness : x] I ,I 3.2.5.4 Emergency Response xi ;

3.2.5.5 Medical Support :x

3.2.5.6 Emergency Transition lx ;’

F

Operator Intervention I I1 x—.3:2.5:6.2

+—Economic Loss / ,x,

3.2.5.7 Emergency Recovery x ! I

*:’Recovery Procedures { -. :x——Implementation ‘x’. .

3.2.5.9 Operations/Field Office Manager 11~ ~x~;Responsibilities

3.2.5.10 Site/Facility Manager Responsibilities

3.2.5.11

x

Operational Emergency BaseGeneral x

~3.2.5.12 ! O~erational Emergency Base Related , ‘ x!’1-

; Regulations and P-lans-1

! i

~ 3.2.5.13 ; Operational Emergency Base Planning I : I x

i 3.2.5.14 I Operational Emergency Base lx I III Preparedness l’, !

— --I 3.2.5.15 Operational Emergency Base Response x

3.2.5.16 Operational Emergency Hazardous I lxMaterial Program I I

I 3.2.5.17 Operational Emergency Events andConditions I ix

3.2.5.18 Public Affairs Policy and Planning x: I

3.2.5.19 Evaluations and Readiness Assurance I I x

3.2.5.20 Emergency Readiness Assurance ! ‘x

Appraisals and Assessments

ml— Contractor Requirements x 14

3.2.6.1, Item A Regulatory Compliance — x

‘ 3.2.6.1, Item B Regulatory Compliance x

! 3.2.6.1, Item C ! Regulatory Compliance ______ .—-—..——.——— —_L-_-’ x!’.—. - .... ..—— — .

B-3


Verification MethodRequirement I Requirement Title WA T D All s

I 3.2.6.1, Item D.—

Regulatory Compliance x~3.2.6.1, Item E Regulatory Compliance lx-—.

3.2.6.1, Item F———

Regulatory Compliance , x ~

3.2.6.1, Item G-——

Regulatory Compliance x;.———-.—.-—._————3.2.6.1, Item H , Regulatory Compliance (

—— . .—.—--—.....——— _L.~_l_ x ‘-I 3.2.6.1, Item I ~ Regulatory Compliance ‘X11

3.2.6.1, Item J Regulatory Compliance I x I

3.2.6.1, Item K Regulatory Compliance3.2.6.2

1-I Fire Protection

—.-. -.- ...-. ..-+ ,J, xi !.—----

3.2.6.2, Item A... . ..—-.. -.1.—- ._._T ,.—.-.._ . .

I Fire Protection ‘“”- ‘“ ‘-- , ~ 1 xi—.— —.—-.-—...-.-—...-.—.-.. ..- ———-—..—.——.— ~—. .3.2.6.2, Item B ! Fire Protection 1 lx’———-—3.2.6.2, Item C ! Fire Protection x j.——3.2.6.2, Item D ~ Fire Protection I x I3.2.6.2, Item E I Fire Protection

Ix,!

I 3.2.6.2, Item F ; Fire Protection 1, ~x~:3.2.6.3 Radiological Protection ix:

3.2.6.3.1 Sampling Airborne Radioactwe Materials :x I————j 3.2.6.3.2 Radiation Shielding IX~3.2.6.3.3 ~ALARA

1 I :x3.2.6.3.4 ~ Key Radiation Protection Positions ‘ 1 I lx—— ——3.2.6.4 ~Worker Protection I xl!3.2.6.4.1, Item A

1\ Worker Protection Program I xl

3.2.6.4.1, Item B I Worker Protection Program I Xj’

3.2.6.4.1, Item C ] Worker Protection Program-

I x I3.2.6.4.2

.——----] Industrial Hygiene Program J Ii xl]

3.2.6.5———

i Material Handling1

x; I——.

3.2.6.6 ~ Comprehensive Monitoring x! I-

f3.2.6.6.1 ] Safety and Operating Status3.2.6.7

—--—- ..-.\ Nuclear Criticality Safety -----+++-+ 1 I ~

3.2.6.7, Item A—.—

I Nuclear Criticality Safety — 1 x:’I 3.2.6.7, Item B t Nuclear Criticality Safety I I ~ ‘x———

3.2.6.7, Item C Nuclear Criticality Safety ‘x

3.2.6.7, Item D Nuclear Criticality Safety ,x

~ 3.2.6.7.1 I Nuclear Criticality Alarms xi I

~ 3.2.6.7.2 ~ New Facilities Design /x I

3.2.6.7.3 ~ Nuclear Criticality Safety m Operations x; I 11

3.2.6.7.4 I Nuclear Criticality Safety Tramlng .- ~ I ;Xi

3.2.6.8 ~ Pressure Safety !X! !—-——— —. _—

13.2.6.9 I Hazard Prevention ‘x

i 3.2.6 .10.1 ; Performance Indicator Program I x I

3.2.6 .10.2 Root Cause Analyses I x3.2.6 .10.3 Feedback Mechanisms x I3.2.6 .10.4 Management Information System xl!

3.2.6 .10.5 Program Assessments I x’3.2.6 .10.6 Analytical Data x

3.2.6 .11.1 Investigation Procedures x

3.2.6 .11.2 Type A / Type B Investigations x ,!’-3.2.6.12 ~ Nuclear Safety Implementation Plan I I x ,3.2.6 .12.1

——-—+-----1- !Relief from Nuclear Safety Requirements i I x I

3.2.6 .12.2 Exemptions1 x]----——-

I 3.2.6 .12.2 (1) Requesting and Granting DOE Nuclear I iX!’I

I Safety Exemptions 1


Verification MethodRequirement I Requirement Title I T DIA\ll S3.2.6.13 ] NEPA Implementing Procedures ~x~3.2.6.14 I Planning and Conduct of Operational - ~

] Readiness ReviewsL

xil~x!

3.2.6.15 I Safety Analysis Reporting lmp~mentation I i jxj

3.2.7.1 ~ Safeguards and Security Program I ‘x~!~3.2.7.2

—.—.———..—.I Personnel Security - xl

3.2.7.3”-—-—------ —----—-—+-——— i

Review of Sensitive Activities I lx;3.2.7.4 Materials Control and Accountability xl

3.2.7.4.1 (l)(a) i Materials Control and Accountability Plan I IX

3.2.7.4:1 (1) (b) : Management Approval ‘——--.—.. .. .—.. ..._...—+-—..- 33.2.7.4.1 (1)(c) ~Minimum Requirements

L...,x~;

._J__ ‘ x ‘———

---1 ——*3.2.7.4.1 (l)(d) \ International Atomic Energy Agency

——

$1( IAEA) and NRC Standards I I

3.2.7.4.1 (l)(e) I I~ASTM and ANSI Standards 1 lx

3.2.7.4.1 (2) I Graded Safeguards I 1 ]x~

3.2.7.4.1 (3) \ Materials Control and Accountability 1: I I lxRequirements for Source and Other ~, I

Nuclear Materials13.2.7.4.1 (4)(a) Vulnerability Assessment ‘x

3.2.7.4.1 (4)(b) , Performance Testing I x;!

3.2.7.4.1 (5) 1 Monitoring Programs I !x~ I )I 3.2.7.4.1 (6) Administrative Controls I I I

3.2.7.4.2 (1) Accounting Systems,

3.2.7.4.2 (1) (a) Material Inventories and DataI

3.2.7.4.2 (2) i Physical Inventories3.2.7.4.2 (2)(a) ~ Program Compliance3.2.7.4.2 (2)(b) ; Responsibilities -= * ,~1x

.-—-—-—...i–.––3.2.7.4.2 (2)(c) I Fre uenc~—–----L-- 1 xl

3.2.7.4.2 (3) I Measurements and Measurement Control Xi I———3.2.7.4.2 (4) I Material Transfers iXi I

—.—.. — 43.2.7.4.2 (5) I Material Control Indicators !Xl I3.2.7.4.2 (6) \ Documentation and Reporting -_ [ l.’ x’

3.2.7.4.3 (1) General x

3.2.7.4.3 (2) Plan Documentation x

~3.2.7.4.3 (3) Access I I x:3.2.7.4.3 (4) Surveillance x

, 3.2.7.4.3 (5) I Controls Program ‘xl I

3.2.7.4.3 (6) Detection/Assessment - 1 x!3.2.7.5_

1! Information Security x.-—-...—-.-~-——-—————--—+-—-—-—

I 3.2.7.5,1 ~Access to Classlfied;nd Sensmve— .—- -—

xI Unclassified Information I

1 I3.2.7.5.2 Classified Information Systems x I3.2.7.5.3

!Deviations I xi

3.2.7.5.4, Item A Supplementary Directives I x;

