ML21246A254

General Atomics Triga Reactor Facility Decommissioning Plan

ML21246A254
Person / Time
Site:	General Atomics
Issue date:	07/09/1999
From:	General Atomics
To:	Office of Nuclear Material Safety and Safeguards
Marlayna Doell, 301-415-3178
Shared Package
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References
PC-000482/3
Download: ML21246A254 (180)

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'o-S GENERALATDMECB

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GENERAL ATOMICS GA2175 9/89)

(REV. RNECTCONTROL SSW

SUMMARY

DOC.CODE PROJECT DOCUMENT NO. REV.

@ RGN 9009 PC-000482 3' TITLE:

GeneralAtomicsTRIGA*ReactorFacilityDeconunissioningPlan APPROVAL(S) REVISION CMAPPROVAL/ PREPARED RESOURCE/ DESCRIPTION/

DATE REV BY SUPPORT PROJECT W.O.NO.

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0 A.J.Welch V.Nicolayeff G.C.Bramblett InitialIssue W.O.9009.303.055 APR171997 .

K.E.Asmussen 4/7/97

> 1 .Greenwood c y f ,@/4 GeneralRevisions to

.C amble t address NRC comments JAN29 1999 /' 09009.303.05500 K '.Asmusse //g9 S #

2 J.GreenwoodV.Nicolayef yf Reva.sed pages 2-23, G.C.Brambe#@ 3-5, 3-11, A-pr38p$L APR27 1999 A-8 to addresa NR1$

.. ^. smusse 4/ g7 comments 09009.303.05500 3 .Greenwood V.Nicolayef . . ramb e Revised page 2-17 JUL09 1999 A& K.E. musse 09009 303. . 05500 7 h/97 .y CONTINUE ONGAFORM21751

• SeeListOfEffectivePages m

jTHISDOCUMENTISTHEPROPERTYOF GENERALATOMICS. ANYTRANSMITTAL OF THISDOCUMENT OUTSIDEGA WILLBE IN CONFIDENCE.EXCEPTWITHTHEWRITTEN CONSENT OF (1)

GA, THISDOCUMENT MAYNOTBECOPIED INWHOLE ORINPART ANDWILL BERETURNED UPONREQUEST ORWHENNOLONGER NEEDED BYRECIPIENT AND(2) INFORMATION CONTAINED HERElN MAYNOTBE COMMUNICATED TOOTHERS ANDMAYBEUSED BYRECIPIENT ONLYFORTHEPURPOSE FORWHICHITWASTRANSMITTED.

@ NOGAPROPRIETARY INFORMATION PAGE fi OF

• PC-000482

/3 LiSTOF EFFECTIVEPAGES PageNumber PageCount Revision ithrough iii 3 3 ivthrough ix 6 2 1-1 through 1-13 13 2 2-1through2-16 16 2 2-17 1 3 2-18 through 2-23 6 2 3-1 through 3-19 19 2 4-1through 4-4 4 2 5-1 1 2 6-1 1 2 7-1 1 2 8-1 1 2 9-1 1 2 10-1 through 10-2 2 2 A-1through A-68 68 2 B-1through B-28 28 2 Total 171 m

PC000482/2 TABLE OF CONTENTS PROJECT CONTROL ISSUE

SUMMARY

........................,..,...ii LISTOF EFFECTIVE PAGES.............................,.. iii TABLE OF CONTENTS..............................,................ iv LIST OF FIGURES ...,............................,......,,............ vi LISTOF TABLES ...................==........=.,,....................... vi LISTOF ACRONYMS/ABBREVIATIONS...................,.............vii 1.

SUMMARY

OF PLAN.........................................11 1.1Introduction.........................................................................<................1-1 1.1.1 Overview ........................................................................n...........................1-1 1.1.2 Decommissioning PlanProvisions.......................,.....................=......1-1 1.2Background.............................................................................................................18 1.2.1 Reactor Decommissioning Overview.....,......,............,,........,,,............1-10 1.2.2 Estimated Cost...................................................................................................1-11 1.2.3 Availability ofFunds................................................................,................1-11 1.2.4 Program Quality Assurance.................................................................................1-11

2. DECOMMISSIONING ACTIVITIES .........................................21 2.1Decommissioning Alternatives........................=.......,,.............................,.....2-1 2.2Facility Radiological Status..............................................................................................2-1 2.2.1 Facility Operating History ......................................,.........,21 2.2.2 Current Radiological Status ofthe Facility...............................................................2-3 2.3Decommissioning Tasks................................,........................,....,...........25 2.3.1 Activities andTasks......................................................................................2-5 576A 2.3.2 Schedule..,.........,,...........,.......................=....................................,....2-13

• • 2.4Decommissioning- Organization andResponsibilities...........,..........................................2-14 2.4.1 Decommissioning Project Manager............................................................2-14 2.4.2 TRFPhysicist-in-Charge.....................................................................2-18 2.4.3 Manager, Health Physics...................................................................................2-18 2.4.4 Manager, Quality Assurance........................<..................................<...2-18 2.5Training Program............................................................................................,.............2-18 2.5.1 General Employee Radiological Training (GERT 4 Hour)................,................2-19 2.5.2 Radiological Worker Training (RWTHour)............................................................2-19 16 2.5.3 Health Physics Technician Training............................................,...2-19 2.5.4 Equipment Operator Training...........................................................................2-19 2.5.5 Safety/Accident Prevention Training ..........................................................2-19 2.5.6 Hazard Communication Training......................................................<......................2-19 2.5.7 Contamination Control Training ...................................................................2-19 2.5.8 Respirator Training ..............................................................................2-20 2.5.9 Confined Space Entry Training........................................................................2-20 2.5.10 Emergency Response Training................................................2-20 2.5.11 Hazardous Materials Training................................................................................2-20 2.5.12 HAzWOPER Training Course.............................-,.........,...........2-20 2.5.13 Hazardous Materials Packaging.........................................................................2-2 2.5.14 Waste Acceptance Criteria ..........,......................................220 2.5.15 Dangerous Waste Regulations............................................................

2.5.16 Emergency Response Training......................................................

2.5.17 RCRAFacility Standards Overview Training..............................................

2.6Contractor Assistance ..................................................................................

2.6.1 Contractors.................................................................................

) 2.6.2 Tasks...........................................................................................

2.6.3 Potential Contractors.................................................

iv

PC000482/2 2.6.4 Subcontractors.....,<..,,.....................,,.,,..,....<.,.....2-21 a 2.7Decontamination 2.8Facility Release andDecommissioning Documents Criteria......................................,...,..........222 andGuides..,...............2-22 W"'

3. PROTECTION OF THE HEALTHAND SAFETYOF RADIATIONWORKERS AND THE PUBLIC....................................=............................31 3.1Radiation Protection...,....,..,............,.,.,.,..,,.,.,.................=3-1 3.1.1 Ensuring As Low AsIs Reasonably Achievable Radiation Exposures...........,.3-1 3.1.2 Health Physics Program....,....,.,.,..., ..............,........3-3 3.1.3 Radioactive Material Controls.,............. .....,........... 3-10 3.1.4 DoseEstimates................,..........,.,.,........,.....,..<...,..3-11 3.2Radioactive Waste Management,....,,.............,........,...........3-14 3.2.1 Fuel Removal..,................................,....=,...=.....,.3-14 3.2.2 Radioactive Waste Processing.. .. ,...., .....,.................3-14 3.2.3 Radioactive Waste Disposal ....=..... ... ...<.......,< .......3-14 3.2.4 General Industrial Safety Program. , ...,,. ...........,..<,.<,.,..,.....3-16 3.3Radiological Accident Analyses.,..=.....==.......,....,<.,.. ....=...,...3-17

4. PROPOSEDFINALRADIATION SURVEY PLAN.................................41 4.1Description ofFinal Radiation Survey PlarL........................... ....4-1 4.1.1 Meansfor Ensuring that all Equipment, Systems, Structures, andSite areIncluded inthe Survey Plan...........,............................,,.....41 4.1.2 Means for Ensuring that Sufficient Data isIncluded toAchieve Statistical Goals..........4-1 4.2Background Survey Results.......,........,,.....................,<.,...4-1 4.3Final Release Criteria-Residual Radiation andContamination Levels.......................4-2 4.4Measurements for Demonstrating Compliance with Release Criteria.,.... .......,,.42 4.4.1 Instrumentation-Type, Specifications, andOperating Conditions.......,.....,......4-2 4.4.2 Measurement Methodology for Conduct ofSurveys..,........,.,........4-3 sh 4.4.3 Fixed Contamination Survey Protocol.<...,....=............... ...,.,.4-3 WF 4.4.4 Removable Contamination Survey ProtocoL....,.....=,,,,..................4-4 4.5Methods tobeEmployed for Reviewing, Analyzing, andAuditing Data.............=.,...4-4 4.5.1 Laboratory/Radiological Measurements Quality Assurance,...........,..... ..4-4 4.5.2 Supervisory andManagement Review ofResults.......<......,.............=.4-4

5. TECHNICALSPECIFICATIONS....................,.=..=................51

6. PHYSICALSECURITYPLAN........................................................61

7. EMERGENCYPLAN................................................................71

8. ENVIRONMENTAL REPORT...........................,.....................a81

9. CHANGESTO THE DECOMMISSIONING PLAN..................................91

10. REFERENCES....................................................,...........10-1 APPENDIX A-

SUMMARY

OF CHARACTERizATION RESULTS....=................ A1 APPENDIX B-ENVIRONMENTAL REPORT............................................. B1 V

PC-0004 82/2 LISTOF FIGURES Figure 1-1-Regional Location.............................................................................................1-2 Figure 1-2-GA Site andSurrounding Uses...,............................,...................1-3 Figure 1-3-TRIGA ReactorFacility Site andAdjacent GAStructures........................................1-4 Figure 1-4-TRIGA Reactor Facility Areas Within Decommissioning Plan Scope...........................

Figure 1-5-TRIGA Reactor Facility, RoomDetail, Plan View ..........,.....................,,..... 1-6 Figure 2-1-TRIGA Mark IOperating Chronology....................................................................2-2 Figure2-2-TRIGA Mark F Operating Chronology .....................................................................2-4 Figure 2-3-Reactor Decommissioning ...............=...................................2-9 Figure 2-4-TRIGA Mark IReactor......................................................................................2-10 Figure 25-TRIGA Mark F Reactor....................................................................................2-11 Figure 26-Decommissioning Schedule....=..............,...................,.............215 Figure 2-7-Decommissioning Organization.........................................................................2-17 LIST OF TABLES Table 1-1-Profile ofTRIGA Reactors atGeneralAtomics .....................................=.......1-7 Table 2-1-List ofExpected Radionuclides....................................................................2-6 Table 2-2-Components with Potential Surface Contamination-Group 1.....,.............................2-12 Table 2-3-Components with induced Radioactivity-Group 2 ........................................2-12 Table 2-4-Reactor TankActivated Components-Group 3 .....................................................2-12 Table 2-5-Equipment UsedinDecommissioning Operations-Group 4.......,..,...............,.......2-12 Table 2-6-Acceptable Surface Contamination Levels..................................................2-23 Table 3-1-Specific Health Physics Equipment andInstrumentationUse and Capabilities .................35 Table 3-2-Occupational Radiation DoseEstimates for TRIGA Reactors Decommissioning Tasks

....3-12 vi

PC000482/2 LISTOF ACRONYM8/ABBREVIATIONS ACPR Annular Core Pulsing Reactor ALARA AsLowAsReasonably Achievable ALI AMAD Annual Limit Activity Median onIntake (see Aerodynamic 10CFR20)

Diameter ANSI American National Standards Institute AP Activation Products APPM GA AccidentPrevention Program Manual ARA ASME Airborne Radioactivity American Society of (see Area 10CFR20)

Mechanical Engineers ATPR Advanced TRIGA Prototype Reactor CA ConditionalAuthorization CAL-DTSC State of California Department ofToxic Control Substances CAL-DHS State ofCalifornia Department ofHealth Services CAL-EPA State ofCalifornia Environmental Protection Agency CAL-OSHA State ofCalifornia Occupational Safety andHealth Act CAL-RHB Radiological Health Branch ofCAL-DHS CAM Continuous Air Monitor CCR State ofCalifornia Code ofRegulations CDE Committed Dose Equivalent (see10 CFR 20)

CE Conditional Exemption CFR CodeofFederal Regulations cm centimeter cpm counts per minute CPR Cardiopulmonary Resuscitation CTI Cryogenic Technology Inc. gi D&D Decontamination andDecommissioning W DAC Derived Air Concentration (see 10CFR20)

DDE DECON D ose Deep Equivalent Decontamination (see 20) 10 CFR DNAA Delayed Neutron Activation Analysis dpm EBOR disintegrations Experimental per minute Beryllium (measure Oxide ofradioactivity)

Reactor EDE EH&S EyeDose Equivalent GAEnvironment, (see Health, 10CFR20) andSafety Department ENTOMB Entombment EPA U.S. Environmental Protection Agency FFCRs Fuel-Follower Control Rod(s)

FGR Fission GasRelease FLAIR Flashing Advanced Irradiation Reactor FLIP Fuel Lifetime Improvement Program FP Fission Products g gram, aunit ofmass GA General Atomics GCFR GasCooled Fast-Breeder Reactor GERT General Employee Radiological Training GISO General Industry Safety Orders GM Geiger-Mueller HCF HotCell Facility (GA Bldg. 23)

HEPA High Efficiency ParticulateAir (Filter)

HEU High Enriched Uranium HP GAHealth Physics Department HPGe High Purity Germanium Detector vii

PC000482/2 a HTGR High Temperature Gas-Cooled Reactor WWA LLW Low-Level Waste

• ~

LSA LSNC LowSpecific GALicensing, Activity Safety, (see and 49CFR)

Nuclear Compliance Division MAP MixedActivation Products MDCR Minimum Detectable Count Rate MFP Mixed Fission Products micro-R micro-Roentgen, 10-6hp MIWP City of San Diego Metropolitan Industrial Waste Program MkF TRIGA Mark F Reactor MkI I TRIGA Mark Reactor MkIII TRIGA Mark IIIReactor mR milli-Roentgen, 10-3ROentgen mrad milli-rad, 10-3pag mrem millirem, 10-3 rem MSDS Material Safety Data Sheet MSHA U.S. MineSafety andHealth Administration mSv milli-Sievert (unit ofdose equivalence, see10CFR20), 10-3 3jeyept NAA Neutron Activation Analysis NCRP National Council onRadiation Protection and Measurements NFPA National Fire Protection Association NIOSH National Institute forOccupationalSafety and Health NIST U.S. National InstituteofStandardsand Technology NPR NewProduction Reactor NQA Nuclear Quality Assurance NTS Nevada Test Site ph NWPF GANuclear Waste Processing Facility 95 OSHA Federal Occupational Safety and Health Acts PB Peach Bottom (Nuclear Generating Station) pCi pico-curie, aunit ofradioactivity disintegrationsper minute), 10-"

(2.22 curie PCM Personnel Contamination Monitor POL Possession Only License PTS Pneumatic Transfer System PVC Polyvinyl Chloride QA GAQuality Assurance Organization QAPD Quality Assurance Program Document R Roentgen RA rad Restricted unit Area ofabsorbed (radiation see 10CFR20) dose RCRA Resource Conservation andRecovery Act rem Roentgen Equivalent Man(unit ofdose equivalence,see10CFR20)

RESRAD USDOE Computer Code for Residual RadioactivityCalculations RM Radiation Monitor RO Reactor Operator RWP Radiological WorkPermit RWT Radiological Worker Training SAFSTOR Safe Storage SD-DHS-HMMD County ofSanDiego Department ofHealth Services Hazardous Materials Management Division SDE SNF Shallow Spent Dose Nuclear Equivalent Fuel (see 10CFR20) sar c SNM Special Nuclear Material BAL SS Stainless Steel SV Sievert (unit ofdose equivalence, see10CFR20) vili

PC000482/2 Sx(s) Sample(s) 4ggg TEDE Total Effective Dose Equivalent Facility (see 10CFR20) W$P TFFF TRIGAFuel Fabrication (GABldg.

22)

TKF TRIGAKing Furnace TLD Thermoluminescent dosimeter TRDS TRIGA Reactor Decommissioning Scope (the ofBldg.

part 21andassociated yard area covered inthis Plan)

Decommissioning TRF TRIGA Reactor Facility (GABldg. 21)

TRIGA* Training, Research, Isotopes, Atomics General TTSL TRIGA Thermal Stability Lab TTSX TRIGAThermal Stability X-Ray Room UC2 USAEC Uranium Dicarbide U.S.AtomicEnergy Commission USDOE U.S. Department of Energy USDOT U.S. Department of Transportation USEPA U.S. Environmental Protection Agency USNRC U.S.Nuclear Regulatory Commission WA WorkAuthorization

• TRIGA isaRegisteredTrademark ofGeneral Atomics iX

PC000482/2

1.

SUMMARY

OF PLAN 1.1 Introduction 1.1.1Overview Although General Atomics(GA) continues to offer TRIGA* (Training,Research, Isotopes, General Atomics) reactors andrelated facilities,equipment, materials,andservices, GA has ceased all TRIGA reactor operationsatthe GA mainsite located inSanDiego, CA (USNRC Licenses R-38and R-67). Figure 1-1shows theregional location oftheGeneral Atomics facility; Figure 1-2 depicts the GA site andadjacent surrounding land uses; theTRIGA Reactor Facility (TRF) site andadjacent GA structures areshown on Figure 1-3;theTRF areas tobedecommissioned within the scope ofthis plan aredepicted on Figure 1-4andare defined astheTRIGAReactor Decommissioning Scope (TRDS) Figure 1-5presents a plan view oftheroomswithin the TRF. GA hasdecided toshut downanddecommission the TRIGAReactors duetoreduced market demandfor GA'sreactor irradiationservices.

The objective ofthis Decommissioning Plan isto conduct decontamination (DECON) ofthe TRDSandremoval ofradiologically-contaminated and/or radioactive materials,equipment, components, andsoil, toobtain release to unrestricted usebytheU.S. Nuclear Regulatory Commission (USNRC) andState ofCalifornia ofthe TRDSincluding partoftheTRFand part oftheassociated adjacent Controlled Yard areas.TheTRFhashoused three TRIGA reactors, which havebeenvariously usedsince 1958 to provide controlled neutronand gamma irradiation for diverse research projects. The threereactors arereferred toherein as the TRIGAMarkI,TRIGAMarkF,andTRIGAMark III reactors. Itshould benoted that this Decommissioning Plan addresses only the TRIGA Mark Iand TRIGAMarkF reactors; a profile ofthese tworeactors ispresented inTable 1-1. Inasmuch asUSNRC FacilityLicense R-100waspreviously terminated, thedecommissioning of theTRIGAMarkIII Reactor,

, adjacent rooms, andyard areas will beimplemented byGA in accordance with theGA Site f$$ Decommissioning Plan (Ref. 10.14); these activities arenotfurther addressed inthis plan.

C This Decommissioning Plan hasbeen prepared using the guidance and formatofNUREG -

1537 Rev. 0,Guidelines for Preparing andReviewing Applications for theLicensing of Non-PowerReactors (Ref. 10.1).

1.1.2Decommissioning Plan Provisions This Decommissioning Plan provides the following:

1.1.2.1A description ofthepresent radiological condition oftheTRFandadjacentControlled Yardareas.

1.1.2.2A description oftheplanned approach tobeemployed todecommission the TRDS.

1.1.2.3Descriptions ofthemethods that will beutilized to ensure protectionofthehealth and safety oftheworkers andto protect theenvironment andthepublic fromradiological hazards associated with the subject TRDSDecommissioning Projectactivities.

1.1.2.4A description ofTRDSphysical security andmaterial accountabilitycontrols thatwillbein place during the various phases ofDecommissioning Project activities.

1.1.2.5A description ofthe radioactive waste management anddisposal.

1-1

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PC000482/2 (gj$/ Table 11-Profile ofTRIGAReactors at General Atomics

• • Item Description TRIGA Mki TRIGA MkF WMMDMM@$WMRM@MWSEMMERMMEMM@h@WhM Classification: Research, Pool-Type, Water-Cooled, Thermal, PrivatelyOwned Owner: Atomics General Location: TRIGA ReactorsFacility 21),

(Bidg.3550General AtomicsCt.,SanDiego, CA92121-1194 Operator Owner Owner Licensee: Owner Owner Architect/Engineer: RalphM.Parsons Co. FerverDoriand & Assoc.

Nuclear Design: Owner Owner Research & Development: Owner Owner Core Manufacturer Owner Owner Construction: Owner Owner PrincipalUses: Training, NAA, DNAA, Transient Radiation Thermionic Studies, Power Development, n-Radiography BMEMEWMMWi8MWMPMSMMMEMMkMWCEREEWWWFWEMW Criticality:

initial 5/3/58 7/2/60 Date Secured: 10f2997 3/22/95 USNRC UtilizationFacility Lic.

1. R38 R-67 USNRC FacilityDocket #: 50-89 50-163 RMMSkicMtig$Migji@WWMj@@paWWW$$R4H@@GRE$EWAE@igM&WWWENNEWB MaximumPower, Steady State,MW(t): 0.25 1.5 Max.imumPower, Pulsing, MW(t): 1000. 6400.

ea Steady State,(nv): 1.40E+13 3.30E+13 ow Pulsing, (nv): 5.40E+16 1.40E+17 ow Steady (nv):

State, 4.50E+12 4.40E+13 Pulsing, 4,3,rm,, (nv): 1.80E+16 1.90E+17 SpecificPower (kW/kg 2syy 80 420 A Core Power Density, (kW/I): 3.5 20 W FuelMaterial: UzrH,.oorUzrHu UzrH,.e FuelUranium Content,wt% U: 8.5 8.5,30 Uranium Enrichment, %asU: 20% 20%,70%,93%

FuelElement Geometry: rods, Cylindrical 1.42: cm)

(3.61dia.x 15" (38.1 cm)activelength Element Cladding Material: 1100FAlor304SS 304SS Element Cladding Thickness: 1100FA1:

0.03" cm);

(0.076 304SS:0.02" (0.051 cm)

Core Configuration: Circular array Hexagonal array Core ActiveHeight:: 15"(38.1 cm) 15" (38.1 cm)

No.ofAvailable FuelPositions: 91 121 Coolant: Lightwater Lightwater Moderator: Light water, 2rH Light water, zrH Reflector: Graphite Water NOTE-The profile above relates general tothe characteristics during ofthereactors therespective periodsofoperation. inthe course of operations,bothofthe reactorswere toaccommodate modified utilization ofthefacility b reactor users;such modificationswerecarried outbythe implementation ofappropriate changes tothecorrespondingTechnical Speci orbyapplication cations, ofthe of10 provisions CFR50.59.

1-7

PC000482/2 1.1.2.6 A description ofTRDSphysical inplaceduring thevarious phases securityandmaterial ofDecommissioning accountability controls Projectactivities.

that willbe g@

5$9 1 1.2.7A description ofthe radioactive waste management anddisposal.

1.1.2.8 A cost estimate for decommissioning the TRDS,andthe source offunding forthese activities.

1.1.2.9 A schedulefor the subject TRDSDecommissioning Project.

1.1.2.10 A description of theQuality Assurance Program applicable to theTRDS DecommissioningProject.

1.1.2.11 A description ofthe Training Program tobeestablished forpersonnel performing work insupport oftheTRDSDecommissioning Project.

1.1.2.12 AnEnvironmental Report concerning theexpected impact ofperforming theactivities involved intheTRDSDecommissioning Project.

1.2 Background

M General Atomics Theproperty, onwhich issituated the General Atomics TRIGA Reactor SiteandFacility, wasacquired in1956 from the City ofSanDiego, aspart of a ~290 acre (~117 hectare) -

tract, by theGeneral Dynamics Corporation, withthe expressed purpose of the (g$

establishment ofthe John J.Hopkins Laboratory for Pure & Applied Science, later named **

General Atomic Division ofthe General Dynamics Corporation. One of the first goals of thenewly-established General Atomic DivisionofGeneral Dynamics was the development ofa new family ofsmall nuclear reactors,which could beutilized in both industrial and academic applications for training, research, andisotope production.Between 1957 and 1966three TRIGAreactors wereconstructed intheTRIGAReactorFacility (TRF),

although thisDecommissioning Planaddresses thetwo reactors whichare currently licensed (in Possession-Only-License, POL,status), i.e.,theTRIGA MarkIand Mark F reactors. Figure 1-5s hows t he c urrent TRF configuration. Thespecific TRFrooms and yard areas tobeaddressed inthe TRDSDecommissioning Projecthereinare listedbelow.

MkIReactor andControl Room,21/102 (~860 area) ft2 Vestibule, 21/102 (~60 area) ft2 Offices, 21/103-21/104 (~280 area) ft2 Tool Shop, 21/105 (~230 area) ft2 Counting Room,21/106 (~280 area) ft2 MkFReactor Room,21/107 (~870 area) ft2 MkFControl Mezzanine Room,21/108 above 21/108

(~280

(~280 area) ft2 area) ft2 Mezzanine above 21/109 (~280 area) ft2 MkIControlled Yard (~1100 ft2area)

MkFControlled Yard (~1440 area) ft2 Plus additional portions ofthe Cooling Tower Controlled Yard andother outdoor areas associatedwith the TRFCooling Tower underground pipingsystem.

1-8

PC000482/2 Figure 1-4 shows the TRDSarea, which isincluded inthe scope ofthis Decommissioning Project.

TRIGA MarkIReactor As part of earlynuclear reactor development efforts,General Atomics initiated plansto design,build, andoperate aprototype reactorunitonthe company's Torrey Pines Mesa site. To this end, inlate 1957, GArequested andobtained a Construction Permit and Utilization Facility License from theU. S.Atomic Energy Commission (USAEC) to authorize thisactivity. Immediately working thereafter, with theRalph M. Parsons Company astheArchitect/Engineer, General Atomics proceeded with construction ofthe Isotope Reactor Building, laternamed the TRIGAReactor Facility (Building 21), tohouse the Prototype TRIGAReactor andsupportingsystems (e.g.,Instrumentation andControl Systems, Forced Cooling System, Water DemineralizationSystem, Ventilation/Exhaus System, Radiation Monitoring Systems, etc.). Following building construction andreactor hardware installation, thePrototype TRIGA Reactor wasbrought toinitial criticalityon May 3, 1958. Continuously operational fromthat date until late 1997, thePrototype TRIGAReactor waslater designated as theTorreyPines TRIGAReactor, andlater yet,as the TRIGAMarkIReactor. AtGA's request, theUSNRCissued anamendment tothe TRIGAMark Iutilization facilitylicenseon October 29,1997, which placed the in reactor Possession-Only-License (POL) status.

TRIGAMark F Reactor InMarch 1960, GA submitted anapplication tothe USAEC requesting a Construction Permit andUtilization Facility License fortheFlashing Advanced Irradiation Reactor g (FLAIR). These documents wereissued toGAbythe USAEC andthereafter,working

@r ; with the Rooms21/107 Fervor-Dorland and21/108 Engineering tohouse Co.,Building the 21was modified bytheaddition FLAIRReactor andReactor Instrumentation &

of Control Systems, respectively. This whichwasbrought to initial criticality onJuly

'~

reactor, 2,1960, wascontinuously maintained andoperated byGAfromthat time untilMarch 22, 1995, whentheUtilization Facility License was amended, at therequest ofGA, to authorize Possession-Only-License (POL) activities.

