ML21246A254
| 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 | |
| ML21246A250 | List: |
| References | |
| PC-000482/3 | |
| Download: ML21246A254 (180) | |
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PC-000482/3
'o-S GENERALATDMECB
^
GENERAL ATOMICS GA2175(REV.9/89)
RNECTCONTROLSSW
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.
~"
0 A.J.Welch V.Nicolayeff G.C.BramblettInitialIssue W.O.9009.303.055 APR171997 K.E.Asmussen 4/7/97
> 1
.Greenwood c
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,@/4 GeneralRevisionsto
.C amble t addressNRC comments JAN291999
/'
09009.303.05500 K
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Reva.sed pages 2-23, 2
J.GreenwoodV.Nicolayef yf G.C.Brambe#@ 3-5, 3-11, A-pr38p$L A-8 to addresa NR1$
APR271999
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smusse comments 4/ g7 09009.303.05500 3
.Greenwood V.Nicolayef
. ramb e Revised page 2-17 A&
09009
. 303
. 05500 JUL091999 7h/97 K.E.
musse.y CONTINUE ONGAFORM21751
- SeeListOfEffectivePages m
jTHISDOCUMENTISTHEPROPERTYOFGENERALATOMICS.ANYTRANSMITTAL OFTHISDOCUMENT OUTSIDEGAWILLBEIN
'CONFIDENCE.
EXCEPT WITHTHEWRITTENCONSENT OFGA,(1)
THISDOCUMENT MAYNOTBECOPIEDINWHOLEORINPARTANDWILL BERETURNED UPONREQUEST ORWHENNOLONGER NEEDEDBYRECIPIENT AND(2)
INFORMATION CONTAINED HERElNMAYNOTBE COMMUNICATED TOOTHERS ANDMAYBEUSEDBYRECIPIENT 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 2-18through 2-23 6
2 3-1through 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 10-1through 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 LISTOF 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 2.4.4Manager, Quality Assurance........................<..................................<...2-18 2.5Training Program............................................................................................,.............2-18 2.5.1 General Employee Radiological Training (GERT 4Hour)................,................2-19 2.5.2 Radiological Worker Training (RWT 16Hour)............................................................2-19 2.5.3 Health Physics Technician Training............................................,...2-19 2.5.4 Equipment Operator Training...........................................................................2-19 2.5.5Safety/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 SpaceEntry 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 WasteAcceptance 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 andDecommissioning Documents andGuides..,...............2-22 W
2.8Facility Release Criteria......................................,...,..........222 3.PROTECTION OF THE HEALTHAND SAFETYOF RADIATIONWORKERS AND THE PUBLIC....................................=............................31 3.1Radiation Protection...,....,..,............,.,.,.,..,,.,.,.................=3-1 3.1.1 Ensuring As Low AsIsReasonablyAchievable 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 3.2.2Radioactive 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 MeansforEnsuring that all Equipment,
- Systems, Structures, andSite areIncluded intheSurvey Plan...........,............................,,.....41 4.1.2 MeansforEnsuring that Sufficient DataisIncluded toAchieve Statistical Goals..........4-1
4.2Background
Survey Results.......,........,,.....................,<.,...4-1 4.3Final Release Criteria-Residual Radiation andContamination Levels.......................4-2 4.4Measurements forDemonstrating Compliance with Release Criteria.,....
.......,,.42 4.4.1Instrumentation-Type, Specifications, andOperating Conditions.......,.....,......4-2 4.4.2 Measurement Methodology forConduct ofSurveys..,........,.,........4-3 sh 4.4.3 Fixed Contamination Survey Protocol.<...,....=...............
...,.,.4-3 WF 4.4.4Removable Contamination Survey ProtocoL....,.....=,,,,..................4-4 4.5Methods tobeEmployed forReviewing, 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 APPENDIXA-
SUMMARY
OF CHARACTERizATION RESULTS....=................
A1 APPENDIX B-ENVIRONMENTAL REPORT.............................................
B1 V
PC-000482/2 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, PlanView 1-6 Figure 2-1-TRIGA Mark IOperating Chronology....................................................................2-2 Figure2-2-TRIGA Mark FOperating Chronology
.....................................................................2-4 Figure 2-3-Reactor Decommissioning
...............=...................................2-9 Figure 2-4-TRIGA MarkIReactor......................................................................................2-10 Figure 25-TRIGAMarkFReactor....................................................................................2-11 Figure 26-Decommissioning Schedule....=..............,...................,.............215 Figure 2-7-Decommissioning Organization.........................................................................2-17 LIST OF TABLES Table 1-1-Profile ofTRIGAReactors atGeneralAtomics
.....................................=.......1-7 Table 2-1-List ofExpected Radionuclides....................................................................2-6 Table 2-2-Components withPotential 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 forTRIGA ReactorsDecommissioning Tasks
....3-12 vi
PC000482/2 LISTOF ACRONYM8/ABBREVIATIONS ACPR Annular CorePulsing Reactor ALARA AsLowAsReasonably Achievable ALI AnnualLimit onIntake (see 10CFR20)
AMAD Activity Median Aerodynamic Diameter ANSI American National Standards Institute AP Activation Products APPM GA AccidentPrevention Program Manual ARA Airborne Radioactivity Area(see 10CFR20)
ASME American Society ofMechanicalEngineers ATPR Advanced TRIGA Prototype Reactor CA ConditionalAuthorization CAL-DTSC State ofCalifornia Department ofToxic Substances Control 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 AirMonitor CCR State ofCalifornia CodeofRegulations CDE Committed DoseEquivalent (see10 CFR 20)
CE Conditional Exemption CFR CodeofFederal Regulations cm centimeter cpm countsperminute CPR Cardiopulmonary Resuscitation CTI Cryogenic Technology Inc.
gi D&D Decontamination andDecommissioning W
DAC Derived AirConcentration (see 10CFR20)
DDE DeepDoseEquivalent (see 10CFR20)
DECON Decontamination DNAA Delayed Neutron Activation Analysis dpm disintegrations perminute(measure ofradioactivity)
EBOR Experimental Beryllium Oxide Reactor EDE EyeDoseEquivalent (see 10CFR20)
EH&S GAEnvironment,
- Health, 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 FuelLifetime 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 (GABldg.
23)
HEPA HighEfficiency Particulate Air(Filter)
HEU HighEnriched Uranium HP GAHealth Physics Department HPGe HighPurity Germanium Detector vii
PC000482/2 a
HTGR HighTemperature Gas-Cooled Reactor WWA LLW Low-Level Waste
- ~
LSA LowSpecific Activity (see 49CFR)
LSNC GALicensing,
- Safety, andNuclear Compliance Division MAP MixedActivation Products MDCR Minimum Detectable Count Rate MFP Mixed FissionProducts micro-R micro-Roentgen, 10-6 hp MIWP City ofSanDiego MetropolitanIndustrial Waste Program MkF TRIGA Mark FReactor MkI TRIGA Mark IReactor MkIII TRIGAMark 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 andMeasurements NFPA National Fire Protection Association NIOSH National Institute for OccupationalSafety andHealth NIST U.S.
National Institute ofStandards and Technology NPR NewProduction Reactor NQA Nuclear Quality Assurance NTS Nevada TestSite ph NWPF GANuclear WasteProcessing Facility 95 OSHA Federal Occupational Safety andHealth Acts PB Peach Bottom(Nuclear Generating Station) pCi pico-curie, aunit ofradioactivity (2.22 disintegrationsper minute), 10-"
curie PCM Personnel Contamination Monitor POL Possession OnlyLicense PTS Pneumatic Transfer System PVC Polyvinyl Chloride QA GAQuality Assurance Organization QAPD Quality Assurance Program Document R
Roentgen RA Restricted Area(see 10CFR20) rad unit ofabsorbed radiation dose RCRA Resource Conservation andRecovery Act rem Roentgen Equivalent Man(unit ofdoseequivalence, see10CFR20)
RESRAD USDOEComputer CodeforResidual Radioactivity Calculations RM Radiation Monitor RO Reactor Operator RWP Radiological WorkPermit RWT Radiological Worker Training SAFSTOR Safe Storage SD-DHS-HMMD County ofSanDiegoDepartment ofHealth Services Hazardous Materials Management Division SDE Shallow DoseEquivalent (see 10CFR20)
SNF Spent Nuclear Fuel SNM Special Nuclear Material sar c
BAL SS Stainless Steel SV Sievert (unit ofdoseequivalence, see10CFR20) vili
PC000482/2 Sx(s)
Sample(s) 4ggg TEDE Total Effective DoseEquivalent (see 10CFR20)
W$P TFFF TRIGAFuelFabrication Facility (GABldg.
22)
TKF TRIGAKingFurnace TLD Thermoluminescent dosimeter TRDS TRIGA Reactor DecommissioningScope(the partofBldg.
21andassociated yard areacovered inthis Decommissioning Plan)
TRF TRIGA Reactor Facility (GABldg.
21)
TRIGA*
- Training, Research,
- Isotopes, General Atomics TTSL TRIGA Thermal StabilityLab TTSX TRIGAThermal Stability X-Ray Room UC2 Uranium Dicarbide USAEC U.S.AtomicEnergy Commission USDOE U.S.
Department of Energy USDOT U.S.Department of Transportation USEPA U.S.
EnvironmentalProtection Agency USNRC U.S.Nuclear Regulatory Commission WA WorkAuthorization
- TRIGAisaRegistered Trademark ofGeneral Atomics iX
PC000482/2
- 1.
SUMMARY
OFPLAN 1.1 Introduction 1.1.1 Overview Although General Atomics(GA) continues tooffer TRIGA*
(Training,
- Research, Isotopes, General Atomics) reactors andrelated facilities, equipment, materials, andservices, GAhas ceased all TRIGA reactor operationsattheGAmainsite located inSanDiego, CA(USNRC Licenses R-38and R-67). Figure 1-1showstheregional location oftheGeneral Atomics facility; Figure 1-2 depicts theGA site andadjacent surrounding landuses;theTRIGA Reactor Facility (TRF) site andadjacentGA structures areshownonFigure 1-3;theTRF areas tobedecommissioned within thescopeofthis planaredepicted onFigure 1-4andare defined astheTRIGAReactor Decommissioning Scope(TRDS)
Figure 1-5presents aplan viewoftheroomswithin the TRF.