3.2.7.5.4, Item B Supplementary Directives I lx3.2.7.5.4, Item C Supplementary Directives IX I3.2.7.5.5, Item A Guides x3.2.7.5.5, Item B \ Guides — .—+–—. ‘ 1X1

~3.2.7.5.6 ! Responsibilities and Auth~rities -. .-..3.2.7.5.7

----- -—-Program Management

I

3.2.7.5.8 Operations Security Program –+:t ~ i 1:! i32.7.5.9 Classified Information Systems Security ‘x~—..—.—..—..—-— _——- .._.. ——.. . ,- - .—..L_ .— .-——

B-5

*WU Safe Storage System Revision OSvstem Requirements Document Mav 1998

Verification MethodRequirement Requirement Title NIA T D A I s3.2.7.5.10 Protection and Control of Classified x

1 Matter3.2.7.5.11 \ Identification of Classified Information I x3.2.7.5.12 I Contractor Information Security Program3.2.7.6 I Unclassified Computer Security Program ~ ———..—_3.2.7.7 ‘-——

—i Risk Management

3.2.7.8 \ Site Specific Characteristics

---+--j -- / x ~ ~ t;1

x !3.2.7.9 I Deviations Requirements _3.2.7.10 I standardization -—-~+–””; -------

x ,!,= ,_-,___ , .-~ ;—.—-.-.... .—— ——. --- .—--———--,—7—.

3.2.7.”11 I Threat

3.2.7.12 “-- Site Safeguards and Securit~-Plan3.2.7 .12.1 Plan Contents

‘a ‘“---”’---T-– ‘-; ~1

3.2.7.13 Security Plan x I

3.2.7.14 Plan Review I x !3.2.7.15 Training Program I x

i 3.2.7.16 Training Standardization I ,Xi3.2.7.17 ~ Unclassified Controlled Nuclear I :x;

~ Information I

~3.2.7.18I I I 4

~ Training Records I I lx~3.2.7.19 Safeguards and Security Awareness I

I xi 3.2.7.20 — Self-Assessment x

3.2.7.21 Performance Assurance x ‘i3.2.7.22 Documentation I x3.2.7.23 Contractor Requirements I x3.2.7.24 I Protective Force Program I x 1

3.2.8.1 Reliability—.—.+.

‘x3.2.8.1.1 Reliability Allocations3.2.8.2 _ -

~ ‘,

, Availability3.2.8.3 I Maintainability — I3.2.9 Human Factors x3.2.10.1 I Orgamzation ! I x3.2.10.2 Organlzatlonal Responsibilities \x!-3.2.10.2.1 , Documentation x,

, 3.2.10.3 ! Subcontractor Personnel I I I x II 3.2.10.4 \ Personnel Selection lx

~3.2.10.5 IProcess 1 IX

I 3.2.10.6 Certification I 1 x I

3.2.10.7 Training ! lx !.——.—3.2.10.7.1 ‘“– Graded Approach ~-—–l--’----: x ‘,

3.2.10.7.2 Implementation Matrix ix

3.2.10.7.2 (1) Training Responsibility I x ;3.2.10.7.2 (2) Justification for Exceptions x I I

3.2.10.7.2 (3) Matrix Substitution x1

3.2.10.7.3 Program Basis3.2.10.7.4

XflTraining and Qualification Needs x

3.2.10.8 Operator and Supervisor Examination x

3.2.10.9 Operator and Supervisor Reexamination x

3.2.10.10 Requalification :x

3.2.10 .10.1 Administration x

3.2.10.11 Exceptions to Training Requirements ,I x !

,3.2.10.12 ! Extensions ‘xi ___ i—.——— .—.———.— —.

2Su Safe Storage System Revision OSystem Requirements Document May 1998

Verification Method[ Requirement I Requirement Title /tWA] T D]A 11sI 3.2.10.13 I Alternates to Education and Experience ~ X I I1

~ Requirements I I 1~1~:

‘ 3.2.10.14 \ Record Requirements ~1 I x ,

3.2.10 .14.1 : Standardization of Training RecordsI xi /

3.2.10 .14.2I

‘ Personnel Qualification and Certification ~ lx! Records ) I

}- -——-11—— -.~.—-4.-

3.2.10.15 , Worker Protection Training I ix’ II 3.2.10.16 ! Measurement Training Plan x

\ 3.2.10 .16.11

; Measurement x 4I 3.2.10 .16.2 Proficiency Demonstration IX!’—-——— ————~2.10.16.3

——-———... —... .—._. .—-+..—.--J.. .—_._l_. —, Requalification ‘x, : I+..———

~3.2.10.17 Contractor Requirements Document ~ ! ! 1 x !I 3.2.10.17, Item A Contractor Requirements Document i I x I~ 3.2.10.17, Item B ! Contractor Requirements Document x I

~ 3.2.10.17, Item C Contractor Requirements Document ~ i ,! x j

‘ 3.2.10.17, Item D Contractor Requirements Document I 1lx

3.2.10.17, Item E Contractor Requirements Document X3.2.11.1 Operations Design x

3.2.11.2 Design Modifications ,x

~ 3.2.11 .2.1 Design and Analysis lx’3.2.11.3 Natural Phenomena Hazards Mitigation I Xi

~3.2.11 .3.1———-

I Natural Phenomena Hazards Approach I I lx’‘ 3.2.11 .3.2 Safety Classifications ( I I x

3.2.11 .3.3 I Safety Class SSCs I I x !

‘ 3,2.11 .3.4 Ij Wind/Tornado Hazard Data I x’I 3.2.11 .3.5 ! Flood Protection and Emergency I x ~

~Operations PlansI

—I 3.2.11 .3.6 ; Site Investigations 1 I I ,x ,I 3.2.11 .3.7 ‘ Other Considerations xi 1!%mz---- Industry Codes and Standards 1 \Q_ x!__

3.2.11.5———

Minimization of Economic Loss. xi I

3.2.11.6 Construction Materials x

3.2.11 .6.1 Work Area Coatings x

3.2.11 .6.2 Industry Standards x

3.2.11.7 Design Requirements Application x, I

3.2.11.8 Applicability xi

3.2.11.9 Existing Facilities x;,

3.2.11.10 Site Investigation Program 1 lx,:3.2.11.11 IAnalysis Techniques I x’_— .——. —. ..———.-—__. —. .——

3.2.11.12 I Part-time Inventory 1 I I x,

I 3.2.11.13 I Electrical Design I ~ lx!;! 3.2.11 .13.1 Facility Safety Class Electrical Systems !

, I xi

3.2.11.14 Backup Power Sources, x

3.2.11.15 , Ventilation Systems ‘x ,~~3.2.11 .15,1 Procurement and Testing of HEPA Filters i xii

3.2.12.1y

LCAM Approach x j

3.2.12.2 LCAM Practice(s) x

3.2.12.3 Performance Measures x ~!

3.2.12.4 Acquisition Approach x

~3.2.12.5 \ Project Management System It-~- ~xi’

~ 3.2.12.5.1 ] Conceptual DesignI (

1 Ix\j

3.2.12.5.1, Item A ; Mission Need I x-—.—....————— .———.- —.—....—_—-. ——-..— ,_.. _ ._____ . ..__ ————-..

B-7

2=U Safe Storage System Rev/s/on OSystem Requirements Document May 1998

Verification MethodRequirement Requirement Title pJ/A_ T D A 1 s3.2.12.5.1, Item B Minimum Technical Functional

Requirements3.2.12.5.1, Item C Proposed Cost and Schedule Ranges I x ‘3.2.12.5.1, Item D Preliminary Environmental Strategy

,I x

3.2.12.5.1, Item E Project Technical and Organizational ,-——+——

x

F I Interfaces3.2.12.5.1, Item F I Integration With Other Projects and

I I xAgencies I

: 3.2.12.5.2—

Execution I I

l&.M.2, Item A—

xl

- ““ ._.._._....+.:-:+ “--’--- ““-”’~”- 1 ;——.——...——. .-..—-....

Project Objectives. . . .