During theoperating period, the reactor installation wasdesignated asthe AdvancedTRIGAPrototype Reactor (ATPR) and also later referred toasthe TRIGA MkFReactor.

Cunent.EgilltLStalu.gi TheTRIGAMkIReactor, situated inTRFRoom21/102, wasplaced in"Possession-Only-License" (POL) under status, Amendment No.35tothe USNRC License No.R-38, dated October 29,1997 (Ref. 10-2), andispresently inoperable. Allreactor fuel elements have been removed from the MkIReactor pool, andtransferred/relocatedtothe MkFfuel storage canal inRoom21/107. Moreover, anumber ofadditionalcomponents and hardware items, previously installed aspart ofthe MkIReactor Control andInstrumentation systems, have beendismantled, surveyed, andremoved fromtheTRF forrecycle use;this partial dismantlement anddisassembly ofthe MkIsystems was performed by implementing instructions setforth inaplan, which wasprepared, reviewed, andapproved inaccordance with the administrative provisions of10CFR50.59.

TheTRIGAMkF Reactor (situated inRoom 21/107) was previously placed in "Possession-Only-License" (POL) status underUSNRCLicense No.R-67 (Ref. 10-3),as

, amended onMarch 22,1995, andisalso inoperable.

currently Allreactor fuel elements gW have Canal.

been removed Thenon-fuel from theMkFreactor components ofthe core/shroud MkFreactor, andplaced including inthe the core MkFFuel support Storage structure, 1-9

PC000482/2 bridge shroud, beamtubes, andassociated hardware, remain inthe pool.

reactor TheFuel a Storage Canal portion Fuel (SNF) elements ofthe MkFreactor previously removed pool currently fromthe houses all MkI,MkF andMkIII oftheSpent Nuclear Reactors.

f@

All

• required protection barriers andsecurity systems, including those forHigh necessary Enriched Uranium (HEU) (i.e.,electrical service, domestic watersupply) storage, are maintained inaccordance with GA'sNRC-approved physical protectionplan.

All TRFbuilding utility services required for facility operation andmaintenance under POL conditions areactive.

TRFbuilding airventilation andHEPA-filteredbuilding exhaust systems,airsupply compressors, andlicense-required radiologicalmonitoring instrumentation systems arein normal continuous operation.

Allmanually-actuated andautomated fire alarm/suppression systems intheTRF are operational.

All installed TRFsecurity andradiological alarm systems are activeandnormal.

Independent waterdemineralization systems serving theTRIGAMkIandTRIGAMkF Reactors remain fully operational.

A commonforced water cooling system servingboth the TRIGAMkIandMkF Reactors remains fully operational.

1.2.1Reactor Decommissioning Overview Prior toimplementing thedecommissioning actions described herein, theTRFwill have been cleared ofall extraneous fixtures, equipment andmaterials, except forthespent TRIGAfuel. Thespent TRIGAfuel will bestored inthe TRIGAMkF Reactor Fuel Storage Canal until approval foroff- site shipment isobtained.

Decommissioning ofthe MkIandMkF will beseparate activitiesbutmay be conducted concurrently. Activities presented below address both reactors.

Summary ofActivities 1.2.

1.1 Reroute services toisolate theTRIGAMkF Reactor andControl Rooms.(21/107 and 21/108) to maintain fuel storage support.

1.2Dismantle, 1.2. decontaminate orpackage asLLW, the TRIGAMkIReactor components, tank andpit structures. Thecriticality equipment pit will besimilarly addressed.

1.3Decontaminate 1.2. anyremaining contaminated areas within theTRDSexcept the TRIGA MkFReactor andControl Rooms, (21/107 and 21/108).

1.2.

1.4Dismantle, decontaminate, orpackage asLLW,the TRIGAMkF Reactor components, tank andpool structures except where activities would potentially interfere withsafe fuel storage under normal oraccident conditions.

1.5Obtain 1.2. necessary approval, andship the stored spent TRIGAfuel from TRIGAMkF the Reactor Fuel Storage Canal.

1-10

PC000482/2 1.2. 1.6 Decontaminate anyremaining contaminated areas inthe TRIGAMkFReactor andControl

( Rooms and service yard (21/107 and21/108).

1.2. 1.7 Dismantle, decontaminate orpackage asLLW, the TRIGAMkFReactor components, tank and pit structures.

1.2. 1.8Remove any contaminated soils inadjacent orunderlying locations.

1.2. 1.9Prepare,package, process, andship all radioactive wastematerials,as appropriate throughout the activities.

1.2. 1.10Perform anddocument thefmal radiological survey(s) andsubmit a request tothe USNRCand State of California for performance surveyssubsequent ofconfirmatory and release tounrestricteduse.

1.2.2Estimated Cost Thecost estimate isconsistent with the scope of work coveringD&Dofthe MkIandMkF Reactors. D&D ofthe TRDSwill be accomplished without ofthe dismantlement building.

This project cost estimate $5,584K. Cost breakdown isgiven below.

LSNC 960 MarkID&D 656 MarkFD&D 775 Other D&DTasks 314 Outside Contracts 100 Waste Management 140 Waste Disposal & Shipping

• 92 A

t@

n QA Principal Investigator 339 339 E Project Management 638 Independent Confumatory Survey (ifrequired) .3.0.0 Subtotal 4,653 Contingency 20% 931 Total $5,584K

• Theestimate for LLW disposal isbaseduponthe wastebeing buried atthe NTS.

1.2.3Availability ofFunds Estimates ofthe costs ofdecommissioning all ofGeneral USNRC(and Atomics' of State California) licensed facilities andsites inSanDiego were provided inGA'sMay20,1996 submittal toUSNRC(Ref. 10.5) which included theTRIGAReactor Facility.That submittal also described themethod bywhich GAproposed toprovidefinancial assurance for funding its total cost ofthe subject decommissioning. Byletter datedJuly 9,1996 the USNRCacknowledged acceptance ofGA'sproposal (Ref. 10.6).

1.2.4Program Quality Assurance 1.2.4. 1 TheGA Quality Assurance (QA) program isdescribed intheGA Corporate Quality Assurance Manual.

TheGA Quality Assurance program meetsthe requirementsofthefollowing quality assurance regulations and standards:

1-11

PC000482/2

• CodeofFederal Transportation Regulations Title ofRadioactive Subpart 10,Part Material,"

71 (10 H,

CFR 71),"Packaging "Quality Assurance."

and @$

WF e ASME-NQA-1-1989 (Ref. 10.7), "Quality Assurance Program Requirements for Nuclear Facilities."

a ANS Standard 15.8 (Ref. 10.16), "Quality Assurance Program Requirements for Research Reactors."

TheGA Corporate Quality Assurance program was reviewed andaccepted by the USNRCTransportation andStorageInspection Section, Spent FuelProject Office, Nuclear Materials Safety and Safeguards, Approval No.0030, Revision 6, dated July 9, 1996, expiration date June 30, 2001 (Ref. 10.8).

Thequality assurance programused for decommissioning ofthe TRDSisdescribed ina Quality Assurance Program Document (QAPD) prepared forthe Decommissioning ofthe TRIGAReactor Facility. TheQAPD invokes the useofthe GAQA Manual on this project andprovides project-specific QArequirements, includingOrganization, andtheQA measures applied toplanning, dismantlement, radiological surveys, material shipments, andwaste certification.

Consistent with the QAManual andUSNRCRegulatory Guide 7.10, Appendix A (Ref.

10.9), theQAprogram isapplied tothe various project activities ina graded approach, the i.e., QAeffort extended onanactivity iscommensurate with itsimportance tosafety andits impact onproject goals.

Therelationship ofthe QAfunction tothe Decommissioning organization andtofacility management isshown inFigure 2-7.

1.2.4.2 Audits, Inspections, andManagement Review Formal Quality Assurance audits will beperformed annually inaccordance with ASME-NQA-1,to verify compliance withtheTRDSDecommissioning quality assurance program andtoverify itseffectiveness. These audits will beperformed in accordance withwritten checklists bypersonnel whodonothave direct responsibility for performing activities the being audited. Audit reports will bedistributed toresponsible management, uptothe Senior Vice Presidentlevel. Follow-up action will betaken, where indicated.

Project technical assessments andQAsurveillances will beperformed frequently to assess compliance with established procedures. These assessments will becoordinated bythe project QAmanager. Theassessment teamwill consist ofquality assurance and technicalpersonnel. Assessments will beperformed inaccordance with a written plan.

Assessment reports will beapproved bythe project QAmanager anddistributed tothe projectmanager andother project personnel. Follow-up action will betaken, where indicated.

Inspections will beperformed onprocured andfabricated items toverify compliance with controlling documents. Inspections will be conducted by qualified inspectors in accordance with inspection plans prepared bya quality engineer. Discrepancies will be documented ina Nonconformance Report, which will bedispositioned bya quality engineer, oraMaterial Review Board, asappropriate.

1-12

PC000482/2 Additional reviews or management assessments will whendeemed be performed appropriate bythe of prior tostartanewtask, Manager.

Project or Suchassessments Management Assessments.

Readiness mayinclude Reviews 1-13

PC000482/2

2. DECOMMISSIONING ACTIVITIES 2.1 Decommissioning Alternatives Theobjective ofthe TRDSDecommissioning Project istoobtain regulatory ofthe release portions of theTRFand adjacent contiguous controlled yard identified areas, on Figure1-4,tounrestricted use. Onthis basis safe storage (SAFSTOR) orentombment (ENTOMB) wereconsidered inappropriate toGA'sfuture plans.

SAFSTOR poses essentially the samepotential risks andenvironmental impactsasthe proposed project, but potentially for a muchgreater period oftime. This alternative would necessitate continuedsurveillance andmaintenance ofthe TRDSovera substantial time period. During thisperiod, therisk ofenvironmentalcontamination would continueto exist. Moreover, development ofthe land around the GAsite over the nextfewyears may significantly increase thelocal employment population density andincrease for potential public exposure.

ENTOMB would necessitate continued surveillance andmaintenance ofthe TRDSover a substantial time period. During this period, the risk ofenvironmentalcontamination would continue toexist. Moreover, developmentof the land around the GAsite over thenextfew years maysignificantly increase the localemployment populationdensity andincrease potential for public exposure.

DECON isthe option chosen. Tothe extent possible, decontamination offacility equipment andstructural components will beconducted to minimize radioactive waste.Structural

, portions ofthe building andsurrounding soils andmaterials, found toberadiologically

Wik, contaminated and/or activated, shall beremediated, decontaminated, sectioned and removed orprocessed, asnecessary. This would befollowed byanextensive andcomprehensive final radiation andcontamination survey demonstrating that theTRDS meets the approved criteriafor release tounrestricted use. Theresults ofthis final survey will bedocumented inareport which will besuomitted tothe USNRCandState along with a request thatthe site bereleased tounrestricted useanddeleted from GA'slicenses.

2.2 Facility Radiological Status 2.2.1 Facility Operating History 2.2.1.1TRIGAMarkI Startup: May, 1958 Shutdown:October, 1997;USNRC Utilization Facility License. #R38 presently 10.2).

limited to PossessionOnlyLicense (POL) status (see Ref.

Max.Power: 250kW(t) Steady State TheMarkI'IRIGA Reactor wasoriginally constructed byGA toprove theinherent operational safety of(U,zr)H, TRIGAfuel matrix. Figure 2-1provides a listingof operations conducted intheGA 'IRIGA MkIReactor. Through October 1997, the integrated power generated during operation ofthe TRIGAMkIReactor isestimatedtobe 84MW-days.

2-1

PC000482/2 TRIGAMark1: r Startup: 5/58  ;

Shutdown: 10/97 Max. Steady Power: 250kW(t) State 5/58 Radiation Streaming thru DryTubes 6/58 Reactor Transient Experiments 7/58 Irradiation ofUCinGraphite forFPDiffusion 8/58 Transient Reactivity Compensation 12/58 Subcritical Assemblies 4/59 frradiation ofPbTeThermoelectric Elements 4/59 Determination ofTemperature Coefficient 4/59 Transient Irradiations byDiamond Ordnance FuseLab& Signal Corps 12/59 HTGRFuel Compact Radiation Flash 2/60 lrradiation ofThermoelectric Experiment 4/60 lrradiation ofCsCell for Thermionic Direct Conversion 5/60 initialExperiments with inCore TRIGAKing Fumace (TKF) 3/61 Experiments with High Hydride SSCiad Fuel 3/61 Continued CsCell Irradiation 8/61 Irradiation ofSemiconductors 11/61 InitialStearate RuninTKF 2/62 Generation of"Ar gasfor HCFStack Monitor Calibration 11/63 Pilot irradiation ofEBOR2F1Sxs 2/64 Epithermal Neutron Absorption 6/64 Continued TKFStearate andFGRStudies 7/64 ITransport Experiment 10/64 In-Core Irradiation/Firing ofExplosive Actuators 1/65 Irradiation ofFissionable Materials inSealed Canisters 5/65 In-Core Irradiation of "Li 9/65 Modify TKF for Pulsing 3/66 Irradiation ofElemental Na 1/67 Irradiation ofAqueous PuSolution 2/68 Fission Product Decay RateExperiments 8/69 Irradiation ofCartridge Primer inPneumaticRabbit 3/70 Irradiation ofEncapsulated "U, "U,"Npand"Pu 3/70 UseofGraphite Pouch for TKF Irradiations 10/70 Irradiation ofF29Capsule Rods inTKF 2/71 inCore Oscillator Measurements 3/71 UseofShielding Materials inTKF 5/71 Irradiation ofUzrHInTKF 6/71 Ambient Temperature TKFIrradiations 8/71 High-Capacity TKFruns Out-of-Core 9/71 Simultaneous ofMultiple Operation TKFs 10/71 Installation ofAuxiliary CadmiumShielded Pneumatic Transfer System 1/72 Installation ofNewLinear Channel Component .

6/72 Installation ofNewServoController Linear Channel  ;

6/72 Removal ofFreon Cooling System Hardware 8/72 TKFIrradiation ofHigh-Burnup Fuel Specimens 3/73 WetHelium TKFPurge Test Experiments 12/73 Installation of'"B Shieldin Pneumatic Transfer System Terminus 4/74 Automated TKFControl steminstallation 4/74 Fuel Hydrolysis Experiments inTKF 2/75 UseofAmBeStarter Neutron Sources 5/75 Irradiation ofHighly)Radioactive Specimens inTKF 4/76 UseofNePurge Gasfor TKFInsulation 11/76 Irradiation ofHighlyRadioactive Specimens inTKF 12/76 Irradiation ofPBCompacts inTKF 2/80 Installation ofNewOperating Console 6/80 installation ofUninterruptable Power System 7/80 Useof"BShielded PTSatHigher Power Levels 4/82 High-Pressure Experiments toDetermine Diffusion Rates 7/84 installation ofMicroprocessor-Based Control Systems DigitalControl Console Phase 11 11/85 Pressure Vessel for Neutron Pulse Irradiation Tests 3/86 Pulse-Irradiation of"UDoped Concrete 9/86 Digital Control Console installation Phase ill 4/87 installation ofPVCPiping inCold-Leg ofCooling System 12/87 Installation ofStepping Motors for Control RodDrive 2/88 Digital Control Console Installation Phase IV 6/88 Square-Wave to250kWSSOperation Experiments 6/88 Phase V Dital Control & Instrumentation System 1/89 installation o Ground Fault Detector Test Circuitry 5/89 installation ofNewScramTimer'Circuit 6/89 Installation ofNewCAM 8/89 Irradiation ofNPRLithium Target Specimens 6/90 Installation ofNewReactor Core TopGrid Plate 2/91 Extension ofNPRLithium Target Irradiations 3/91 Multiple Pulsing Program 3/91 Modification ofNM1000 Wide-Range Power Channel 5/91 Installation ofNFC-1000 Flux Controller 8/91 installation ofLoss-of-Magnet Voltage Relay-In ScramLoop 3/92 installation ofLa e Diameter inCore IrradiationDryTubes 9/92 Modification of ital Communications Network 12/96 TRIGA Reactor Demonstrations and,Operator Training

/o/9'7 Shuti o@

Figure 21-TRIGA MarkI Operating Chronology 2-2

PC000482/2 2.2.1.2 TRIGA MarkF Startup: July, 1960 Shutdown: March,1995;USNRC Utilization Facility License. #R67, presently limited to Possession-OnlyLicense (POL) status (Ref. 10.3)

Max.Power: 1500kW(t) Steady State TheGA TRIGA Mark F Reactor wasoriginally constructed byGA asa prototypical testing reactor,to act asaproof testreactor for the TRIGAReactor supplied byGAtothe Defense Atomic Support Agency, Bio-Medical Radiation Research Facility, National Naval Medical Center, Bethesda, MD, under Contract No.27757, dated 4/4/60. InApril, 1961, while continuing to operate extensively for the Bethesda testing campaign, GA began toutilize the MarkF Reactor ona multi-user basis forseveral other irradiation experiments, themost conspicuous ofwhich weretheIn-Pile Thermionic and Thermoelectric Power Conversion Projects andrelated experiments. Another primary user ofthe reactor, beginning in June, 1963,wasthe Department ofDefense Special Weapons Testing Los Center, Alamos, NM, involving the in-pile survivability testing of high-explosive ordnance fortheU.S. Army. Figure 2-2provides a listing ofthe experiments performed using the7RIGA Mark F Reactor.Integrated power generated during operation ofthe TRIGAMkF Reactor is estimated tobe4,200 MW-days.

2.2.2 Current Radiological Status oftheFacility 2.2.2.1 General Routine radiological surveys showthat theradiation levels and contamination levels measured atthe TRFhave consistently been low.A radiological studyconducted in March1997, andsummarized inAppendix A, confirmed thatonly minor quantities of residual radioactivity orradioactive contamination arepresent. The information indicates that the radioactive portions ofthe facilityare primarily confined tothe reactor internals andbiological shield.

Estimates ofthe radioactive inventory canbedetermined byconsidering the constituent elements ofthematerial inquestion andcalculating theduration ofexposure to the neutron flux andthe energies ofthe incident neutrons. Direct measurements, however, are generally morereliable andwill beused during actual removal and/or dismantlement ofcomponents. This information will further define thebasis forspecifyingthe necessary safety measures andprocedures forthevarious dismantling, removal, decontamination, waste packaging, andstorage operations sothat exposure topersonnel ismaintained ALARA, 2-3

PC-000482/2 TRIGAMark F:

Startup: July, 1960 Shutdown:March, 1995 Max.

Power:1500 kW(t)

Steady State 660 Construction Authorized 750 Reactor Startup Experimental Program 950 BiologicalTargets Authorized 4S1 Thermionic Direct Power Conversion 561 Support ofHarry Diamond Laboratory, Forest MD Glen, 8/61 Thermoelectric Device Targets Authorized 10/61 Uraniumzirconium Carbide Thermionic Emitter 1151 Core Loaded with SSClad zrH,.7 Nelames 1141 Support ofAFRRI (Armed Forces Radiation Researchinstitute), MD Bethesda, 12/62 Support ofSandia National Laboratory, Albuquerque, NM 253 Pulsed,Fueled Experiments Authorized 4/63 Pulsing Program Continuing, to$4.00 Sk/k Insertion 6/63 InCore Irradiation ofExplosives, HanyDiamond Laboratory, Forest MD Glen, 7/63 installation of2"d Transient Rod 8/63 Fuel Fission Product Release Studies 9/63 Irradiation ofUltrapure Al 11/63 Irradiation ofXylenes for Radiation Damage Studies 3/64 installation of FFCRs andD-Ring Transient Rod 4/64 Irradiationof Agzn/KOH Batteries 6/64 Irradiation ofLaser Rods, Squibs, & Electronics 9/64 Thermionic/Thermoelectric Device Targets Authorized 365 IrradiationofSLiF and Red Phosphorus, Sandia National Laboratory, NM Albuquerque, 11/65 Experimental PulsingProgram Authorized 2/66 Experimental Pulsing Program Authorized 3/66 Fueled TKFExperiments Authorized 3/66 TKFHTGRDevelopment Work Authorized 8/66 Pulsing Program Continuing, to$4.60 Sk/kinsertion 787 ACPRPulsing Configuration Authorized 7/67 in-Core TKFAuthorized 8/67 Routine UseofTKFfor SS& Pulsing Irradiation 8/68 Uranium Vaporization from Seawater Media t 8/68 600CiyIrradiation Experiment 10/68 Installation ofFLIP Elements 1/69 Irradiation ofassU Doped Concrete 1/69 Modification ofTarget Thermionic Device Design 2/72 Explosive Targets Authorized 3/73 Continued TKFTesting 4/73 Installation ofMark IllFuel inMark FCore 4/74 Reconfiguration ofMark FtoSmall Core High PowerDensity 1/75 installation ofMark Ill Console toMark F 4175 Routine PulsingProgram Development 5/75 Pulse Testing Irradiation ofNewTRIGA Fuel 12/75 Continued TKFTesting 10/76 Cold Neutron Radiography ofzr Program (CTI Nuclear) 11/76 Cryogenic nModerator UseAuthorized (CTI Nuclear) 2/77 Testing of1/2" dia.Fuel atSteady State 12/77 Continued operations forCTINuclear andTKF 4/78 Continued Testing of1/2" dia. Fuel forRomania TRIGAReactor 6/78 Testing ofCentral FluxTrap inPulsing Mode 11/80 Small Core Pulse Testing 5/82 High Pressure TKFTesting 10/82 Isotope Production ofMAr & B28p 7/83 Fuel Performance Evaluation andImprovement Experiments 9/84 Reactor Modifications forThermionic Device Irradiation 5/88 Misc. Modifications forContinuing Thermionic Device Irradiation 1003 Continued Thermionic Device Irradiation 395 Shutdown Figure22-TRIGA MarkF Operating Chronology 2-4

PC000482/2 2.2.2.2 Principal Radioactive Components This section isbased uponprocess knowledge andisconsistent with information obtained as a result ofactual decommissioning experience of a TRIGA Mark IReactor at the University of Texas, Texas.

Austin, Themost highly radioactive component islikely tobethe stainless steelconstruction Rotary Specimen Rack Mark inthe IReactor which may expected a dose be tohave rate of= 16R/hr at 1 ft.

Other components to behandledandprocessed during TRFDecommissioning which mayrange upto= 5 R/hr atthe surface are:

e Upper andLowerGrid Plates fromboth TRIGAMarkIandMarkF Reactors; aluminum constructionwith integral stainless steelfasteners.

e Core Support Structure ofboth TRIGA MarkI andMarkF Reactors; primarily aluminum construction, withstainless steel components.

e Graphite Reflector Assembly installed radially around TRIGAMarkIReactor core.

a Miscellaneous fasteners,especially stainless steel bolts, nuts, andpossibly helicoils, other reactor-related hardwareitems.

2.2.2.3 Radionuclides Theradionuclides which areknown tobepresent, orare possibly present indetectable levels within the TRDSarelisted inTable 2-1.

2.3 Decommissioning Tasks 2.3.1Activities andTasks 2.3. 1.1 Preparation ofthe TRFfor Decommissioning 2.3. 1.1.1 Characterization Surveys Aspart ofDecommissioning Project planning actions, studies have been conducted to determine the type, quantity, andlocation condition, ofradioactive and/or hazardous materials which are,ormay be,present intheTRF andsurrounding areas. A comprehensive radiological survey ofthe TRFwascompleted inMarch 1997 bythe GA Health Physics organization. Data andresults from these surveys areprovided inthis document asAppendix A:"Summary ofCharacterization Results."

2.3. 1.1.2Transfer ofSpent TRIGAFuel toTRIGA Mark F Fuel Storage Canal Inorder to comply withtherequirements ofthePossession-Only-License (POL) conditions and10.3, for theTRIGAMarkIandMarkF Reactors respectively), all irradiated TRIGAFuel inthe (as set forth TRDShasbeen inReferences removed 10.2 from the tworeactor cores, andhasbeen physically transferred tothe TRIGAMarkF Fuel Storage Canal.

2-5

PC-000482/2 Table 21: List ofExpected Radionuclides Nuclide HalfLife Decay Notes (yr) Mode

'4C 5730. p- AP; from n-activation ofgraphite reflectorstructure (TRIGA Mkionly) 54Mn 0.86 e y

, AP; shortlived specie; from n-activationofSS hardware 55Fe 2.73 e AP;from n-activation ofSShardware "Co 5,27 p, y AP; from n-activation ofSShardware; expected tobepredominant APspecie present 59Ni 76000. e y

, AP; from n-activation ofSShardware 3Ni 100. p~ AP; from n-activation ofSShardware "Sr 29.1 p- FP;probable FPconstituent; activity expected tobeproportional to that of'"Cs 94Nb 20000. p,y AP; unlikelyAP inventory constituent; possible from of n-activation SShardware, gNb impurities arepresent "9Tc 213000. p,y FP,andminor APinventory constituent; possible from of n-activation SShardware, IMoimpurities arepresent 12sSb 2.76 E,y FP;relatively shortlived specie "4Cs 2.07 E,y FP;minor FPinventory constituent 370s 30.17 p,y FP;expected tobepredominant FPspecie present

'4Ce 0.78 p,y FP; shortlived specie 1saEu 13.48 p-p+, e y

, FP,andminor APinventory constituent; possible from n-activation of concrete, EEuimpurities exist inbiologicalshield structure Symbols/Abbreviations: p- = Beta p+ = Positron e = Electron Capture y = GammaRay AP = Activation Product FP = Fission Product Radionuclide Half-Life andDecay values Modeinformation used above aretaken from Ref. 10.15.

ofexpected Thelist radionuclides provided above isbased ontheassumption that operations oftheTRIGAMarkIandMarkF have Reactors resulted inthe activation neutron ofreactor core components andother integral hardware orstructural memberswhich adjacent aresituated orinclose to, proximity thereactor to, coreduring operations. Specificitems which are tohave considered beenexposed toneutron include activation materials composed ofaluminum, steel, stainless-steel, graphite, cadmium, lead, andpossibly concrete Based others. onearlierstudies andexperience gained insimilar research reactor decommissioning projects, andreactorspecific calculations which considered measured values for neutron leakage fluence, integrated power operating histories, core/pool reactor configurations, structural andmaterial composition ofexposed pool structures, neutron of activation beyond materials theconcrete liner/biological shield structure (i.e.,into surrounding volumes) soil isngexpected for the either TRIGAMark InorMarkFReactors.

2-6

PC000 482/2 2.3. 1.

1.3General Cleanup ofTRFandAdjacent Controlled Yard Areas Inpreparation fordecommissioning activities, non-reactor related equipment and materials situated throughout the subject areahasbeen collected, surveyed, packaged, and appropriately dispositioned inaccordance with established procedures. Examples of items which have been processed andremoved from the TRFduring these efforts arethe TRIGA King Furnaces irradiation facilitiesandassociated power andcontrol systems.

2.3. 1.

1.4Partial Removal of the TRIGAMark IInstrumentation andControl System InJune,1998, major portions oftheTRIGAMarkI Reactor Instrumentation and Control (I&C) system were dismantled, surveyed, released, andshipped from the TRF for subsequent off-site recycle use.All ofthe actionsinvolving theremoval ofthe TRIGA MarkII&Csystem were authorizedandperformed inaccordance with specific written instructions, which were reviewed andapproved under the provisions of10 CFR50.59. Specific I&Ccomponents thus removed from service atthat time included the Control System Console, the Data Acquisition and Control Cabinet, the NM-1000 Wide-Range Digital Power M onitor, andtheControl RodDrives. Reactor-related instrumentation systems requiredfor the surveillance andmaintenance oftheTRIGA Mark Iunder current POLconditions, were left inplace orrerouted tothe TRIGAMark F Control Room.