GA hasdecided toshutdownanddecommission the TRIGAReactors duetoreduced market demandforGA'sreactorirradiation services.
The objective ofthis Decommissioning Plan istoconduct 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 oftheTRDSincluding partoftheTRFand partoftheassociated adjacent Controlled Yard areas.TheTRFhashoused three TRIGA
- reactors, whichhavebeenvariously usedsince 1958 toprovide controlled neutronand gammairradiation fordiverse research projects.
The threereactors arereferred toherein as theTRIGAMarkI,TRIGAMarkF,andTRIGAMark III reactors. Itshould benotedthat this Decommissioning Planaddresses onlythe TRIGA Mark IandTRIGAMarkF reactors; a
profile ofthese tworeactors ispresented inTable 1-1. Inasmuch asUSNRCFacility License R-100waspreviously terminated, thedecommissioning of theTRIGAMarkIIIReactor, adjacent rooms,andyardareaswill beimplemented byGA in accordance withtheGASite f$$
Decommissioning Plan(Ref.
10.14);
these activities arenotfurther addressed inthis plan.
C ThisDecommissioning Planhasbeenprepared using the guidance and formatofNUREG 1537Rev.0,Guidelines for Preparing andReviewing Applicationsfor theLicensing ofNon-PowerReactors (Ref.
10.1).
1.1.2Decommissioning PlanProvisions ThisDecommissioning Planprovides thefollowing:
1.1.2.1 A description ofthepresent radiological condition oftheTRFandadjacentControlled Yardareas.
1.1.2.2 A description oftheplanned approach tobeemployed todecommission theTRDS.
1.1.2.3 Descriptions ofthemethods that will beutilized toensure protection ofthehealth and safety oftheworkers andtoprotect theenvironment andthepublic fromradiological hazards associated withthesubject TRDSDecommissioning Project activities.
1.1.2.4 A description ofTRDSphysical security andmaterial accountability controls that will bein place during thevarious phases ofDecommissioning Project activities.
1.1.2.5 Adescription oftheradioactive wastemanagement anddisposal.
1-1
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9 Figure14-TRIGAReactor Facility AreasWithinDecommissioning PlanScope 1-5
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Table11-Profile ofTRIGAReactors atGeneralAtomics Item Description TRIGAMki TRIGAMkF WMMDMM@$WMRM@MWSEMMERMMEMM@h@WhM Classification:
- Research, Water-Cooled, Pool-Type,
- Thermal, PrivatelyOwned Owner:
General Atomics Location:
TRIGAReactors Facility (Bidg.
21),
3550General Atomics Ct.,
- SanDiego, CA92121-1194 Operator Owner Owner Licensee:
Owner Owner Architect/Engineer:
Ralph M.Parsons Co.
FerverDoriand
&Assoc.
Nuclear Design:
Owner Owner Research
&Development:
Owner Owner CoreManufacturer Owner Owner Construction:
Owner Owner Principal Uses:
- Training, NAA, DNAA,Transient Radiation
- Studies, Thermionic Power Development, n-Radiography BMEMEWMMWi8MWMPMSMMMEMMkMWCEREEWWWFWEMW initial Criticality:
5/3/58 7/2/60 DateSecured:
10f2997 3/22/95 USNRCUtilization Facility Lic.
R38 R-67 USNRCFacility Docket 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.
eaSteady State,(nv):
1.40E+13 3.30E+13 owPulsing, (nv):
5.40E+16 1.40E+17 ow Steady State,(nv):
4.50E+12 4.40E+13 4,3,rm,,
- Pulsing, (nv):
1.80E+16 1.90E+17 Specific Power(kW/kg 2syy 80 420 A
CorePowerDensity, (kW/I):
3.5 20 W
FuelMaterial:
UzrH,.o orUzrHu UzrH,.e FuelUranium
- Content, wt%U:
8.5 8.5, 30 Uranium Enrichment,
%asU:
20%
20%,70%,93%
FuelElement Geometry:
Cylindrical
- rods, 1.42:
(3.61 cm) dia.
x15" (38.1cm)activelength Element Cladding Material:
1100F Alor304SS 304SS Element Cladding Thickness:
1100F A1:0.03" (0.076 cm);
304SS:0.02" (0.051cm)
CoreConfiguration:
Circular array Hexagonal array CoreActive Height::
15"(38.1 cm) 15" (38.1 cm)
No.ofAvailable FuelPositions:
91 121 Coolant:
Light water Light water Moderator:
Light
- water, 2rH Light
- water, zrH Reflector:
Graphite Water NOTE-Theprofile aboverelates tothegeneral characteristics ofthereactors during therespective periods ofoperation.
inthe courseof operations, bothofthereactors weremodified toaccommodate utilization ofthefacility b reactor users; suchmodifications werecarried outbytheimplementation ofappropriate changes tothecorresponding Technical Speci
- cations, orbyapplication oftheprovisions of10 CFR50.59.
1-7
PC000482/2 1.1.2.6 A description ofTRDSphysical security andmaterial accountability controls that will be g@
inplaceduring thevarious phases ofDecommissioning Projectactivities.
5$9 11.2.7A description oftheradioactive wastemanagement anddisposal.
1.1.2.8 A cost estimate fordecommissioning theTRDS,andthesource offunding forthese activities.
1.1.2.9 A schedulefor the subject TRDSDecommissioning Project.
1.1.2.10 A
description of theQuality Assurance Programapplicable to theTRDS DecommissioningProject.
1.1.2.11 A description ofthe Training Program tobeestablished forpersonnel performing work insupport oftheTRDSDecommissioning Project.
1.1.2.12 AnEnvironmental Report concerning theexpected impact ofperforming theactivities involved intheTRDSDecommissioning Project.
1.2 Background
M General Atomics Theproperty, onwhich issituated theGeneral Atomics TRIGA ReactorSite andFacility, wasacquired in1956fromtheCityofSanDiego, aspart of a~290acre(~117 hectare) tract,by theGeneral Dynamics Corporation, withthe expressed purpose ofthe (g$
establishment oftheJohnJ.Hopkins Laboratory forPure& Applied Science, later named General Atomic Division oftheGeneral Dynamics Corporation. One ofthefirst goals of thenewly-established General Atomic Division ofGeneral Dynamics was the development ofanewfamily ofsmall nuclear
- reactors, whichcould beutilized in both industrial and academic applications fortraining,
- research, andisotope production.
Between 1957and 1966three TRIGAreactors wereconstructed intheTRIGAReactorFacility (TRF),
although thisDecommissioning Planaddresses thetwo reactors whichare currently licensed (in Possession-Only-License, POL,status),
i.e.,
theTRIGAMarkIand Mark F
reactors.
Figure 1-5showsthecurrent TRFconfiguration.
Thespecific TRFrooms and yard areas tobeaddressed intheTRDSDecommissioning Project herein arelisted below.
MkIReactor andControl Room,21/102 (~860 ft2area)
Vestibule, 21/102
(~60 ft2area)
- Offices, 21/103-21/104
(~280 ft2area)
- ToolShop, 21/105
(~230 ft2area)
Counting Room,21/106
(~280 ft2area)
MkFReactor Room,21/107
(~870 ft2area)
MkFControl Room,21/108
(~280 ft2area)
Mezzanine above 21/108
(~280 ft2area)
Mezzanine above 21/109
(~280 ft2area)
MkIControlled Yard
(~1100 ft2area)
MkFControlled Yard
(~1440 ft2area)
Plusadditional portions oftheCooling TowerControlled Yardandother outdoor areas associated withtheTRFCooling Towerunderground piping system.
1-8
PC000482/2 Figure 1-4shows theTRDSarea, which isincluded inthescope ofthis Decommissioning Project.
TRIGA MarkIReactor Aspart ofearlynuclear reactor development
- efforts, General Atomics initiated plans to design,build, andoperate aprototype reactor unit onthecompany's Torrey Pines Mesa site.
Tothis end, inlate 1957,GArequested andobtained a Construction Permit and Utilization Facility License fromtheU.S.AtomicEnergy Commission (USAEC) to authorize thisactivity.
Immediately thereafter, working withtheRalphM. Parsons Company astheArchitect/Engineer, General Atomics proceeded withconstruction ofthe Isotope Reactor
- Building, laternamedtheTRIGAReactor Facility (Building 21),
tohouse thePrototype TRIGAReactor andsupportingsystems(e.g.,
Instrumentation andControl
- Systems, Forced Cooling
- System, WaterDemineralizationSystem, Ventilation/Exhaus
- System, Radiation Monitoring Systems, etc.).
Following building construction andreactor hardware installation, the Prototype TRIGA Reactor wasbrought toinitial criticality on May3,1958.Continuously operational fromthat dateuntil late 1997,thePrototype TRIGAReactor waslater designated as theTorreyPines TRIGAReactor, andlater yet,as theTRIGAMarkIReactor.
AtGA's request, theUSNRCissued anamendment tothe TRIGAMark Iutilization facility licenseon October 29,1997,whichplaced thereactor in Possession-Only-License (POL) status.
TRIGAMarkFReactor InMarch1960,GAsubmitted anapplication tothe USAEC requesting a Construction Permit andUtilization Facility License fortheFlashing Advanced Irradiation Reactor g
(FLAIR).
Thesedocuments wereissued toGAbytheUSAEC andthereafter,working
@r withtheFervor-Dorland Engineering Co.,Building 21was modified bytheaddition of Rooms21/107 and21/108 tohousetheFLAIRReactor andReactor Instrumentation
'~
Control
- Systems, respectively.