I 3.2.12.5.2, Item B Scope, Schedule, and Cost Baselines ~ ‘-’-– “--– “–--”:–--––;”+ j———— .—

‘ 3.2.12.5.2, Item C Life Cycle Cost Analysis--’--’-j-

___+______ ‘x3.2.12.5.2, Item D Preliminary Safety Assessment x3.2.12.5.2, Item E Project Controls

-—”——t—— ~ ~ ~x

3.2.12.5.2, Item F NEPA Documentation III

X!~3.2.12.5.2, Item G Verification Of Performance Criteria ,: I x

3.2.12.5.2, Item H Design Alternatives ,x!...—— —3.2.12.5.3 I Operation I ;X;’3.2.12.5.3, Item A

——I Turnover Plan I ]x~, ,

i 3.2.12.5.3, Item B ] Verification Of Performance Criteria I 1’ x].—: 3.2.12.5.3, Item C Operational Readiness x~3.2.12.5.4 Conduct of Operations x

3.2.12.6 Operation and Maintenance Process ~ 1 I x3.2.12.7 Disposition Process ——— __+._._+.._ ‘ ‘— ‘x3.2.12.8 Utility Services -L— — —x——.—.3.2.12.9 Asset Database

-l—————J———! —+~.. ~ x—-—

3.2.12.10

—_5

.—Compliance x

3.2.12.11 Logistics3.2.12 .12.1

-1--- ~ ,xComponent Decontamination – _~,~ X ~ ,———--—--

3.2.12 .12.2 I Decontamination Solutions x: ~+--

3.2.12 .12.3 ] Minimal Effort to D&D ]X” ~-..3.2.12 .12.4 ~ Federal Requirements and Orders ~ :x::3.2.13.1

—— ——.State and Tribal Laws and Agreements ‘x

3.2.13.2 ] Local Ordinances ix!(! 3.3.1.1 Processing Capacity and Capability ] ‘x’ II 3.3.1 .1.1 Isotope Separation for Beneficial Use ] iX,t 3.3.1 .1.2 Duration of Processing Capability I x;

3.3.1.2 Stabilization Capability 1 I x—.——‘ 3.3.1.3

.-—---4...-. .-...-. .----..———..—.—-.—--I Variant Materials Processing 1 x

I ~i

I 3.3.2.1 Receive Materials –—-~–—---- —- lx’

1 3.3.2.2 Transfer to External Systems IX3.3.2.3 Remove from Packaging Containers x3.3.2.4 Converl to Stable Lonq-term Forms3.3.2.5 Stabilize for Packaging x!3.3.2.6 Package to ‘J3U Safe Storage Standard ~ x

3.3.2.6.1 Package Labeling x

3.3.2.7 Handle Packages lx3.3.2.8 Stage Materials xi

3.3.2.9 Collect Waste Byproducts

‘“: -*~ ~

lx’

3.3.2.9.1—.

Segregate, Pretreat, and Transfer Wastes; 3.3.2.10 Characterize Materials x—.. — —..—-.-..—.... ..—.—.-I 3.3.2 .10.1 — Sampling Capability xl

‘XL) Safe Storage System Revision OSystem Requirements Document May 1998

1 Verification Method~Requirement Requirement Title ]wA\TID A I s

3.3.2 .10.2 Non-Destructive Assay (NDA) Capabilities 1:~xl i1 3.3.2 .10.3 Transfer Provisions x

3.3.2.11 Open Containers1

—–---.-.-L. .~ ~. :

I 3.3.2.12 Provide Blending Capabilities )~3.3.11.1

—.-. .Design Life __..+_x;.--x ‘

3.4.1.1ix

50 Year Storage Capability I ( I

~ 3.4.1.2... .. .. . . --.-————

Temporary Storage Capacity ~x;~j! 3.4.1.3 Package Handling Throughput x ]; j

3.4.2.1 Receive Packaged Materials x;3.4.2.2

——-.—-—-.—-------- —--.“~ —..-—---Identify Packaqe Materials x I_—— —-...——.. . . .; . .... ..L.._._- ..._...___l_~

3.4.2.3 Transfer Packaged Materials -i——— x

=4—--. — 4.——. .—L..-..-

Safely Store Packaged ‘3aU Materials j _ Ixi1

i 3.4.2.5 Retrieve ‘3aU Packages from Storage ;X I! 3.4.2.6 Collect, Segregate, Package, and x

Transfer WasteII!1:

I

3.4.2.7 Handle Damaged Packages ix:

3.4.2.8 ~ Provide Surveillance Capability x ;

3.4.2.9 ~Transfer Materials to Staging Area ! x’ I

3.4.6.1 ~Critically Safe Storage Arrays ! x

3.4.6.2 i Radiation Shielding I I ix :

3.4.9.1 \ Operator Intervention Lx ;; x-1 3.5.1 Performance I

I I i

: 3.5.2.1 Receive Materials —+-A--- X I

3.5.2.2—

identify Materials /x j!/ 1—-

I 3.5.2.3 Transfer Materials Between Subsystems ! !3.5.2.4 Coordinate External Shippin

!

; 3.5.2.5 Overpack for Shipment g --------- /

I 3.5.2.6 Provide Temporary Storage ~; Ix:

~3.5.2.7 Acquire Shipping Containers I

‘ 3.5.5.1 Regulatory Compliance___ ... ...._~x~_~-~x~

ixi i3.5.5.2 Medical Resources ! \

I {x3.5.6.1 Confinement x:.——3.5.6.2 ~Off-site Transfers x

3.5.6.3 Type A Raaioactwe Material PacKaglng x

3.5.6.3.1 I Retesting x

3.5.6.4 I Type B or Fisslle Radioactwe MaterialI Packaging

:xI

3.5.6.4.1 ] Use of NRC-Certified Packaging i .K.._3.5.6.4.2 ~ Use of DOE-HQ Certified Packaging x

—--~__ —--..._ ———. —

3.5.6.5 On-site Transfers , I 1—.

‘x

3.5.6.5.1 Methodology and Compliance Process ‘;” xi~,

3.5.6.6 Safety Documents xl

3.5.6.6.1 Effective Date I lx

3.5.6.7 Contractor Motor Carrier SafetyI [x 1

Regulations .—i 3.5.6.8 DOE Employee Motor Carrier Safety

IIx

Regulations

3.5.6.9 Transportation by Aircraft I

x.1-T--——.—.

Safeguard Termination Limits x.——

‘ ““---t-+

— -.. -.. ..-- .——-——- .-—--3.5.7,2 Materials in Excess of STLS

, 3.5.7.3 Use of Transpiration Safeguards System ~(TSS) Sewices-.-—-------.-—.—— — ._—.—— . ........-— — -.-1-- - -------.——.--.—---~

B-9

2=U Safe Storage System Revision OSvstem Requirements Document Mav 1998

Verification MethodRequirement \ Requirement Title IWAIT]DIAI IIS3.5.7.3.1 I Request for TSS Serwces x

~3.5.7.3.2 TSS Packaging Requirements andCriteria

3.5.8.1 Subsystem Reliability I

IXl

I I-.—

3.5.8.2 Reuse and Availability xl—

1

3.5.8.3 Impact on Shipping Schedules x I

3.5.8.4 System Capacity x3.5.12.1 Dec)artmental Materials Trans~ortation !

—(Xi

aterials Transportation Plan I I II 1X1 I

3.5.12.2.2 Transportation Information Network (TIN) x3.5.12.3 Transportation Tracking and x

Communications(TRANSCOM) System3.5.12.3. Item A I Spent nuclear fuel lx

3.5.12.3, Item B ~ High-level waste 1’ lx, I

3.5.12.3. Item C ~ High-visibility shipments and campaigns :x !

! 3.5.12.4 Shipment Procedures I lx

; 3.5.12.5 Contractor Requirements Document for ; lxDepartmental Materials Transportation !and Packaging Management

3.6.1.1 Receipt Capacity x

3.6.1.2 Waste Handling x !3.6.1.3 Operating Life lx3.6.2.1 Receive Waste x3.6.22 Recover Waste lx

5:3 Collect Wastes x3.6.2.4 Segregate and Treat Waste x3.6.2.5 Package Waste xi

I 3.6.2.6 Provide Temporary Storaqe ix~, Il!

3.6.2.7 : Transfer Materials x ~ I

2-U Safe Storage System Reviskm OSystem F?equirements Document May 1998

APPENDIX C: RELATED DOCUMENTS

The following related documents provided additional guidance on how to carry out therequirements and operations of the ’33U Safe Storage Program.