2.3. 1.2Decontamination ofthe Facility This Decommissioning Plan involves the sequential dismantling ofthe tworeactors, the reactor pits andliners, andanyassociated systems,in a safe mannerandinaccordance with ALARAprinciples, andfinally thedecontamination and survey ofthe entire TRDS.

tE There aretwo distinct reactors addressed. First the'IRIGA Mark IReactor will be W dismantled. Second, theMarkF will bedismantled intwo steps. Included inthe decommissioning step isremoval ofall equipment inMarkF not associated with fuel storage andwhere removal would notaffectorcompromise safe secure fuel storage.

Following removal ofthe fuel from theFuel Storage Canal, the remaining TRIGA Mark F Reactor components (e.g.thepool) willbe dismantled. Figure 2-3 depicts the decommissioning ofthe MarkI andthe two decommissioning steps for the MarkF.

Views ofthe tworeactors being addressed herein are shown inFigure 2-4and Figure 2-5.

Foreach reactor, components above the pool will beremoved, including reactor pool deck plates, bridge structure, cables andreactor conduits, andtherotary rack drive dismantled anddecontaminated tothe extent feasible. Reactor components with induced activity will beremoved usinggrapples andplaced inshielded containers fordisposal as LLW.This will befollowed bya survey anddischarge ofthe reactor pool water. Water inthe Mk F andFuel Storage Canal will notberemoved until after the fuelhasbeen removed. Thedismantling ofthe reactor tanksand pits will proceed after installationofa confinement barrier inthe reactorroomanda dedicated ventilation system toprevent the spread ofairborne contaminants. Thealuminum reactor tank will besectioned inplace, removed from the pit andthe contaminated sections packaged for disposal. Surface and coring samples ofthe concrete biological shield will beperformed todetermine the contaminated areas. Thecontaminated sectionswill becutawayandpackaged. Because ofthe limited removal ofmaterial andavailability ofshoring ifrequired, the structural integrity ofthepit will notbe compromised bynecessary decontamination. The remaining portions ofthe concrete biologicalshield willremain intact. Anyrequired sampling andanalysis ofthe surrounding soilwill bedone bycoring andrepaired after sampling. Shoring andcovering ofthepit will provide industrial-protection, until the 2-7

PC000482/2 final confirmatory release surveys havebeenperformed. Theremaining tasks are:

dismantlement of theconfinement barrier, removal of any remaining surface ,

contamination inthe rooms, andf'mal confirmatory release surveys. Thepackaged waste is to beshipped tothe U.S. DOENevada TestSite (NTS).

2.3.

1.3Dismantling Sequence Dismantling will occur sequentially to thedetailed schedule showninSection 2.3.2.

Items removed from the tworeactors will begrouped asfollows:

Group 1 Equipment which does nothave induced radioactivity but which mayhave surface contamination.

Group 2 Core components andother components which have induced radioactivity (excluding the reactor tank).

Group 3 Reactor tank liner, anchors and concrete inthe proximity ofthe former location ofthe reactor core and which have been neutron activated.

Group 4 Equipment tools andsystems which have been contaminated during decommissioning operations.

Components andequipment inthefour groups are identified inTable 2-2, Table 2-3, Table 2-4andTable 2-5.

TheRotary Specimen Rackinthe TRIGAMkIReactor pool isexpected tohave the highest induced radioactivity. This expectation isconsistent with the UniversityofTexas g experience Rack andother ina similar Group TRIGAReactor 2items will decommissioningproject. TheRotary behoisted from the pooland lowered into Specimen a shielded

$$l container which willhave been prepared toaccept the items. Additional shielding will be provided forworker protection ifnecessary.

After components, equipment andparts listedinTable 2-2andTable 2-3 havebeen removed, aconfinement barrier will beinstalled. Thepurpose ofthis barrier is tocontain airborne contaminants generated duringreactor pitdemolition, andtopreventtheir spread inthe Reactor Roomandpossibly inthe surrounding areas.

Theconfinement barrier will beerected which willsurround the reactor pit. Associated with this enclosure willbeanindependent localizedventilation system which will ensure a negative pressure with respect tothe Reactor Roomwhile providing high efficiency filtration onthe exhausted air, andasource ofclean airsupply within the enclosure.

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PC000482/2 Table2-2-Com onentswithPotential Surface Contamination-Grou 1 Purification System urification looanddeionizer tank iin demineralizer OtherComponents cables andconduits coldecklates rotarack drive r6actorbrid e structure neumatic transfer s stem Table23-Com onents withinduced Radioactivit -Grou 2 Rotas ecimen rackMki ong Control roduide tubesanddetector tubes o ridlate Bottomridlate Reflector Core su ort Fasteners andconnectors Pneumatic transfer s stemterminus Table2-4-Reactor Tank Activated Com onents-Grou 3 Reactor liner it Concrete Anchors Reinforcement bars Table25-E ui ment Used in Decommissionin O erations-Grou 4 General ventilation s stem Localized s stem ventilation Confined barrier Contaminated ande uiment tools Contaminated clothin TheReactor Roomwill bemaintained ata negative pressure with respect to the surrounding areas butless than thepressure differential maintained between the confinement barrierandthe Reactor Room.This willensure that the airwill travelfrom the non-contaminated area tothe increasinglycontaminated areas.

Theactivated linersection will beseparated, removed, andprocessed, andthe activated thickness ofthe concrete biological shieldwillberemoved. Tominimize dust dispersal, a localized finewatermist maybesprayed overtheareabeing demolished. TheGA Nuclear Waste Processing Facility (NWPF) operates aFiltration Station for the treatment ofliquid wastes. Thetreated water isdischarged into thesanitary sewer ifitmeetsthe discharge limitsforGA'sIndustrial Wastewater Discharge Permit. Waste water that cannot meetdischarge limits issolidifiedforoff-site disposal aslow-level radioactive waste. Activated concrete will beremoved a section ata time andshoring supports will beplaced inthecavity formed asneeded, before proceeding with the next section.

Atthe completion ofactivated concreteremoval, dose ratemeasurements will bemadeto determine ifallnecessary portions have been removed. Post-remediation surveys may 2-12

PC-000482/2 include concrete andsoil coringsampling andanalysis. As the demolition ofactivated

( material proceeds, the material radioactive willbepackaged for shipment anddisposal.

ofthistask:

There are twopotential safety radiological concerns during performance 1) external exposure fromtheactivated components ofthetank, and2)inhalation of airborne material. To minimize therisk, workareas will bemonitored frequently and radiation levels will bemonitored continuously, todetermine sudden changes inthe radiological conditions.

Upon completion ofdismantlement tasks inthe reactor pit,theconfinement barrierwillbe dismantled andthe plastic sheets compacted andpackaged. Surface contamination willbe removed fromcontaminated portionsoftheventilation system andthey willthen be packaged fordisposal. The reactorroomwill thenbe cleared andallsurface contamination removed.

2.3.1.4 Surveys Following decontamination andremediation activities ofeach reactor, a finalradiation survey ofeach ofthereactor rooms and otherapplicable locations covering the entire TRDSwill beperformed anddocumented by GAHealth Physics.

2.3.2Schedule Theproject schedule ispresented asFigure 2-6. The scheduled time fromregulatory approval ofthe Decommissioning Plan tosubmittal for release of the sitetounrestricted use is41months. Itshould benotedthat fuelstored intheMkF Reactor Fuel Storage Canal is a scheduled for timely removal andshipment offsite.Ifthe DOE fails toapprove shipment to g@E accommodate thetimely ofthedecommissioning, continuation a day-to-day schedule slippage ofPhase 2ofthe D&Dwill occur untilsuch time asthe fuel isshipped off the GA m site.

Schedule 2.3.2.1 for Off-Site Shipment ofGASpent Nuclear Fuel (SNF)

GA plans tohandle thespent TRIGAfuel currently stored intheTRIGA MkF Fuel Storage Canal asawork activity under the existing USNRCFacility License No. R-67; (non-TRIGA related irradiated fuel materials stored at GA will be shipped under provisions ofcurrent USNRCandState ofCalifornia Radioactive Material Licenses issued toGA).

TheU.S.Department ofEnergy (USDOE) iscommitted toprovide for off-sitereceipt andstorage ofGASNF.However, GAhas been notified ofaprogram delay. Receipt of the GASNFatthe established receiving organization (INEEL) isnotscheduled tooccur before CY2003 under plans.

current Risks associated with theoff-site shipment, transport, andINEELreceipt oftheGA SNF,areaddressed inanEnvironmental Impact Statement (EIS), separately issued by the USDOE tocover the subject tasks.

2.3.2.2 Request for Termination ofUSNRC FacilityLicense Although all work associatedwith theMark1maybecompleted and Facility License No.

38termination requested, final completion ofthe TRDSDecommissioning Project work, asdescribed herein, cannot beaccomplished until all ofthe SNFcurrently stored inthe TRDShasbeen physically removed fromthesubject area, (see discussion above, 2-13

PC000482/2 regarding planned SNFoff-site shipment schedule). Uponfinal removalofspent a TRIGA remaining fuel from the TRIGAMark tasks decontaminate to F Fuel Storage anddecommission Canal,GAplans toproceed theTRDSina timely with all manner. *

$3 Based onproject schedule informationdocumented hereinFigure 2.6, GAestimates that a formal request for termination ofFacility License No.R-67will besubmittedtothe USNRC approximately six months afterthe final shipment ofSNFhasbeen dispatched from GA.

2.4 Decommissioning Organization andResponsibilities GAiscommitted to, and retains ultimate responsibility forfullcompliance the with existing USNRC and State licenses and theapplicable regulatory requirements during decommissioning. Company principles, policies, andgoals willbefollowed toensure high standards ofperformancein accomplishing the decommissioning tasks.

Theplanned organization for the TRDS Decommissioning asshown inFigure2-7will be maintained, individuals performing the functions mayvary overthe duration.)

Project Specialized contractors maybeutilized, under the direction oftheTRDSDecommissioning Project Manager, whennecessary andappropriate.

KelPolitiong 2.4.1Decommissioning Project Manager-The TRDS Decommissioning Manager Project has the overall responsibility for successful completion oftheProject.The Decommissioning Project Manager functions include:

a Controlling andmaintaining safetyduring decommissioning activities andprotecting of g the environment a Determining project staffing andorganization

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a Assuring performance tocost andschedule a Reporting ofperformance a Approving decommissioning plans andprocedures e Approving subcontracts e Approving budgets andschedules a Ensuring, with the assistance ofthe GA Licensing, Safety, andNuclear Compliance (LSNC) Organization, that theconduct ofdecommissioning activities with all complies the applicable regulations andisinaccordance with theGAlicenses.

Theminimum qualifications for theDecommissioning ProjectManager are:

e A four year degree inengineering ornatural science a Fiveyears ofproject management experience inthenuclear industry including decommissioning projects a Familiarity with the GATRIGAReactor Facility a Appropriate training inradiation protection, nuclear safety,hazardous communication, andindustrial safety 2-14

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2. 4. 2TRF PhysicistinCharge-The functions ofthe TRDSPhysicist-in-Charge include:

a Maintaining theTRDSina safe andproper condition during theevolution of Decommissioning Project inaccordance activities, withthe requirements setforth inthe applicable USNRCfacility licenses

• Approval of plans and procedures e Providing engineering support for the decommissioning activities Theminimumqualifications for this position are:

e A current senior reactor operator license fortheGA TRIGAReactors issued bythe USNRC a A four year degree inEngineering orNatural Science a Five years experience inaresearch reactorfacility environment e Substantial knowledge oftheTRDS andassociatedsystems 2.4.3Manager, Health Physics-The Health Physics Manager isresponsible for providing radiologicalsafety support inthe decommissioning oftheTRDS.This function ensures that involving activities potential radiologicalexposure areconducted incompliance with the applicable licenses, Federal andState regulations, andGA procedures. Theposition includesresponsibility for maintaining TRDSsurveillance andmonitoring program andthe development ofHPradiological protection procedures.

Theminimum qualifications for thisposition are:

e A four year degree inHealth Physics orarelated field ma a Three years supervisory experience inHealth Physics WiP a Five years operationa1 experience related toradiation safety 2.4.4Manager, Quality Assurance-The Quality Assurance Manager isresponsible for implementing and managing theQuality Assurance program for the TRDS Decommissioning Project, inaccordance with the applicablerequirementsof ASME-NQA-1,Quality Assurance Program Requirements for N uclearFacilities and 10 CFR 71, Subpart H, Quality Assurance for Packaging and Transportationof Radioactive Material, andfor certification ofradioactive waste toensure compliance with theapplicable Waste Acceptance Criteriaofthe Radioactive Waste Disposal Facility.

Theminimum qualifications for thisposition are:

e A four-year degree inengineering ornatural science e Five years experience innuclear related Quality Assurance e Twoyears experience inthe decommissioning ofnuclear facilities andradioactive waste processing 2.5 Training Program Trainingisconducted andcontrolled inaccordance withapplicableGAprocedures, license commitments, andthe WorkAuthorization for the 'IRDS Decommissioning Project, and focuseson safety, knowledge ofapplicable regulations, andtechnical requirements. The training program shall comply with therequirements establishedbythe USNRC in10CFR (as 19.12 described and10CFR71.105(d);

in more detailin the GARadiological byOSHAin29CFR1910.120(e)

Contingency Plan, Ref.

and29CFR1910.1200(h);

10.17) by 2-18

PC000482/2 BA theU.S. Environmental Agency Protection in40CFR265.16; byCAL-EPA inCCR22-thTV 66265.16; andbythe U.S. Department ofTransportation in49CFR172.704.

2.5.1General Employee Radiological Training (GERT 4 Hour)-General employee radiological training willbeprovided to all personnel whoarerequired toenter radiological Restricted Areas (with theexceptionofvisitors andinfrequent support personnel), butare notauthorized toperform hands-onradiological work.

2.5.2RadiologicalWorker Training (RWT 16Hour)-Radiological worker training will beprovided topersonnel whorequire unescorted access toradiological Restricted Areas, andwhoareauthorized toperform radiological job functions.

GERTandRWTareadministered toemployees, asapplicable, with refresher training provided every year.

2.5.3Health Physics Technician Training Health Physics Technicians mustsuccessfully completeRadiological Worker Training. In addition, Health Physics Techniciansare trained tothe procedures used fortheir workand mustreview andunderstand other HP procedures according to theHealth Physics Technician Procedure Review Sign-off Forms. Health Physics Technicians willalso review applicable procedurerevisionsina timely manner. Health Physics Technicians will also befamiliarized with theSite andFacility characterization results andthe contents of this Plan.

2.5.4Equipment Operator Training All equipment operators willhaveproper training completed and documented prior to

= performing unsupervised workwith the equipment. Reactor operators mustbelicensed by the NRC.

2.5.5 Safety/Accident Prevention Training GA hasanInjury andIllnessPrevention Program (IIPP) which isdefined in theIIPP Manual, a.k.a. theAccident Prevention Program Manual (APPM). Allemployees are required toabide bythe requirementssetforth inthis Manual. Additional specific TRDS Decommissioning Project requirements may be specified, as required inProject procedures.

2.5.6 HazardCommunication Training-A hazard communication training program has been developed for this inaccordance Project with OSHA1910.1200 andtheGA IIPP.

This program promotes awarenessofchemical hazards that are present atthis Facility,and provides meanstocommunicate those hazards toemployees. A designated person will maintain the hazardous materialinventory andMaterial Safety Data Sheets (MSDS) foron-site hazardous materials,andprovide all Project personnel with information advising them ofthe potential for hazardous constituents intheworkplace. A list ofsuch materials is maintained atthe job site, andcopiesofthe MSDS appropriate available are tosite workers upon request. TheMSDSform provides moredetailed information about the chemical than a label does. A hazardous chemical inventory is maintained which reflects thecurrent supplies located inthe workarea. Anychemicals notpreviously located andidentified or newchemicals received onthe jobsitewill beadded tothe inventory list.

2.5.7 Contamination Control Training-Personnel will betrained incontamination control d together with boundary ventilation control, control, etc. Cross contamination will belimited 2-19

PC-000482/2 by theuseoftraining andradiological controls. Radiological andhazardous materiala contamination will bestrictly controlled during alldecommissioning work. This control $3 will beaccomplished using qualified workers toperform work identified inapproved work #

procedures. Insomeinstances, special briefings anddry-runs maybeused toperfect techniques, demonstrate approaches, andqualify theworkers.

2.5.8 Respirator Training-Each individual whomayusearespirator will berequired to receive respiratory protection training, bemedically qualified touse respirator protection, andreceive aquantitative fit test for each specific devicethat they arequalified touse.

Training will meet the requirements ofthe U.S. Department ofHealth, Education, and Welfare, NationalInstitute for Occupational Safety andHealth (NIOSH), andANSIz88.2-1980,PracticesforRespiratoryProtection (Ref. 10.11).Respirator fit testswill be administered before initial assignments tojobs requiring the useofarespirator, andwill be conducted asnecessary thereafter. Medical qualification will beassessed annually.

Confined 2.5.9 Space Entry Training-Employees required toenter confined orenclosed spaces will betrained tothe OSHA confined space entryrequirements. They willbe instructed astothe nature ofthe hazards involved, thenecessary precautions tobetaken andthe useofrequired emergency andprotective equipment, asprescribed bythe Health andSafety Manager ordesignated person.A confined space permit mustbeissued prior to access into the confined space.

2.5.10Emergency Response Training-GA hasa GA SiteRadiological Contingency Plan, asrequired bythe USNRC andthe State ofCalifornia. The TRDS hasa specific procedure insupport ofthese plans.

2.5.11Hazardous Materials Training Training for hazardous materials isdependent onthe job description for each individualand thetypes andamountsofhazardous materials or hazardous wastes being handled as specified inthe position's training plan. Ingeneral, thetraining specified for workers and supervisors directly involved with decommissioning includes someorall of thefollowing training requirements:

2.5.12HA2WOPER Training Course-OSHA 1910.120, 40hour classroomand 24hour on-the-job training specific tohazardous materials. An 8hour annual refresher isprovided.

2.5.13Hazardous Materials Packaging-Reviews therequirements forhandling and shipping hazardous materials andwastes asrequired by49CFR,the DOTregulations.A refresher update is required every threeyears.

2.5.14Waste Acceptance Criteria-Training isprovided tothe requirements established for the disposal site. Anannual training update is provided.

2.5.15Dangerous WasteRegulations-Training tofamiliarize hazardous waste technicians andsupervisors with appropriate hazardous wasterequirements for wastedesignations. A refresher isprovided annually orasregulations areupdated.

2.5.16GA Emergency Response Training-Training tofamiliarize emergency response personnel with actions tobetaken inresponding toanunplanned release ofhazardous or radioactive material fromthe TRDS.Hands-on traininginthis area includes conducting drillstoevaluate response capabilities.

2-20

PC000482/2

,a 2. 5. 17RCRA Facility Standards Overview Training-This class coversthe

$5 requirements established under 40CFR264.16 for personnelwhomayhandle hazardous

theFederal Standards anddiscusses wastes within theFacility. Theclass covers compliance requirements for generators ofhazardous andmixed wastes. An annual update isprovided.

2.6 Contractor Assistance 2.6.1Contractors Contractors willhave undergone theGA Quality Assurance approval process when required. Wherevercontracting personnelare used on-site,they will: 1)comply with all provisions ofGA licenses andpermits,and2)betrained inaccordance with GA's commitments.

Contractors will beused on an as needed basis during decommissioning. Theuseof contractors willbecomplementary tothe GA staff andwill normally provide specialty support.

2.6.2Tasks Tasks where contractors maybeused includebut are notlimitedto:

a Shipment anddisposal ofradioactive andnonradioactive waste materials e Laboratory testing andanalysis a Concrete cutting f a Construction/dismantlement support x a Asbestos removal anddisposal a Design andfabrication ofspecialty dismantling toolingandequipment a Specialty engineering anddesign services

• Temporary staff augmentation 2.6.3Potential Contractors Potential contractors for each identifiedtaskwill berequired to provide a statement of qualifications aspart oftheir bidsubmittal. Thequalifications required willemphasize the following:

a Experience with similar work inaradioactive environment

• Adequacy ofqualified workers

• Ability tomeetschedule TheQuality Assurance organization atGAmaintains anapproved supplierlistandhasan extensive approval process which ensures that contractor qualifications adequate are tothe need.

2.6.4 Subcontractors Subcontractors whowill work with licensedradioactive materials willberequired to:

a Attend andcomplete applicable Radiological Worker Training

• Provide required exposure history information 2-21

PC000482/2 a Readandsign anapplicable RWPandcomply with instructions ggh e Beissued proper dosimetry bycognizant HPpersonnel W

• Follow all special instructions given byHP e Be escorted by a cognizant authorized person listed on theTRDSWA, unless specifically listed themselves onthe TRDSWA 2.7 Decontamination andDecommissioning Documents andGuides Health Physics, Industrial Health criteria, andother standards that guided theactivities described inthisDecommissioning Plan a re discussed in Section 3.1.2, Health Physics Program, Section 3.2.3, Radioactive Waste Disposal and Section 3.2.4, General Industrial Safety Program. Relevant documents andguides used are noted therein andinSection 10, References.

2.8 Facility Release Criteria The proposed decommissioning alternative thathas beenpresented in this Decommissioning Plan does notnecessitate the dismantlement ofthe TRF.Theresults of the site andfacility radiological characterization have indicated that the structures maybe directly releasable without need for extensive decontamination.

This section provides the specific criteria forrelease ofthe TRDS. TheFinal Release approach will usetheguidance provided inNUREG/CR-5849 (Ref. and 10.10),

described inSection 4.

Uponcompletion ofthe decontamination andremediation activities (e.g. seeSection 2.3), gg a final radiation andradiological contamination survey ofthe TRDS will beperformedWP anddocumented byGAHealth Physics. Theresults ofthe survey(s) will besummarized inareport which will besubmitted toNRC,asrequired bytheU.S. Nuclear Regulatory Commission Regulatory Guide1.86 (Ref. 10.18), insupport of a license termination request.

Since the objective ofdecommissioning the TRDSistoultimately release the facility/site tounrestricted use,a final radiation andradiological contamination survey report will demonstrate compliance with theradiological criteria given inRegulatory Guide 1.86.

Specifically, the criteriafor release ofthe TRDStounrestricted useandfor termination of the corresponding licenses (which have b een a mended to allow possession only) a re as follows:

1.Surface contamination levels mustnotexceed thevalues presented inTable 1, "Acceptable Surface Contamination Levels," oftheU.S.NRC Regulatory Guide 1.86, "Termination ofOperating License for Nuclear Reactors" (Ref. 10.18). Table 2-6 presents the limits from the regulatory guide. Additionally,

2. Residual radionuclides -

present asaresult offacility operation -

mustnotresult inan exposure rate inexcess of5 micro R/hr above natural background measured at 1 meter from the surface (Ref. 10.19).

Removable surface contamination will beeliminated where possible bywiping orother proven decontamination methods. Release criteriaforfixed andsmearable residual radioactivity forbeta-gamma emitters would bebased uponthe relative concentrations of isotopes onthe material andtheir respective releasecriteria ifmorethan onecategory of nuclide for beta-gamma emitters applies from Table 2-6.

2-22

PC-000482/2 431F Table26-Acce tableSurface Contamination Levels Nuclides' cm2)

(dpm/100 Average* Maximuma Removable' U-nat, assy,23aU, & associated decay products 5,000 15,000 1,000 Transuranics, 22eRa, 22aRa, 230Th, 22eTh, aslPa, 227Ac, 12sl,1291 100 300 2)

Thnat, 232Th, "0Sr, 22aRa, 224Ra, 232Q 126l 133[ 1311 1,000 3,000 200 Beta/gamma emitters (nuclideswith decay modes other than alpha 5,000 15,000 1,000 orspontaneous emission fission) except "Sr andothers noted above.

a Wheresurface contamination by both alphaandbeta/gamma-emittingnuclides thelimits exists, foralpha-established and beta/gamma-emitting nuclidesshould applyindependently.

b Asused inthis table dpm(disintegrations perminute) meanstherate ofemission material by radioactive by asdetermined correcting the counts per minute observed by anappropriatedetector for efficiency, background, andgeometric factors associated with theinstrumentation.

c Measurements ofaverage contaminant should not beaveraged over morethan1square For meter. ofless objects surface area,the averageshould bederived for each such object.

d Re maXimum Contamination level @lies toan area ofnot more 100 than crna, e Theamount ofremovable radioactive material per 100 cm2ofsurface areashouldbedetermined that bywiping with area filter dry smear)

(e.g.,orsoft onthewipe with an absorbent appropriate paper (e.g.,

instrument masslin), applying moderate pressure, ofknown efficiency. When removable andassessing the ofradioactive amount onobjects contamination material surface ofless areais determined,then pertinent levels should bereduced proportionally andthe surface entire bewiped.

should contamination

• lncluding byinduced radioactivity, i.e.,activation.

2-23

PC000482/2 a 3. PROTECTION OF THE HEALTHAND SAFETYOF RADIATION (WW WORKERS AND THE PUBLIC 3.1 Radiation Protection 3.1.1Ensuring As Low As Reasonably Achievable (ALARA) Radiation Exposures Decommissioning activities atthe GA TRIGAReactor Facility involving theuseand handling ofradioactive materials will beconducted such that radiation exposure willbe maintained AsLow As Reasonably Achievable (ALARA), taking into account the current state oftechnologyand economics ofimprovements inrelation tothe benefits.

h GA's currentpractice isasfollows:

e A documented ALARAevaluation willberequired forspecific tasks ifa Project HP determines that 5%ofthe applicable dose limits forthe following maybeexceeded:

TotalEffective Dose Equivalent(TEDE)

Thesumofthe Deep-Dose Equivalent (DDE) and the Committed Dose Equivalent (CDE) toanyindividual organ ortissue other than the lensofthe eye EyeDose Equivalent (EDE)

Shallow-Dose Equivalent (SDE) a A documented ALARAevaluation will berequired if Project HP determinesthat TRF effluentaveraged over year expected o ne is to exceed 20% ofapplicable concentration in10CFR20,Appendix B,Table 2,Columns 1and2.

Decommissioning Project management positions responsible forradiation protection and maintaining exposures ALARAduring decommissioning include theProject Manager, and Project HPManager.

Various methods will beutilized during Decommissioning Project worktoensure that occupational exposure toradioactive materials iskept ALARA.Themethods include the WorkAuthorization (WA), theRadiological WorkPermit (RWP),special equipment, techniques, andpractices, asdescribed inthe following subsections.

W Authorization forworktobeperformed inaccordance with reactor licenses and/or this Decommissioning Plan, mustbeobtained through the GALSNCDivision, bypreparation andmaintenance ofa WA. TheWAidentifies theproposed workscope andactivities, quantity andform ofradioactive materials involved, individuals authorized toperform the work,andapplicable workprocedures. An estimate oftheisotope(s), physical and chemical form, andquantity ofradioactive material generated aswasteduring a twelve-month period isincluded inthe WA.Anassessment ofthe magnitude andsignificance of estimated releasesofradioactivity tothe environment isalso provided. Implementation of operating procedures iscontingent uponapproval ofthe WA.Workisperformed instrict accordance with the methods andprecautions provided inthe approved WA.