This
- reactor, which wasbrought to initial criticality onJuly 2,1960, wascontinuously maintained andoperated byGAfromthat time untilMarch22, 1995,whentheUtilization Facility License wasamended, attherequest ofGA, to authorize Possession-Only-License (POL) activities.
During theoperating
- period, the reactor installation wasdesignated astheAdvanced TRIGAPrototype Reactor (ATPR) and also later referred toastheTRIGAMkFReactor.
Cunent.EgilltLStalu.gi TheTRIGAMkIReactor, situated inTRFRoom21/102, wasplaced in"Possession-Only-License" (POL)
- status, under Amendment No.35totheUSNRCLicense No.R-38, dated October 29,1997(Ref.
10-2),
andispresently inoperable.
Allreactor fuel elements have beenremoved fromtheMkIReactor
- pool, andtransferred/relocated totheMkFfuel storage canal inRoom21/107.
- Moreover, anumber ofadditional components andhardware
- items, previously installed aspartoftheMkIReactor Control andInstrumentation
- systems, have beendismantled,
- surveyed, andremoved fromtheTRFforrecycle use;thispartial dismantlement anddisassembly oftheMkIsystems wasperformed byimplementing instructions setforth
- inaplan, which wasprepared,
- reviewed, andapproved inaccordance withtheadministrative provisions of10CFR50.59.
TheTRIGAMkF Reactor (situated inRoom21/107) was previously placed in "Possession-Only-License" (POL) status under USNRCLicense No.R-67(Ref.
10-3),
as amended onMarch22,1995,andisalso currently inoperable.
Allreactor fuel elements g
havebeenremoved fromtheMkFreactor core/shroud andplaced intheMkFFuelStorage W
Canal.
Thenon-fuel components oftheMkFreactor, including thecore support structure, 1-9
PC000482/2 bridge shroud, beamtubes, andassociated
- hardware, remain inthereactor pool.
TheFuel a
Storage Canal portion oftheMkFreactor pool currently houses alloftheSpent Nuclear f@
Fuel (SNF) elements previously removed fromtheMkI,MkFandMkIIIReactors.
All required protection barriers andsecurity
(i.e.,
electrical
- service, domestic watersupply)
- storage, are maintained inaccordance withGA'sNRC-approved physical protection plan.
AllTRFbuilding utility services required forfacility 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 intheTRFare operational.
Allinstalled TRFsecurity and radiological alarm systems areactive andnormal.
Independent waterdemineralization systems serving theTRIGAMkIandTRIGAMkF Reactors remain fully operational.
A commonforced watercooling systemservingboth theTRIGAMkIandMkFReactors remains fully operational.
1.2.1Reactor Decommissioning Overview Prior toimplementing thedecommissioning actions described
- herein, theTRFwillhave beencleared ofallextraneous
- fixtures, equipment andmaterials, except forthespent TRIGAfuel.
Thespent TRIGAfuel will bestored intheTRIGAMkF Reactor FuelStorage Canal until approval foroff-site shipment isobtained.
Decommissioning oftheMkIandMkFwill beseparate activities butmay be conducted concurrently.
Activities presented below address both reactors.
Summary ofActivities 1.2.
1.1 Reroute services toisolate theTRIGAMkFReactor andControl Rooms.(21/107and 21/108) tomaintain fuel storage support.
1.2.
1.2Dismantle, decontaminate orpackage asLLW,theTRIGAMkIReactor components, tank andpit structures.
Thecriticality equipment pit will besimilarly addressed.
1.2.
1.3Decontaminate anyremaining contaminated areas within theTRDSexcepttheTRIGA MkFReactor andControl Rooms,(21/107 and21/108).
1.2.
1.4Dismantle, decontaminate, orpackage asLLW,theTRIGAMkFReactor components, tankandpool structures except whereactivities wouldpotentially interfere withsafe fuel storage under normal oraccident conditions.
1.2.
1.5Obtain necessary
- approval, andship thestored spent TRIGAfuel fromtheTRIGAMkF Reactor FuelStorage Canal.
1-10
PC000482/2 1.2. 1.6 Decontaminate anyremaining contaminated areas intheTRIGAMkFReactor andControl
(
Rooms andservice yard(21/107 and21/108).
1.2.
1.7 Dismantle, decontaminate orpackage asLLW,theTRIGAMkFReactor components, tank and pit structures.
1.2.
1.8Remove any contaminated soils inadjacent orunderlying locations.
1.2.
1.9Prepare,package, process, andshipallradioactive wastematerials, asappropriate throughout the activities.
1.2.
1.10Perform anddocument thefmalradiological survey(s) andsubmit a request tothe USNRCandState of California for performanceofconfirmatory surveys andsubsequent release tounrestricteduse.
1.2.2Estimated Cost Thecostestimate isconsistent with the scope ofworkcovering D&DoftheMkIandMkF Reactors.
D&DoftheTRDSwill beaccomplished without dismantlement ofthebuilding.
This project costestimate
$5,584K.
Cost breakdown isgiven below.
LSNC 960 MarkID&D 656 MarkFD&D 775 Other D&DTasks 314 Outside Contracts 100 WasteManagement 140 A
WasteDisposal
& Shipping 92 t@
n QA 339 Principal Investigator 339
,E Project Management 638 Independent Confumatory Survey (if required)
.3.0.0 Subtotal 4,653 Contingency 20%
931 Total
$5,584K
- Theestimate forLLWdisposal isbased uponthewastebeing buried attheNTS.
1.2.3Availability ofFunds Estimates ofthecostsofdecommissioning allofGeneral Atomics' USNRC(and State of California) licensed facilities andsites inSanDiego wereprovided inGA'sMay20,1996 submittal toUSNRC(Ref.
10.5) whichincluded theTRIGAReactor Facility.
That submittal also described themethod bywhich GAproposed toprovide financial assurance forfunding itstotal costofthesubject decommissioning.
Byletter dated July 9,1996the USNRCacknowledged acceptance ofGA'sproposal (Ref.
10.6).
1.2.4ProgramQuality Assurance 1.2.4.
1TheGA Quality Assurance (QA) program isdescribed intheGA Corporate Quality Assurance Manual.
TheGAQuality Assurance program meetstherequirements ofthefollowing quality assurance regulations andstandards:
1-11
PC000482/2
- CodeofFederal Regulations Title 10,Part71(10CFR71),"Packaging and Transportation ofRadioactive Material,"
Subpart H,"Quality Assurance."
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 Assuranceprogram wasreviewed andaccepted bythe USNRCTransportation andStorageInspection
- Section, SpentFuelProject
- 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 oftheTRDSisdescribed ina Quality Assurance Program Document (QAPD) prepared fortheDecommissioning ofthe TRIGAReactor Facility.
TheQAPD invokes theuseoftheGAQAManual onthis project andprovides project-specific QArequirements, includingOrganization, andtheQA measures applied toplanning, dismantlement, radiological
- surveys, material shipments, andwastecertification.
Consistent withtheQAManual andUSNRCRegulatory Guide 7.10,Appendix A(Ref.
10.9),
theQAprogram isapplied tothevariousproject activities inagraded
- approach, i.e.,
theQAeffort extended onanactivity is commensurate withits importance tosafety andits impact onproject goals.
Therelationship oftheQAfunction totheDecommissioning organization andtofacility managementisshowninFigure 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.
Theseaudits will beperformed in accordance withwritten checklists bypersonnel whodonothavedirect responsibility for performing theactivities being audited.
Audit reports will bedistributed toresponsible management, uptotheSenior VicePresident level.
Follow-up action will
- betaken, where indicated.
Project technical assessments andQAsurveillances will beperformed frequently to assess compliance withestablished procedures.
These assessments will becoordinated bytheproject QAmanager.
Theassessment teamwill consist ofquality assurance and technical personnel.
Assessments will beperformed inaccordance withawritten plan.
Assessment reports will beapproved bytheproject QAmanager anddistributed tothe project manager andother project personnel.
Follow-up action will
- betaken, where indicated.
Inspections will beperformed onprocured andfabricated items toverify compliance with controlling documents.
Inspections willbeconducted by qualified inspectors in accordance withinspection plans prepared byaquality engineer.
Discrepancies will be documented ina Nonconformance
- Report, whichwillbedispositioned bya quality
- engineer, oraMaterial Review
- Board, asappropriate.
1-12
PC000482/2 Additional assessments ormanagementreviews willbeperformed whendeemed appropriate bytheProject Manager.
Suchassessments mayinclude Readiness Reviews prior tostart ofanewtask, orManagement Assessments.
1-13
PC000482/2 2.
DECOMMISSIONING ACTIVITIES 2.1 Decommissioning Alternatives Theobjective oftheTRDSDecommissioning Project istoobtain regulatory release ofthe portions of theTRFandadjacent contiguous controlled yard
- areas, identified onFigure 1-4,tounrestricted use.Onthis basis safe storage (SAFSTOR) orentombment (ENTOMB) wereconsidered inappropriate toGA'sfuture plans.
SAFSTOR poses essentially thesamepotential risks andenvironmental impacts asthe proposed
- project, but potentially foramuchgreater period oftime.
Thisalternative would necessitate continuedsurveillance andmaintenance oftheTRDSoverasubstantial time period.
During this
- period, therisk ofenvironmentalcontamination wouldcontinue to exist.
- Moreover, development oftheland around theGAsite overthenextfewyears may significantly increase the local employment population density andincrease potential for public exposure.
ENTOMBwouldnecessitate continued surveillance andmaintenance oftheTRDSovera substantial time period.
During this
- period, therisk ofenvironmentalcontamination would continue toexist.
- Moreover, developmentof the landaround theGAsite overthenextfew years maysignificantly increase thelocalemployment populationdensity andincrease potential forpublic exposure.
DECONistheoption chosen.
Totheextent possible, decontamination offacility equipment andstructural components will beconducted tominimize radioactive waste.Structural portions ofthebuilding andsurrounding soils andmaterials, found toberadiologically
- Wik, contaminated and/or activated, shall beremediated, decontaminated, sectioned andremoved orprocessed, asnecessary.