\ DOE G 420.1-X (DRAFT) I IMPLEMENTATION GUIDE FOR NON-REACTOR NUCLEAR I

1 FACILITY SAFETY~0= G 420.1 -Y(DRAFT) I GUIDE FOR MITIGATION OF NATURAL PHENOMENA II I

I

DOE G 440.1-5 ! FIRE SAFETY GUIDEL— ..—~DOE G441.1-1

— ——-—~

I DOE G 460.1-1 I IMPLEMENTATION GUIDE FOR PACKAGING ANDI I TRANSPORTATION SAFETY~ DOE G 460.2-1 ~ IMPLEMENTATION GUIDE FOR DEPARTMENTAL

I METERIALS TRANSPORTATION AND PAC~AGINGI1

MANAGEMENTDOE G 5633.3A GUIDE FOR IMPLEMENTATION OF DOE 5633.3A (2/93)DOE GPG-FM-01 through 33 (SERIES) GOOD PRACTICES GUIDES FOR

IMPLEMENTATION OF DOE ORDER 430.1; DOE M 430.1 (Draft) ‘ DIRECTIVES MANAGEMENT DOCUMENT FOR DOE O

430.1 I; DoE/EM-40 ! DECONTAMINATION AND DECOMMISSIONING GUIDANCE ~

~ DOCUMENT, DRAFT 3

t DOE-EM-STD-5505-96 I OPERATIONS ASSESSMENTS

I DO E-H DBK-1OO2-96 ~GUIDE TO GOOD PRACTICES FOR TRAINING AND~QUALIFICATION OF CHEMICAL OPERATORS

~ DOE-HDBK-1OO3-96 I GUIDE TO GOOD PRACTICES FOR TRAINING AND; QUALIFICATION OF MAINTENANCE PERSONNEL J—. —-— ——

DOE-HDBK-1O62-96 ~ DOE FIRE PROTECTION HANDBOOK

DOE-HDBK-1O81-94 PRIMER ON SPONTANEOUS HEATING ANDPYROPHORICITY

DOE-HDBK-1O85-95 , DOE ENFORCEMENT PROGRAM ROLES ANDRESPONSIBILITIES

DOE-HDBK-1O87-95 ; ENFORCEMENT HANDBOOK: ENFORCEMENT OF DOEI ~ NUCLEAR SAFETY REQUIREMENTS I._—.- —--. _..... -_—

, DOE-HDBK-1O89-95 , GUIDANCE FOR IDENTIFYING, REPORTING AND~TRACKING NUCLEAR SAFETY NONCOMPLIANCES ~I

DOE-HDBK-1O99-96 ESTABLISHING NUCLEAR FACILITY DRILL PROGRAMS

DOE-H DBK-1 100-96 I CHEMICAL PROCESS HAZARDS ANALYSIS

DOE-HDBK-11O1-96 PROCESS SAFETY MANAGEMENT FOR HIGHLYHAZARDOUS CHEMICALS

, DOE-HDBK-1 106-97 , RADIOLOGICAL CONTAMINATION CONTROL TRAININGFOR LABORATORY RESEARCH

. . . . —— ——

I DOE-HDBK-1204-97 GUIDE TO GOOD PRACTICES FOR THE DEVELOPMENT i1OF TEST ITEMS

———.. ———..-— .—.— ——— .-—--L————---- ——— — . ... . ..-.. -... —--...—

c-1

2SU Safe Storage System Revision OSystem Requirements Document Mav 1998

DOE-HDBK-3012-96I

GUIDE TO GOOD PRACTICES FOR OPERATIONALI READINESS REVIEWS (ORR), TEAM LEADER’S GUIDE [

DOE-HDBK-5504-95 ~GUIDANCE FOR EVALUATION OF OPERATIONAL1 EMERGENCY PLANS

( DOE-NE-STD-1OO4-92I 1! ROOT CAUSE ANALYSIS GUIDANCE DOCUMENT

‘ DOE-STD-1 009-92 ~GUIDE TO GOOD PRACTICES FOR THE DEVELOPMENT ;, ] OF TEST ITEMS II

‘ DOE-STD-1O1O-92 ~GUIDE TO GOOD PRACTICES FOR INCORPORATING ~! OPERATING EXPERIENCES

DOE-STD-1O1-92 ; COMPILATION OF NUCLEAR SAFETY CRITERIA FORPOTENTIAL APPLICATION TO DOE NONREACTORNUCLEAR FACILITIES

DO E-STD-1 030-96 I GUIDE TO GOOD PRACTICES FOR LOCKOUTS AND ~TAGOUTS

DOE-STD-1O31-92 GUIDE TO GOOD PRACTICES FOR COMMUNICATIONS

DOE-STD-1 032-92 GUIDE TO GOOD PRACTICES FOR OPERATIONS~ORGANIZATION AND ADMINISTRATION

DOE-STD-1O34-93 ~ GUIDE TO GOOD PRACTICES FOR TIMELY ORDERS TOI OPERATORS

DOE-STD-1O35-93 I GUIDE TO GOOD PRACTICES FOR LOGKEEPING

DOE-STD-1O36-93 ~ GUIDE TO GOOD PRACTICES FOR INDEPENDENT~VERIFICATION

~ DOE-STD-1O37-93 I GUIDE TO GOOD PRACTICES FOR OPERATIONSI

1ASPECTS OF UNIQUE PROCESSES~

DOE-STD-1O38-93 GUIDE TO GOOD PRACTICES FOR OPERATIONS, TURNOVER

DOE-STD-1 039-93 GUIDE TO GOOD PRACTICES FOR CONTROL OFEQUIPMENT AND SYSTEM STATUS

DOE-STD-1O4O-93 ‘ GUIDE TO GOOD PRACTICES FOR CONTROL OF ON-SHIFT TRAINING

DOE-STD-1041 -93 ; GUIDE TO GOOD PRACTICES FOR SHIFT ROUTINES ANDI OPERATING PRACTICES

DOE-STD-1O42-93 I GUIDE TO GOOD PRACTICES FOR CONTROL AREAACTIVITIES

I DoE-sTD-1043-93 GUIDE TO GOOD PRACTICES FOR OPERATOR AIDI

I! POSTINGS

I DOE-STD-1 044-93 GUIDE TO GOOD PRACTICES FOR EQUIPMENT AND ~I PIPING LABELING ,

i DOE-STD-1 045-93 GUIDE TO GOOD PRACTICES FOR NOTIFICATIONS AND ~INVESTIGATION OF ABNORMAL EVENTS— ——

DOE-STD-1O5O-93 GUIDELINE TO GOOD PRACTICES FOR PLANNING, ~I SCHEDULING, AND COORDINATION OF MAINTENANCE

AT DOE NUCLEAR FACILITIES—— .... . .————————. — ..—-....———..—..- —. . —

‘ml) Safe Storage System Revkmn OSystem Requirements Document May 1998

DOE-STD-1O51-93 GUIDELINE TO GOOD PRACTICES FOR MAINTENANCEORGANIZATION AND ADMINISTRATION AT DOE NUCLEAR !