3-1

PC-000482/ 2 RWPs are used when:

a a work task isnotdescribed inthe established WorkAuthorization, provided that the margin of safetyprovided bythe RWPiscomparable to,orgreater that than, specified inthe WA, a personnel not listed asAuthorized Individuals onthe WorkAuthorization mustperform work, a oroutside contractors orsubcontractor personnel mustperform limited orroutine work inthe established Restricted Area (RA).

TheRWP isissuedin accordance withexisting GA Health Physics procedural requirements, andisinitiated by the Facility Principal Investigator orother responsible individualwhohasgood knowledge ofthetask tobeperformed andother workbeing performed inthe area.

Theuseofengineering controlstomitigate the airborne radiological hazardatthe source willbethe choice first withrespect tocontrolling theconcentrations ofairborne radioactive material.There maybe,however, circumstances where engineeringcontrols arenot ormaynotbesufficient practical, toprevent airborne concentrations inexcess ofthose that constitutean airborne radioactivityarea. Insuchcircumstances where worker access is required,respiratory protective equipment will beutilized tolimitinternal exposures. Any situationwhereby workers areallowed access toanairborne radioactivity area, orallowed toperform excess workthat of0.1DAC,the hasa high decision degree toallow oflikelihood access will togenerate airborne radioactivity beaccompanied bythe in performance %P7 p@4 ofrepresentative measurements ofairborne radioactivity toassess worker intake. The resultsofDAC-hour trackingandair sample results foranyintake will bedocumented.

Workers willprovide nasalsmears forHP evaluation following the use ofrespiratory protectiveequipment for radiological purposes asnecessary.

TheGAHPProgram establishesradioactive material controls that ensure:

a Deterrence ofinadvertent release oflicensed radioactivematerials tounrestricted areas.

a Confidencepersonnelnotinadvertently that are exposed to licensed radioactive materials.

• Minimization of thevolumeof radioactive wastesgenerated during the decommissioning.

Allmaterialleaving the Restricted Area will besurveyed toensure that material radioactive isnotinadvertently released fromtheTRDS.SeeSection 3.1.3 "Radioactive Material Controls" foradescription ofthe specific survey methods that willbeused.

3-2

PC000482/2 3.1.2Health Physics Program GAHealth Physics hasprocedures inplace which will beimplemented during the TRDS Decommissioning Project. Ifnewadditional Health Physics procedures arerequired at somepoint in the work to support thedecommissioning, they willbedeveloped and in approvedaccordance with GAHealth Physics policy andprocedure.

GA senior management isreadilyaccessible toensure timely resolutionofdifficulties that maybeencountered. The HP Manager, while organizationally independent oftheProject staff,hasdirect accessto the Decommissioning Project Manager onadaily basis, andhas full authoritytoactinallaspects ofprotection ofworkers andthe public from the effects of radiation.Conduct ofthe TRDS Decommissioning Project HP program willbeevaluated according toGApolicy andprocedure byboth GAQuality Assurance oversight, andGA site HPaudit activities.

During Decommissioning Project work, aspects of the Project maybeassessed bythe GA QualityAssurance Department, through audits, assessments, andinspections ofvarious aspectsofdecommissioning performance, including HPasdescribedin Section 1.2.4.

Formal audits oftheGA Health Physics program are conducted annually inaccordance with GAHPprocedure, andthe requirements of10CFR 20. These audits will include aspectsofthe TRDSDecommissioning Project.

C Additional assessments or management reviews may be performed whendeemed E appropriate bythe Decommissioning Project Manager and/or the PIC.

GAhasselected HP equipment andinstrumentation suitable topermit ready detection and quantification ofradiologicalhazards toworkers andthe public, andtoensurethe validity ofmeasurements taken during remediation andfinal release surveys. Theselection of equipment andinstrumentation tobeutilized wasbased upondetailed knowledge of the radiological contaminants, concentrations,chemical forms, andchemical behaviors that are expected toexist asdemonstrated during radiological characterization, andasknown from process knowledge oftheworking history ofthe TRF.Equipment andinstrumentation selectionalso takes intoaccount the working conditions, contamination levels, andsource termsthat arereasonably expected to beencountered during theperformance of decommissioning work aspresented inthis Plan.

Thefollowing sections present details oftheequipment andinstrumentation presently selectedfor useduring the decommissioning. Itisanticipated that throughretirement of wornor damaged equipment/instrumentation or increases inquantities ofavailable components orinstruments, thatnewtechnology will permit upgrades or,ata minimum, like-for-likereplacements. GA iscommitted to maintaining conformance to minimum performance capabilities statedinthis Plan whenever newcomponents orinstruments are selected.

3-3

PC000482/2 CBS 49 A sufficient inventory andvariety ofinstrumentation will bemaintained on-site tofacilitate effective measurement ofradiological conditions andcontrol ofworker exposure consistent with ALARA, andtoevaluate suitability ofmaterials forrelease to unrestricted use.

Instrumentation andequipment will becapable ofmeasuring therange ofdose rates and radioactivityconcentrations expected tobeencountered during conduct ofremediation and decontamination of the TRDS, aswell asfor finalsurvey measurements, andtoless than the minimum values required for release orALARAdecision-making.

Project HPstaff will select instrumentation thatissensitive tothe minimum detectionlimits for the particular task being performed, butalso withsufficientrange toensure thatthe full spectrum ofanticipated conditions for atask orsurvey canbemetbythe instrumentation in use. Consumable supplies willconform tomanufacturer and/or regulatory recommendation toensure thatmeasurements meetdesired sensitivity and are validfor the intended purpose.

GAwill continue review ofregulatory information notices andbulletins for applicability to Project HPinstrumentation.

Instrumentation Survey instruments will bestored ina common location under thecontrol ofTRDS Decommissioning Project HP personnel. A programto clearly identify andremovefrom service anyinoperable orout-of-calibration instruments or equipment asdescribed inHP procedures will beadhered tothroughout theTRDSDecommissioning Project. Survey instruments, counting equipment, air samplers, air monitors, and personnel contamination monitors willbecalibrated atlicense-required intervals,manufacturer-prescribed intervals (if shorter frequency) or prior to use against standards that are NIST traceable in accordance withGA Calibration Laboratory procedures, HP procedures, or vendor technical manuals. Survey instruments willbeoperationally testeddaily when inuse.

Counting equipment operability will be verified daily wheninuse. The personnel contamination monitors areoperationally tested on a daily basis whenwork isbeing performed.

Table 3-1provides details oftheHP equipment andinstrumentation thathasbeen selected foruseintheTRDSDecommissioning Project. As discussed earlier, theselection of instrumentation issubject tochange asolder equipment andinstruments areretired. GA will maintain conformance tominimum performance capabilitiesorbetter, whenever new components orinstruments areselected.

3-4

PC-000482/2 Table 31-S ecific Health Ph sicsE uiment and instrumentation Use and Ca abilities

$3 instrument Model Detector Type instrument Detection Rangeor Capability Application EberlineRO-2 and 2A chamber lonization RO-2 Beta/gamma exposure rate measurements Eberline RO20 05,000 mR/hr Minimum detection: 0.2mR/hr RO-2A 050R/hr RO-20 0-50 R/hr Eberline Teletector6112D/B GM tube 01,000R/hr Telescoping detector with GMprobe forhigh range Ludium-M239F Monitor Floor Gasproportional 0500,000cpm Alpha andbeta/gamma floor monitor 434enf with 2221ratemeter/d3-37 1370s efficiency approximately 30%4n probe 239Pu efficiency approximately 17%4n Eberline-RM-14,14SA/HP- GMtube pancake RM14 Beta/gamma surface contamination measurements 260probe orHP100BGS probe 050,000cpm Canbeused with several types ofprobes-Information for HP-260 probe.

probe RM-14SA "Sr efficiency -

32%4n 0 5,000,000 cpm 15.5 cm2 HP100BGS probe "Sr efficiency 36%4n,100cm2 Ludium Model 12with4368 GasProportional0500,000 cpm Beta-Gamma surface contamination measurements probe Canberra LowLevel GasProportional Detection capability Low-level a/p smear samples Alpha/Beta Counting System typically

<25dpm/100cm2 Ludium-177 znS(

scintill

)

on 0500,000 cpm Handheld alpha frisker (50 cm2 area)

Ludium Model 19pR Nal(TI)Scintillator 05,000 gR/hr Lowgamma exposure rates (i.e.,5mR/hr) Minimum detection: 1gR/hr Eberline SAC-4 znS(Ag) Scintillator 6Decade scalar Alpha laboratory measurement ofair samples andsmears Eberline BC-4 Shielded GM 6 Decade scalar Beta laboratory measurement ofair samples andsmears pancake tube REGECanberra S-100or HPGe Detection capability: Gamma laboratory measurement ofwater, air, smear/media samples

& equivalent Gamma-ray (e.g.,Soil, asphalt, concrete, s;0.18 pCi 1370s/g tar, vegetation) aggo spectroscopy system

~

4 Eberline Personnel GasProportional Detection capability: Personnel monitor with microprocessor contaminationmonitor/walk-in 7 Contamination <5,000 dpm/100cm2 control and radon reject capability.

Monitor PCM-2 SAIC RADeCO H809V N/A 1-30 cfm High Volume air sampling for minimum detectioncapability "HiVol" SAICRADeCO HD-29A N/A 0.5-3.5 cfm Lowvolume air sampling for long term air sampling "Goose Neck" Technical Assoc. GM 10-105 cpm Local airborne monitor with alarm capability FM5ABN2CH modularair monitors Ametek MG4Air Sampler N/A 5 4,000 cc/min. Lapel airsampler foruseinchronic exposure situations TheTRDSDecommissioning Project will utilize theexisting GA HP Program forthe Project. This Program prescribes policy, method, andfrequency for effluent monitoring, conduct ofradiological surveys, personnel monitoring, contamination control methods, and protective clothing usage.

Efflu.eert.Monitoring-Until such time asthe decommissioning effort hasreached the point where theHEPAsystem isnolonger needed, the TRDSventilation system exhaust points will becontinuously sampled downstream ofeach HEPAfiltration system byanisokinetic sample collection particulate sample point (a grab-type change-out frequency sample) which isapproximately isincontinuous weekly; sample operation.

media The are analyzed for particulates using laboratory counting systems ina timely manner after filter 3-5

PC000482/2 media change-out. TheGAHPDepartment also operates several continuous environmental g$3 air sample stations on the main GA site tofurther assess the potentialfor environmental 'S" airborne radiological effluents.

Anypotentially contaminated liquids that maybegenerated orstored atthe facility will be sampledand analyzed for radioactivity prior to disposal. Ifthese liquids arefound to contain radioactivity, they will beevaluated fordisposal options inaccordance with applicable permits and State andFederal regulations.

RadiationSurves-Radiation, airborne radioactivity, andcontamination surveys during decommissioning will be conducted inaccordance with approved HP procedure(s). The purposes ofthese surveys will beto(1) protect the health andsafety ofworkers, (2) protect the health andsafety ofthegeneral public,and(3) demonstrate compliance with applicable license, federal, andstate requirements, aswell asDecommissioning Plan commitments.

HP personnel will verify thevalidity ofposted radiological warning signs during the conduct ofthese surveys. Surveys will beconductedinaccordance withprocedures utilizing survey instrumentation andequipment suitable for the nature andrange ofhazards anticipated. Equipment andinstrumentation will becalibrated and,where applicable, operationally tested prior to useinaccordance with procedural requirements. Routine surveys areconducted ata specified frequency toensure that contamination andradiation levels inunrestricted areas donotexceed license, federal, state, orsite limits. HP staff will also perform surveys during decommissioning whenever workactivities create a potential toimpact radiological conditions.

-Externalmonitoring will beconducted in accordance with the prospective external exposure evaluation for theTRDS.Prospectivegra external whenever exposure changes evaluations inworker will beperformed, exposures warrant.

ata minimum, Visitors on an annual totheTRDS willbemonitored basis, or in W

accordance with requirements specified inGA HP procedures, and according to the radiological hazards ofareas tobeentered.

Internal monitoring beconducted will inaccordance with the prospective internal exposure evaluation for the TRDS. This prospective internal exposure evaluation will be evaluated on an annual basis, ata minimum, or whenever significant changes inplanned work evolutions warrant A comprehensive it. air sampling program isconducted attheTRDS to evaluate worker exposures regardless ofwhether internal monitoring isspecified. The results ofthis air sampling program will beutilized toensure validityofspecified internal monitoring requirements for TRDSpersonnel. Ifatanytime during the decommissioning, hazards that maynotbereadily detected bythe preceding measures are encountered, special measuresbioassay, or asappropriate, will beinstituted toensure the adequate surveillance ofworker internal exposure.

Monitoring will berequired ifthe prospective dose evaluation shows that anindividual(s) dose islikely toexceed 10%ofthe applicable limits andfor individuals entering a high or very high radiation area.

Rh-The GArespiratory protection program provides direction for use ofNational Institute forOccupational Safety andHealth/Mine Safety andHealth Administration (NIOSH/MSHA) certified equipment. This program isadministered byGA HPinconsultation withGAIndustrial Hygiene.

NIOSH/MSHA approved equipment areair purifying respirators which includes full face piece assemblies with air purifying elements toprovide respiratory protection against hazardous vapors, gases, and/or particulate matter toindividuals inairborne radioactive 3-6

PC000482/2

- materials areas. Individuals mayberequired tousecontinuous orconstant flow full-face

($j$ airline respirators for workinareas with actual orpotential airborne TheHP radioactivity.

• • "" Manager will also ensure that therespiratory protection program meetstherequirements of 10 CFR Part 20,subpart H.

Maintenance-When respiratory protectionequipment requires cleaning,thecartridges will be removed. Therespirator will be cleaned andsanitized afterevery usewitha cleaner/sanitizer andthen rinsed thoroughly inplain warmwaterinaccordance with HP procedures.

Storage-Respiratory protective equipment will bekept inproper working order.When anyrespirator showsevidence ofexcessive wear orhas failedinspection, it will berepaired orreplaced. Respiratory protective equipment that isnotinusewill bestored ina clean dry location.

Contamination Control-Contamination controlmeasures thatwill beemployed include, as appropriate, the following:

e Worker training will incorporate methods and techniquesfor thecontrolofradioactive materials, andproper useanddonning/doffing ofprotectiveclothing

• Procedures incorporate HPcontrols tominimize spreadofcontamination duringwork

• Radiological surveys will bescheduled andconducted byHP a Containment devices such asdesigned containers and barriers, plastic bagswillbeused toprevent the spread ofradioactive material a Physical decontamination ofTRDSareas oritems

$jjg e Physical barriers such asHerculite sheeting, strippable paint, andtacky mat step-off

• • • A pads tolimit contamination spread a Posting, physical area boundaries andbarricades a Clean step off pads atthe point entrance tocontaminated areas Personnel entries into radiological contaminated areas willrequire theuse ofprotective clothing. Thisclothing will consistofa suitable combination ofitems such as the following, dependent uponthe conditionsoutlined inthe WAorRWP:

a Heavyweight lab coat e Heavyweight canvas, cotton, orcotton/polyester coveralls a Heavyweight hoods e Plastic calf-high booties e Rubber, plastic orcloth shoe covers

• Plastic orrubber gloves which mayrequire cloth liners.

a Tyvek paper coveralls orplastic rain suitdisposable outerclothing

• Face shield orother protective device Access Control-A Restricted Area (RA) will beestablished andproperly posted so.as to prevent unauthorized access.

Engingred Controja-Personnel exposure to airborne radioactive materials will be minimized byutilizing engineering controlssuch asthe following:

3-7

PC-000482/2

• Ventilation devices-in-place orportable HEPAfilters orTRDSventilation systems, ggg localexhaust byuseofvacuums  %$9 a Containment devices-designed containment barriers, containers, plasticbags, tents, and glove-bags a Source term reduction-application offixativesprior tohandling, mistingofsurfaces to minimize dust and resuspension W-Monitoring for the intake ofradioactive material is required by10 CFR 20.1502(b) ifthe intakeislikely toexceed 0.1ALI(annual limit on intake) during the year for anadult worker orthe committed effective dose equivalent is likely toexceed 0.10 rem (1.0 mSv) forthe occupationally exposed minor ordeclared pregnant woman.Airsampling will beperformed inareas where airborneradioactivityis present orlikely.

Prospective estimates ofworker intakes andair concentrations used toestablish monitoring requirements will bebased onconsideration ofthe following:

a The quantity ofmaterial(s) handled e TheALIfor the material(s)being handled e Therelease fraction for theradioactive material(s) based upon itsphysicalform anduse

• Thetype ofconfinement being used forthematerial(s) being handled e Other factors that maybeapplicable

~

HP personnel will usetechnical judgment indetermining the situations that necessitateair sampling regardless ofgeneralized, prospective evaluations done for the TRDS.

aea Prior toidentifying the location foranair sampler, thepurpose oftheradiologicalair $A*

sample will beidentified. Various reasons existfor collectingair samples. Thefollowing areafewexamples:

a Estimation ofworker intakes

• Verification ofconfinement ofradioactive materials a Early warning ofabnormal airborne concentrations ofradioactive materials e Determining the existenceofcriteria forposting anAirborne RadioactivityArea (ARA).

Smoke tubes andbuoyant markers maythen beused todetermine airflow patternsin the area. Air flow patterns maybereevaluated ifthereare changes atthe TRDSthat mayimpact thevalidity ofthe sampling locations.Such factorsmight include thefollowing:

a Changes inthe work process a Changes inthe ventilationsystem e Useofportable ventilation that rnight earlier alter assessments After identifying the purpose fortheair sample andflow patterns areestablished, air sample locations are established asfollows:

e For verification ofconfinement ofradioactive materials:

Locate samplers inthe air flow near thepotential oractual releasepoint.

Morethan onesampling point maybeappropriate whenthere aremorethan one potential oractual release points.

3-8

PC000482/2 e Forestimationofaworker intake:

Sampler intakes will belocated asclose tothe workers breathing zones aspractical without interfering with thework orworker General workplace air sampler intakes will notbeplaced inornear ventilation exhaust ducts unless their purposeistodetect system leakage during normal operation, andif quantitative measurements ofworkplace concentrations arenotrequired. Locations or number ofair samplers will bechanged whendictated by modifications to Facility structure, changes in work processes, orelimination ofpotential sources.

A sufficient inventory and variety ofoperable andcalibrated portableandsemi-portable air sampling equipment will be maintained toallow foreffective collection,evaluation, and control ofairborne radioactive material andtoprovide backup capabilityforinoperable equipment. Air sampling equipment will becalibrated atprescribed intervalsorprior touse against certified equipment having known valid relationships to nationally recognized standards. Table 3-1 listsanticipated air sampling equipment.

Whenthe workbeing performed isa continuous process, a continuous sample with a weekly exchange frequency isappropriate. For situations where short-lived radionuclides areimportant considerations, the exchange frequency will beadjusted accordingly. Longer sample exchange frequencies maybeapproved by HP management forsituations where airborne radioactive material andnuisance dustare expected toberelatively low. Grab sampling for continuous processes mayalso beapproved byHPmanagementbased upon consideration ofvariability ofthe expected source term for the andprocess.

facility Grab sampling istheappropriate meansofairborne sampling forprocessesconducted

& intermittently, andfor short duration radiological workthatinvolves apotentialfor airborne W release.

Sources ofradiation orcontamination exposure maybeassessed byprocess knowledge, radiological survey data, surveys performed during characterization, previous and current jobcoverage surveys, ordaily, weekly andmonthly routine surveys.

Classification ofpotential sources mayalso beidentified by,radionuclide, physical properties, volatility, andradioactivity.

Worker exposure tosignificant external deep-dose radiation fieldsisconsidered unlikely during this project duetothe nature ofthe contaminants and/or thework precautions and techniques employed. Worker exposure to airborne radioactivitymay occurduring decontamination operations/work evolutions which mayinvolve abrasives ormethods that volatilizeloose and/or fixed contamination.

Exposure ofthe public toexternal orinternal radiation from thisDecommissioning Project isnotconsidered credible because ofthecontainment provided bytheFacility andthe access control provided for the Facility andthe area surrounding it.

Thetype(s) ofexposure controls used takes into account the currentstateoftechnology and theeconomics ofimprovements inrelation tothe benefits. Control ofpotential sources of radiation exposure toworkers andpublic asa result ofdecommissioning activitieswill be achieved through, butnotlimited to,the useofadministrative, engineering, andphysical controls.

3-9

PC-000482/2 Administrative controls consist ofbut arenotlimited to:

a Administrative dose limits thatarelower thanregulatory limits e Training e Radiological surveys Physical barriers suchas radiological warning rope/ribbon, incombination with radiological warning tape, lockable doors/gates aswell asinformation signs andflashing lights orotherapplicable barriers mayalso beused.

Engineering controls may consist ofbut arenotlimited to:

e HEPAventilation/enclosures e Protective clothing/equipment a Access restrictions/barriers e Confinement Subcontractor personnel may be usedfor certain required workduring theTRDS Decommissioning Project. Subcontractors who willworkwith licensed radioactive materials will berequired to:

e Attend andcomplete appropriate radiation safetycourse a Provide required exposure historyinformation

• Read andsign anapplicable RWPandcomply with instructions sh a Follow allspecial instructions givenby HP %59 a Be escorted bya cognizant authorized person listed onthe WA, unless specifically designated as an Authorized Individualinthe c urrent TRDS WA.

3.1.3Radioactive Material Controls GA'sradiation protection program establishes radioactive material controlsthat ensure the following:

e Prevention ofinadvertent radioactivematerial(licensed material) release touncontrolled areas.

e Assurance that personnel arenotexposed inadvertently to radiationfromlicensed radioactive materials.

a Mmimization of theamountof radioactive wastematerial generated during decommissioning.

Allmaterials leaving the TRDSRestricted Area will beradiologically surveyed toensure that radioactive materials (i.e., licensedmaterials) arenot inadvertently removed.

Decommissioning Project andGAHealth Physicsprocedures will beusedtoensure that all potentially radioactive orcontaminated items removed from the TRDSsite aresurveyed.

Theperformance ofthese surveys incorporate will theguidance presented inU.S.NRC Circular No.81-07, "Control ofRadioactively Contaminated andU.S.NRC Material,"

Information Notice No.85-92, "Surveys ofWastes Before Disposal FromNuclear Reactor Facilities," (References 10-20 and10-21). Thefollowing survey methodswill beused:

3-10

PC000482/2 e W -

Direct frisking with a portable Geiger-Mueller detector ff$)

V (e.g.,Ludlum minimum Model level 44-9 ofdetection orEberline above Model background HP-210, ofless orequivalent) than orequal having to 5,000 a

dpm/100 cm2

• Sme.arjS.amplai -

Analysis with aGeiger-Mueller detector (e.g., Ludium Model 44-9 orEberline Model HP-210, orequivalent) having aminimum level ofdetection above background ofless than orequal to1,000 dpm/100 cm2 a Bulk Materials (e.g.,sand andsoil) -

Analysis ofrepresentative sample(s) with a high resolution gamma spectroscopy system having lower limits of detection, above system background,

' Cs(i.e.,

calibrated toa value ofless than orequal to0.18 pCi/gram for 5180 pCi/kg).

Materialswill bereleased if nodiscernable facility-related activity isdetected within the capabilityofthe survey methods presented above.

Inevaluation ofequipment and materials forfixed or smearable licensed radioactive materials,items painted with other than original manufacturer's paint willnotbereleased unlessclear process knowledge demonstrates that the paintwas applied toa clean, non-radioactive surface prior to usein the TRDS Restricted Areaor approval from Decommissioning Project Health Physics, has beenobtained andan acceptable survey course for this situationhasbeen approved. If thepotential exists for contamination on inaccessible surfaces, theequipment will beassumed tobeinternally contaminated unless (1)the equipment isdismantled allowing accessfor surveys, (2) appropriate tool orpipe monitors with acceptable detection capabilities areutilized that would provide sufficient confidence that nolicensed materials werepresent, or(3) itmayreadily beconcluded that surveys fromaccessible areas arerepresentative of the inaccessible surfaces (i.e.,

ggg, surveying theinternal surface fromboth ends ofa straight pipe froma nonradioactive

%Pf ..

process system withcotton swabs would berepresentative ofthe inaccessible areas).

x Radioactive material (licensed material)maybetransferred from the TRDS Restricted Area toother locations on,oroff, GA'ssite having appropriate radioactive material licenses issued bytheNRC oran Agreement State, orotherwise authorized to possess such radioactive material (e.g.,U.S. DOEsites).

3.1.4DoseEstimates Thetotal projected occupational exposure tocomplete theDecommissioning ofthe GA TRDSisestimated tobe20person-rem. A task-by-task breakdown ofthis dose estimate is provided herein asTable 3-2. Task-specific doseestimates are based onthe nature ofthe workinvolved ineach task item, theexpected number ofpersons tobeassigned toeach andthe task, individual task duration periods asshown onthe overall projectSchedule for TRDSD&D (see Figure 2-1).

h 3-11

PC-000482/2 TABLE 32:OCCUPATIONAL RADIATION DOSEESTIMATES FORTRIGA REACTORS DECOMMISSIONiNG TASKS Task

'TasIt Description

.'.' P DurationANo.vg,Dose.Rat Total Dose Subtotal Total No.

C A .

A . bra. persons? '.Premlhr'persrem persrem' persrem l

1 TRIGAReactor Facility D&D 2 NRC/State approval of Decommissioning Plan l 3 Decommission MkiReactor 4 Radiological Survey 112 2 0.0002 0.0448 0.04 5 RemoveReactor Componentsabove Pool 80 4 0.0002 0.064 0.06 6 RemoveReactor Components inPool 7

8 l Grapple/Hoist/Survey Disassemble asnecessary 72 72 3

3 0.005 0.005 1.08 1.08 9 Decontaminate orPackage asLLW 64 3 0.005 0.96 3.12 10 Reactor TankWater 11 Survey/Sample/Analyze 40 3 0.0002 0.024 12 Discharge/Filter asnecessary 40 3 0.0002 0.024 0.05 13 Install Confinement Barrier around Reactor Pit 40 3 0.0003 0.036 0.04 14 AlTankRemoval 15 Cut/Remove insections 80 4 0.0025 0.8 16 Segregate clean sections 64 4 0.0025 0.64 17 Package LLWsections 56 4 0.002 0.448 1.89 18 Concrete Liner 19 Demolish activated portion 120 4 0.002 0.96 f;@

20 l Remove/Package 112 4 0.002 0.896 W 21 Survey remaining Concrete 32 2 0.0005 0.032 22 Demolish remaining portion toexpose Soil 80 4 0.0005 0.16 23 Survey Soil presumed tobeclean 40 2 0.0002 0.016 24 Shore/Cover Pit 40 4 0.0002 0.032 2.10 25 Survey/Remove Storage Wells, ifcontaminated 160 4 0.0003 0.192 0.19 26 lDismantle Barrier/Package for LLWdisposal 40 4 0.0002 0.032 0.03 27 Decontaminate MkiReactor Roomsurfaces 80 4 0.0002 0.064 0.16 28 Decommission remaining areas, except MkF 29 RemoveHotDrain Lines 104 4 0.0003 0.1248 30 Removecontaminated sections, exc. from MkFRoom 80 4 0.0003 0.096 31 Reroute services toisolate MkFRoom 224 4 0.0002 0.1792 32 RemoveMake-Up Water Tank 80 4 0.0002 0.064 33 Dismantle/Dispose ofremaining equipment inYard 160 3 0.0003 0.144 34 j ShiLLWtoNTS 80 4 0.0003 0.096 0.70 (CONTINUED) 3-12

PC-000482/2 TABLE32: OCCUPATIONAL RADIATION DOSEESTIMATES FORTRIGAREACTORS DECOMMISSION1NG TASKS,(CONTINUED)

Task?