Thiswouldbefollowed byanextensive andcomprehensive final radiation andcontamination survey demonstrating that theTRDS meets theapproved criteria forrelease tounrestricted use.Theresults ofthis final survey will bedocumented inareport whichwill besuomitted totheUSNRCandState along with arequest that the site bereleased tounrestricted useanddeleted fromGA'slicenses.
2.2 Facility Radiological Status 2.2.1 Facility Operating History 2.2.1.1 TRIGAMarkI Startup:May,1958 Shutdown:October, 1997;USNRCUtilization Facility License.
- R38 presently limited to PossessionOnlyLicense (POL)status(see Ref.
10.2).
Max.Power: 250kW(t)
Steady State TheMarkI'IRIGA Reactor wasoriginally constructed byGA toprove theinherent operational safety of(U,zr)H, TRIGAfuelmatrix.
Figure 2-1provides a listing of operations conducted intheGA'IRIGA MkIReactor.
Through October 1997,the integrated powergenerated during operation oftheTRIGAMkIReactor isestimated tobe 84MW-days.
2-1
PC000482/2 TRIGAMark1:
r Startup:
5/58 Shutdown: 10/97 Max.Power: 250kW(t)
Steady State 5/58 Radiation Streaming thruDryTubes 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 HTGRFuelCompact Radiation Flash 2/60 lrradiation ofThermoelectric Experiment 4/60 lrradiation ofCsCell forThermionic Direct Conversion 5/60 initial Experiments withinCore TRIGAKingFumace(TKF) 3/61 ExperimentswithHighHydride SSCiadFuel 3/61 ContinuedCsCellIrradiation 8/61 Irradiation ofSemiconductors 11/61 InitialStearate RuninTKF 2/62 Generation of"ArgasforHCFStack 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 ofF29CapsuleRods 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 Operation ofMultiple 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 TKFPurgeTestExperiments 12/73 Installation of'"B Shieldin Pneumatic Transfer System Terminus 4/74 Automated TKFControlsteminstallation 4/74 FuelHydrolysis Experiments inTKF 2/75 UseofAmBeStarter Neutron Sources 5/75 Irradiation ofHighly)Radioactive Specimens inTKF 4/76 UseofNePurge GasforTKFInsulation 11/76 Irradiation ofHighlyRadioactive Specimens inTKF 12/76 Irradiation ofPBCompacts inTKF 2/80 Installation ofNewOperating Console 6/80 installation ofUninterruptable PowerSystem 7/80 Useof"BShielded PTSatHigher PowerLevels 4/82 High-Pressure Experiments toDetermine Diffusion Rates 7/84 installation ofMicroprocessor-Based Control Systems Digital Control Console
- Phase11 11/85 Pressure Vessel forNeutron PulseIrradiation Tests 3/86 Pulse-Irradiation of"UDopedConcrete 9/86 Digital Control Console installation Phaseill 4/87 installation ofPVCPiping inCold-Leg ofCooling System 12/87 Installation ofStepping Motors forControl RodDrive 2/88 Digital Control Console Installation PhaseIV 6/88 Square-Wave to250kWSSOperation Experiments 6/88 PhaseV DitalControl
&Instrumentation System 1/89 installation o Ground Fault Detector TestCircuitry 5/89 installation ofNewScramTimer'Circuit 6/89 Installation ofNewCAM 8/89 Irradiation ofNPRLithium Target Specimens 6/90 Installation ofNewReactor CoreTopGrid Plate 2/91 Extension ofNPRLithium Target Irradiations 3/91 Multiple Pulsing Program 3/91 Modification ofNM1000Wide-Range PowerChannel 5/91 Installation ofNFC-1000 FluxController 8/91 installation ofLoss-of-Magnet Voltage Relay-In ScramLoop 3/92 installation ofLa eDiameter inCore Irradiation DryTubes 9/92 Modification of ital Communications Network 12/96 TRIGAReactor Demonstrations and,Operator Training
/o/9'7 Shuti o@
Figure21-TRIGAMarkIOperating Chronology 2-2
PC000482/2 2.2.1.2 TRIGA MarkF Startup:
July,1960 Shutdown:
March,1995;USNRCUtilization Facility License.
- R67, presently limited to Possession-OnlyLicense (POL) status(Ref.
10.3)
Max.Power:
1500kW(t)
SteadyState TheGATRIGA Mark F Reactor wasoriginally constructed byGAasa prototypical testing
- reactor, to act asaproof test reactor fortheTRIGAReactor supplied byGAtothe Defense AtomicSupport
- Agency, Bio-Medical Radiation Research
- Facility, National NavalMedical
- Center, Bethesda, MD,under Contract No.27757, dated 4/4/60.
- InApril, 1961,while continuing to operate extensivelyfortheBethesda testing
- campaign, GA began toutilize theMarkF Reactor onamulti-user basis forseveral other irradiation experiments, themostconspicuous ofwhichweretheIn-Pile Thermionic and Thermoelectric Power Conversion Projects andrelated experiments.
Another primary userofthereactor, beginning
- inJune, 1963,wastheDepartment ofDefense Special Weapons Testing
- Center, LosAlamos, NM, involving thein-pile survivability testing of high-explosive ordnance fortheU.S.
Army.
Figure2-2provides a listing ofthe experiments performed using the7RIGA Mark F Reactor.Integrated powergenerated during operation oftheTRIGAMkF Reactor is estimated tobe4,200MW-days.
2.2.2Current Radiological Status oftheFacility 2.2.2.1 General Routine radiological surveys showthat theradiation levels and contamination levels measured attheTRFhaveconsistently beenlow.A radiological studyconductedin March1997,andsummarized inAppendix A,confirmed thatonly minor quantitiesof residual radioactivity orradioactive contamination arepresent.
The information indicates that theradioactive portions ofthefacility areprimarily confined tothe reactor internals andbiological shield.
Estimates oftheradioactive inventory canbedetermined byconsidering the constituent elements ofthematerial inquestion andcalculating theduration ofexposure tothe neutronflux andtheenergies oftheincident neutrons.
Direct measurements,
- however, aregenerally morereliable andwill beusedduring actual removal and/or dismantlement ofcomponents.
Thisinformation willfurther define thebasis forspecifyingthe necessary safety measures andprocedures forthevarious dismantling,
- removal, decontamination, wastepackaging, andstorage operations sothat exposure topersonnel ismaintained
- ALARA, 2-3
PC-000482/2 TRIGAMarkF:
Startup: July, 1960 Shutdown:March, 1995 Max.Power:1500kW(t)
Steady State 660 Construction Authorized 750 Reactor Startup Experimental Program 950 Biological Targets Authorized 4S1 Thermionic Direct PowerConversion 561 Support ofHarry Diamond Laboratory, Forest
- Glen, MD 8/61 Thermoelectric Device Targets Authorized 10/61 Uraniumzirconium Carbide Thermionic Emitter 1151 CoreLoaded withSSClad zrH,.7 Nelames 1141 Support ofAFRRI(Armed Forces Radiation Research institute),
- Bethesda, MD 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 IrradiationofExplosives, HanyDiamond Laboratory, Forest
- Glen, MD 7/63 installation of2"d Transient Rod 8/63 Fuel Fission Product Release Studies 9/63 Irradiation ofUltrapure Al 11/63 Irradiation ofXylenes forRadiation 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 Irradiation ofSLiF and Red Phosphorus, Sandia National Laboratory, Albuquerque, NM 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 UseofTKFforSS&Pulsing Irradiation 8/68 Uranium Vaporization from Seawater Media t
8/68 600CiyIrradiation Experiment 10/68 Installation ofFLIPElements 1/69 Irradiation ofassU DopedConcrete 1/69 Modification ofTarget Thermionic Device Design 2/72 Explosive Targets Authorized 3/73 Continued TKFTesting 4/73 Installation ofMarkIll Fuel inMarkFCore 4/74 Reconfiguration ofMarkFtoSmall CoreHighPower Density 1/75 installation ofMarkIll Console toMarkF 4175 Routine Pulsing Program Development 5/75 Pulse Irradiation Testing ofNewTRIGAFuel 12/75 Continued TKFTesting 10/76 ColdNeutron Radiography ofzrProgram (CTI Nuclear) 11/76 Cryogenic nModerator UseAuthorized (CTI Nuclear) 2/77 Testing of1/2" dia.
Fuel atSteady State 12/77 Continued operations for CTINuclear andTKF 4/78 Continued Testing of1/2" dia.
Fuel forRomania TRIGAReactor 6/78 Testing ofCentral Flux TrapinPulsing Mode 11/80 Small CorePulse Testing 5/82 HighPressure TKFTesting 10/82 Isotope Production ofMAr&B28p 7/83 FuelPerformance 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 sectionisbaseduponprocess knowledge andisconsistent withinformation obtained asaresult ofactual decommissioning experience ofaTRIGAMarkIReactor at the University
Themost highly radioactivecomponent islikely tobethestainless steel construction Rotary Specimen RackintheMarkIReactor whichmaybeexpected tohaveadose rate of= 16R/hr at 1ft.
Other components tobehandledandprocessed during TRFDecommissioning which mayrange upto= 5 R/hr atthesurface are:
e UpperandLowerGrid Plates frombothTRIGAMarkIandMarkF Reactors; aluminum constructionwith integral stainless steel fasteners.
e CoreSupport Structure ofboth TRIGA MarkIandMarkF Reactors; primarily aluminum construction, with stainless steelcomponents.
e Graphite Reflector Assembly installed radially aroundTRIGAMarkIReactor core.
a Miscellaneous fasteners, especially stainless steel bolts,nuts,helicoils, andpossibly other reactor-related hardware items.
2.2.2.3 Radionuclides Theradionuclides which areknowntobepresent, orare possibly presentindetectable levels within theTRDSarelisted inTable 2-1.