I FACILITIES

~ DOE-STD-1 052-93 I GUIDELINE TO GOOD PRACTICES FOR TYPES OF ~MAINTENANCE ACTIVITIES AT DOE NUCLEAR FACILITIES I

I DOE-STD-1 053-93 GUIDELINE TO GOOD PRACTICES FOR CONTROL OF :MAINTENANCE ACTIVITIES AT DOE NUCLEAR FACILITIES ~

! DOE-STD-1 054-93 GUIDELINE TO GOOD PRACTICES FOR CONTROL AND ~I CALIBRATION OF MEASURING AND TEST EQUIPMENT

1I ! (M&TE) AT DOE NUCLEAR FACILITIES~ .. ——.—~ DOE-STD-1 055-93

—-.— —.—.—

, GUIDELINE TO GOOD PRACTICES FOR MAINTENANCE ,

1

‘ MANAGEMENT INVOLVEMENT AT DOE NUCLEARI FACILITIES 1

DOE-STD-1O56-93 GUIDE TO GOOD PRACTICES FOR LINE AND TRAINING ~MANAGER ACTIVITIES RELATED TO TRAINING

DOE-STD-1O57-93 ~ GUIDE TO GOOD PRACTICES FOR THE SELECTION.TRAINING. AND QUALIFICATION OF SHIFT TECHNICALADVISORS

DOE-STD-1O58-93 GUIDE TO GOOD PRACTICES FOR DEVELOPING AND; CONDUCTING CASE STUDIES

DOE-STD-1O59-93 I GUIDE TO GOOD PRACTICES FOR MAINTENANCE ~~Supervisor SELECTION AND DEVELOPMENT

‘ DOE-STD-1 060-93 GUIDE TO GOOD PRACTICES FOR CONTINUINGI TRAINING

II

~ DOE-STD-1O61-93 I GUIDE TO GOOD PRACTICES FOR THE SELECTION, ~I TRAINING. AND QUALIFICATION OF SHIFT SUPERVISORS

I ———-

~ DOE-STD-1O63-93 ~ ESTABLISHING AND MAINTAINING A FACILITYI REPRESENTATIVE PROGRAM AT DOE NUCLEAR

FACILITIES

DOE-STD-1O64-94 GUIDELINE TO GOOD PRACTICES FOR SEASONALFACILITY PRESERVATION AT DOE NUCLEAR FACILITIES

: DOE-STD-1O65-94 GUIDELINE TO GOOD PRACTICES FOR POST-1 ~MAINTENANCE TESTING AT DOE NUCLEAR FACILITIES

I DOE-STD-1 067-94 I GUIDE TO GOOD PRACTICES FOR MAINTENANCE !t FACILITIES, EQUIPMENT, AND TOOLS AT DOE NUCLEAR

I ! FACILITIES

DOE-STD-1O68-94 GUIDE TO GOOD PRACTICES FOR MAINTENANCEHISTORY AT DOE NUCLEAR FACILITIES

DOE-STD-1O69-94 GUIDELINE TO GOOD PRACTICES FOR MAINTENANCE iTOOLS AND EQUIPMENT CONTROL AT DOE NUCLEAR ~FACILITIES

I DOE-STD-1 070-94” ] GUIDELINES FOR EVALIJATION OF NIJCLEAR FACILITYI

, TRAINING PROGRAMS—— —-. — —.-....—..—.._....— —

C-3

2=U Safe Storage System Revision 0System Requirements Document May 1998

DOE-STD-1 071-94 GUIDELINE TO GOOD PRACTICES FOR MATERIALRECEIPT, INSPECTION, HANDLING, STORAGE.RETRIEVAL, AND ISSUANCE AT DOE NUCLEARFACILITIES

DOE-S- 2-1072-94 GUIDELINE TO GOOD PRACTICES FOR FACILITY, CONDITION INSPECTIONS AT DOE NUCLEAR FACILITIES

DOE-STD-1073-93- PT.1 GUIDE FOR OPERATIONAL CONFIGURATIONMANAGEMENT PROGRAM, PART I

DOE-STD-1073-93 -PT.2 I GUIDE FOR OPERATIONAL CONFIGURATIONMANAGEMENT PROGRAM, PART II

CG-SS-3,E.O. UPDATE CLASSIFICATION GUIDE FOR SAFEGUARDS ANDSECURITY INFORMATION

oRNuMD/LTR-60 STRATEGY FOR THE FUTURE USE AND DISPOSITION OF ~233:UOVERVIEW

2UU Safe Storage System Rev/s/on OSystem Requirements Document May 1998

APPENDIX D: BASES AND ADDITIONAL INFORMATION FOR 233USAFE STORAGE SYSTEM REQUIREMENTS

I

D-1 Requirements Bases and Additional Information

Note: The following section numbers refer to the sections of the main bodv of the SRD.

3.1 System Description

The system description is based on the results of the analysis by the 97-1 Team assignedby DOE to respond to the DNFSB Recommendation 97-1. The Team analyzed therecommendation and determined that the Program should focus on two initial efforts.along with recognizing that disposition and beneficial uses must be addressed in thefuture:

● .An interim effort to respond to DNFSB concerns as to the safety of the currentinventor} und to take whatever steps w-e necessary to stabilize this material in anacceptable condition until ~ long-term solution is in place

. Develop md implement a long-term solution for the storage of ‘S3V.

. Assess the potential disposition options to try to minimize the rework required in thefuture

. Retain the option for future beneficial uses of the material

This SRD defines the requirements for the long-term storage solution. The interimconcerns are addressed in the site characterization efforts and the potential dispositionoptions ha~e been addressed in an ORNTLreport ORNL/TM- 13550. A transition from [heinterim storage status to the avfiilability of the long-term sare storage system will beaddressed in {TBD }. System unalysis indicated that the system has the following foursubsystem functions:

. Processing - this includes the chemical conversion of any materials that do not meetthe safe storage specification [SA17-0067], stabilization of all of the materials toremove volatile impurities and moisture, and packaging mto a container that meetsthe storage standard.

. Storage - this includes the operation, placement and retrieval of materials at the long-term storage facility

. Waste Management - this includes the storage, packaging and handoff to EM for allwaste materials. It may also include the processing of any existing materialsdetermined to be wastes (i.e.. below the Safeguards Termination Limits).

D-1


● Transportation - this includes the logistics. packaging, unpacking and associatedfacilities for the transportation of materials and wastes. Off-site transportation is tobe handled by external systems.

In addition to these four subsystems. six external systems have been identified that haveinterfaces with one or more of the subsystems of the long-term storage system. Theseare:

. Current ’33U storage systems containing material that must be accommodated by thelong-term storage system - this is the inventory of materials as currently stored.Materials will be withdrawn, processed as required, and stored in the long-termstorage system facility. There are multiple sites and at least two basic forms of thematerials (unused ’33U reactor fuel mixed with Thorium. and pure. or near pure, ~33Ucompounds or metals).

. 94-1 MSRE - this is the inventory of ‘q~l-lcurrently in the .MSRE fi~cility that is beingprocessed under the W-1 program. Once converted. and as soon as the long-termstorage facility is available. it will be transferred to the ’33U long-term storage systemticilities.

. Natural and depleted uranium - this system represents a potential source of blendingmaterials if the decision is made to blend the ’33U materials with natural and depleteduranium for storage. This would possibly be a consequence of potential dispositionoptions.

. Potential beneficial uses (nominally via DOE-Nuclear Energy) - this is a potential enduse that could take multiple forms. The option that is currently being considered isthe extraction of selected daughter isotopes for use in cancer treatment.

● DOE-EM Waste ,Management - EM is the lnternai DOE orgamzatlon chartered tohandle the disposition of nuclear and hazardous waste materials. This interfaceincludes transfer of \vaste materials from the ‘~% Safe Storage System to EM WasteManagement. It may also include receipt of specialized storage or transportpackaging from EM or its designated agents.

. DOE-MD Disposition - this system 1sexternal to the %-J Safe Storage System, buta participating component of the overall 97-1 program. This interface will occurwhen a decision is made regarding disposition options for the program. This mayoccur early in the program if some of the ‘~% material is sent to MD sites for earlydisposition and again later (possibly multiple times) for the remaining materials.

This analysis of the DNFSB concerns established the “context” for the long-term ’33USafe Storage System (see Figure 3-1).

is


3.1.1 System Components

The ’33U long-term storage system consists of four major subsystems:

. A processing subsystem to convert the material to a suitable form for long-term storage

. A Storage subsystem with a design life of at least 50 years

. A waste management subsystem to treat. collect and transfer waste material towaste disposition agencies (DOE-E.M)

. A Transportation subsystem to manage the shipping and receiving for each ofthe subsystems

These components interact with external systems throu~h shipping agencies. bothDOE and commercial.

3.1.2 System Interfaces

The system interffices represent all of the transactions tha[ the system will berequired to peti-otm between both internal and external components. Theseinterfaces are key elements of the process of managing the long-term storageprogram as these interfaces represent “contracts” between the organizations thatare responsible for each componenr that must be actively managed or the systemwill not perform as needed. The external systems are panicularly importantbecause they involve organizations that are not directly responsible forimplementing the long-term storage solution. Some of these external systems willrequire information generated by the design and implementxion of the 97-1program I[he ~[or~ge Standard for example I

Suppotfjnq Information:

The current inventory of ‘s~U materials is undergoing changes in parallel with thelong-term storage system development. Some material may be processed to put itin a safer form and, where possible, ’33U material may be consolidated into fewerfacilities or locations during the interim storage rogram. thereby reducing the

fnumber of sites and increasing the amounts of’3 U material in interim storage atthe major sites (primarily INEEL and ORNL).

The interface with the external DOE uranium materials system is necessary in theevent that a beneficial use is identif~ed that requires blending or that the Long-term Storage form is determined to require blending with Uranium (’natural ordepleted). Processing of ‘3SUmaterial to remove decay products may be requiredfor material with higher ‘3ZUcontent for some applications. This changingsituation will be addressed in an interim storage strategy and planning document.


The Current ~33Ustorage systems, which contain the material that must beaccommodated by the long-term storage system interface with the 94-1 program.

‘J?represent approximately 37 Kg of ‘3% material. This material will be receiv dfrom the 94-1 program as a result of the processing of .MSRE fuel under that

program.

The 213USafe Storage System will interface with the DOE disposition system forPlutonium, spent fuel, or high level waste to allow processing of ’33U with otherDOE excess or waste materials if it is determined that disposition of ’33U materialis appropriate.

There are potential beneficial uses for a~% and it is assumed that any potentialbeneficial use or disposition would happen as a part of the beneficial use actionafter it is withdrawn from long-term storage. Beneficial use material could beeither permanently transferred to a beneficial use program or returned to the safestorage system after use (removal of radioisotopes for example). Beneficial use istreated as an external system for the purposes of this program. Once beneficialuse actions are complete. [he material may return to the ’53U Safe Storage Systemor may be retained by the beneficial use system.