'.'Task'Des'cription 1

11 1 /Durationj jNo;j'.yg,jDose Rat ETotal'Dose.

CSubtotal'Total g , . ..

y A x .

q pp .

g, .

44 4,& ,,

35 Decommission MkF Reactor 36 Radiological Survey 120 2 0.002 0.48 0.48 37 ' RemoveReactor Components inPool j 38 Grapple/Hoist/Survey 80 3 0.005 1.2 39 Disassemble asnecessary 80 3 0.005 1.2 40 Decontaminate orPackage asLLW 64 3 0.005 0.96 3.36 41 Prepare to Ship F uel 42 Ship Fuel stored inMkFCanal 360 4 0.002 2.88 2.88 43 Reactor TankandStorage Canal Water 44 Survey/Sample/Analyze 40 3 0.0002 0.024 45 Discharge/Filter asnecessary 40 3 0.0002 0.024 0.05 46 Install Confinement Barrier around Reactor Pit 40 3 0.0003 0.036 0.04 47 TankRemoval 48 Cut/Remove insections 72 4 0.0025 0.72 49 Segregate clean sections 64 4 0.0025 0.64 50 Package LLWsections 40 4 0.002 0.32 1.68 51 Concrete Liner a 52 Demolish activated portion 112 4 0.002 0.896 Waiillp**

53 Remove/Package 120 4 0.002 0.96 54 Survey remaining Concrete 40 2 0.0005 0.04 55 Demolish remaining portion toexpose Soil 80 4 0.0005 0.16 56 Survey Soil presumed tobeclean 40 2 0.0002 0.016 57 Shore/Cover Pit 40 4 0.0002 0.032 2.10 58 Dismantle Barrier/Package forLLWdisposal 40 4 0.0002 0.032 0.03 59 Decontaminate MkFReactor Roomsurfaces 80 4 0.0002 0.064 0.06 60 Package contaminated tools andequipment 40 6 0.0002 0.048 0.05 61 Ship LLWtoNTS 72 4 0.0002 0.0576 0.06 62 Survey Soil 112 2 0.0002 0.0448 0.04 63 Prepare Survey Report 64 Submittal for Release toUnrestricted Use 3-13

PC000482/2 This estimateisprovided forplanning purposes only. Detailed exposure estimates and exposure controls shall during bedeveloped detailed inaccordance planningofthe with therequirements decommissioning oftheGA activities.Area dose tid ALARA program rates used forthis estimate arebased on process knowledge andcurrent survey maps (where available).

Thedoseestimate tomembersofthepublic asa result ofdecommissioning activities is estimated tobe negligible. This isbecause siteperimeter controls willrestrictmembers of thepublic from the area where decommissioning activities aretaking place. This is consistent with the estimate given forthe"reference research reactor" inthe "Final Generic Environmental Impact Statement ondecommissioning of nuclear (NUREG-0586) facilities" (Ref. 10-22). Thedose tothepublic during decommissioning (DECON) andtruck transport transportation ofradioactive waste from the reference research reactor referred to inthe Final Generic ImpactStatement isestimated tobe"negligible (less than 0.1man-rem)."

Activated pieces andanycontaminated debris will beremoved andshielded ifrequired to meetU.S. DOTshipping requirementsand NTS Waste Acceptance Criteria.

3.2 Radioactive WasteManagement 3.2.1Fuel Removal TheDOEhasagreed thatithasa contractual obligation to accept all ofthe TRIGAreactor fuel ata DOEdesignated fuelstorage (see facility Contract DE-CR01-83NE4436). A date for shipment has notyetbeen determined andisthe subject of ongoing negotiation.

Thecurrent fuelstatus isasfollows:

TRIGAMarkF Reactor-All reactor fuelelements have been removed from the TRIGA MarkF reactor core/shroud andplaced intheFuel Storage Canal.

TRIGAMark IReactor-All reactor fuelelements have been relocated tothe TRIGA Mark F Fuel Storage Canal.

3.2.2Radioactive WasteProcessing Theprocesses ofdecontamination, remediation, anddismantlement ofthe TRDSwill result insolid andliquid lowlevel radioactive waste,mixed waste, andhazardous waste. Limited soil remediation isanticipated which willresultinsolid radioactive waste. This waste will be handled (processed andpackaged), stored, anddisposed ofinaccordance with applicable sections oftheCodeofFederal Regulations (CFR), California Codeof Regulations (CCR), SanDiego County andCity Regulations, disposal site Waste Acceptance Criteria,respective State Administrative Codes, GALicenses andPermits, and the applicable implementing plans andprocedures. Radioactive waste processing includes wasteminimization orvolume reduction, radioactive andhazardous wastesegregation, waste characterization, neutralization, solidification stabilization, andpackaging.

3.2.3Radioactive WasteDisposal Lowlevel radioactive waste willbeprocessed and packaged for disposalatthe Nevada Test Site under the terms ofanagreement withDOE.Thevolume oflowlevel radioactive waste A isestimated at4,000 cu. ft.Mixed lowlevelwaste maybetreated atGA'sNuclear Waste W 3-14

PC000482/2 o, Processing Facility orprepared for shipment tooff-site commercial processing anddisposal

$ v facilities less than such 50cu.

asEnvirocare ft.

ofUtah. Lowlevel mixed waste isexpected tobeminimal, 10CFR 61,Licensing Requirements for Land Disposal ofRadioactive Waste, Subpart D-Technical Requirements for LandDisposal Facilities, establishes minimum radioactive waste classification, characterization, andlabeling requirements. These requirements will bemetthrough theimplementation ofProject Packaging andCharacterization Procedures, Disposal SiteWaste Acceptance Criteria, andtheQuality Assurance Program Document.

Training will be provided forProject Waste Certification Officials, WastePackaging personnel, andWaste Characterization personnel toassure conformance toapplicable 10 CFR61requirements as stated inthe specificimplementing procedures andplans. Quality Assurance conducts audits and surveillances per the Quality Assurance Program Document based on ASME-NQA-1-1989, whichconfirms conformance withDisposal Site Acceptance Criteria andapplicable 10CFR61requirements.

10 CFR 71,Packaging and Transportation ofRadioactive Material, establishes requirements for packaging, shipment preparation, andtransportation oflicensed material.

Theradioactive wastethat will bepackaged andshipped will beLSAmaterial. GA isa USNRC andState ofCalifornia Licenseeto receive, possess, use, andtransfer licensedby-product andsource materials. 10 CFR 71 requirements will be met through the implementation ofProject andGA's Nuclear Waste Processing Facility (NWPF) Packaging andShipping Procedures. Training willbeprovided forWastePackaging Personnel and Waste Shipping Personnel toassure conformance to applicable 10CFR71requirements.

LSNC's Nuclear Material Accountability Department provides compliance oversight and off-site shipment notices. Quality Assurance will confirm conformance to 10CFR71 a Subpart H (Quality Assurance) requirements through the implementation ofthe GAQuality Manual andQuality Assurance 10CFR 71 applicable A

Assurance Program Document.

Quality Assurance requirements apply todesign, purchase, fabrication, handling, shipping, storing, cleaning, assembly, inspection, testing, operation, maintenance, repair, and modification ofcomponents ofpackaging which areimportant tosafety.

10CFR 20.2006, Transfer for Disposal andManifests, establishes requirements for controlling transfers oflow-level radioactivewaste intended for disposal ata land disposal facility; establishes a manifest tracking system; supplements requirementsconcerning transfers andrecord keeping; andrequires generator certification that transportedmaterials areproperly classified, described, packaged, marked, andlabeled, andareinproper condition for transport. These requirements will bemet through theimplementation of Project andNWPFPackaging andShipping Procedures with theoversight ofGA's LSNC's Nuclear Material Accountability Department.

Radiological andmixed wastes will bedisposed ofatdisposal sites pertheapplicable Disposal Site's Acceptance Criteria. Associated implementing plans andprocedures will reflect thecharacterization, processing, removal ofprohibited items, packaging and transportation requirements. Appropriate documentation will besubmitted todesignated disposal sites including, as required, certification plans, qualification statements, assessments, waste stream analysis, evaluations andprofiles, transportation plans, and wastestreamvolume forecasts. Wastecharacterization, wastedesignation, waste traceability, wastesegregation, wastepackaging, wasteminimization, andquality assurance andtraining requirements ofthe designated disposal sites will beincorporated in implementing procedures toassure conformance todisposal site requirements.

g W

Generator State (California) andTreatment/Storage/Disposal Facility States(Nevada, Utah, etc.) requirements for r adioactive andmixed waste management will beincorporated into 3-15

PC000482/2 plans andprocedures toassure conformance with applicable stateregulations, licenses, and ,

permits. Applicablestate regulations includeCalifornia Hazardous Waste Management@$

Regulations (CaliforniaCodeofRegulations, Title 22),andUtahDepartment of #

Environmental Quality Rules (R313) for thecontrol ofionizing radiation reflected in Envirocare's Utah Radioactive Material UT2300249.

License, will TheProjectconform to GACAL-DHS, Radiological Health Branch (CAL-RHB) License No.0145-80 topossess andusesource andbyproductmaterials asdirected byCCR, Title 17.GA will also conform tothe CAL-EPA requirements (EPA IDNumber CAD067638957) which permit/authorize GA tooperate asagenerator ofhazardous waste, totreat hazardous waste on site under California's Tiered Permit program Conditional Authorization (CA) or Conditional Exemption (CE) tiers, andtomanage radioactive mixed wastes under Interim Status granted bytheState ofCalifornia Department ofToxic Substances Control (CAL-DTSC). TheProject will also conform to the GA Health Permit tomanage hazardous materials issued bytheCounty ofSanDiego Department ofHealth Services Hazardous Materials Management Division (SD-DHS-HMMD). Project Plans andProcedures will also incorporate Metropolitan Industrial Waste Program(MIWP) requirements forthe discharge ofindustrial waste waters into thesanitary sewersystem managed bythe City ofSanDiego (San Diego Metropolitan Water District).

Radioactive waste will bestaged indesignated controlled areas inaccordance with USNRC 10CFR19and20requirements, CAL-DHS 17 CCR requirements, andthe requirements ofGA'sSpecial Nuclear Material License and State ofCalifornia Radioactive Material License. Mixed wastes will bestaged indesignated controlled areas perEPA40CFR requirements, CAL-DHS 22CCR, 10CFR19and 20, andperlocal andstate permits.

Measures willbeimplemented through plans andprocedures to control thespread of contamination, limit radiation levels, prevent unauthorized access, prevent unauthorized material removal, prevent tampering, andprevent weather damage. The designatedgy controlled areaswill beapproved byWAs,Radiological Work Permits, and/or Hazardous %&F WorkPermits Radioactive andmixed waste material will bepackaged for shipment per 10 CFR, 40CFR, 49CFR, 17CCR, 22 CCR, andthedesignated Disposal Site Criteria and placedin permitted interim storage (staged) until shipped. Thequantity ofwastepackages staged for shipment will bea function ofwastegeneration andpackaging rate, shipment preparation rate, shipment rate, anddisposal site acceptance rate. Tomeetthis objective,shipments will bescheduled throughout the life ofthe Project todesignated treatment, storage, and disposal facilities.

Radioactive material storage areas will becontained inside posted restricted areas according toexisting GAprocedures andconsistent with 10CFR20.

General 3.2.4 Industrial Safety Program Industrial Safety andIndustrial Hygiene personnel, with Project Management, shall be responsible toensure that the Project meets occupational healthandsafety requirements of Project personnel andthe general public. Primary functional responsibility istoensure compliance with the OSHAof1973asimplemented byCalifornia Labor CodeSection 6400andtheGeneral Industry Safety Orders (GISO 3203). Specific responsibilities include conducting anindustrial training program toinstruct employees ingeneral safe workpractices; reviewing Decommissioning Project procedures to verify adequate coverage ofindustrial safety andindustrial hygiene concerns andrequirements; performing periodic inspections ofworkareas andactivities to identify andcorrect anyunsafe conditions andworkpractices; providing industrial hygiene services as required; administering theHazardous Work Authorization Program; andadvising Project 3-16

PC000482/2 management onindustrial safety matters andonthe results safety ofperiodic inspections.

(j[ The Project issupported byGAIndustrial Safety and Industrial Hygiene personnel.

All personnel working on TRDS the Decommissioning will Project receive Health and Safety training inorderrecognize to andunderstand the risks potential involving personnel healthand safety associated with the workatthe TRDS.TheHealth andSafety training implemented atGA toensure is compliance with therequirements ofthe USNRC(10 CFR),the EPA (40 CFR),and both OSHAandCAL-OSHA (29 CFRandCCRTitle 8).

Workers andregular visitors will befamiliarized with plans, procedures, andoperation of equipment toconduct themselves safely. Inaddition, each workermustbefamiliar with procedures that provide forgood quality control. Section 2.5, Training Program, provides additional information.

3.3 Radiological AccidentAnalyses Thepotential radiological accidents for the decommissioning oftheTRDSwill bemainly associated with the approximately 250 TRIGA fuel elements storedinanexisting Fuel Storage Canal within theformer Mark F reactor pool complex. This fuel storage may remain ineffect during apart ofthe decommissioning ofthe buildings andfacilities related tothe MarkIandMark F reactors ifarrangements toremove thefueloffsite are delayed.

Factors considered inassessing potential radiological accidents are:

1)Fuel storage and removal 2)Seismicity a 3)Fire o .

4)Other considerations FuelStorage Thespent TRIGAfuel elements willbestored inracks inthe storagecanalassociated with theMarkF reactor The pool. storage canal is15 feet w ith deep adequate radiation protection provided bythe depth ofwater over the storedfuel.

ThePossession-Only-License conditions set forth inRefs. 10.2and10.3 requires that fuel bemovedandstored inaccordance with theexisting Technical Specifications andGA procedures, until removed from the site. Theproposed decommissioning action does not pose anyadditional criticalityorfission product release risk. Operations toremove MarkF reactorequipment notassociated with fuel storage willbeconducted soastoavoid possible disruption ofthe Fuel Storage Canal while it isbeing used tostorefuel.

Aspreviously stated inSection 2.3.1.2, GAplans toperform limiteddecommissioning tasks onthe TRIGAMark Freactor prior toremoval offuel from theFSC.These actions, which include thesurvey, handling, removal, sectioning, packaging,and disposal of hardware items notassociated with orrequired for fuelstorage,willnecessarily becarried outinproximity tothe irradiated TRIGAfuel situated inthe FSCportion ofthe TRIGA Mark F pool. Inorder toprotect the security ofstored fuel materials inthe FSCduring such operations, several administrative and engineering controlswillbeapplied during this work, including the following existing or additional measures:

ff W

1)All existing place during protective deck plates covering anydecommissioning-related the FSCwill activities.

beinstalled andsecured in 317

PC000482/2 2)All work, including decommissioningrelated activities,occurring inthe TRIGAMark 4, F Reactor Roomwill beperformed by,orunder the direct supervision of,currently$$E licensed Senior Reactor Operator(s).

3)Prior tothe start ofdecommissioning-related workinvolving the TRIGA Mark F pool, all unnecessary equipmentand materials shall beremoved from the TRIGAMarkF Reactor Room (refer toFigure 2.5), andaStaging Area onthe northside ofthe TRIGA MarkFpool shall becleared andprepared for receiptofhardware items removed from the pool.

4)Hardware items to be hoisted and removed from the TRIGAMarkF pool areprimarily aluminum-construction pieces suchasthereactor shroud, grid-plates, beam tubes, neutron/gamma radiation detectors, andetc.,with no single item or component expected toexceed 200lbs.

5)Hardware items removed from the TRIGA Mark F pool shall besecurely grappled and rigged with appropriately-certified lifting equipment.

6)Hardware items removed from the TRIGA Mark F pool shall behoisted no higher than deck levelwhich isoverthe pool, using the installed 3 Toncapacity ElectricHoist or equivalent, andshall beimmediately translated in a northerly direction tothe Staging Area forsubsequent processing. During decommissioning-related work, limitcontrols shall beinstalled onthe 'IRIGA MarkF Electric Hoist toprevent translation ofloads over theFSC.

SAsmi.city SanDiego County hasbeen considered oneofthe moremoderate seismic risk regions in Southern California. Thehistorical pattern of seismic activity has generally been characterized by a broad scattering of small magnitude earthquakes, whereas the surrounding regions are characterized bya high rateofseismicity withmany moderate-to-large-magnitude earthquakes.

Arecent occurring (see study Appendix inCalifornia onthe B,Ref.

major 5.8) strands estimated ofthe the probabilities SanAndreas fault oflargeearthquakes system. Inaddition to theprincipal traces ofthe SanAndreas fault, earthquakes occurring on the other major faultsofthe system (San Jacinto, Imperial, etc.) were also considered. Thestudy estimated the that probability ofamagnitude 7orgreater earthquake occurring inthe next30yearsin Southern California (along the Southern SanAndreas, Imperial, orSanJacinto faults) is 0.5orgreater. However, a quake ofmagnitude close to7 on these fault lines isnot expected tosignificantly impact the GAsite because ofintervening distance.

Current Coronado information Bank, (see SanDiego Appendix Trough, B, Ref.

LaNacion, 5.9) however, andElsinore indicates fault theRoseCanyon, zones arecapable of generating strong ground motion inthe SanDiego area.Possible Richter magnitudes for earthquakes onthese faults canbeashigh as7.0, 7.5, 7.5, 6.3and7.5, respectively.

Passing approximately 3 miles (5km)westofthe GAsite, the RoseCanyon faultisthe nearest activefault.

Thepresence ofthree small, local faults was confirmed by theWoodward-Clyde Consultants faultinthe field northern reconnaissance portion ofthe ofthesite site trends (see east Appendix B, towestthrough Ref. 5.11).

proposed An unnamed lots 25,26, w 31,and32. TheSalk towest.A northerly fault ismapped trending fault inthe southern islocated portion ofthe inthesoutheastern andalso site trends areaandcrosses east the ff 3-18

PC000482/2 Ae Genesee Avenue canyon. Allofthese faults aremapped asbeing overlain byearly Pleistocene considered formations active.

which have notbeen displaced. Therefore, the faultson-site arenot Decommissioning activities will involve decontamination andremediation. Plans and specifications for any remediation which could affectthe structural integrity of the b uilding would bereviewed by astructural engineer toassure that these alterations would notrender the buildingunsafe. Decommissioning willnotpose added risk toworkers during aseismic event.

Ei.re TheTRDSwill notcontain combustible material insufficient quantity tosupport a major fire.possible It is for a small fire to occur a sa result ofanelectrical fault, asanexample.

Portable extinguishers anddetection will beprovided asneeded. There should beno radiological hazardasaresult offire.

Other Considerations Radiological accidents could occur duringremoval and packagingofactivated components andequipment. However, this risk isvery low considering the administrative precautions which will betaken during decommissioning.GA experience inD&Dprojects, including the handling ofactivated/contaminated components and control ofjob activities utilizing written andapproved procedures, will ensure thesafe conduct ofthe project.

Consequences ofa pool leak are lowbecause the pool water iscontinuously treated and g, contains negligibleradioactivity. Themain function ofthe pool is to provideshielding for

%y' workers positioned the FSCduring A

near orover anyrequiredhandling, inventory related, ortraining operations. Thewaterisnotrequired for fuel cooling. Any failure tomeet shielding requirements would result inworker restrictionsonapproach to theFSCuntil the requirement couldbemet.Theother potentialconsequence would bedue to flowing water carrying loose contamination toa newlocation within the facility, outside the facility, or into the soil. Since loose contamination isminimal, the risk ofspread ofcontamination is low. There isnopotential for airborne contamination from such anevent.

3-19

PC000482/2

4. PROPOSED FINALRADIATIONSURVEYPLAN Theintended course ofaction for TRDSdecommissioning, based upon consideration ofsite and facility radiological characterization results, is strive to todecontaminate structural materials to the extentpracticable in balance with radioactive waste minimization considerations, and dismantle TRDSsystems tothe extent necessary for remediation, andpackaging for burial those materials that cannot reasonablybe decontaminated. Assuch, theFinal Release Survey Plan (andsubsequent FinalSurvey Report) discussed in this section deals with release ofthe building structure ofthe TRDSremaining after decontamination andremediation actions, andtheTRDSproperty to unrestricted use. Thissectionwill also discuss the survey methods that will beutilized.

4.1 Description ofFinal Radiation SurveyPlan Thepurpose ofthe Final Radiation Survey is todemonstrate that the radiologicalcondition ofthe TRDSsite anticipation ofU.S.

structure areator below established release NRCapproval to terminate the TRIGA criteria Reactor (seeSection licenses 2.8) andtorelease in the TRDSfor unrestricted use. TheFinal Release Survey Plan (and report) willdeal with release ofthe TRDSstructure andsite tounrestricted use.

GA hasdeveloped its Final Release Survey Plan using theguidance provided in NUREG/CR-5849 (draft) (Ref. 10.10).

4.1.1Means forEnsuring that all Equipment, Systems, Structures, andSite are Included intheSurvey Plan Every item that isto beremoved fromtheTRDSwillbe evaluated forability to decontaminate andradiologically surveyed to ensure that radioactive (i.e.,licensed) materials arenotinadverently removed from the facility(see Section 3.1.3). When itis impractical ornotpossible todecontaminate anitem such that itexhibits nodiscernable facility<elated activity whensurveyed following methods presented inSection 3.1.3,the itemwillbe treated as radioactive waste.The systematic approach to TRDS decommissioning will ensure that every item orstructural component inthe 'IRDS is specifically evaluated for release before beginning theFinal Release Survey. The Final Release Survey will treatthe TRDSas"affected" toensure 100%survey coverageprior to requesting TRDSreactor license termination andrelease ofthe property for unrestricted use.

4.1.2Means forEnsuring that Sufficient DataisIncluded toAchieve Statistical Goals GAhasdeveloped the'IRDS Final Release Survey Plan using the guidance presented in NUREG/CR-5849. By using this guidance, theProject will satisfy theU.S.NRC recommended statistical goals.

4.2 Background Survey Results TheFinal Release Survey Guideline values for residualactivity are taken tobelevels above the naturally occurring background radiation. Thefinal release measurements will consist ofacombination ofgeneral area radiation values andarea surveys. Inaddition, a detailed micro-R radiation survey oftheremaining structureandsite will beperformed and compared tobackground measurements.

4-1

PC-000482/2 Background radiation asencountered atanylocation includes contributions duetoboth a natural radiation sources andmanmade sources. Natural radiation sources include NEE terrestrial radioactivity due naturally to occurring radioisotopes insoils andconstruction media, "

airborne radioactivity (principally radon andradon progeny) from the radioactive decay of certain of these naturally occurring radioisotopes, andcosmic radiation from high speed particle interactions inthe earth's atmosphere. Manmade background radiation asit would impact theFinal Release Survey would primarily consist of atmospheric fall-out of fission products dueto weapons testingreactor and accidents and anycontribution that might exist asa result of other licensees' activities.

Thegeneral area background radiation aswould bemeasured with the micro-R meteris influenced by number of a factors, the principally naturally occurring radioactivity insoils andother nearby materials, radon and radon progeny concentrations in the a ir,and extent ofcosmic radiation (whichvaries with elevation). Due to the n umber of influences, the natural day) background andseason-to-season varies appreciably from asrelated to l

changing ocationto weather location, day-to-day conditions and (even materials time in of the surroundings.

Thesite andfacility characterization study included measurements toestablish background radioactivity in soils, concrete, andasphalt t hat were considered representative ofthose that would encountered be in the F inal Release Survey. One ofthe principal of constituents global fallout, 137CS, which isfound principally as a result of atmosphericweapons testing andreactor accidents isalso the principalproduct fission contaminant atthe T RF. l"Cs has been t obe seen persistent inthe upper (6 15 cm in.) o f soil with concentrations decreasing beyond this depth (Ref. 10.12).

Release criteria (e.g., Regulatory Guide 1.86) wereestablished as anincrement inexcess A ofbackground values. Therefore, the Final Release Survey will include the establishment W ofbackground area radiation levels using theguidance ofNUREG/CR-5849. Asphalt, concrete andother construction material background values will beestablished bytaking measurements onunaffected facilitiesand/or portions ofthe GAproperty representative of unaffected TRDSconstruction materials.

4.3 Final Release Criteria-Residual Radiation andContamination Levels Thecriteria for release ofthe TRDSfacility/site tounrestricted use, after completion of the decommissioning activities described inthis plan, arepresented inSection 2.8. In summary, they are: 1) t hosegiven inthe U .S. NRC Regulatory Guide 1.86, "Termination ofOperating Licenses for Nuclear Reactors," and2)anexposure rateduetoresidual radionuclides -

asaresult offacility operation -

notinexcess of5 micro R/hr above natural background measured at1meter from thesurface. (Ref. "Action Plan t o Ensure Timely Cleanup ofSite Decommissioning Management Plan Sites," FRVol. 57No.74April 16, 1992).

4.4 Measurements forDemonstrating Compliance with Release Criteria 4.4.1Instrumentation-Type, Specifications, and Operating Conditions Instrumentation utilized during the Final Release Survey (and equipment andmaterials survey) will beselected based uponthe need toensure that site residual radiation willnot exceed the release criteria. Inorder toachieve this goal, instrumentation that issensitive to the isotopes ofconcern andcapable ofmeasuring levels below 75%ofthe guideline values a forthose isotopes recommendations will beselected.

ofNUREG/CR-5849.

Instrumentation Instrumentation selected that will bebased isavailable uponthe forthe Final "

4-2

PC000482/2 Release Survey, and their respective detection rangecapability waspresented inTable 3-1

@ of thisplan.

and standards Instrumentation that that isused areNISTtraceable inthesurveys andrepresentative will becalibrated ofthe against representative sources isotopes encountered at the TRDS. Instruments will beoperationally tested daily, orprior toeach use, whichever isless frequent. Instruments willnotbeused inconditions that arenotin conformance withmanufacturer recommendations.

4.4.2 Measurement Methodology forConduct ofSurveys Theentire TRDS site willbetreated asan"affected" area inaccordance with the def'mition provided in NUREG/CR-5849. The yard area was characterized during facilityradiological characterization scoping survey. This Decommissioning Plan presumes that the TRDShas been decontaminated tothe extent practicable prior tothe Final Release Survey. TheTRDS structure andsite will bemethodically remediated asnecessary prior toconduct oftheFinal Release Survey. Thecharacterization resultsandthe continuous feedback from remediation surveys will be theb asisfor remediation efforts.

Theonly radionuclides identifiedin the TRFandadjacent yards during radiological characterization effortswere137Cs (predominant nuclide),60Co andto'a lesser extent (in only onesoil sample) *Cs.These isotopes are readily detectable using p-y sensitive instrumentation. Furthermore, all ofthese isotopes arereadily detectable with gamma spectrometry techniques as well.

Tosupport the finalsurvey, portions ofthe TRDS will begridded into areas that are10 meters by 10meters. Eachgrid will besurveyed initially with a surface scanning instrument system to ascertain locations ofanyelevated concentrations. Inaddition, systematic measurements maybeperformed within each grid atlocations equidistant an between the center and each ofthe four grid blockcorners.

g Ifanylocation within agrid requires remediation inorder tosupport adecision infavor of release tounrestricted use, the entire affected gridwillbescanned again after completion of remediation efforts.