2.3 Decommissioning Tasks 2.3.1Activities andTasks 2.3.
1.1Preparation oftheTRFforDecommissioning 2.3.
1.1.1Characterization Surveys AspartofDecommissioning Project planning
- actions, studies havebeen conducted to determine thetype,quantity, condition, andlocation ofradioactive and/or hazardous materials whichare,ormaybe,present intheTRFandsurrounding areas.A comprehensive radiological survey oftheTRFwascompleted inMarch1997bytheGA Health Physics organization.
Dataandresults fromthese surveys areprovided inthis document asAppendix A:"Summary ofCharacterization Results."
2.3.
1.1.2Transfer ofSpent TRIGAFuel toTRIGAMarkFFuel Storage Canal Inorder tocomplywiththerequirements ofthePossession-Only-License (POL) conditions fortheTRIGAMarkIandMarkF Reactors (as setforth inReferences 10.2 and10.3, respectively),
all irradiated TRIGAFuelintheTRDShasbeenremoved from thetworeactor
- cores, andhasbeenphysically transferred totheTRIGAMarkF Fuel Storage Canal.
2-5
PC-000482/2 Table21:List ofExpected Radionuclides Nuclide HalfLife Decay Notes (yr)
Mode
'4C 5730.
p-AP;fromn-activation ofgraphite reflector structure (TRIGA Mkionly) 54Mn 0.86 e, y AP;shortlived specie; fromn-activation ofSShardware 55Fe 2.73 e
AP;fromn-activation ofSShardware "Co 5,27 p,y AP;fromn-activation ofSShardware; expected tobepredominant APspecie present 59Ni 76000.
e, y AP; fromn-activationofSShardware 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 fromn-activation of SShardware,gNb impurities arepresent "9Tc 213000.
p,y FP,andminorAPinventory constituent; possible fromn-activation of 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,andminorAPinventory constituent; possible from n-activation of
- concrete, EEuimpurities exist inbiological shield structure Symbols/Abbreviations:
p- = Beta p+ = Positron e
= Electron Capture y
= GammaRay AP
= Activation Product FP
= Fission Product Radionuclide Half-Life values andDecayModeinformation usedabovearetaken fromRef.10.15.
Thelist ofexpected radionuclides provided aboveisbasedontheassumption that operations oftheTRIGAMarkIandMarkF Reactors haveresulted intheneutron activation ofreactor corecomponents andother integral hardware orstructural members which aresituated adjacent to,orinclose proximity to,thereactor coreduring operations.
Specific items whichareconsidered tohave beenexposedtoneutron activation include materials composed ofaluminum,
- steel, stainless-steel,
Based onearlier studies andexperience gained insimilar research reactor decommissioning
- projects, andreactorspecific calculations whichconsidered measured values forneutron leakage
- fluence, integrated operating power histories, reactor core/pool structural configurations, andmaterial composition ofexposed poolstructures, neutron activation of materials beyond theconcrete liner/biological shield structure (i.e.,
into surrounding soilvolumes) isngexpected foreither the TRIGAMarkInorMarkFReactors.
2-6
PC000 482/2 2.3. 1.1.3GeneralCleanup ofTRFandAdjacent Controlled YardAreas Inpreparation fordecommissioning activities, non-reactor related equipment and materials situated throughout thesubject areahasbeencollected,
- surveyed, packaged, and appropriately dispositioned inaccordance with established procedures.
Examples of items which havebeenprocessed andremoved fromtheTRFduring these efforts arethe TRIGA King Furnaces irradiation facilities andassociated powerandcontrol systems.
2.3.
1.1.4Partial Removal oftheTRIGAMarkIInstrumentation andControl System InJune,1998, major portionsoftheTRIGAMarkIReactor Instrumentation and Control (I&C) system were dismantled, surveyed,
- released, andshipped fromtheTRF forsubsequent off-site recycle use.Alloftheactions involving theremoval ofthe TRIGAMarkII&Csystem were authorizedandperformed inaccordance withspecific written instructions, which were reviewed andapproved under theprovisions of10 CFR50.59.
Specific I&Ccomponents thus removed fromservice atthat timeincluded theControl System Console,the Data Acquisition andControl
- Cabinet, theNM-1000 Wide-Range Digital Power
- Monitor, andtheControl RodDrives.
Reactor-related instrumentation systems requiredfor the surveillance andmaintenance oftheTRIGA MarkIunder current POLconditions, were leftinplace orrerouted totheTRIGAMark FControl Room.
2.3.
1.2Decontamination oftheFacility ThisDecommissioning Planinvolves the sequential dismantling ofthetworeactors, the reactor pits andliners, andanyassociated systems,in asafe mannerandinaccordance with ALARAprinciples, andfinally thedecontamination and survey oftheentire TRDS.
tE Therearetwo distinct reactors addressed.
First the'IRIGA Mark IReactor willbe W
dismantled.
Second,theMarkF willbedismantled intwo steps.
Includedinthe decommissioning stepisremoval ofallequipment inMarkF not associated withfuel storage andwhereremoval wouldnotaffect orcompromise safe secure fuel storage.
Following removal ofthefuel fromtheFuelStorage
- Canal, the remaining TRIGA Mark F Reactor components (e.g.
thepool) willbedismantled.
Figure 2-3 depicts the decommissioning oftheMarkIandthetwodecommissioning steps for the MarkF.
Viewsofthetworeactors being addressed herein areshowninFigure 2-4and Figure 2-5.
Foreachreactor, components abovethepoolwill beremoved, including reactor pool deckplates, bridge structure, cables andreactor
- conduits, andtherotary rack drive dismantled anddecontaminated totheextent feasible.
Reactor components with induced activity will beremoved using grapples andplaced inshielded containers fordisposal as LLW.Thiswill befollowed byasurvey anddischarge ofthereactor pool water.Water intheMkF andFuelStorage Canalwill notberemoved until after thefuel hasbeen removed.
Thedismantling ofthereactor tanks andpits will proceed after installation ofa confinement barrier inthereactor roomandadedicated ventilation system toprevent the spread ofairborne contaminants.
Thealuminum reactor tankwill besectioned
- inplace, removed fromthepit andthecontaminated sections packaged fordisposal.
Surface and coring samples oftheconcrete biological shield will beperformed todetermine the contaminated areas.
Thecontaminated sections will becutawayandpackaged.
Because ofthelimited removal ofmaterial andavailability ofshoring ifrequired, thestructural integrity ofthepitwill notbecompromised bynecessary decontamination.
The remaining portions oftheconcrete biological shield willremain intact.
Anyrequired sampling andanalysis ofthesurrounding soil will bedonebycoring andrepaired after sampling.
Shoring andcovering ofthepitwill provide industrial-protection, until the 2-7
PC000482/2 final confirmatory release surveys havebeenperformed.
Theremaining tasks are:
dismantlement of theconfinement
- barrier, removal ofanyremaining surface contamination intherooms,andf'mal confirmatory release surveys.
Thepackaged waste is to beshipped totheU.S.DOENevada TestSite(NTS).
2.3.
1.3Dismantling Sequence Dismantling will occursequentially tothedetailed schedule showninSection 2.3.2.
Items removed from thetworeactors will begrouped asfollows:
Group1 Equipment whichdoes nothaveinduced radioactivity butwhich mayhave surface contamination.
Group 2
Core components andother components which haveinduced radioactivity (excluding the reactor tank).
Group3 Reactor tank liner, anchors andconcrete intheproximity oftheformer location ofthe reactor core andwhich havebeen neutronactivated.
Group4 Equipment tools and systems which havebeencontaminated during decommissioning operations.
Components andequipment inthefour groups are identified inTable 2-2,Table 2-3, Table 2-4andTable 2-5.
TheRotary Specimen RackintheTRIGAMkIReactor pool isexpected tohavethe highest induced radioactivity.
Thisexpectation is consistent with theUniversityofTexas g
experience inasimilar TRIGAReactor decommissioningproject. TheRotary Specimen $$
Rackandother Group2items will behoisted fromthepooland lowered into ashielded container whichwill havebeenprepared toaccept theitems.
Additional shielding will be provided forworker protection ifnecessary.
After components, equipment andpartslisted inTable 2-2andTable 2-3 havebeen
- removed, aconfinement barrier will beinstalled.
Thepurpose ofthis barrier is tocontain airborne contaminants generated during reactor pit demolition, andtopreventtheir spread intheReactor Roomandpossibly inthesurrounding areas.
Theconfinement barrier will beerected whichwill surround thereactor pit.
Associated withthis enclosure will beanindependent localized ventilation systemwhichwill ensure anegative pressure withrespect totheReactor Roomwhileproviding high efficiency filtration ontheexhausted
- air, andasource ofclean airsupply within theenclosure.
2-8
PC-000482/2 Phase1 (TRIGA Mk.IReactor)
/ / / /
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PC000482/2 Table2-2-ComonentswithPotential Surface Contamination-Grou 1
Purification System urification looanddeionizer tank iin demineralizer OtherComponents cables andconduits coldecklates rotarackdrive r6actorbridestructure neumatic transfer s stem Table23-Com onents withinducedRadioactivit
-Grou 2
Rotas ecimen rackMkiong Control roduidetubes anddetector tubes o
ridlate Bottomridlate Reflector Coresu ort Fasteners andconnectors Pneumatic transfer s stemterminus Table2-4-Reactor TankActivated Com onents-Grou 3
Reactor itliner Concrete Anchors Reinforcement bars Table25-E uiment UsedinDecommissionin O erations-Grou 4
General ventilation s stem Localized ventilation s stem Confined barrier Contaminated tools ande uiment Contaminated clothin TheReactor Roomwillbemaintained ata negative pressure withrespect to the surrounding areasbutlessthanthepressure differential maintained between the confinement barrier andtheReactor Room.Thiswill ensure that theairwill travel from thenon-contaminated area totheincreasingly contaminated areas.
Theactivated liner section will beseparated,
- removed, andprocessed, andtheactivated thickness oftheconcrete biological shield will beremoved.