It is assumed that existing DOE mechanisms for the transport of nuclear materialswill be used for the transport of 233U. Some modification of shipping containers. . .could be required because of the higher radiation levels associated with ‘“U.

3.2 System Level Requirements

The requirements for the long-term 2J3U Safe Storage System are derived from twosources: derived and externally imposed requirements. This document includes both.E~ch requirement \vill have the source of the requirement identified in brackets ] at thernci of the paragraph. The system level requirements are those which apply [o the systema> a whole and potentially to individual subsystems. These requirements are prlmardyexternally driven requirements from DOE Orders. Federal Laws and regulations derivedfrom these laws.

3.2.1 Performance

System performance requirements are derived from the DNFSB recommendationand from the program technical and schedule objectives developed by DOE. Keyrequirements are contained in the safe storage standard [DOE-SAFI’-OO67].Other performance requirements will be derived from schedule milestoneobjectives as they are established by the program.

The amount of material to be processed is that shown in Tables 3-1 through 3-4less any material that is transferred to an early disposition processor site as isbeing considered for the u308 Monolith material at ORNL.


3.2.2 Functional

System and subsystem functions were derived from the basic system levelrequirements and mission statement by the 97-1 Team.


System and subsystem interfaces were identified by the 97-1 Team from analysesof the functions to be peti-ormed and identified external dependencies.

An intert’ace control document [ICD) will be prepared to define all of the interfacerequirements for each interface. Each ICD will be prepared by and agreed to byall parties associated with the interface.


The referenced directives establish minimum requirements for the design,procurement. and implementation of information systems that process. store.transfer. or provide access to classified information.

3.2.6 Environmental Safety and Health

The design and construction of the safe storage system must comply with therequirements of the numerous laws and regulations:

. The DOE Environmental Protection Program is established in DOE O 5400.1.which provides environmental program requirements DOE-wide. DOE O5400.1 establishes the driver laws and regulations that require implementationof measures to ensure that the environment is protected from unacceptabledamage bt Its actions.-.

● Additional policy has been issued regarding ES&H requirements in DOE P450.2.4 and DOE P -!50.1.

The National Environmental Policy Act of 1969 (NEPA) [40 CFR Parts 1500-1508] requires that all agencies of the Federal Government utilize a systematic,interdisciplinary approach which will insure the integrated use of the natural andsocial sciences and the environmental design arts in planning and in decisionmaking which may have an impact on man”s environment. Because this programwill potentially require construction or modification of a facility or facilities forprocessing of 2~3U,the requirements of NEPA may apply.

. DOE Order451. 1A establishes DOE internal requirements andresponsibilities for implementing the National Environmental Policy Act of1969 [NEP.4], the Council on Environmental Quality Regulationsimplementing the procedural provisions of NEPA. and the DOE NEPAimplementing procedures

233USafe Storage System Rev/s/on O


● The Resource Conservation and Recovery Act (RCRA) regulates solid waste.which includes both the ordinary garbage generated in our households and

offices and the more hazardous chemical wastes produced by industrialprocesses. RCRA also regulates medical wastes and underground storagetanks containing hazardous substances. Because some of the processingsubsystem activities may utilize hazardous materials and generate wastere~ulated under RCRA, processing facilities under this program may be

required to comply with RCRA. DOE Order 5480.3 establishes internalrequirements and responsibilities implementing RCRA.

. The Clean Water Act (CWA) was enacted in 1972 and established afederal/state scheme for controlling the introduction of pollutants into thenation’s navigable surface water. Any processing facilities that dischargewaste waters to either a surface water body (i.e.. not ground water) or a

publicly-owned treatment system must ensure compliance with CWA.Facilities that directly discharge waste ~vaters must obtain a Xational PollutantDischarge Elimination System permit. This permit specifies the dischargestandards and monitoring requirements that the facility must achieve. To theextent that this applies. the processing and storage facilities must comply withthis law.

. The Clean Air Act (CAA) was enacted in 1963 and last amended in 1990. Theobjective of CAA is to protect and enhance the quality of the nation’s airresource and protect public health and welfare. while fostering a beneficialproductive capacit]. LTnderCAA. standards are set for air pollutants. Facilitiesthat generate and release pollutants to the air are required to obtain anoperating permit and comply with these standards. For the ~“13Ufacilities. thismay require process modification or some form of treatment before emissionsare released to the environment such as for 2QQRn]

● The Safe Drinking Water .\ct (SDWA) was enacted in 1974 with the primarypurpose of protecting drinking water resources. Primary drinking waterstandards set by the SDWA apply to drinking water “at the tap” as deliveredby public water supply systems. Of equal significance, drin~ng waterstandards are used to determine ground water protection re~ulations under anumber of other statutes. including CERCLA. SDW.A states each federalagency having jurisdiction over a federally-owned or operated public watersystem must comply with all federal, state. local requirements for theprovision of safe drinking water. To the extent that a water system is required

for the safe storage system. this Act applies to this program.

. The discharge of dredged or fill material into waters of the United States iscontrolled by 33CFR323 and permitting is [he responsibility of the Corps ofEngineers. To the extent that construction work on facilities associated withthis program may require such measures. the requirements of these regulationsapply.


. The Toxic Substances Control Act (TSCA) was enacted in 1976 and isenforced by EPA. It requires that specific chemicals be tested and theirprocessing and use restricted to protect human health and the environmentfrom unreasonable risk from exposure. TSCA specifically regulates thecontrol of any waste materials that contain more than 50 parts per million ofpolychlorinated biphenyls (PCBS). To the exten[ that such regulatedchemicals are used, this program must comply with this act.

● Section 4.2 of DOE 0420.1 (chg. 2) has primacy over all other DOE Orderswith respect to matters concerning fire protection for facilities trefer to DOE440. 1A for worker protection requirements). To the extent that potentialconflicts may arise resulting from the implementation of these requirements inrelation to other DOE Orders or Directives, the cognizant fire protectionAuthority Having Jurisdiction (AHJ) within the Office of the AssistantSecretary for Environment, Safety and Health is responsible for resolving theissue in concert with the other AHJs.

c The ‘~sU processing facilities, sites and activities (including design andconstruction) must be characterized by a level of fire protection that is

sufficient to fulfill the requirements of the best protected class of industrialrisks (“Highly Protected Risk” or “Improved Risk”) and be providedprotection to achieve “defense-in-depth.” This includes meeting the applicablebuilding code and National Fire Protection Association Codes and Standards.or exceeding them (when necessary to meet safety objectives), unless anexemption is granted.

. The ~pplicable codes and standards are those in effect when facility designcommences (“code of record”). In the event that some or all of the processingfacilities result in significant modifications to a iacllity, the current edition ot

:he code or smndard applies to the mociificxlon.

Other SuDpoflinq Information:

‘::U has a gaseous daughter product ‘zORn. In addition to anremove radioactive particles. a system should be provided to

off-gas svstem tocontrol 210Rn

migration and prevent releases of the gaseous product to the environment aboveacceptable levels.

DOE has instituted a policy that radiation exposure resulting from its operationsbe maintained below regulatory limits and that deliberate efforts be taken tofurther reduce exposures as low as reasonably achievable (ALARA).

‘s~ll material exhibits higher gamma radiation fields than other uranium materialsand will require additional protection for workers than for traditional methods ofhandling uranium. A specific concern of this program is a high energy [2.6million electron volts (MeV)] gamrn~ ray is emitted from thallium-208 (:08Tl), a

233USafe Storage System Revision O


daughter nuclide of ‘3ZUdecay. Depending on the amount of ‘3% present in the‘3JU, the surrounding radiation field can range up to tens of rem/hr. This radiation

field causes handling for visual inspection, repackaging, or any similar form ofprocessing to be difficult from an As Low As Reasonably Achievable (ALARA)

standpoint (exposure to ionizing radiation).

Implementation Guide DOE G 441.2-1, Occupational ALARA Program (DOE,1997c), provides detailed guidance on the essential elements of an ALARAprogram.

The safe storage system may also utilize other hazardous materials and systemdesign will provide adequate protection from these hazards.


Note that terms commonly used in the Safeguards and Security Program aredefined in the “Safeguards and Security Definitions Guide. ” which is maintainedby the Office of Safeguards and Security.


The subsystems ~vill be designed with maintainability a key consideration inselection of components and layout. .Maintainability includes the ability tomaintain the components with minimal occupational exposure and minimal timerequired to perform maintenance tasks. The cost and quantity of spare parts

inventory will be considered as well.