4.4.3 Fixed Contamination Survey Protocol Thesurfaces ofequipment andmaterials will besurveyed inaccordance withProject and GAHPprocedures for release ofequipment andmaterials tounrestricted use. Direct frisk will beperformed with either a portable Geiger-Mueller, or a gasflow proportional detector, asdictated bythe minimum detectableactivities ofthe instrument/probe, orbeta-scintillatorforthecontaminants ofconcern andtheassociated release criteria. Inany situations where process knowledge would suggest a potential foralpha activity, survey with alpha detection instruments orcounters will also beemployed. Inevaluation of equipment andmaterials for fixedorsmearable licensedmaterials, items painted with other than original manufacturer's paint will notbereleased unless (1) clear process knowledge demonstrates that paint the wasapplied toaclean non-radioactive surfaceprior touseinthe restrictedarea, (2) the paint isremoved or(3) Health Physics approved paint sampling survey demonstrates that radiation levels under thepaint arebelow the releasecriteria. Ifthe potentialexists forcontamination oninaccessible surfaces, the equipment will beassumed tobeinternally contaminated unless (1) the equipment isdismantled allowing access for surveys, (2) appropriate tool orpipe monitors with acceptable detection capabilities are utilizedthat would provide sufficient confidence thatnolicensed materials werepresent, or (3)it mayreadily beconcluded that surveys from accessibleareas are representative ofthe inaccessible surfaces (i.e.,surveying the internalsurface from both ends ofa straight pipe from a nonradioactive process system with cottonswabs would berepresentative ofthe

/ inaccessible areas). Theresults ofcontamination surveyswill berecorded either on survey 4-3

PC-000482/2 maps or special release logs. Results ofall surveys will becompared to average and maximum criteriaprior toany material being released.

4.4.4Removable Contamination Survey Protocol Removable contamination willbeassayed bycollection of100cm2 smears from surfaces, oraspracticable. The smear samples will beevaluated using suitable hand-held instruments or low level beta counting systems. As discussed inSection 4.4.3, smears will be evaluated for alpha contaminants ifprocess or survey information recommends this, though TRDSDecommissioning Health Physics personnel routinely evaluates a portion ofits positive smears for alpha contamination. Survey evaluations arerecorded inthesame manner described in Section 4.4.3.

4.5 Methods tobeEmployed for Reviewing, Analyzing, andAuditing Data 4.5.1Laboratory/Radiological Measurements Quality Assurance During decommissioning survey activities, many direct andindirect measurements and sample media samples will be collected, measured, andanalyzed forradiological contaminants. Theresults ofthese surveyswill beutilized toevaluate the suitability ofthe materialoritem for release tounrestricted use, or whether decontamination ofstructures, components, andthe surrounding site have achieved the desiredresult. Sample collection, analysis,andthe associated documentation will adhere towritten procedures andmeetthe guidance ofthe U.S. NRC,aswell ascomply withrecognized industry recommendations andgoodpractices. Outside (i.e., non-GA) laboratories selected to analyze TRDS decommissioning samples shallbeapproved bythe GAQuality Assurance organization and onthe listed QAApproved Suppliers List maintained bytheGA Quality Assurance Group.

Organizations that perform radiological monitoring measurements recognize the needto establishquality assurance programs toassure that radiological monitoring measurements arevalid.These programs areestablished for the following reasons: (1) to readily identify deficienciesinthe sampling andmeasurement processes tothose individuals responsible forthese activitiessothat promptcorrective action canbetaken, and(2) to routinely monitor the survey andlaboratory measurement results inorder toassure that results and conclusions are valid.

4.5.2Supervisory andManagement Review ofResults Radiological surveys areconducted byHealth Physics Technician staff members who are trainedandqualified. Inaddition, radiological surveys andsample results are reviewed bya seniorlevel member ofthe Health Physics staffother than theindividual that performed the survey. Final Radiation Survey data isalso reviewed bythe HP Manager andthe TRDS Decommissioning Project Manager.

4-4

PC000482/2

5. TECHNICALSPECIFICATIONS Currently applicable Technical for Specifications theGATRIGA MarkIReactor aresetforth in Amendment No. 35toFacility License No.R-38(TRIGA MarkI Reactor)-General Atomics (TAC No.M97502), Issuedbythe USNRC,dated October 29,1997(Reference 10.2).

Currently applicable Technical Specifications for theGA'IRIGAMarkF Reactor aresetforth in Amendment No.43 to Facility License No.R-67(TRIGAMarkF Reactor)--General Atomics (TAC No.M90380), Issued bythe USNRC,dated March22,1995 10.3)

(Reference Asdecommissioning progresses, further for requests changes tothe Specifications Technical will besubmitted inanapplicationfor amendment tothelicense to10CFR50.59.

pursuant

=

51

PC000482/2 6., PHYSICALSECURITYPLAN AllGA radiation restricted areas aresecured from unauthorized During entry. non-working hours, all nuclear facilities are locked. GAmaintains 24hour security topatrol watchmen thesite.

Existingphysical security andmaterial control andaccounting plansapproved bytheNuclear Regulatory Commission, asmaybeamended, willcontinue tobeimplemented.

Theseexisting plansmeet therequirements in10CFR70.38 fordecommissioning, andwillbe maintained asrequired by the MkF Possession Only License amendment(Ref.

10.3),andtheM kI Possession Only License amendment (Ref. 10.2).

Compliance with Parts 50and73 ofthephysical security plan because isassured ofthe all elements plan of the are maintained until the f uelisremoved offsite.

Decommissioning activities beconducted will with the fuel intheFSC andall physical andsurveillance security inplace.

Once ofcommonservices isolation has beenimplemented, the ofthe security andcontrol MarkF reactor roomscanbemaintained without impact inthe on decommissioning activities Mark Ireactor room.

Workers will be limited in number andappropriately trained before s ite.

tothe Oversight entry will beprovided during anyentry into theMarkF room forpurposes ofreactor equipment removal not associatedwith the FSCorfuel.

6-1

PC000482/2

7. EMERGENCYPLAN GAhas a Radiological ContingencyPlan, supplemented byprocedures specific tothe

'IRF, as required by the USNRC andStateofCalifornia.

Training ontheRadiological Contingencyis Plan providedtothe Emergency ResponseandRecovery Director Emergency andAlternates. Response Team for members receive trainingappropriateresponding toemergencies.

7-1

PC-000482/2

8. ENVIRONMENTALREPORT TheEnvironmental isprovided Report asAppendix B.

c 8-1

PC-000482/2

9. CHANGES TO THE DECOMMISSIONING PLAN Asthedecommissioning totheTechnical Specifications uptotermination of progresses, changes thelicense will bevia aRequest forLicense Amendment to10CFR50.90.

pursuant GArequests that other changes to the Decommissioning Planbeallowedwithout USNRC prior approval whichinvolve decommissioning activities unless safety an unreviewed questions is involved. Anunreviewed safety question involves:

1 Theincrease ofprobability ofoccurrence orthe ofconsequences increase ofanaccident or malfunction ofequipment important tosafety compared previously situation tothat evaluated in the SAR,or

2. Thepossibility for anaccidentor malfunction ofadifferent than type previously analyzed inthe SAR,or 3.Thereduction inmargin ofsafetyasdefined inthe SAR.

Reports, records ofchange, andretentionofdocuments will beinaccordance with applicable the portions of10CFR50.59.

9-1

PC-000482/2

10. REFERENCES 10.

1 NUREG-1537 Rev.0, "Guidelines forPreparing andReviewing forthe Applications Licensing ofNon-Power Reactors".

10.2Amendment No.35toFacility License No.R-38(TRIGA MarkI Reactor)-Genera Atomics(TAC No.M97502), Issued bythe USNRC,dated October 29,1997.

10.3Amendment No. 43 toFacility License No.R-67(TRIGA MarkF Reactor)-General Atomics (TAC No. M90380), Issued bythe USNRC,dated March 22,1995.

10.4USNRC License No.R-100 (terminated).

10.5Asmussen, Keith E.LetterNo. 696-2581 toDocument Control Desk, USNRC,ATTN:

Mr.Alexander Adams, Jr. And Mr. Charles E.Gaskin, "Docket Nos. 70-0734,50-89and 50-163; Decommissioning Financial Assurance,"dated May20,1996.

10.6Weiss, Seymour H.AndRobert C.Pierson LettertoDr.Keith E.Asmussen, "Financial Assurance for USNRC Licenses SNM-696, R-38, R-67/Docket Nos. 70-0734, 50-50-89, 163," dated July 9,1996.

10.7ASME-NQA-1-1989, "Quality Assurance Program Requirements for Nuclear Facilities" 10.8General Atomics QualityAssurance Program Approval by the USNRCTransportation &

Storage Inspection Section, Spent FuelProject Office, Nuclear MaterialsSafetyand Safeguards, Approval No.0030, Rev. 6,July 9,1996.

b 10.9USNRC Regulatory Guide 7.10, "Establishing Quality Assurance Programs forPackaging Used inthe Transport ofRadioactive Material".

10.10NUREG/CR-5849, "Manual forConducting Radiological Surveys inSupport ofLicense Termination," Draft forComment, June 1992.

10.11ANSI288.2-1980, "Practices forRespiratory Protection".

10.12National Council onRadiation Protection andMeasurements (NCRP), NCRPReport No.

50, "Environmental Radiation Measurements," December 27,1976.

10.13U. S.Nuclear Regulatory Commission Regulatory Guide 4.15, "QualityAssurancefor Radiological Monitoring Programs (Normal Operations)-Effluent Streams andthe Environment," Revision 1,February 1979.

10.14"General Atomics SiteDecommissioning Plan" Licensing, Safety, andNuclear Compliance Organization, General Atomics, SanDiego, CA;Dated September, 1996, Revised December, 1996, April,1997, January,1998, andJuly, 1998.

10.15"Nuclides andIsotopes, Chart ofNuclides; 14th Edition," Nuclear Energy Operations, General Electric Company, San Jose,CA; 1989.

10.16ANSStandard 15.8,"Quality Assurance Program Requirements for Research Reactors."

10.17GARadiological Contingency Plan.

10-1

PC000482/2 10.18 U.S. Atomic Energy Commission, Guide Regulatory "Termination 1.86, ofOperating Licenses forNuclear Reactors," dated June1974.

10.19 U.S. Nuclear RegulatoryCommission, "Action Plan Cleanup Timely toEnsure ofSite Decommissioning Management Plan Sites," Register/Vol.

Federal 57,No.74/Thursday, April 16, 1992.

10.20 U.S. Nuclear Regulatory Commission, IECircular No.81-07, ofRadioactively "Control ContaminatedMaterial," May14,1981.

10.21 U.S.Nuclear Regulatory Commission, IEInformation Notice No.85-92, "Surveys of Wastes Before Disposal From Nuclear Facilities,"

Reactor December 2,1985.

10.22 U.S.Nuclear RegulatoryCommission, NUREG-0586, "Final Generic Environmental Impact Statement on decommissioning ofnuclear 1988.

August facilities,"

10-2

PC000482/2 A1

PC000482/ 2 LISTOF TABLES AM Table A-1-TRF Area Classifications for Characterization........................... A-4 #

Table A-2-Results ofRadiochemical Analyses for TRFSoil Media Samples................ A-5 Table A-3-Results ofRadiochemical Analyses for7RF Asphalt/Concrete Media Samples A-6 ......

LISTOFFIGURES Figure A-1-Grid Mapof'IRIGA ReactorFacility used forMedia Sample Locations for Radiological ScopingStudy.................................................... A-7 Figure A-2-Grid MapofTRIGA Reactor Facility showing Radiological Measurement Results from Radiological Scoping Study.............=..........,......... A-8 Figure A-3-Schematic ofthe RoomLayout for the TRIGA Reactor Facility, Building 21 ....... A-9 LISTOF SURVEY RESULTS Rm."21/102, Survey

1. 21-97-00004 .................................. ................A-10

-00005 ........................................... ....A-11

-00023 ..............................................A-12

-00009 ......................................................A-13

-00019 ............................ .........................A-14 Rm."21/105, Survey

1. 21-97-00030 ........................................................A-15

-00036 ..............................................A-16

-00032 .................. ....................A-17

-00037 ..........................................A-18 few W

-00031 ........................................................A-19 Rm."21/106, Survey

1. 21-97-00029 , =....................,., .................,.........A-20

-00038 ...........................................................A-21

-00033 ..... ..................... .<...........A-22

-00039 ......................................................A-23

-00034 ..........................................................A-24 Rm."21/107, Survey

1. 21-97-00010 ................................=................A-25

-00011.............................................................A-26

-00024 .........................................................A-27

-00012 ........................................A-28

-00014 . ........................ L ..............A-29 Rm."21/108, Survey

1. 21-97-00025 ............................=.........A-30

-00027 .,.....................................................A-31

-00040 ............. .....

..............................A-32

-00026 . .=.... ...........,....A-33

-00028...........................................................A-34 Rm."21/109, Survey

1. 21-97-00046 .............................. ................A-35

-00048 ..............................................A-36

-00044 ................................................................A

-00050 ..........=..................... ,...A-38

-00045 ..................................................

Rm."21/110, Survey

1. 21-97-00041...................................................

-00047 .....,.....................................A-41

-00043 .....................,..............................

-00049 ............................<.... .......A-43

-00042 .....................=.......................

A-2

PC000482/2 Rm."21/111, Survey #21-97-00016............................................................A-45

-00017.......................................................A-46

-00022......................................................A-47

-00018<..........................................A-48

-00015.....................=................A-49 Rm."21/112, Survey

1. 21-97-00052..........................................A-50

-00054........................................................A-51

-00055............................................................A-52

-00059..........................................................A-53

-00058............................................................A-54 Rm.21/113, Survey

1. 21-97-00051.............................................................A-55

-00053................................,........................A-56

-00056......<..................................A-57

-00060..................=................A-58

-00057..................n......................A-59 Rms.21/114 "

& 115, Survey"

1. 21-97-00063......................,....................A-60

-00064.............................................A-61

-00062.................................................A-62

-00061......................................................A-63 21/Roof, Survey #21-97-00006...............................................................A-64

-00007............................................................A-65

-00020..................................................A-66

-00008..=..~..=..........................A-67

-00021...........,................................A-68

PC000482/2 APPENDIX A

SUMMARY

OF CHARACTERIzATION RESULTS da W

A radiological scoping study performed was on theTRIGA Reactor Facility (TRF) tosupport decommissioning planning. Due tothe operational status ofthe'IRIGA MarkI Reactor, the radiological scoping characterization was notan invasive study that involved defacingfacility structures by collection ofbuilding construction mediasamples. Outside the TRFmedia samples wereobtained for surrounding soils, and asphalt,concrete.

TheTRFwasfirst evaluated from process knowledge andpast radiological Based surveillance.

uponthis evaluation, variousportions ofthe complexandits associated yard are aseither classified "affected" or"unaffected." Affected areas are areasthathave potential radioactive contamination (based on process knowledge) orknown radioactive contamination (based on pastradiological surveillance). Unaffected areas areall areas notclassified asaffected. Table A-1showsthe classifications ofareas within the facility.

Table A1-TRF AreaClassifications forCharacterization AffectedAreas Unaffected Areas Room102-Mark IReactor andControl Room Room 100-Office Room105-Tool Sho Room 101-Office Room106-Countin Room Room 101A-Dark Room Room107-Mark FReactor Room 103-Office Room108-Mark F Control Room Room104-Office Room109-Mark III Control Room Restrooms Room110-Mark III Ex erimental Area En andOffice Area Corridors Room111-Mark III Reactor Pads Electrical #A Room112-Thermal Stabilit X-Ra Room U Room113-Thermal Stabilit Lab RoomI14-North En Room115-Decontamination Room AllYardArea/Roof MarkIShed Coolin Tower Yard Area Stora eShed Machine Sho Sampling protocol, sample preparation, survey andmedia result documentation, andanalytical methods forthe scoping study werebased upon Refs.

A-1through A-7. Pages A-10through A-68 are copies ofthe survey maps from the study.

W A gridmapofthe TRF,including building surroundingareas (soils, asphalt, concrete) isprovided inFigure A-1.

Systematic media samples ofthe TRFwereobtained atgrid intersections shown inFigure A-2. In addition, onejudgment sample location wasused toobtain soil/asphalt samples based onprocess knowledge. Thirty-two soil media samples, 21asphalt media samples, andoneconcrete media sample were obtained for radiochemical Thefirst analysis. approximate 6 inch depth ofsoil inthe shape ofa 4 inch diameter cylinder, carved outbya coring tool, wasobtained for media soil samples. Inonecase, location (X,1), nosoil couldbecollected duetothe depth ofthe asphalt.

Asphalt andconcrete media samples wereobtained similarlyusing thecoring tooltoproduce approximate presents the

.6 inch media tall, sample 4 inch diameter radiological results samples cylindrical onthe entered grid ofasphalt/concrete.

map, for theTRF.

Figure A-2 A W

A-4

PC000482/2 The results ofradiological analyses forsoil media samples includingsample location andidentifica-tionnumber areprovided inTable A-2. Theresults ofradiologicalanalyses for asphalt/concrete mediasamples including sample location andidentification number areprovided inTable A-3.

FM Theradiological scoping survey showed the facility tobewell areas maintained only with minor amounts ofresidual radioactivity discovered. Itisrecognized that components associated withthe TRIGAreactors, and some surrounding structural materialswillbeactivated ofreactor asa result operations. Inside ofthe facility itself, surveys ofaffected areas showed very little residual radioactivity. Rooms102 and 107,the MarkIandMarkF Reactor rooms respectively, both showed several locationsoffixed radioactivity onthe surfaces, floor andRoom107also hadone location ofloose surfaceactivity. Figure A-3 isaschematic ofthe roomlayout for the TRF.

Table A2-Resultsof Radiochemical AnalsesforTRF Soil Media Sam les Location & Remarks Sam leID Gamma Isoto icResults(Ci/)

GridX,4 soil

, sam lebeneath ashalt 21S-97-001 naturalactiviton)

Grid(X,5 soil

, sam lebeneath ashalt 21S-97-002 0.04 137Cs GridY,4 soil

, sam lebeneath ashalt 21S-97-003 naturalactivi onl Grid 5 soil 2, , sam lebeneathas halt 21S-97-004 0.04 134C3137CS gjg GridY,6 soil

, sam lebeneath ashalt 21S-97-005 naturalactivi onl Gridz,6 soil

, sam lebeneath ashalt 218-97-006 0.06 "Co,0.37 137C3 GridY+0.5, 6.5soil

, sam lebeneath ashalt 21S-97-007 0.26 137C3 Grid/Y,7 soil, sam lebeneath ashalt 21S-97-0080.03 "Co, 0.53 137C3 GridX,6 soil

, sam leonl 218-97-0090.45 "Co, 0.02134Cs, '37G 1.24

(

T" -

Grid Grid (Y,5 soil (2,7 soil samlebeneath sam leonl ashalt 21S-97-010naturalactivit onl 21S-97-0119.24 "Co,29.59 137C3 Grid W,4 soil

, samlebeneath ashalt 218-97-012natural activit onl z,

Grid 2 soil

, sam leonl 21S-97-0130.43 0.59"Co, l"Cs Grid2,1 soil

, sam leonl 215-97-0140.69 "Co, 0.43 137Cs Grid z,0 soil

, sam le onl 21S-97-0150.30 6"Co,0.30 l"Cs GridY,0 , soil samleonl 21S-97-0160.16 "Co, 0.42 137C3 GridA, 1 soil

, sam leonl 2lS-97-0170.95 6"Co,1.26 137C3 Grid(2,-1 soil

, sam leonl 215-97-0180.11 "Co, 0.17 l"Cs Grid Y,-1), soilsam leonl 21S-97-0190.06 "Co, 0.20 '"Cs GridX,-1 soil, sam le onl 21S-97-0200.22 "Co, 0.29 137CS GridU,1 soil

, samleonl 21S-97-0210.11 "Co, 0.60 137Cs GridA,4 soil

, sam lebeneath ashalt 21S-97-0230.10 '"Cs GridA,3 soil

, samlebeneath ashalt 21S-97-024natural activit onl GridA,2 soil

, sam lebeneathconcrete 21S-97-0250.04 '"Cs GridV,2 soil

, samlebeneath ashalt 21S-97-026 activit natural onl Grid 1 soil V, , samlebeneath ashalt 21S-97-027natural activit onl Grid(X,0 soil

, sam lebeneathashalt 218-97-028natural activit onl GridX,3 soil

, sam lebeneathashalt 21S-97-0290.06 13703 GridV,0 soil

, sam lebeneathashalt 21S-97-030natural activit onl W,

Grid 0 soil, sam le beneathashalt 21S-97-031natural activit onl Grid(W, 1 soil

, samlebeneath ashalt 21S-97-032natural activi onl GridY,1 soil

, samlebeneath ashalt 21S-97-033natural activi onl A-5

PC000482/2 Table A3-Results ofRadiochemical AnalysesforTRF Asphalt/Concrete Media a Sam les WE Location & Remarks Sam leID Gamma Isoto icResults (Ci/)

GridX,4 as halt

, samle 21B-97-001natural activit onl GridX,5 ashalt

, sam le 21B-97-002natural activit onl GridY,4 ashaltsam le

, 21B-97-003 natural activit onl Grid2,5), ashalt sam le 21B-97-0040.48 l"Cs GridY,7), ashalt samle 21B-97-0050.38 1.38 6"Co, 137C3 GridY,6), ashalt sam le 21B-97-0060.30 137Cs Grid2,6 ashalt

, samle 21B-97-007 1.32 l"Cs GridY+0.5, 6.5ashalt

, sam le 21B-97-008 2.90 137Cs W,

Grid 4 ashalt

, sam le 21B-97-009 natural activit onl (Y,5 ashalt Grid , sam le 21B-97-010 0.40 60Co, 0.16 137C3 GridX,3 ashalt

, sam le 21B-97-011 0.22 137Cs GridA,4),ashalt samle 21B-97-012 0.31 6"Co, 0.25 137C3 GridX,0),ashalt samle 21B-97-013 natural activi onl GridY,1), ashalt samle 21B-97-014 0.35 137CS GridV,2 ashalt

, sam le 21B-97-015 natural activit onl GridV, 1 ashalt

, samle 21B-97-016 natural activit onl W,

Grid 1 ashalt

, sam le 21B-97-017 natural activit onl GridV,0 ashalt

, samle 21B-97-018 natural activi onl GridW,0 ashalt

, sam le 21B-97-019 natural activit onl GridX,1 as halt

, sam le 21B-97-0200.73137Cs GridA,3), as halt samle 21B-97-021natural activit onl Grid (A,2), concrete sam le 21C-97-001natural activit onl Unaffected Areas Theremaining roomsandareas ofthe'IRFare considered unaffected areas.For these unaffected radiological areas, surveys consisted oflarge area masslin smears ofthe and walls toroughly floor 2meters above the floor,at1m2intervals, floor monitor/surface scan surveys,and contamination surveys offloor drains No areas andsinks. ofcontamination werediscovered in surveys of unaffected areas.

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PC000482/2 B-1

PC000482/2 TABLEOF CONTENTS 1.PURPOSE ANDNEEDFORACTION...........................................B4 2.FACILITY DESCRIPTION, PROPOSED ACTIONAND ALTERNATIVES, AND ADMINISTRATIVE CONTROLS..........................................B4 2.1Facility Description............................................................................ B-4 2.2Proposed Action and Alternatives..........................................B-10 2.3Administrative Controls..............................,..............................B-11 3.DESCRIPTION OF THE AFFECTED ENVIRONMENT.......................B12 3.1Man-Made Environment...................................,,................B-12 3.1.1Radioactive Materials...................................................................B-12 3.1.2Hazardous Materials....................................................................B-14 3.1.3 Transportation................................................B-14 3.1.4Cultural andHistorical Resources..........................<.......................B-15 3.1.5Population andLand Use.....,..................................................B-15 3.1.6 Noise....................................................................B-15 3.1.7Aesthetics........................................................................B-16 3.2Natural Environment.................................................................B-16 3.2.1Topography, Geology andSeismicity................. .................B-16 3.2.2Climate andAir Quality ..............................................................B-17 3.2.3Hydrology.............................................................................B-19 3.2.4Biology ...................................................B-20 3.2.5Socioeconomics andEnvironmental Justice.........................................B-21 4.POTENTIALENVIRONMENTAL CONSEQUENCES OF PROPOSED ACTIONAND ALTERNATIVES................................................B-21 .

4.1HumanHealth Effects....................................................................B-21 fo C

4.1.1Hazard Identification.........................................................B-21 4.1.2Potential Exposures................................................B-22 4.1.3Transportation...................................................................B-23 4.2Waste Disposal......,................................................................B-23 4.2.1Hazardous Waste ....,............,=...........................B-23 4.2.2Low-Level Radioactive andMixed Waste..............................................B-23 4.2.3Non-Hazardous Solid Waste.....................................................B-24 4.3Noise...................,..................,,..........................B-24 4.4Seismicity...........................................................................B-24 Quality 4.5~Air ............................................................................B-24 4.6Regulatory Issues................=............................................B-25 4.7Areas NotAffected...........................................................................B-25 4.8Cumulative Effects..............................................,.....................B-25 4.9Alternatives toProposed Action........................................B-27 5.REFERENCES ...................................................................B-27 B2

PC000482/2 g

gyr LISTOF FIGURES Figure B-1-Regional Location......................=............B-5 Figure B-2-GA SiteandSurrounding Uses............................................. B-6 Figure B-3-TRIGAReactor Facility Site and Adjacent GA Structures..........................B-7 Figure B-4-TRIGA Reactor Facility Areas Within Decommissioning PlanScope.............

Figure B-5-TRIGA Reactor Facility, RoomDetail, PlanView.............................B-9 LISTOF TABLES Table B-1-List ofPotential Radionuclides......................................................B-13 Table B-2-Applicabilityof Environmental Statutes and Regulations..., ....................

1 B3

PC 000482/2 APPENDIXB ENVIRONMENTAL REPORT Rh

1. PURPOSE AND NEED FORACTION Asa result ofnuclear research training andisotope production, activities conducted since 1958forthe DOE andits predecessor agency, the A tomic Energy Commission (AEC), and commercialcustomers, the TRIGA* Reactor Facility (TRF) hasbecome contaminated with varyingamounts of radioactive materials andsmall amounts ofhazardous materials. GA decided toshutdown theTRFdueto reduced demand forirradiation services and continuing private industrial development around thesite. Decontamination and Decommissioning (D&D) ofthe TRFwill eliminate thepotential forfuture inadvertent environmental releases.The goal ofthe proposed D&Dactivities istoobtain from the United States Nuclear Regulatory Commission (USNRC) andtheState ofCalifornia -

Department ofHealth Services (CAL-DHS) release ofthe sitefor "unrestricted use." The term"unrestricted use" means that there willbenofuture restrictionsonthe useofthe site, otherthan those imposed bythe City of San Diego zoning ordinances.