Tominimize dust dispersal, a
localized fine watermistmaybesprayed overtheareabeing demolished.
TheGA Nuclear Waste Processing Facility (NWPF) operates aFiltration Station forthetreatment ofliquid wastes.Thetreated waterisdischarged intothesanitary sewerifitmeetsthe discharge limits forGA'sIndustrial Wastewater Discharge Permit.
Wastewaterthat cannotmeetdischarge limits issolidified foroff-site disposal aslow-level radioactive waste.Activated concrete will beremoved asection atatimeandshoring supports will beplaced inthecavity formed
- asneeded, before proceeding withthe nextsection.
Atthecompletion ofactivated concrete
- removal, doseratemeasurements will bemadeto determine ifallnecessary portions havebeenremoved.
Post-remediation surveys may 2-12
PC-000482/2 includeconcrete andsoil coring sampling andanalysis.
Asthedemolition ofactivated
(
material
- proceeds, theradioactive material will bepackaged forshipment anddisposal.
There aretwopotential radiological safety concerns during performance ofthis task:
1) external exposure fromtheactivated components ofthetank,and2)inhalation of airborne material.
Tominimize
- therisk, workareaswill bemonitored frequently and radiation levels will bemonitored continuously, todetermine sudden changes inthe radiological conditions.
Upon completion ofdismantlement tasks inthereactor
- pit, theconfinement barrier will be dismantled and the plastic sheets compacted andpackaged.
Surface contamination will be removed fromcontaminated portionsoftheventilation systemandtheywill thenbe packaged fordisposal.
The reactorroomwillthenbe cleared andallsurface contamination removed.
2.3.1.4 Surveys Following decontamination andremediation activitiesofeachreactor, a final radiation survey ofeachofthereactor rooms and otherapplicablelocations covering theentire TRDSwill beperformed and documented by GAHealth Physics.
2.3.2Schedule Theproject schedule ispresented asFigure 2-6.
The scheduled timefromregulatory approval oftheDecommissioning Plan tosubmittal for release ofthesite tounrestricted use is41months.
Itshould benoted that fuel stored intheMkF Reactor FuelStorage Canal is a
scheduled fortimely removal andshipment offsite.
Ifthe DOE fails toapproveshipment to g@E accommodate thetimely continuation ofthedecommissioning, a day-to-day schedule slippage ofPhase 2oftheD&Dwill occur until suchtime asthe fuel isshipped offtheGA m
site.
2.3.2.1 Schedule forOff-Site Shipment ofGASpent Nuclear Fuel(SNF)
GAplans tohandle thespentTRIGAfuelcurrently stored intheTRIGA MkF Fuel Storage Canal asaworkactivity undertheexisting USNRCFacility License No.
R-67; (non-TRIGA related irradiated fuelmaterials stored atGA willbeshipped under provisions ofcurrent USNRCandState ofCalifornia Radioactive MaterialLicenses issued toGA).
TheU.S.Department ofEnergy (USDOE) iscommitted toprovide foroff-site receipt andstorage ofGASNF.However, GAhasbeennotified ofaprogram delay.
Receipt of theGASNFattheestablished receiving organization (INEEL) isnotscheduled tooccur before CY2003under current plans.
Risks associated withtheoff-site
- shipment, transport, andINEELreceipt oftheGA SNF,areaddressed inanEnvironmental Impact Statement (EIS),
separately issued by theUSDOEtocoverthesubject tasks.
2.3.2.2 Request forTermination ofUSNRCFacility License Although all workassociated with theMark1maybecompleted andFacility License No.
38termination requested, final completion oftheTRDSDecommissioning Project
- work, asdescribed
- herein, cannotbeaccomplished until alloftheSNFcurrently stored inthe TRDShasbeenphysically removedfromthesubject area,(see discussion
- above, 2-13
PC000482/2 regarding planned SNFoff-site shipment schedule).
Uponfinal removal ofspent a
TRIGA fuel fromtheTRIGAMarkF FuelStorage
- Canal, GAplans toproceed withall $3 remaining tasks todecontaminate anddecommission theTRDSina timely manner.
Based onprojectschedule informationdocumentedhereinFigure 2.6,GAestimates that aformal request fortermination ofFacility License No.R-67will besubmitted tothe USNRC approximately sixmonths after thefinal shipment ofSNFhasbeendispatched from GA.
2.4 Decommissioning Organization andResponsibilities GAiscommitted to, and retains ultimate responsibility forfull compliance withtheexisting USNRCandState licenses and theapplicable regulatory requirements during decommissioning.
Company principles,
- policies, andgoals will befollowed toensure high standards ofperformancein accomplishing thedecommissioningtasks.
Theplanned organization for the TRDS Decommissioning asshowninFigure 2-7will be maintained, individuals performing the functions mayvaryovertheProject duration.)
Specialized contractors maybeutilized, under thedirection oftheTRDSDecommissioning Project
- Manager, whennecessary andappropriate.
KelPolitiong 2.4.1Decommissioning Project Manager-The TRDS Decommissioning Project Manager hastheoverall responsibility forsuccessful completion oftheProject.The Decommissioning Project Manager functions include:
a Controlling andmaintaining safety during decommissioning activities andprotecting of g
theenvironment
($
a Determining project staffing andorganization a
Assuring performance tocostandschedule a Reporting ofperformance a Approving decommissioning plans andprocedures e Approving subcontracts e Approving budgets andschedules a Ensuring, withtheassistance oftheGALicensing,
- Safety, andNuclear Compliance (LSNC)
Organization, that theconduct ofdecommissioning activities complies with all theapplicable regulations andisinaccordance withtheGAlicenses.
Theminimum qualifications fortheDecommissioning Project Manager are:
e A four yeardegree inengineering ornatural science a Fiveyearsofproject management experience inthenuclear industry including decommissioning projects a Familiarity with theGATRIGAReactor Facility a Appropriate training inradiation protection, nuclear
- safety, hazardous communication, andindustrial safety 2-14
PC-000482/2 i
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M3M 3M 37M 3M 4M 4M 3Decommission Mark FReacor Radioogica Suvey 3Remove Reaco Componens inPoo 3Gae/Hois/Suve Disassembe asnecessa Deconaminae oPacae as LLW 4DOE Appova oShip Fue Ship Fue Sored inMF Cana Reaco Tank
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44Suve/Sampe/An 45Dischage/Fie asnecessay insa Coninemen Barier around Reaco Pi 4Cu/Remove insecions Q
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Remove/acage O
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y Dismane Barier/Pacag or LLW disposah Deconami MkF Reacor Roomsua D
SCHEDULE FOR TRGA REACTOR FACLTY D&D 4Tank Remova Pacage conaminae oos and equipmen 6
Ship LLW oNTS Survey SoiPepare Suvey Repo Submia orReease oUnresri Use o
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VCEPRESDENT VCEPRESDENT VCE PRESDENT RESEARCH&
MVCEPRESDENT DEVELOPMENT E
LCENSNG,S CORPORATECR NUCLEAR QUALTYAS SAFETYCO S
K.E.ASMUSS B.L.COLEMAN W.L.WHTTEMORE NfO@
- MANAGER, PRO HEALTHPH QU L.Q.GON2 V.NCOLAYE 0DE F
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PC-000482/2
- 2. 4. 2TRF PhysicistinCharge-The functions oftheTRDSPhysicist-in-Charge include:
a Maintaining theTRDSina safeandproper condition during theevolution of Decommissioning Project activities, inaccordance withtherequirements setforth inthe applicable USNRCfacility licenses Approval ofplansandprocedures e
Providing engineering support forthedecommissioning activities Theminimumqualifications forthis position are:
e A current senior reactor operator license fortheGATRIGAReactors issued bythe USNRC a
A four year degree inEngineering orNatural Science a
Fiveyears experience inaresearch reactorfacility environment e Substantial knowledge oftheTRDS andassociatedsystems 2.4.3Manager, Health Physics-The Health Physics Manager isresponsible forproviding radiological safety support inthe decommissioning oftheTRDS.Thisfunction ensures that activities involving potential radiologicalexposure areconducted incompliance withthe applicable
- licenses, Federal andState regulations, andGA procedures.
Theposition includes responsibility formaintaining TRDSsurveillance andmonitoring program andthe development ofHPradiological protection procedures.
Theminimumqualifications forthis position are:
e A four yeardegree inHealth Physics orarelated field ma a Three years supervisory experience inHealth Physics WiP a
Fiveyears operationa1 experience related toradiation safety 2.4.4Manager,Quality Assurance-The Quality Assurance Manager isresponsible for implementing and managing theQuality Assurance program for theTRDS Decommissioning
- Project, inaccordance withtheapplicable requirementsof ASME-NQA-1,Quality Assurance Program Requirements forNuclear Facilities and 10 CFR 71, Subpart H,Quality Assurance for Packaging andTransportation ofRadioactive
- Material, andforcertification ofradioactive wastetoensure compliance withthe applicable Waste Acceptance Criteria oftheRadioactive WasteDisposal Facility.
Theminimum qualifications forthis position are:
e A four-year degree inengineering ornatural science e Fiveyears experience innuclear related Quality Assurance e Twoyears experience inthedecommissioning ofnuclear facilities andradioactive waste processing 2.5 Training Program Training isconducted andcontrolled inaccordance withapplicable GAprocedures, license commitments, andtheWorkAuthorization forthe'IRDSDecommissioning
- Project, and focuses
- onsafety, knowledge ofapplicable regulations, andtechnical requirements.
The training program shall comply withtherequirements established bytheUSNRCin10CFR 19.12(as described inmoredetail intheGARadiological Contingency
- Plan, Ref.10.17) and10CFR71.105(d);
byOSHAin29CFR1910.120(e) and29CFR1910.1200(h);
by 2-18
PC000482/2 BA theU.S.
Environmental Protection Agency in40CFR265.16; byCAL-EPAinCCR22-thTV 66265.16; andbytheU.S.Department ofTransportation in49CFR172.704.