3.2.9 Human Factors

Human factors specialists will review and approve designs.

3.2.10 Training and Personnel

It has been some time since any significant amount of ’35U has been handled inthe DOE complex. The DNFSB recognized that retention of key skills will beimportant to [he successful execution of the 97-1 program. Actions have beentaken to compile the experience with ’33U materials and identify the available

staff, It will be a specific objective to incorporate this experience base intotraining efforts for the personnel who will operate this system once implemented.


The requirements of Section 3.2.11 apply to the activities of design andconstruction of new Hazard Category 1.2. and 3 DOE non-reactor nuclearfacilities and to the design and construction of modifications to existing DOEHazard Category 1, 2, and 3 non-reactor nuclear facilities when the proposedmodifications significantly degrades the approved safety basis for the facility.

233USafe Storage System Revwon OSystem Requirements Document May 1998

3.2.12

Draft guidance has been developed and provided in DOE G 420. 1-X (Draft) andDOE G 420.1 -Y(Draft) and it is assumed that this guidance will be formallyapproved and released before implementation of this subsystem is begun and willbe applicable.

Life Cycle Asset Management (LCAM)

The design. construction, and operation of the 213USafe Storage System willrequire the participation of organizations external to the program. A logistics planto identify those acti~ities and the responsible parties will be developed as anaction item identified in the Program Execution Plan (PEP). The Transportation.subsystem will play a key role in operational logistics for the operational system.

Decontamination and decommissioning (D&D) planning is necessary in theanalysis of life cycle costs and will be addressed during the design of any. .facilities for the ‘J3U Safe Storage System. The D&D concerns and costs of anyexisting iacllities to be utilized or modified under the 97-1 program will beconsidered in any analysis of alternatives.

3.3 233U Processing Subsystem Requirements

The processing subsystem will process all materials in current inventory (less any sent forearly disposition ) that do not meet the requirements of the storage standard. It isexpected that the near term characterization efforts underway concurrent with theplanning and implementation of the long-term safe storage system will provide much ofthe information LOdetermine the scale of the processing effort. However. due to the planto avoid unnecessary worker exposures in the near term by not opening every can. therewill be uncertainties remaining in the amount of material that must be processed that canonly be resolved at the time processing begins and ph~sical inspection of the material cmoccur.

Processing includes ~hechemical conversion of materials not in the form prescribed by[he standard to an acceptable form. stabilization of the material as required by thestandard. and packaging of the material into storage canisters that meet the requirementsof the standard.

3.3.1 Petiormance

There are several specific concerns related to the processingthe processing system design must address. Specifically,

. The subsystem must be designed to contain ‘zORn.

of ’33U materials that

. The design of the processing system must be such that the need toaccommodate the radiation fields associated with ’33U materials, especiallythe 2.6 Nlev gamma from ‘08T1does not compromise the schedule objectives,


3.3.2

3.3.3

3.3.7

3.3.8

. The system must be capable of removing the ‘S3U packages from storage for

transfer to a beneficial use facility, and receiving returned material inpackages that meet the storage standard.

Functional

Not all of the functions identified in Section 3.3.2 apply to every item currently ininventory. Which functions apply are affected by the status and condition of thematerial.

Integration and Interface Control

.An interface control document fICD) will be prepared to define all of the interfacerequirements for each interface. Each ICD will be prepared by and agreed to byall parties associated with the interface. It is intended that as the decomposition ofthe functions proceeds. additional lower Ie\el interfaces will be identified anddocumented in a similar manner.

Safeguards and Security

Because highly-enriched ’33U material has potential uses as a weapons material,the safe storage system for such material must be designed to provide adequatesafeguards for the material while in-process. Access controls for processing areasand in-line secure storage may be required to adequately protect this materialduring processing and when the process equipment may be unattended.

Reliability, A vai/abi/ity, and Maintainability

The reliability of the processing subsystem equipment must be designed to meetthe throughput requirements for the system and to minimize personnel exposuresresulting from maintenance 01 [he equipment.

3.4 Storage Subsystem Requirements

The storage subsystem is the component of the ‘1% Safe Storage System that will ensurethat the material is safely maintained for a period of at least 50 years. It is an objectivethat this system function with a minimum of required operating staff and be ofsufficiently robust design that the systems will require minimum maintenance over its lifecycle. The balancing of these objectives will be accomplished in the desi=~ to minimizelife cycle costs. These objectives will be considered in the trade studies conducted toselect among the alternatives available to accomplish the program.

3.4.1 Performance

The storage subsystem must be able to receive and insert material canisters intostorage with minimal delay



lklaterial may come to the storage subsystem from two other subsystems..Material processed by the processing subsystem and material currently in interim

storage that already meets the safe storage standards may be transferred to thelong-term storage subsystem. In some cases the transfer could be from a co-Iocated processing or interim storage subsystem. It is also conceivable thatinterim storage facilities may be satisfactory for long-term storage and norelocation will be required.

3.4.6 Environments/ Safety and Hea/th

In the event a material storage container is breached ‘zORnmaybe released as agas which must be contained within facility systems to prevent releases to theenvironment above acceptable levels.


Safeguards will be required for all materials above STLS. If ‘3% is blended withdepleted or natural uranium from the El_JiDELTsystem it may be possible toreduce the cost of storing the material even though the quantity of material issubstantially increased. The decision to do so will require trade studies thatbalance processing costs. storage costs, impact on beneficial uses. and dispositionimpacts.

3.5 Transpotiation Subsystem Requirements

The transportation subsystem as defined for this system refers to the facilities to receiveand ship material for my of the other subsystems. This includes the capability to receivethe material from a co-loc~(ed process. place the material into appropriate. approvedshipping containers. remove received matericd from such containers. order and coordinatethe required shipping services. md operate the shipping facilities.

Transportation facilities will be co-located \vith storage, processing, or wastemanagement facilities associated with the ’33U Safe Storage System. Transportationfacilities include all equipment necessary to perform the above functions. including theshipping containers.

3.5.1 Performance

It is intended that the transportation subsystem be able to handle all requiredtransfers without undue delays due to lack of subsystem capacity. Subsystemcapacity will be determined by analysis during the conceptual design phase of thisprogram.]


Some portions of this subsystem may not be required in the case of co-location ofother subsystems (co-located processing and storage for example could share asingle transportation subsystem).]

3.5.3 Integration and /nterface Control

The transportation subsystem will manage the movement of materials to and froml~sU Safe Storage System facilities. Each facility will have a shipping andreceiving component with the capability to package and remove packaging fortransport. The subsystem will also be responsible for acquiring and maintainingtransportation packaging that meets all DOE and DOT requirements. Facilitieswill include equipment to handle material and transportation packa~ing.

3.6 Waste Management Subsystem Requirements

The waste management subsystem will receive find store all of the wastes produced bythe other subsystems. The generating subsystem will be required to provide the materialin a disposable form and with required documentation. Waste management will store the

material and eventually ensure that the material is shipped to appropriate disposal sites.

There are some existing materials in storage that may be reclassified as wastes. If this isthe case, the waste management subsystem will be responsible for retrieving it andtransmitting it to the appropriate DOE E.34organization for treatment and disposal.

3.6.1 Performance

The waste management subsystem will be capable of receiving and storing allmaterials that are produced by the other subsystems of the ~j% safe storagesubsystem }vithout impacting the performance of those subsystems.

3.6.2 Functional

Because the \vaste management facilities are expected to be co-located inprocessing and storage facilities. security and access control must be governedprimarily by the requirements of those subsystems.

3.6.3 Integration and Intetiace Control

The waste management subsystem will support the other three ’33U Safe StorageSystem components by receiving wastes and managing those wastes until transferto EM for disposition. If it is economical, some recovery of nuclear materialsfrom the wastes to reduce waste volumes could be performed resulting in somematerial being returned for transfer to processing and/or storage and a modifiedform for waste disposition. Some of the wastes may already exist and some maybe existing materials that are reclassified as waste as a result of the effort underthis program resulting in an interface with existing site stored materials. [


D-2 Site Descriptions and Capabilities.

D-2.1 Oak Ridge National Laboratory I

D-2. 1.1 ORNL Existing Processing Capability.

ORNL Building 3019 processing systems were utilized in the past for a variety of~;~gr~is (including,the Manhattan Project) involving handling and (reprocessing ‘33U,

U, - Pu and a variety of other rfidionuclides. These formerly used systems exist buthave not been utilized since operations were discontinued.