2. FACILITY,DESCRIPTION, PROPOSED ACTION AND ALTERNATIVES, AND ADMINISTRATIVE CONTROLS 2.1 Facility Description TheTRFislocated within the General Atomics (GA) Torrey Mesa"Main Site," inSan Diego,CA. GAoccupies approximately 120acres (48 hectares) on two contiguous areas approximately 13miles (21 k m) north of downtown San Diego, California which is situated southwest ofthe convergence ofInterstates 5and805, and approximately onemile &

eastofthe Pacific Ocean. Thetwo locations arereferred toas the "Main Site" andthe W "Sorrento Valley Site',orcollectively asthe GAsite. Figures B-1 through B-5 depict the specific location ofGAandthe TRF.

TheTRFoccupies GABuilding 21and anoutdoor adjacent service yard. The interior of Building21has approximately 7,600 ft2 offloor spaceconsisting ofoffices, three reactor rooms, operating roomsandauxiliary areas. Building 21issurrounded bya 43,800 ft2 fencedservice yard.

TheTRIGAReactor Facilityhashoused three TRIGAreactors, which have been variously usedsince 1958 toprovide controlled neutron andgamma irradiation for diverse laboratory projects.

research W

TheTRIGAMkIReactor, situated inTRF Room21/102, was placed in"Possession-Only-License" (POL)status, under Amendment No. 35to theU SNRC License No. 38,dated October 29,1997 (Ref.5.14), and ispresently inoperable. All T RIGA Reactor fuel elements have been removed fromthe TRIGAMkIReactor pool, andtransferred/relocated tothe TRIGAMkFFuel Storage CanalinRoom21/107. Moreover, a number ofadditional components andhardware items, previouslyinstalled aspart oftheTRIGAMkIReactor Control andInstrumentation systems, have been dismantled, surveyed, andremoved from theTRFfor recycle use; this partial B-4

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PC-000482/2 dismantlement implementing anddisassembly instructions set forth of theTRIGAMkI systems inaplan, which wasprepared, was performed reviewed, by andapproved19 in accordance with the administrative provisions of10CFR50.59.

TheTRIGA MkF Reactor (situated inRoom21/107) was previously placedin "Possession-Only-License" (POL) status under USNRC License No. R-67 (Ref.),as amended on March 22, 1995, andisalso currently inoperable. All reactor fuelelements have been removed from the TRIGAMkFreactor core/shroud andplaced inthe TRIGA MkF Fuel Storage Canal. Thenon-fuel components ofthe TRIGAMkFreactor, including the core support structure, bridgeshroud, beamtubes, andassociated hardware, remainin the reactor pool. TheFuel Storage Canal portion ofthe TRIGAMkFreactor pool currently houses allofthe SpentNuclear Fuel (SNF) elements previously removed from theTRIGA MkI,MkF andMkIII Reactors. Allrequired protection barriers andsecurity systems, including those necessary for High Enriched Uranium (HEU) (i.e.,electrical service, domestic watersupply) storage, are maintained inaccordance withGA'sphysical protection plan.

All TRFbuilding utility services required for facility operation andmaintenance under POL conditions are active.

TRFbuilding air ventilation andHEPA-filtered building exhaust systems, airsupply compressors, andlicense-required radiological monitoring instrumentation systems arein normal continuous operation.

Allmanually-actuated andautomated fire alarm/suppression systems intheTRF are operational.

All installed TRFsecurity andradiological alarm systems are active and normal.

Independent waterdemineralization systems serving theTRIGAMkI and TRIGA MkF Reactors remain fully operational.

A commonforced water cooling system serving both theTRIGAMkIandMkF Reactors remains fully operational.

2.2 Proposed Action andAlternatives TheProposed Action andthe Alternatives areasfollows:

a Proposed Action (DECON)-Decontamination andDecommissioning of theTRF followed bythe release ofthe sitefor unrestricted usebythe USNRC.

e Alternative 1 (SAFSTOR)-In safe storage, the TRFisplaced andmaintained ina condition that allows ittobesafely stored andsubsequently decontaminated toa level permitting release ofthe property bythe USNRC.

e Alternative 2 (ENTOMB)-In entombment, radioactive materials areencased ina structurally long-lived material suchas concrete. The entombed structureis appropriately maintained andsurveillance iscontinued until the radioactivity decaystoa level permitting release ofthe property bythe USNRC.

Implementation ofthe Proposed Action will involve performance ofthe following tasks:

B10

PC000482/2 1 decontaminate orpackage aslowlevel waste (LLW) the TRIGAMkIReactor

( 2.2.

2.2.2 Dismantle, components, tank andpit.

Decontaminate anyremaining contaminated areas except theTRIGAMkF Reactor and Control Rooms.

2.2.3 Reroute required utilityservices toisolate the TRIGAMkFReactor and Control Rooms.

2.2.4 Obtain USDOE approval andship thespent TRIGAfuel fromtheTRIGAMkF Fuel Storage Canal. DOE is contractually committed to take spent fuel atINEEL butthe actual shipping date isuncertain. TheDecommissioning Plan hasbeen m odified to describe the arrangements andshipment "schedule" both the in Appendix and in Section 2.3.2. The shipping schedule andthe time requiredto complete Phase 2 oftheplan, inturn, determines the date for thelicense termination request.

2.2.5 Dismantle, decontaminate orpackage asLLW,the TRIGAMkFcomponents, tank andpit.

2.2.6 Ship the LLW generated asaresult ofdecommissioning activities.

2.2.7 Perform finalradiological survey andsubmit a request tothe USNRCfor release ofthe subject areas for unrestricted use and the t ermination of the T RIGA Reactor licenses.

2.3 Administrative Controls 2.3. 1 Tominimize the risksofinadvertent exposure, contamination and/or radioactive releases, all Decommissioning will be operationsimplemented inaccordance with appropriate technical andadministrative controls, including:

' 2.3.2 Performance ofall project work pursuant toapproved proceduresimplementing USNRC andCAL-DHS-approved Decommissioning Plan. GAwill continueto be responsible for assuring anddemonstrating compliance with USNRCandCAL-DHSlicenses, aswell as other applicable federal, stateorlocal laws, regulations, licenses and/or permits.

2.3.3Utilization ofcontainment structures, tents, andbags under negative pressure and/or appropriate contamination barriers toisolate operation areas aridprevent inadvertent release ofcontaminants.

2.3.4Employment ofmonitored, high-efficiency particulate air (HEPA) filtrationsystems forair ventilation inthe work areas.

2.3.5 Maintenance ofemergency ventilation, power, andsupplies, asappropriate.

2.3.6Application ofALARAprinciples such asemphasizing radiation protection for workers and the general public, employing personnel andarea dosimetry, using personal protective equipment andclothing andconducting work through approved Radiological Work Authorization Permits. Theterm"ALARA"meansaslowasreasonably achievable, taking into account the stateoftechnology and the economics ofimprovements inrelation tothe benefits topublic health andsafety, andother societal andsocioeconomic considerations.

GAHealth Physics staff would have the authority tostop anyoperations which they believe mayinvolve unusual, unnecessary orexcessive radiological risk tothe worker, the public orthe environment.

(g4 2.3.7 Maintenance ofindustrial security access control tothe work site andfacility, torestrict

'ST unauthorized individuals from the work area.

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PC-000482/2 2.3.8 Integration GA of Quality Assurance andGAHealth andSafety requirements into Decommissioning Projectdocuments. (j

3. DESCRIPTION OF THE AFFECTEDENVIRONMENT 3.1ManMade Environment 3.1.1 Radioactive Materials Thepublic iscontinuously exposed to radiation fromnatural sources; primarily from cosmic radiation;external radiation from natural radioactive material intheearth andglobal fallout; andinternal radiation fromnatural radioactive materials taken into the body via air, water, andfood. Thepublic receives andaccepts therisks associated with radiation exposures from medical X-rays, nuclear medicine procedures, andconsumer products. On average, amember ofthe public inthe United States receives approximately 300mrem/yr from natural sources ofradiation; approximately 50mrem/yr from medical procedures; and approximately 10mrem/yr from consumer products, for atotal of360mrem/yr (Ref. 5.1).

InSanDiego, atelevation near sealevel, thebackground radiation from natural sources is about 240mrem/yr andthe total background radiation isapproximately300mrem/yr.

Residual radioactive contamination resulting from past TRIGAReactor operations is contained within the TRFBuilding which iscontinuously monitoredunder an extensive surveillance andmaintenance program. Existingmonitoring data, historical information, andcurrent surveys indicate that TRFbuilding contamination iscomprised ofcertain fission product andactivation product nuclides. Some 'IRF reactor components are contaminated with radionuclides. This is primarily the result of deposition and adherence of airborne andwater-soluble contaminants. Theradionuclideslisted inTable B-1potentially exist inthe TRF.

Radioactive atoms undergo spontaneous nuclear transformations and release excessenergy inthe form ofionizing radiation. Such transformations are referred toas radioactive decay.

Asa result ofthe radioactive decay process, oneelement istransformed into another; the newly formed element, called a decay product, will possess physical and chemical properties different from those ofits parent, andmayalso beradioactive.A radioactive species ofa particular element isreferred toasa radionuclide orradioisotope. Radiation emitted byradioactive substances cantransfer sufficient localized energy to atoms to remove electronsfrom the electric field oftheir nucleus (ionization). Inliving tissue this energy transfer candestroy cellular constituents andproduce electricallycharged molecules (i.e., free radicals). Extensive biological damage canlead toadverse health effect (Ref.

5.3). Theadverse biological reactions associated with ionizing radiation, andhence with radioactive materials, are skin injury, cancer, genetic mutation andbirth defects (Ref. 5.4).

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PC-000482/2 Table B1: List ofExpected Radionuclides Nuclide HalfLife Decay Notes (yr) Mode "C 5730. p- AP; from n-activation ofgraphite reflectorstructure (TRIGA Mkionly) 54Mn 0.86 e, y AP; shortlived specie; from nactivation ofSShardware 55Fe 2.73 e AP;from n-activation ofSShardware "Co 5.27 E,y AP; from nactivationofSShardware; expected tobepredominant AP specie present 59Ni 76000. e y

, AP; from n-activation ofSShardware "Ni 100. p- AP; fromnactivation ofSShardware "Sr 29.1 p- FP;probableFP constituent; activity expected tobeproportional to that of"70s "4Nb 20000. .p~,

y AP; unlikely APinventory constituent; possible from n-activation of SShardware, if Nbimpurities are present "Tc 213000. p,y FP,andminor APinventory constituent; possiblefrom nactivation of

( "5Sb 2.76 p,y SShardware, FP; relatively ifMoimpurities short-lived specie arepresent "4Cs 2.07 p,y FP;minor FPinventory constituent

'37Cs 30.17 p,y FP;expected tobepredominant FPspecie present "4Ce 0.78 p,y FP;shortlived specie m2Eu 13.48 p,p+, e y

, FP,andminor APinventory constituent; possible fromnactivation of concrete, iff Euimpurities exist inbiological shield structure Symbols/Abbreviations: p- = Beta p+ = Positron e = Electron Capture y = Gamma-Ray AP = Activation Product FP = Fission Product Radionuclide values HalfLife andDecay Modeinformation used above are taken from Ref. 10.15.

Thelist ofexpected provided radionuclides above isbased onthe assumption that operations oftheTRIGAMark IandMark F have Reactors resulted inthe activation neutron ofreactorcorecomponents and other integral hardware orstructural members which are situated adjacent orinclose to, proximity the to, reactorcore during operations. Specific items which areconsidered tohave beenexposedtoneutron include activation composed materials ofaluminum, steel, stainless-steel, graphite, cadmium, lead, andpossibly concrete others.

Based onearlier andexperience studies gained insimilar research reactordecommissioning projects, calculations andreactor-specific which considered measured values for neutron leakage fluence, integrated operating power histories, core/pool reactor andmaterial configurations, structural composition ofexposed poolstructures, neutron of activation beyond materials theconcrete shield liner/biological structure (i.e.,into surrounding soil volumes) isnotexpected foreither the TRIGAMarkInorMark F Reactors.

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PC000 482/2 Major types ofionizing radiation include alpha particles, beta, andgamma orX-ray radiation. Alpha particles expend their energy inshort distances andwill notusually 93 penetrate the outer layerofskin. Alpha particles represent a significant hazard only when taken into the body, where theirenergy iscompletely absorbed bysmall volumes of tissues. Beta particles constitute external hazards if theradiation iswithin a fewcentimeters ofexposed skin surfaces andifthebeta energy isgreater than 70keV. Internally, beta particles deposit much less energy tosmall volumes oftissue and, consequently, inflict muchless damage thanalpha particles. Gamma radiation areofthe mostconcern as external hazards.

3.1.2Hazardous Materials Based on preliminary surveys andinspections ofthesubject workareas, thespecific hazardous materials ofconcern interms ofpotential exposure to project workers, on-site GAemployees andoff-sitepersons are elemental lead, cadmium andasbestos.

1 Elemental 3.1.2. Lead-The predominant hazardous material inthe TRF,interms ofmass,is elemental lead (used primarily in various radiation shielding applications). Mostlead contained inthefacility consists ofsolid, non-dispersible bricks, fittings, liners and weights. Leadisa cumulative poison. Increasing amounts canbuild upinthebody eventually reaching apoint where symptomsand disability occur. Theeffects ofexposure tolead dust through inhalation andingestionmay not develop quickly. Symptoms may include decreased physical fitness, fatigue, sleep disturbance, headache, aching bones andmuscles, constipation,abdominal pains anddecreased appetite. Lead canalso cause irritation tothe skin andeyes. These effects arereported tobereversibleif exposure ceases. Systemic effectsarepossible ifa long-term exposure occurs and birth defects 3.1.2.2 have been reported.

Asbestos-Asbestos ispresent inTRFconstruction materials (e.g., floor tiles, roofing

(

material). Asbestos isnotahazard unless itis "friable," that isinpowder orfiber form.

Inhalation ofthe fiberscancause asbestosis andlung cancer. Gastrointestinal cancercan becaused byingestion. Asbestos found tobepresent inthe TRFwillbe removed bya licensed asbestos abatement contractor.

2.3Cadmium-Cadmium 3.1. ispresent intheTRF intheformofmetal foil. Inhalation or ingestion ofcadmium dust orfumes canaffect the respiratory system, kidneys,prostate andblood Symptoms are: pulmonary edema, dyspnea, cough, tight chest, substemal pain, headache, muscular chills, aches, nausea, diarrhea, anosmia, emphysema.

3.L3 Transportation Themain roadways inthe vicinityofthe GAsite are shown onFigure B-2. They include Genesee Avenue beyond the southern boundary, John Jay Hopkins Drive beyond aportion ofthe western boundary, North Torrey Pines Roadfurther tothe west,andInterstate 5 to the east. Genesee Avenue isasix-lane primary arterial. North Torrey Pines Roadnorth of Genesee Avenue isasix-lane primary arterial. North ofScience Park Road, North Torrey Pines Roadbecomes a four-lane primary arterial. John JayHopkins Drive isa four-lane collector streetwhich connects Genesee Avenue with North Torrey Pines Road.

TheGA site isgenerally accessed fromtheInterstate 5 freeway, exiting on Genesee Avenue andtraveling west,turning north onJohn JayHopkins Drive andeast onGeneral Atomics Court. Thesite canbeentered through twoentrances shown onthe map(Figure B-2) from General Atomics Court andfrom John Hopkins Court. Traffic ontothe site is controlled byaguard posted ataguard station and bypersonnel atanoffice reception area.

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PC000482/2 Off-hour access isthrough akeycard gate atthe south entrance.Thenearest entrance tothe

() GA site isapproximately 1,500 (457 ft. m)fromtheTRF.

3.1.4 Cultural andHistorical Resources No significant archeological orcultural resources have been found insurveys ofthe GA site. The mentions nohistorical structures orsites within theboundary ofthe plant.There isa state park, called Torrey Pines State Park, located onemile to thenorthwest ofthe site, which contains a unique species ofpine tree.

Nohistorical, archaeological orcultural properties arebelieved tobeunder consideration on ornear theTRF.

Population 3.1.5 andLand Use Thesite islocated within theTorrey PinesMesa area andiscurrently zoned SR(Scientific Research). TheUniversity Community Plan designates open space andscientific research land uses for the site. Land usessurrounding the GAsite include scientific research and development parks to the north and to the eastacross Interstate 5,undeveloped land associated with Torrey Pines State Park, research and developmentparks anda hospital to the westand the University ofCaliforniaat San Diego (UCSD) tothe south. Surrounding land uses are shown graphically onFigure B-2.

Thepresent population within theUniversity Census Tract Subregion, in which themain site lies,isprimarily ofanindustrial anduniversity campus makeup,with anestimated daytime total ofupto52,000 people (Ref. 5.5) including about 1,200 GAemployees. The University Subregion contains six Census Tracts. Theimmediate vicinityofthe Flintkote Avenue facilitiesis zoned for industrial activity.

y Estimates offuture growth indicatethat the University Subregioncould haveadaytime total of57,000 people byyear 2000, based f uture Valley

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upon industrialgrowth in the Sorrento area andanincreased number ofstudents on the university campus. Because ofterrain, zoning, andcurrent land use, mostfuture residential development will occur beyond a two mile radius from the site.

Nearby sensitive human populations include:

GAnon-radiological workers; Agouron Pharmaceuticals, located 0.25 miles (0.4 km) tothe west; Children ataday care center, located onJohn JayHopkins Drive, approximately 0.45 miles (0.7 km) tothe west; Scripps Green Hospital, located 0.5 miles (0.8 km) tothewest; UCSDdormitories located about 0.9 miles (1.5 km) tothe south;and Aresidence along Torrey Pines Roadacross from theUCSDcampus (about 1.2 miles or2kmtothe southwest).

Noise 3.1.6 Within GAsite boundaries, the ambient noise environment isgenerated byvehicular traffic, g

jet aircraft, general aviation aircraftandbuilding, heating, ventilating and air conditioning equipment.

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PC000482/2 3.1.7 Aesthetics The TRF islocated againsta backdrop ofcoastal bluffsinterspersed with steeply sloping canyons. Itisintheinterior oftheGA site andisnotvisible to adjacent neighbors.

However, the TRFisvisible ata 0.5 mile (0.8 km)distance from Interstate 5 totheeast andScripps Green Hospital tothe west. TheTRFwill bevisible fromfuture science-related development tothe northeast.

3.2 Natural Environment 3.2. 1 Topography, Geology and Seismicity 3.2. 1 Topography 1.

Site topography istypical ofcoastal SanDiego County, with bluffs andmesas interspersed with cliffs andravines. Themesa runs ina northerly direction paralleling thecoast and rising toa height of400ft. (122m) above sea levelbetween the s iteand the o cean. The topography ofthe siteischaracterizedby steeply sloping canyons andrelatively level mesa areas. Themain GAsite isonTorrey Pines Mesa about onemile east ofthe ocean atan elevation of340ft. (105m) a bove sea level.

3.2. 1.2Geology TheTRFhasbeen builton materials that have been mapped asartificial fill(Ref. 5.6).

Areas immediately adjacent tothe artificial fill are mapped as Ardath Shale, amember ofthe LaJolla Group ofEocene Deposits, that ispredominantly weakly fissile,olive-gray shale.

A cross section on the DelMarquadrangle shows subsurface formations approximately a 750ft. (228 m) northeast ofthe TRF. Based onthis cross section, the Ardath shale deposit (MA inthe TRFarea isapproximately 300ft. (91 m)thick, isunderlain by approximately 500ft. "

(150 m)ofTorrey Sandstone over approximately 250ft. (76 m) ofDel Mar Formation.

3.2. 1.3Soils Soils present atthe TRFhave been mapped asHuerhuero loam, 5 to9 percent slopes and eroded (Ref. 5.7). The Huerhuero series soils have d eveloped in sandy marine sediments andconsist ofmoderately well drained loams that have a clay subsoil. A representative Huerhuero profile hasa surface layer that isbrown andpale-brown, strongly acid and medium acid loam about 12inches (0.3 m) thick, anupper subsurface layer that extends to a depth underlying ofabout brown, 41inches mildly (1.0 alkaline m)loamandsandy clay and is brown, m oderately loam layer alkaline that clay extends a nd toa depth an ofmorethan alluvium 60inches derived from (1.5 m).

metabasic Small areas andmetasedimentary of Las Flores rocks are and Olivenhain included inthe soils area.

and Soils immediately downslope ofthe 'IRF have been mapped asAltamont Clay, 15to30 percent slopes (AtF) Huerhuero loam, 5 to 9 percent slopes and eroded. The Altamont series consists ofwell-drained clays that formed inmaterial weathered fromcalcareous shale. A representative Altamont profile hasa surface layer that isdark-brown andlight olive-brown, over soft moderately calcareous alkaline shale.Small heavy areas clay ofLinne loam about clayloam 8 inches andareas (0.2 where m) thick thesoil that lies isonly 10inches (0.2 m)overshale are included inthe survey area (Ref. 5.7).

There maybelocalized areas ofsoil contamination. Theextent ofcontamination will be defined through the site characterization process.

B16

PC000482/2 3.2.1.4 Seismicity San Diego County hasbeen considered oneofthe moremoderate seismic riskregionsin Southern California. Thehistorical pattern of seismic activity hasgenerally been characterized by broad a scattering of small magnitude earthquakes, whereas the surrounding regions arecharacterized bya high rate ofseismicity with manymoderate-to-large-magnitude earthquakes.

A recent study (Ref. 5.8) estimated the probabilities oflarge earthquakes occurringin California onthe major strands ofthe SanAndreas fault system. Inaddition totheprincipal traces oftheSanAndreas fault, earthquakes occurring onthe other major faults ofthe system (San Jacinto, Imperial, etc.)w ere also considered. The study estimated thatthe probability ofa magnitude 7 or greater earthquake occurring inthenext30years in Southern California (along the Southern SanAndreas, Imperial, orSanJacinto is faults) 0.5orgreater. However, a quake of magnitude close to7 on these fault linesisnot expected tosignificantly impact theGA site because ofintervening distance.

Current information (Ref.5.9) however,indicates the Rose Canyon, Coronado Bank, San Diego Trough, LaNacion, andElsinore fault zones are capable ofgenerating ground strong motion inthe SanDiego area. Possible Richter magnitudes for earthquakes onthesefaults canbeashigh as7.0, 7.5, 7.5, 6.3and7.5, respectively. Passing approximately 3 miles (5km)westoftheGAsite, the RoseCanyon fault isthe nearest active fault.

Recent excavations (Ref. 5.10) showed definite evidence o f Halocene (within the last10,000 years) activity. Itisclear that SanDiego hasexperienced major earthquakes inthe recent geologic past.

1 Thepresence Consultants field ofthree small, reconnaissance local ofthe faults site was confinnedby the Woodward-Clyde (Ref. 5.11). Anunnamed fault inthe northern portion ofthe site trends east towestthrough proposed lots 25,26,31, and 32. TheSalk fault ismapped inthe southern portionofthe site andalso trends east to west. A northerly trending fault islocated inthe southeastern area andcrosses theGeneseeAvenue canyon.

All ofthese faults aremapped asbeing overlain byearly Pleistocene formations which have notbeen displaced. Therefore, the faults on-site are notconsidered active.

3.2.2 Climate andAirQuality 3.2.2.1 Climatology TheTorrey Pines MesaandSorrento Valley, aswith mostofSanDiego County's coastal areas, hasa semi-arid Mediterranean climate characterized byhot, dry s ummers andmild, wetwinters. Themeanannual temperature in the p roject vicinityis 610F ( with 33.80C),

summer high temperatures inthe low-90s (500C) andwinter lowsinthe mid-30s (160C)

(Ref. 5.12).

Thedominating meteorologic feature affecting theregion isthe PacificHigh Pressure zone, asemipermanent high pressure cell located over t heP acific Ocean. This high pressurecell maintains clear skies formuchofthe year, drives the prevailing westerly tonorthwesterly winds, andcreates twotypes oftemperature inversions (reversalsofthe normal decreaseof temperature with h that eight) acttodegrade local air quality. Whena buoyant parcelof polluted air rises, itcools byexpansion. Ifthe air around the parcel iswarm,asinan

& inversion, theparcel sinksback downtoward itssource andiseffectively prohibited from

~

dispersing.

air massinthe Insummer, Pacific a marine/subsidence High Pressure zone inversion isundercut isformed byashallow whenthe layer warm,sinking ofcool marineair flowing onshore. This inversion forms over entire t he coastalplain andallows formixing B-17

PC000482/2 below theinversion base at1,100 1,500 ft. (457 m), butnotanyhigher. During the winter offshore flow regime, cold air pools inlowareas andair incontact with the cold ground coolswhile the air aloftremains warm.A nightly shallow inversion layer [at about 800 ft. (244 m)) forms between the twoair masses which cantrap pollutants.

Inthesummer, whenthe high pressure system isatits mostnortherly extent, eastward-travelingstorm andpressurecenters areblocked, resultinginlittlerain duetofrontal activity.The migration ofthis system toits mostsoutherly extent inthe winter allows the transient stormand pressure centers topass through thearea,resulting inwinter rains in southern California.

Thepredominant pattern is sometimes interrupted byso-called Santa Anaconditions, when high pressure overtheNevada-Utah area overcomes theprevailing westerlies, sending strong, steady, hot, dry winds east over the mountains andouttosea. Strong Santa Anas tend toblow pollutants outover the ocean, producingclear days. However, atthe onset or breakdown ofthese conditions or if theSanta Anaisweak,air quality maybeadversely affected. Inthese cases, emissionsfrom theSouth Coast AirBasin tothe north areblown outover the ocean, andlowpressureover BajaCaliforniadraws thispollutant laden air masssouthward. As thehigh pressure weakens, prevailing northwesterlies reassert themselves andsend this cloud ofcontamination ashore inthe SanDiego Air Basin. There isapotential for such anoccurrence about 45days ofthe year, butthe region isadversely impacted ononly about five ofthem. Whenthis impact does occur, the combination of transported andlocally produced contaminants produces the worst air quality measurements recorded inthe SanDiego basin.

Local 3.2.2.2 Winds andDispersion Data Theprevailing daytime wind direction iswesterly, althougheasterly windsas almost as commonduring the winter months. During the day, thewesterly winds developing from the Pacifichigh-pressure system are reinforced bythe sea-landbreeze caused bythe Pacific Ocean resulting instronger average wind velocities[6to9mph(10 to15 km/h)) than from the easterly land breeze [1to7 mph(1.6 to 11.6 km/h)). Thelandbreezes aremost commonduring stable conditions anddominate the flow toward the ocean during the night andearly morning hours. Theairflow ineither directionischanneled effectively by topographical features ofthe area.Strong winds areinfrequent;the strongest recorded was 51mph(82 km/h) from the southeast in1944.

Data from anon-site meteorological system wereused toprovide atmospheric stabilityand wind frequency results. Theon-site annual wind dataare consistentwith the wind rose data from theMiramar Naval Air Station.

Precipitation 3.2.2.3 Theaverage annual rainfall forthe city ofSanDiego is10.4 in. (26.4 cm), but relatively large variations inmonthly andseasonal totalsoccur. Theaverage monthly precipitation from inJuly.

1940 through Approximately 1970 ranges from 75%oftheannual 2.15 in. cm)

(5.5inFebruary precipitationoccurs from to0.01 in.