2.5.1General Employee Radiological Training (GERT4 Hour)-General employee radiological training will beprovided toall personnel whoarerequired toenterradiological Restricted Areas (with theexception ofvisitors andinfrequent support personnel),
butare notauthorized toperform hands-on radiological work.
2.5.2RadiologicalWorker Training (RWT16Hour)-Radiological worker training will beprovided topersonnel whorequire unescorted access toradiological Restricted
- Areas, andwhoare authorized toperform radiological jobfunctions.
GERTandRWTareadministered toemployees,asapplicable, withrefresher training provided every year.
2.5.3Health Physics TechnicianTraining Health Physics Technicians mustsuccessfully completeRadiological Worker Training.
In
- addition, Health Physics Technicians are trained totheprocedures usedfortheir workand mustreview andunderstand other HP procedures according totheHealth Physics Technician Procedure ReviewSign-off Forms.
Health Physics Technicians willalso review applicable procedure revisions inatimely manner.
Health Physics Technicians will also befamiliarized withtheSite andFacility characterization results andthecontents of this Plan.
2.5.4Equipment Operator Training Allequipment operators will haveproper training completed and documented prior to
=
performing unsupervised workwiththeequipment.
Reactor operators mustbelicensed by theNRC.
2.5.5 Safety/Accident Prevention Training GAhasanInjury andIllness Prevention Program (IIPP) whichisdefined in theIIPP
- Manual, a.k.a.
theAccident Prevention Program Manual(APPM).
Allemployees are required toabide bytherequirements setforth inthis Manual.
Additional specific TRDS Decommissioning Project requirements maybe specified, as required inProject procedures.
2.5.6HazardCommunication Training-A hazard communication training program has beendeveloped forthis Project inaccordance withOSHA1910.1200 andtheGAIIPP.
Thisprogram promotes awareness ofchemical hazards that arepresent atthis
- Facility, and provides meanstocommunicate those hazards toemployees.
A designated person will maintain thehazardous material inventory andMaterial Safety DataSheets (MSDS) foron-site hazardous materials, andprovide all Project personnel withinformation advising them ofthepotential forhazardous constituents intheworkplace.
A list ofsuchmaterials is maintained atthejobsite, andcopies oftheappropriate MSDSareavailable tosite workers uponrequest.
TheMSDSformprovides moredetailed information about thechemical than alabel does.
A hazardous chemical inventory ismaintained whichreflects thecurrent supplies located intheworkarea.
Anychemicals notpreviously located andidentified or newchemicals received onthejobsite will beadded totheinventory list.
2.5.7Contamination Control Training-Personnel will betrained incontamination control d
together withboundary
- control, ventilation
- control, etc.Cross contamination will belimited 2-19
PC-000482/2 bytheuseoftraining andradiological controls.
Radiological andhazardous materiala contamination will bestrictly controlled during alldecommissioning work.Thiscontrol$3 will beaccomplished using qualified workers toperform workidentified inapproved work procedures.
Insomeinstances, special briefings anddry-runs maybeusedtoperfect techniques, demonstrate approaches, andqualify theworkers.
2.5.8 Respirator Training-Each individual whomayusearespirator will berequired to receive respiratory protection training, bemedically qualified touserespirator protection, andreceive aquantitative fit testforeachspecific device that they arequalified touse.
Training will meet the requirements oftheU.S.Department
- ofHealth, Education, and
- Welfare, NationalInstitute for Occupational Safety andHealth (NIOSH),
andANSIz88.2-1980,PracticesforRespiratoryProtection (Ref.
10.11).
Respirator fit tests will be administered before initial assignments tojobs requiring theuseofarespirator, andwill be conducted asnecessary thereafter.
Medical qualification will beassessed annually.
2.5.9Confined SpaceEntry Training-Employees required toenterconfined orenclosed spaces will betrained totheOSHA confined space entry requirements.
Theywill be instructed astothenature ofthe hazards
- involved, thenecessary precautions tobetaken andtheuseofrequired emergency andprotective equipment, asprescribed bytheHealth andSafety Manager ordesignated person.A confined space permit mustbeissued prior to access into theconfined space.
2.5.10Emergency
Response
Training-GA hasaGA SiteRadiological Contingency
- Plan, asrequired bytheUSNRCandtheState ofCalifornia.
The TRDShasaspecific procedure insupport ofthese plans.
2.5.11Hazardous Materials Training Training forhazardous materials isdependent onthejob description foreachindividualand thetypesandamountsofhazardous materials orhazardous wastes being handled as specified intheposition's training plan.
Ingeneral, thetraining specified forworkers and supervisors directly involved withdecommissioning includes someorall of thefollowing training requirements:
2.5.12HA2WOPERTraining Course-OSHA1910.120, 40hourclassroomand 24hour on-the-job training specific tohazardous materials.
An8hourannual refresher isprovided.
2.5.13Hazardous Materials Packaging-Reviews therequirements forhandling and shipping hazardous materials andwastesasrequired by49CFR,theDOTregulations.A refresher update isrequired every three years.
2.5.14Waste Acceptance Criteria-Training isprovided totherequirements established for thedisposal site.
Anannual training update isprovided.
2.5.15Dangerous WasteRegulations-Training tofamiliarize hazardous wastetechnicians andsupervisors withappropriate hazardous wasterequirements forwastedesignations.
A refresher isprovided annually orasregulations areupdated.
2.5.16GAEmergencyResponseTraining-Training tofamiliarize emergency response personnel withactions tobetaken inresponding toanunplanned release ofhazardous or radioactive material fromtheTRDS.Hands-on training inthis areaincludes conducting drills toevaluate response capabilities.
2-20
PC000482/2
,a
- 2. 5. 17RCRA Facility Standards OverviewTraining-This class coversthe
$5 requirements established under 40CFR264.16 forpersonnel whomayhandle hazardous wastes withintheFacility.
Theclass coverstheFederal Standards anddiscusses compliance requirements forgenerators ofhazardous andmixed wastes.Anannual update isprovided.
2.6 Contractor Assistance 2.6.1Contractors Contractors willhave undergone theGA Quality Assurance approval process when required.
Wherevercontracting personnelareusedon-site, theywill:
1)comply withall provisions ofGA licenses andpermits,and2)betrained inaccordance withGA's commitments.
Contractors will beusedon an as needed basis during decommissioning.
Theuseof contractors will becomplementary totheGAstaff andwillnormally provide specialty support.
2.6.2Tasks Tasks where contractors maybeused includebut are notlimited to:
a Shipment anddisposal ofradioactive and nonradioactive wastematerials e Laboratory testing andanalysis a
Concrete cutting f
a Construction/dismantlement support x
a Asbestos removal anddisposal a Design andfabrication ofspecialty dismantling tooling andequipment a Specialty engineering anddesign services
- Temporary staff augmentation 2.6.3Potential Contractors Potential contractors foreachidentified task will berequired toprovide a statement of qualifications aspartoftheir bidsubmittal.
Thequalifications required will emphasize the following:
a Experience withsimilar workinaradioactive environment
- Adequacy ofqualified workers
- Ability tomeetschedule TheQuality Assurance organization atGAmaintains anapproved supplier list andhasan extensive approval process which ensures that contractor qualifications areadequate tothe need.
2.6.4 Subcontractors Subcontractors whowill workwithlicensed radioactive materials will berequired 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 Beissuedproper dosimetry bycognizant HPpersonnel W
Follow all special instructions given byHP e
Be escorted bya cognizant authorized person listed on theTRDSWA, unless specifically listed themselves ontheTRDSWA 2.7 Decontamination andDecommissioning Documents andGuides Health Physics, Industrial Health
- criteria, andother standards thatguided theactivities described inthisDecommissioning Planarediscussed inSection 3.1.2, Health Physics
- Program, Section 3.2.3, Radioactive WasteDisposal andSection 3.2.4, General Industrial Safety Program.
Relevant documents andguides usedarenoted therein andinSection 10, References.
2.8 Facility Release Criteria The proposed decommissioning alternative thathasbeenpresented in this Decommissioning Plandoes notnecessitate the dismantlement oftheTRF.Theresults of thesite andfacility radiological characterization have indicated that thestructures maybe directly releasable without needfor extensive decontamination.
Thissection provides thespecific criteria forrelease oftheTRDS.TheFinal Release approach willusetheguidance provided inNUREG/CR-5849 (Ref.
10.10),
and described inSection 4.
Uponcompletion ofthedecontamination andremediation activities (e.g.
seeSection 2.3), gg afinal radiation andradiological contamination survey ofthe TRDS will beperformedWP anddocumented byGAHealth Physics.
Theresults ofthesurvey(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 theobjective ofdecommissioning theTRDSistoultimately releasethe facility/site tounrestricted use,afinal radiation andradiological contamination survey report will demonstrate compliance withtheradiological criteria given inRegulatory Guide 1.86.
Specifically, thecriteria forrelease oftheTRDStounrestricted useandfor termination of thecorresponding licenses (which havebeenamended toallow possession only) are as follows:
1.Surface contamination levels mustnotexceed thevalues presented
- inTable1, "Acceptable Surface Contamination Levels,"
oftheU.S.NRCRegulatory Guide 1.86, "Termination ofOperating License forNuclear Reactors" (Ref.
10.18).
Table 2-6presents thelimits fromtheregulatory guide.
Additionally, 2.Residual radionuclides
- present asaresult offacility operation
- mustnotresult inan exposure rateinexcess of5 microR/hrabove natural background measured at1 meterfromthesurface (Ref.
10.19).
Removable surface contamination will beeliminated where possible bywiping orother proven decontamination methods.
Release criteria forfixed andsmearable residual radioactivity forbeta-gamma emitters wouldbebased upontherelative concentrations of isotopes onthematerial andtheir respective release criteria ifmorethan onecategory of nuclide forbeta-gamma emitters applies fromTable 2-6.