Building 3019 has existing capabilities that broadly address the required “W processing. . .

subsystem capabilities. These capabilities currently exist primarily in unshielded glove-box enclosures that provide for the handling, characterizing, conversion to a stablechemical form. and repackaging of high grade ’33U materials. Shielded. remotecapabilities are currently being established to pert-orm these activities for lower quality,higher gamma hazard) ‘331Jmaterials.

D-2. 1.2 ORNL Existing Storage Capability.

The Radiochemical Development Facility (RDF, Building 3019) is the nationalrepository for over half of the ~337Uinventory. It currently holds over 1000 canisters withover 3,000 containers of ’33U in the form of pure and impure metals, oxides, and salts.This material has a total uranium mass of 1,382 kg, including 427 kg of ‘2% and 796.4kg of ‘35U. The facility capacity is ap roximate 80’% utilized (volumetric). Receipt of

fmaterials containing predominately ‘3 U from other DOE sites has begun and is plannedto continue in the near term.

Building 3019 ~ctivities involve the safe storage of ‘:5U: receiving, storing anddispensing ma[erials containing ~s~~: maintaining ‘~% processing systems. liquid storagetankage. process boxes, remotely operated cells and ancillary support equipment;surveillance and technical management support systems including training. configurationmanagement, and conduct of operations and maintenance. The principal features of thebuilding are its storage wells, laboratories (equipped with radiochemical hoods and gloveboxes) and shielded cells. Nuclear criticality safety of material stored in the wells ismaintained by a combination of mass, geometry and concentration controls. A VesselOff Gas (VOG) system is connected to the wells to control potential releases of ’33U fromstorage containers in the wells. Effluent from the VOG system is routed to an off-gastreatment system where it is scrubbed to remove acidic vapors (from other processes atORNL) and filtered through roughing and HEPA filters. This effluent is then exhaustedto the 3039 stack. In the event of an interruption of the off-gas treatment system theVOG is also routed to the main Building 3019 ventilation system which provides HEPAfiltration prior to discharge via the 3020 stack.

The Radiochemical Development Facility (RDF, Building 3019) is a facility originallybuilt in 1942 {TBR ] to demonstrate chemical separation processes for irradiated nuclearreactor fuels.


D-2. 1.3 ORNL Existing Waste Management Capability.

ORiiL radioactive waste management activities primarily involve transuranic waste(TRU) and low-level waste (LLW). Small quantities of naturally occurring andaccelerator-produced radioactive material are generated and managed as LLW.

Radioactive ;vaste management operations include solid. liquid, and gaseous wasteactivities. Each of these areas is summarized below.

. ORNL has the capability for handling of both CH-TRU and RH-TRU wastes.

. Solid Low-ievel Waste – Since January 1994. ORNL solid low-level waste isdisposed of in the above grade tumulus Interim Waste Management Facility.

. Liquid Low-level Waste (LLLW) – ORNL employs two systems for handling andprocessing liquids that contain radioactive constituents: the LLLJY System and theProcess JJ’aste System (PW’S’).

. Process \Vaste - The process waste system handles all liquid aqueous waste thatcontains trace amounts of radioactivity, heavy metals. and organics or has thepotential to be contaminated with these constituents.

. Gaseous Waste - The bulk of gaseous waste that is contaminated or potentiallycontaminated with radionuclides is collected and discharged through existing majorstacks. Where conditions dictate chemical scrubbers are used in the process off-gasstreams to remove reactive gases such as halogens and acidic vapors prior todischarge to the ventilation system.

● Nlixed Jvaste ~lma~ement – \lixed waste contains both hazardous (RCRA and orTSC.A t and radioactive components. Mixed waste IS~Ioredpen~in: availabletreatment and disposal at offsite facilities such as the Envirocare facility in Clive,Utah.

D-2.2 Idaho National Engineering and Environmental Laboratory

D-2.2. 1 INEEL Existing Processing Capability.

The Idaho Nuclear Technology and Engineering Center (lNTEC), formerly the IdahoChemical Processing Plant, still has significant processing capability, although most of ithas not run since prior to April 1992. This capability includes dissolution capability foraluminum-clad fuel material, stainless steel-clad material, and zirconium-clad material.One cycle of solvent extraction using tributylphosphate and two cycles of methylisobutylketone are still in existence. A fluidized bed denigration process still exists to converturanyl nitrate to uranium trioxide. In addition, the support functions for the storage ofspent fuel, liquid and solid waste management, and the capability to convert high-levelliquid waste to calcined oxides still exists.


Small-scale processing includes the Remote Analytical Laboratory, which has hot cell

space with centrifugal contractors for solvent extraction. Unshielded pilot plants provide

the experimental-scale capability for most types of nuclear-related capability. All of

these facilities could be used to process ‘33U.

D-2.2.2 INEEL Existing Storage Capability.

Storage for radioactive materials is extensive at LNTEC and includes basin storage anddry vault storage in either the underground \ aults or the Irradiated Fuel Storage Facilityfor highly-radioactive materials. Standard vault storage is also available in CPP-651. .-Nthe present time, this storage meets the requirements for Category II storage and is largeenough to store the entire inventory of ’33U in the United States.

D-2.2.3 INEEL Existing Waste management Capability.

Until .~pril 1992. INTEC” S primary mission was to process HEU from highly irradiatedspent nuclear fuel. AS a result. a waste system was put in place to deal with all kinds ofwastes generated during the recovery of HEU. The wastes included low-level and high-level liquid wastes. gaseous waste (including the recovery of krypton and xenon), andsolid ~vastes, including the high-level calcine and low-level solid waste that was sent tothe Radioactive Waste Management Complex.

Because of this extensive experience. no waste generated during any processingoperations for ’33U would be expected to present a problem.

D-2.3 Los Alamos National Laboratory

D-2.3. 1 LANL Existing Processing Capability.

Los .Mamos currently has mlnimai processing capability for ~;3U. Glove boxes do exist in

which ‘2:LTitems have been repackaged and consolidated and there are hot cells that xecurrently used to store some ‘33U. There is space available to reconfigure for handling all~33Uat Los Alamos LOmeet the requirements of The Defense Nuclear Facility SafetyBoard Recommendation 97-1 for interim storage of ’33U until a long-term facility is

available.

D-2.3.2 LANL Existing Storage Capability.

Los Alamos has 364 floor hole storage units located in Wing 9 of the Chemistry and,Metallurgy Research Building. These units are made of massive concrete are ventilatedand have capability of cooling. There is the possibility of using approximately 100 ofthese floor hole locations for storing ‘33LT.


D-2.3.3 LANL Existing Waste management Capability.

Los Alamos has a large waste management capability. This operation is capab~e ofdealing with a variety of waste issues that may arise at the Laboratory

D-2.4 .Miscellaneous University find Smaller Laboratory Sites

The inventory and status of the small sites is not fully documented at this point. Continuingeffort to determine quantities and status of these materials will continue. Only the materials atDOE laboratories are well documented

D-3 Disposition System Considerations

The ‘S3LTSafe Storage System will be designed to be compatible with the projected dispositionoptions being planned by DOE to the extent practicable within Life Cycle Cost constraints asdetermined by trade studies. These options are presented in ORNTL~YI- 13550.

The Disposition alternatives under consideration by DOE are summarized in Table D-1.

Table D-1. Disposition AlternativesOption Description Disposition Form

A Dispose as High Level Waste (HLW) Vitrified (glass)in the planned SNF HLW repositoryby mixing with HLW sludgecontaining depleted uranium (DU)and vitrif in a alass 10 .

~B 1 Mix with~U aid conv~rt to a Oxide, uranium oxide for disposal in theI planned SNF HLW repository.,

c I Mix with DU and convert to a OxideI uranium oxide for alsDosal at WI PP.D ~ Mix with DU as an oxlae. fabricate as ‘ uo~

1LWR fuel and use it in a commercialnuclear reactor

~E Direct disposal of LWBR fuel in Clad U02/ThOz FuelWIPP or the SNF HLW repository.

!F Packaae the ‘J3U in alummum cans, Metal in Al can1 press ;he 233Ucans inta sheets and” I

intermix with DU sheets, thenmelting the combination to create asemi-homogeneous solution.Dispose in repository.

G Treat as remote handled or contact ?handled TRU waste by co-processing with TRU wastes.

H Dispose in a Greater Confinement ?Disposal facility (none exist today).

The disposition subsystem may require that material be processed into a form suitable for finaldisposition prior to placing the material in its final location. This \vould require transfer of


material from the transportation subsystem to a disposition processing facility and then to thedisposition facility or facilities.

h is possible that some material may be disposed prior to going to long-term storage. In thisevent. it will be necessary to be able to segregate selected material. place it in appropriatecontainers. and ship it to the designated disposition processing site.