November (0.03 cm) through March.

occurring Themaximum in1941.

annual precipitation during thelast60years was24.9 in. (63.3 cm) 3.2.2.4 Air Quality Under stateregulations, the study area iswithin the SanDiego Air Basin (SDAB). The &

concentration ofpollutants within the SDABis measured ateight stationsmaintained bythe C B18

PC000482/2 County ofSanDiego AirPollution Control District (APCD) andtheCalifornia Air Resources Board (ARB). Airq uality at a particular location is a function of the t ypea nd amount ofpollutants being emitted into the air locally andthroughout the basin andthe dispersal rates of pollutantswithin the region. Theair quality monitoring stationnearest the project area islocated in a school ground atNinth andStratford Court inthe City ofDel Mar. This is four miles (6.4 km) north ofthe site. Air quality measurements are expressed asthe number of days on which air pollutant levels exceed state andfederal clean air standards.

Under federal regulations, the GAfacility islocated inthe southwestern portion ofthe San Diego Interstate Air Quality Control Region. TheEnvironmental Protection Agency (EPA) hasdesignated this region as an"attainment area" for sulfur dioxide andnitric oxides, indicating that theconcentrations ofthese pollutants arebelow thefederal air quality standards. Theregion was classified asa "nonattainment area" with respecttocarbon monoxide, ozone, andsmall suspended particulates (PMio) someyears ago, but inrecent years only ozone f ederal standards have been exceeded.

In1993 atthe APCDmonitoring station in Del Mar, ozone exceeded the standard state on 19days andthe federal standard onthree days. This is characteristic ofthe entireSDAB.

In1992 and1993,themaximum 24-hour measured level ofparticulates less than 10 microns insize inthe SDABwasfound toexceed the state standardon several days.

Annual neither average the 24-hour measured northe PM10 annual levels federal weremarginal with statestandards.

standard for exceeded.

However, PMjo was Hydrology 3.2.3 3.2.3.1 Groundwater TheTRFislocated within the Southwestern portion ofthe Soledad Basin. TheSoledad Basin makes upthe northwestern part ofthe LosPenasquitos hydrographicsubunit andhas notbeen developed for watersupply purposes. No groundwater wells arepresent ator immediately adjacent tothe TRF. Ground water beneath the TRFisapproximately 300 feet below ground surface. Test borings onthe GAsite ranging from approximately 6 to 30 ft.

(1.8 -

9.1 m anygroundwater

)didnotencounter contamination groundwater.

exists under the There iscurrently TRF.Further noreason studies tosuspect that maybeconducted if warranted D&D during activities.

3.2.3.2 Surface Water Based onground surface elevations andsurface drainage patterns, surface run-offfrom the TRFControlled Yard Area currently flows primarily northerly, across paved andunpaved surfaces inthe service yard.

TheTRFislocated within the LosPenasquitos Creek drainage basin. Drainage runs through theSoledad Valley intoLosPenasquitos Creek, which flows tothe northwest and empties into thePacific Ocean. Detention basins andsilt collection structures have been constructed forthedevelopment oftheTorrey Pines Science Park that surrounds and includes theGA site toensure that adverse downstream impacts will notoccur from stormwater run-off.

Surface waterdownstream from thesite cannot beuseddomestically because ofits intermittent flow anddirty condition during periods following rainstorms orheavy run-offs. No freshwater recreation areas exist within thelocal vicinity. Agriculture isnot B-19

PC000482/2 because soils arenotwell suitedforagriculture, precipitation islimited, and prevalent groundwater irrigation.

quality Water (primarily useinthe inPenasquitos vicinity ofthe Valley) islimited site isc onsideredmarginal by ephemeral the or inferior nature of for many (j

streams andthe high suspended solids contentofflow during thewinter.

Floodsdo not represent adanger tothe site asit issituated downstream approximately from the 340ft.

site tothe (103 m)

Pacific above the valley flooronamesa. Also, drainage Ocean isunrestricted. TheTRFis notlocated within a 100-Year Floodzone.

Wastewater collection services are suppliedtotheGAsite bythe SanDiego Department of Public Utilities. Wastewater from the isdischarged site through theCity's sewer system to the Point Lomatreatment plant. Anywastewater released tothe citytreatment system must meetthe requirements ofthe San DiegoIndustrial Waste Discharge Permit.

Biology 3.2.4 Vegetation 3.2.4.1 TheGAsite isprofessionally landscaped. The openspace surrounding the TRFandthe GA site isa combination ofdisturbed/developed lands, several eucalyptus groves andthree distinct types ofnative ornaturalized plantcommunities; coastal mixed chaparral, coastal sage scrub, andsouthern California grassland.

No federally-listed endangered plantspecies are known toexist onornear the GAsite (Ref.5.13).

Themostsignificant natural areas inthe vicinityofthe site as TorreyPines Park, Torrey Pines State Reserve, andLosPenasquitos Lagoon andassociated marsh. These areas are located westand northwest ofthe sitealongthecoast (Figure B-2). Inadditiontoproviding g relatively undisturbed refuge-like the habitats, park andreserve contain a rare species of tipp pine This species isendemic to California, known

~~

pine tree, the torrey (Pinus torreyana). to occur only inSanDiego County andonSanta Rosa Island.

Regional 3.2.4.2 Wetlands Stormwater run-off from the TRFandthe GAsite flows into the LosPenasquitos Lagoon.

TheLosPenasquitos Lagoon andassociated marsh aredesignated by the California Department ofFish andGameasawetland area.Thesaltwater marshandlagoonsupport a diverse fish fauna anda mussel fauna ofabout 20species. ThePacific little-neck cochral andcommon little-neck clamarethemost commonmussel species. A total of approximately 30species ofsalt-marsh plantsoccurs inthe LosPenasquitos Lagoon. The predominant vegetation inthemarsh andlagoon ispickleweed (Solicormia). Solicormia subterminalis occurs inthedrier areas;Solicormia virginica,inthelower-lying areas.

Pickleweed filters outmostofthe suspended material brought inbyupstream drainage.

3.2.4.3 Wildlife A1994 survey ofthe area adjacent tothe TRFconducted byNatural Resource Consultants identified several mammal, birdsandreptile species, with the majorityofthese occurring in the brushland habitats (coastal sage scrub and coastal mixed chaparral).Raptors utilize the grassland andtoalesser extent thebrushland habitats onthe siteforforaging. Raptors are protected inCalifornia andareconsidered sensitive duetothe generaltrend ofdeclining

, populations inmanyspecies andtheir importance inthe ecologicalstructure ofbiological communities. Twospecies observed inthe brushland habitats aroundthe site, black-tailed gnatcatcher (Polioptila melanuria californica) andtheorange-throated whiptail egg (Cnemidophorus hyperythrus beldingi) appear tobeexperiencing declines intheir U B20

PC000482/2 populations in coastalDiegoSan County. Theblack-tailed gnatcatcher isa species of special concern andislisted bythe California Department ofFish andWildlife Service as endangered.

The Torrey Pines Park, Torrey Pines State Reserve, andLosPenasquitos Lagoon and associated marsh area provides habitat for several species ofshorebirds andwaterfowl, as well astwo federally listed endangered species ofbirds, thelight-footed clapper rail (Rallus longirostris levipes) andtheCalifornia least tern(Sterma albifrons browni). These species have been declining because. ofhuman disturbance andwater pollution that destroyed nesting and feeding habitats. TheBelding's Savannah sparrow (Passerculus sandwichensis beldingi), listed bythestate asendangered, isalso associated with the pickleweed habitat ofthe lagoon. It, too, hasbeen declining because of human developments affecting its habitat.Noneofthese unique wildlife species have ever been observed onthe site.

During the biological survey conducted of the adjacent area (Natural Resource Consultants, May10,1994), a total ofthree bird species were observed onthe site. These include the house finch (Carpodacus mexicanus), common raven (Corvus corax), andmourning dove(2enaida macroura). A singlefence lizard (Seeloporus occidentalis) wasalso observed. There arenowildlife species recognized asrare orendangered byanyresource protection agencies known tohabitat within the TRF boundary.

3.2.5 Socioeconomics andEnvironmental Justice Thesocioeconomic environment ofthe GAfacility consists of a well-established, diverse, middle-income community consisting ofresearch institutions, a medium-sized university, light industry, tourism, andresidences. Thesetting isattractive, with the coastline, Torrey Pines Park, andVillage ofLaJolla nearby. Theroad system isadequate with both interstate

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highways andsecondary roads. GAoperations donotconstitute a large percentage ofthe area's economy.

4. POTENTIALENVIRONMENTAL CONSEQUENCES OF PROPOSED ACTION AND ALTERNATIVES This section discusses the potential direct andcumulative effectsofthe proposed action on human health andthe environment.

4.1 HumanHealth Effects Types ofexposures that could lead tohuman health effects considered inthis reportare worker andoff-site exposures tohazardous chemicals orradioactive materials during routine activities orpotential accidents onsite, orduring a transportation accident off-site (involving hazardous orradioactive waste removal). This section identifies anddiscusses potential hazards that mayaffect workers on-site orpeople off-site during normal orroutine TRFDecommissioning activities. Impacts ofthehazards relative tohuman health and safety are summarized inSection 4.1.2.

4.1.1 Hazard Identification During the initial site characterization andthe final site survey, site workers would be taking readings andmeasurements ofanycontamination using direct reading instruments andsampling techniques. Hazards during this workaremostly those involving external B-21

PC000482/2 radiation, inhalationofhazardous orradioactive materials, ordermal contact with these 6 materials.

Forthe Decommissioning activities, thekeyhazards would involve external radiation, inhalation of hazardous orradioactive materials, ordermal contact with those materials during decontamination, dismantling, packaging anddisposal ofreactor andancillary equipment, the TRF structure, andcontaminated soil (ifnecessary).

Generally, the Decommissioning steps described inSection 2ofthe Decommissioning Plan could involve the hazards as itemized below:

1 Hazards-Hazards

4.1.1. include

e External radiation for workers working around radioactively contaminated equipment andmaterials.

e Dermal contact with both radioactive and hazardousmaterials.

a Inhalation ofanyhazardous orradioactive materials.

e Possible confined spaces intents, bags orsmall rooms with oxygen associated content andasphyxiant concerns.

a Heavy equipment movement dangers.

Note: Noflammables orexplosive materials areexpectedto bepresent.

4.1 1.2Controls-For workers, project procedures andconformance with GA licenses and regulatory requirements including but notlimited to:

e Radiological WorkPermits, WorkAuthorizations, andHazardousWork Authorization procedures, asrequired; a 29CFR1910.120 requirements for PPE,air monitoring, workzonecontrols, medical surveillance andbio-assay program, personnel training, emergency response, and health andsafety plan; a personal dosimetry per10CFR20; a confmed space entry procedures per 29CFR1910.146; a HEPAfilter removal ofcontaminants; a dust filterremoval ofcontaminants.

4.1.2Potential Exposures Thecollective dose equivalent estimate toworkers for the entire Decommissioning project is~20person-rem. Thedecommissioning tasks will takeapproximately 2 years. Total person hours involving radiological exposure isestimated tobe6,000 hours.

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PC000482/2 Thepotential exposures tothepublic asa result ofdecommissioning activities and gg radioactive waste shipments isestimated to benegligible. This isconsistent withthe 6W estimate given Impact Statement for the on "reference decommissioning research reactor" ofnuclear inthe"Final facilities" Generic (NUREG-0586)

Environmental (Ref.5.16).

The estimated dose the to public during decommissioning (DECON) andtruck transport transportation of radioactivewaste from the "reference research reactor" asgiven inthe Final Generic Impact Statement is"negligible (less man-rem)."

than 0.1 Theanticipated potential exposurestothe public after licensetermination isalsonegligible.

Thesite willhave been' released tounrestricted use, w ithallareas having been remediated tolevels nottoexceed 5 pR/hrabove background andmeeting thesurface contamination criteria given inU.S. NRC Regulatory Guide 1.86.

4.1.3Transportation Theprimary project impactsto the environment duetotransportation could occurwhen shipments ofwaste travel from the site. Transportation would beconducted inaccordance withapplicable USDOT,USEPA, and USNRC regulations. During suchtransport, hazardous andradioactive materialswould beeffectively packaged toprevent significant radiation external to thetruck. Thus, the primary impacts areaccident risk and emissions/noise from the trucks themselves.

Thetruck route into orfrom theGAproperty coming from orgoing toSanDiego isalong Genesee Avenue westfrom the Interstate 5 freeway, then alongJohn J.Hopkins Drive to General Atomics Court tothe gated GAentrance. This entire route from Interstate 5 tothe GAgate covers adistance ofabout 1-mile.

pgg4 Truck site.

shipments During ofconcern consist TRF Decommissioning ofhazardous activities, waste and radioactive waste short-term transportation leaving the would effects T include employee trips, andless which than occur 12truck under for existing hazardous conditions, a small number andradiological wastetransfer.

of contractor trips, trips Traffic, circulation and parking effects areexpected tobeminor duetothe small increase in trips andtheshort duration ofthis action andwouldnotsignificantly impact the surrounding roadways.

4.2 WasteDisposal 1 Hazardous 4.2. Waste Small amounts ofsolid andliquid hazardous wastefrom TRFDecommissioning activities would beaccumulated insatellite accumulation areas. Afteraccumulation forupto90days, the wastewould betransferred byalicensed contractor toauthorized off-sitecommercial treatment anddisposal facilities orrecyclers. TheHazardous Only waste will beincluded aspart ofthe regular"milk run" shipments made byGA'ssubcontractor.

4.2.2Low-Level Radioactive andMixedWaste Low-level radioactive waste, including anycontaminated soil, would bepackaged in accordance withthe Nevada Test SiteWaste Acceptance Criteria. Liquid waste isfilteredor solidified andsolid wasteiscompacted, whenever possible, inaccordance withthe appropriate regulations. Thewaste would beshipped toUSDOE's Nevada's TestSitefor disposal.

Low-level radioactive waste generated during the TRFDecommissioning areexpected to consist oftwo (2) shipments (approximately 150ft3) ofirradiated hardware requiring a B-23

PC000482/2 Type B container such asthe 10-142cask, andfour (4) truck shipments (approximately 3850 ft3)of"strong tight" containers.

Mixed Waste generated during theTRFDecommissioning areexpected to consist of primarily activated/contaminated leadandcadmium. Estimated volumes ofactivated/con-taminated lead andcadmium are45cubic feet lead and5 cubic feet cadmium. General Atomics expects tomake one(1) shipment toEnvirocare todisposition these wastes.

4.2.3NonHazardous Solid Waste TRFDecommissioning activities willgenerate uncontaminated construction debris which would besenttoalocal sanitary landfill.

4.2.4Spent TRIGA FuelElements GAassumes that allofthe spentTRIGA Reactor fuel elements canbeshipped in5off-site transport trips, utilizing theGeneral Electric Co.Model No.2000shipping caskor appropriate equivalent package.

4.3 Noise During TRFDecommissioning noise will begenerated byequipment activities, suchas jackhammers, scabblers andconcrete saws. Backhoes and other heavy equipment could also beused for partial dismantling activities.

On-site workers will beoutfitted withear protection devices. The closest off-site business isAgouron Pharmaceuticals, Inc. which isapproximately0.25 miles away. Noise from A TRFDecommissioning activities would notimpact employees or off-site businesses. W 4.4 Seismicity TRFDecommissioning activities would involve the removal ofsurface contamination or possibly structural dismantlement activities. Anydismantlement plans and specifications would bereviewed bya structural engineer toassure that activities would not render the TRFbuilding structurally unsafe, should anearthquake occur. Decommissioning activities would notincrease the risk toTRFworkers during a seismic event.

4.5 AirQuality Several Decommissioning-related activitiescould minimally impact air qualityduetoboth mobile and stationary source emissions. A small amount ofmobile source emissions such ascarbon monoxide andnitrogen oxides could bereleased from contractors' trucks and cars. However, theSanDiego AirPollution District doesnotsetthresholds for determination ofsignificant emissions from mobile source emissions. Duetothe temporary nature ofthe truck trips andthe smallnumber, mobile source emissions would below.

Stationary source emissions could be released during decontamination, building dismantlement andsolid remediation butareexpected tobenegligible. Anyreleases from decontamination would occur within theTRF. Hazardous materials would belocated inside the building. Standard asbestos abatement procedures, under theoversight oftheSan Diego County Air Pollution Control District, will beused toremove anyasbestos.

Site workers would beprotected during decontamination andsoil excavation activities through airmonitoring andthe useofPPE andrespirators when required.

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PC-000482/2 Theproposed action isonly a temporary potential source ofair emissions. Negligible amounts ofmobile source, stationary source, andsoil remediation emissions wouldbe produced and would notaffect regional attainment standards.

4.6 Regulatory Issues TableB- discusses the applicability ofvarious state andfederal regulations forthe proposed action.

4.7 Areas NotAffected Theproposed action would notaffect the following areas:

M-The proposed action would increase the compatibility ofGA with other science research activities on-going within theGA site. Future useofthe Building 21site could resultin the addition ofemployees ortenants atGA.

Cultural Resources-There arenocultural resources onthe GAsite.

Aeithst1tice.g--The proposed action would only be visible fromInterstate 5, located approximately 0.5 mile (0.8 km) t othee ast and Scripps Green Hospital, located 0.5mile (0.8 km) to the w est. T he TRF is notcurrently visible to adjacent neighbors. Temporary Decommissioning activities will becompatible with continuing industrial development of thesurrounding areas. Theremaining site would beusedforother industrial-related purposes.

Biology-There are noknown sensitive orendangered species onthe TRFsite.

Hyd.r.gl.ogy-The site elevation isapproximately 340feet above mean sealevel. Itisnotin awetland, norisit ina 100-year flood plain.

4.8 Cumulative Effects No significant cumulative effects areexpected fromtheproposed action, as discussed below:

HumanHealth-The totaldose estimated for decommissioning workers is20person-rem forthe entireproject evolution. This estimate willbeachieved byutilizing ALARApractices including planning of workactivities, utilization of engineered safeguards,and minimization ofexposure times. Thedecommissioning will beconducted under a Work Authorization system using written procedures toensure proper planning, training, and evaluation ofpotential risks. Itshould benoted that a total dose of20person-rem is consistent with18.6 person-rem given inTable 7.3-3 "Summary ofradiation safety analyses fordecommissioning thereference research reactor" ofthe"Final Generic Environmental Impact Statement ondecommissioning ofnuclear facilities"(NUREG-0586)

(Ref. 5.16).

Thedose tomembers ofthe public asa result ofdecommissioning activitiesdescribed in GA'sTRIGAfacility decommissioning plan are expected tobenegligible. Thedominant internal exposure pathway for members ofthe public isinhalation. Thedose tothe public is estimated tobenegligible because access tothe area surrounding thefacility isrestricted andbecause decontamination activities with potential for airborne activitywill beconducted

,, utilizing engineered safeguards such asHEPAequipped enclosures. Further, continued

($&

m,.

operation of thefacility decontamination activities HEPA system conducted within the provides building.

additional Thus, protection potential airborne forall B25

PC000 482/2 TableB2-A licabilit ofEnvironmental Statutes and Re ulations tatute uation vauation ica I ationa nvironmen oicyct eev uation document.

orpotenti environmenimpacts arecontaine in is es a GW n ger pecies ct ocnti itats existin ea ect area, an noa erse mpacts o o "

threatened orendangered species are expected toresult from the proposed action.

as e ans e uations e ro aconisnotoca wi inawean orina ain. o is an i ie co ination c epropos action oesnot orimpact s wi ie nany wayor o mod an bodies ofwater more than10acres In surface area.

arman roection oI e os a on snoa nmeorun ue , o ationa istonc reservaon ere are no iso sites orareas n eocaono e ro a on. o mencan n lan eigiousree om ct epropos a on oesnointe ere wi engto a ve encans to o exercise their freedom.

traditional i an cenic iversc epropos a on noin vewaerways esigna aswi o scenicrivers.

esource an onserva on ecovery ct eproposaction mayinc e egenera on, pacgingan transportaties RCRA ofmixed waste.

ompre ensive nvironmen esponse, yrequr reease reporting wou epeorm ncompance wi es Comensation andLlabiliActCERCLA CERCLA reuirements.

er nsec ci e, ungiciean enticie e propo a onisnoinv in e is on,useorispo o any o ActFIFRA insecticides, funicides orrodenticides.

oxic u stances ontroct estos may eencounter unng operations ic wou e es roe ka edand dis ofinaccordance with TSCA.

ean ir ct estos may e encoun er unngep w c wi containe in o enclosed aces, ckaedanddis edof.

ean aeran ae nn ng ater epropose a on s exp oa su cewaer lesorwaer o su lies. Airemissions would bebelow waminlevels.

oise ontroct seeve s cou a verse ya e wo ers an s wi emi ga y o providing ear protectionfor workers and relocation ofstaff toareas awayfro the activities. The ublic isnot ex ected tobelmacted from the noise.

az ous a en s ranspoon epropos a onw requ re s pmen o raoa vemaena san mixe es (HMTA) wastes. Allwaste willbepackaged and shipped inappropriate containersand dissed ofatlicensed facilities ation mssions ars or azaous e ass t a are app eto icens actities. es Air Pollutants NESHAPS Comliance with emission standard would be demonstrated.

tomicnergy cense requir mplancewe environmen an wo erpro ection es standard.

aiomia nvironmen uaI ct ro a on oes not tn eriscretiona review astate a enc o Iomia ea an aety e, iv. , roposaction mu compywi wo ersaety regu ations. es Ch ter 7.6,Articles 13,14 Iomia ntegratasteanagement ct ransportation o ow everaloacvewasewou require es notification/consultation andmanifest.

iomia eo egu a ons i a , iv. , cense requir omplancew environmen wo er, , a pu ic es Chater 5,Subchter 4,Radiation rotection standard radioactive will benegligible; and, therefore, the potential internal dose tothe public isalso negligible.

Theestimate ofnegligible dose tomembers ofthe public canalso beobtained from the estimate given for thereference research reactor inthe "Final Generic Environmental Impact Statement ondecommissioning nuclear facilities" (NUREG-0586) (Ref. 5.16). InSection 7.3.1 ofNUREG-0586, the dose tothe public asaresult ofdecommissioning operations at the reference research reactor -

including truck transportation ofradioactive waste is-

"estimated tobenegligible (less than 0.1person-rem)." This estimate ofless than 0.1 person-rem includes both internal (from inhalation andingestion) andexternal exposure doses.

Waste Generation-The proposed action could generate approximately 4,000 cubic feet of low-level radioactive waste from TRFDecommissioning activities. TheNevada Test Site is designated for the disposal ofthis waste andhas sufficient capacity toreceive the waste.

Cultural Resources-No cultural resources would beimpacted bythe proposed action.

Popuullion.and.Lanti.le---Only temporary employment for a fewcontractors would be provided bythe proposed action. Noincrease inpopulation would occur. Landusewould notchange.

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PC000482/2 Noise-TRF Decommissioning activities would occur inanindustrial area andwould pgg Aff largely occur significantly within tooff-site GA Building background 21.Theproposed noise levels duetothe action relative would not contribute isolationofthe work site.

Aesthetics-TRF Decommissioning activitieswould notbevisible tomostadjacent site neighbors, with the exception ofthe areasofInterstate 5 andScripps Green Hospital, both located approximately 0.5 miles (0.8 km) away. Following release tounrestricted use, the TRFsite would be usedin amanner consistent with the existing GAsite land usepractices.

Traffic-The temporary contractor andwastetransport trips wouldcontribute an insignificant amountto the average number ofdaily trips designed for Genesee Avenue and John JayHopkins Drive.

-AllTRFDecommissioning activitieswould belocalized; stormwater runoff from exposedareas considered to be radiologically contaminated would becontainedand tested.

Rh-The SanDiego Air Basinisa non-attainment areaforcarbon monoxide, temporary.

ozone,andsmall A small number suspended particulates ofvehicle (PMw).off-site tripswould begenerated during The proposed action shipment is of wastematerials andwould contribute onlynegligible amounts ofthese pollutantstothe basin.

Hyd.rology-No changes to anyland forms would occur andno radionuclides or hazardous materials would bereleased tostorm water run-off, resulting from the proposed action.

Bi.ologicd Resource.s-No biological resources havebeen identified on theTRF site; moreover, TRFDecommissioning activitiesare notexpected toeffect off-site biological resources.

4.9 Alternatives toProposed Action This alternative poses essentially the samepotential risks andenvironmental impacts as the proposed project, but potentially for a much greater period oftime. This alternative would necessitate continued surveillance andmaintenance oftheTRFovera substantial time period. During this period, the risk ofenvironmental contammation would continue to exist. Moreover, development ofthe land around the GAsite over the nextfewyears may significantly increase the local employment population density andincrease potential for public exposure. This alternative isnotenvironmentally preferable.

This alternative would necessitate continued surveillance andmaintenance ofthe TRFover a substantial time period. During this period, the risk ofenvironmental contamination would continue toexist. Moreover, development ofthe land around theGA site overthe nextfewyears maysignificantly increase thelocal employment population density and increase potential for public exposure. This alternativeis notenvironmentally preferable.

5. REFERENCES 5.1 National Council on Radiation Protection andMeasurements (NCRP). lonizing Radi.aation E. Report No.93.1987.

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PC0'00482/2 5.2 Walker, F.W., Perrington, J.R.,andFelner, F.Nuclidesan11.Isgtop.es. General Electric Company. 14th Edition. 1989.

5.3 U.S. EPA. "Risk Assessment Guidance forSuperfund, Volume 1 HumanHealth Evaluation Manual (Part A)." Office ofEmergency andRemedial Response, U.S.EPA, Washington D.C. 1989.

5.4 U.S.EPA. "Risk Assessment Methodology Draft Environmental ImpactStatement for Proposed NESHAPS for Radionuclides." Vol. 1.U.S. Environmental Protection Agency, Office ofRadiation Programs. Washington D.C.

5.5 Source Point. "1990 Census Total Population andHousing Units." SanDiego Association ofGovernments. April 1991.

5.6 Kennedy. "Geology ofthe San Diego MetropolitanArea, California." Bulletin 200A.

1975.

5.7 USDASoils Conservation Service. "Soil Survey SanDiego Area, California." 1973.

5.8 Algermissen, S.T.etal. "Probabilistic Earthquake Acceleration andVelocity for the United States andPuerto Rico." U.S.GeologicalSurvey MapMF-2120.

5.9 Berger, V.AndD.L.Schug, "ProbabilisticEvaluation ofSeismic Hazard intheSan Diego-Tijuana Metropolitan Region," , P.L.

Abbott andW.J.Elliott, Editors, SanDiego Association ofGeologists, 1991.

5.10 Lindvall, S.C.,T.K.Rockwell, andC.E.Lindvall. "The Seismic Hazard ofSanDiego, Revised: Newevidence formagnitudes 6+Halocene earthquakes onthe RoseCanyon fault zone." Proceedings, 4th U.S.Conference ofEarthquake Engineering. May1990.

5.11 Woodward-Clyde Consultants. "Preliminary Geotechnical Reconnaissance ofthe Torrey Pines Science Park." January, 1988.

5.12SanDiego Air Pollution Control District. W.

5.13 City ofSanDiego Planning Department, Environmental Quality Division.Environmental EDQ No.

86-0884. 1986.

5.14 Amendment No.35toFacility License No.R-38(TRIGA MarkI Reactor)-General Atomics (TAC No.M97502), Issued bythe USNRC,dated October 29,1997.

5.15 Amendment No.43toFacility License No.R-67(TRIGA MarkF Reactor)-General Atomics (TAC No.M90380), Issued bythe USNRC,dated March 22,1995.

5.16 U.S.Nuclear Regulatory Commission, NUREG-0586, "Final Generic Environmental Impact Statement ondecommissioning nuclear facilities," August 1988.

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