2-22
PC-000482/2 431F Table26-Acce tableSurfaceContamination Levels Nuclides' (dpm/100 cm2)
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 (nuclideswithdecay modesother thanalpha 5,000 15,000 1,000 emission orspontaneous fission) except "Srandothers noted above.
a Wheresurface contamination bybothalphaandbeta/gamma-emittingnuclides
- exists, thelimits established foralpha-and beta/gamma-emitting nuclidesshould applyindependently.
b Asusedinthis table dpm(disintegrations perminute) meanstherateofemission byradioactive material asdetermined by correcting thecounts perminute observed byanappropriatedetector forbackground, efficiency, andgeometric factors associated with theinstrumentation.
c Measurements ofaverage contaminant should notbeaveragedovermorethan1square meter.
Forobjects ofless surface area,the average should bederived for eachsuch object.
d Re maXimum Contamination level
@lies toan area ofnotmorethan100crna, e Theamountofremovable radioactive material per100 cm2ofsurface area should bedetermined bywiping that areawithdryfilter (e.g.,
smear) orsoft absorbent paper(e.g.,
masslin),applying moderate pressure, andassessing theamount ofradioactive material onthewipewith anappropriate instrument ofknown efficiency.
Whenremovable contamination onobjects oflesssurface areais determined, thenpertinent levels should bereduced proportionally andtheentire surface should bewiped.
- lncluding contamination byinduced radioactivity, i.e.,
activation.
2-23
PC000482/2 a
3.
PROTECTION OFTHEHEALTHANDSAFETYOFRADIATION (WW WORKERSANDTHEPUBLIC 3.1 Radiation Protection 3.1.1Ensuring AsLow AsReasonably Achievable (ALARA)
Radiation Exposures Decommissioning activities attheGATRIGAReactor Facility involving theuseand handling ofradioactive materialswill beconducted suchthat radiation exposure will be maintained AsLow As Reasonably Achievable (ALARA),
taking into accountthecurrent state oftechnologyand economics ofimprovements inrelation tothebenefits.
h GA'scurrent practice isasfollows:
e A documented ALARAevaluation willberequired forspecific tasks ifaProject HP determines that 5%ofthe applicable dose limitsforthefollowing maybeexceeded:
Total Effective Dose Equivalent(TEDE)
ThesumoftheDeep-Dose Equivalent (DDE) andtheCommitted DoseEquivalent (CDE) toanyindividual organ ortissue other thanthelens oftheeye EyeDoseEquivalent (EDE)
Shallow-Dose Equivalent (SDE) a A documented ALARAevaluation will berequired ifProject HPdeterminesthat TRF effluent averaged overoneyearisexpected toexceed 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 iskeptALARA.Themethods include the WorkAuthorization (WA),theRadiological WorkPermit (RWP),special equipment, techniques, andpractices, asdescribed inthefollowing subsections.
W Authorization forworktobeperformed inaccordance with reactor licenses and/or this Decommissioning
- Plan, mustbeobtained through theGALSNCDivision, bypreparation andmaintenance ofaWA.TheWAidentifies theproposed workscopeandactivities, quantity andformofradioactive materials
- involved, individuals authorized toperform the work,andapplicable workprocedures.
An estimate oftheisotope(s),
physical and chemical form,andquantity ofradioactive material generated aswasteduring atwelve-monthperiod isincluded intheWA.Anassessment ofthemagnitude andsignificance of estimated releases ofradioactivity totheenvironment isalso provided.
Implementation of operating procedures iscontingent uponapproval oftheWA.Workisperformed instrict accordance withthemethods andprecautions provided intheapproved WA.
3-1
PC-000482/
2 RWPs areusedwhen:
a a work task isnotdescribed intheestablished WorkAuthorization, provided that the margin ofsafetyprovided bytheRWPiscomparable to,orgreater
- than, that specified inthe WA, a
personnel not listed asAuthorizedIndividuals ontheWorkAuthorization mustperform
- work, a
oroutside contractors orsubcontractor personnel mustperform limited orroutine work inthe established Restricted Area(RA).
TheRWPisissuedin accordance withexisting GA Health Physics procedural requirements, andisinitiated bytheFacility Principal Investigator orother responsible individual whohasgood knowledge ofthetask tobeperformed andother workbeing performed inthearea.
Theuseofengineering controls tomitigate the airborne radiological hazard atthesource will bethefirst choice with respect tocontrolling theconcentrations ofairborne radioactive material.
Theremaybe,however, circumstances where engineeringcontrols arenot practical, ormaynotbesufficient toprevent airborne concentrations inexcess ofthose that constitute anairborne radioactivity area.
Insuchcircumstances whereworker access is
- required, respiratory protective equipment will beutilized tolimitinternal exposures.
Any situation whereby workers areallowed access toanairborne radioactivity area,orallowed toperform workthat hasahigh degree oflikelihood togenerate airborne radioactivity in p@4 excess of0.1DAC,thedecision toallow access will beaccompanied bytheperformance
%P7 ofrepresentative measurements ofairborne radioactivity toassess worker intake.
The results ofDAC-hour tracking andairsample results foranyintake will bedocumented.
Workers willprovide nasal smears forHP evaluation following the use ofrespiratory protective equipment forradiological purposes asnecessary.
TheGAHPProgram establishes radioactive material controls that ensure:
a Deterrence ofinadvertent release oflicensed radioactive materials tounrestricted areas.
a Confidence thatpersonnel arenotinadvertently exposed tolicensed radioactive materials.
- Minimization of thevolumeof radioactive wastesgenerated during the decommissioning.
Allmaterial leaving theRestricted Areawill besurveyed toensure that radioactive material isnotinadvertently released fromtheTRDS.SeeSection 3.1.3"Radioactive Material Controls" foradescription ofthespecific survey methods that will beused.
3-2
PC000482/2 3.1.2Health Physics Program GAHealth Physics hasprocedures inplace whichwill beimplemented during theTRDS Decommissioning Project.Ifnewadditional Health Physics procedures arerequired at somepoint in theworktosupport thedecommissioning, theywill bedeveloped and approved inaccordance with GAHealth Physics policy andprocedure.
GAsenior management isreadilyaccessible toensure timely resolution ofdifficulties that maybeencountered. The HPManager, while organizationally independent oftheProject
- staff, hasdirect access to the Decommissioning Project Manager onadaily
- basis, andhas full authority toactinallaspects ofprotection ofworkers andthepublic fromtheeffects of radiation.
Conduct ofthe TRDS Decommissioning Project HPprogram will beevaluated according toGApolicy andprocedure bybothGAQuality Assurance oversight, andGA site HPaudit activities.
During Decommissioning Project
- work, aspects oftheProject maybeassessed bytheGA Quality Assurance Department, through
- audits, assessments, andinspections ofvarious aspects ofdecommissioning performance, including HPasdescribedinSection 1.2.4.
Formal audits oftheGAHealth Physics program are conducted annually inaccordance withGAHPprocedure, andtherequirements of10CFR 20.Theseaudits will include aspects oftheTRDSDecommissioning Project.
C Additional assessments or management reviews may be performed whendeemed E
appropriate bytheDecommissioning Project Manager and/or the PIC.
GAhasselected HPequipment andinstrumentation suitable topermit ready detection and quantification ofradiological hazards toworkers andthepublic, 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 oftheTRF.Equipment andinstrumentation selection also takes into accounttheworking conditions, contamination
- levels, andsource termsthatarereasonably expected tobeencountered during theperformance of decommissioning workaspresented inthis Plan.
Thefollowing sections present details oftheequipment andinstrumentation presently selected foruseduring thedecommissioning.
Itisanticipated that through retirement of wornordamaged equipment/instrumentation orincreases inquantities ofavailable components orinstruments, that newtechnology will permit upgrades or,ataminimum, like-for-like replacements.
GAiscommitted tomaintaining conformance tominimum performance capabilities stated inthis Planwhenever 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 tounrestricted use.
Instrumentation andequipment will becapable ofmeasuring therange ofdoseratesand radioactivityconcentrations expected tobeencountered during conduct ofremediation and decontamination of theTRDS, aswellasforfinal survey measurements, andtoless than theminimum values required forrelease orALARAdecision-making.
Project HPstaff will select instrumentation that issensitive totheminimum detection limits fortheparticular task being performed, butalso withsufficient range toensure that thefull spectrum ofanticipated conditions foratask orsurvey canbemetbytheinstrumentation in use.Consumable supplies willconform tomanufacturer and/or regulatory recommendation toensure that measurements meetdesired sensitivity andarevalid fortheintended purpose.
GAwill continue review ofregulatory information notices andbulletins forapplicability to Project HPinstrumentation.
Instrumentation Survey instruments willbestored ina common location underthecontrol ofTRDS Decommissioning Project HPpersonnel.
A programto clearly identifyandremovefrom service anyinoperable orout-of-calibration instrumentsor equipment asdescribed inHP procedures will beadhered tothroughout theTRDSDecommissioning Project.
Survey instruments, counting equipment, airsamplers, air monitors, and personnel contamination monitors will becalibrated atlicense-required intervals, manufacturer-prescribed intervals (if shorter frequency) orprior touseagainst standards that are NIST traceablein accordance withGA Calibration Laboratory procedures, HP procedures, orvendor technical manuals.
Survey instruments will beoperationally testeddaily when inuse.
Counting equipment operability willbeverified daily wheninuse. The personnel contamination monitors areoperationally tested on a daily basis whenwork isbeing performed.
Table 3-1provides details oftheHPequipment andinstrumentation that hasbeen selected foruseintheTRDSDecommissioning Project.
As discussed
- earlier, theselection of instrumentation issubject tochange asolder equipment andinstruments areretired.
GA will maintain conformance tominimum performance capabilities
- orbetter, whenever new components orinstruments areselected.
3-4
PC-000482/2 Table 31-S ecific HealthPh sicsE uimentand instrumentation Useand Ca abilities
$3 instrument Model Detector Type instrument Rangeor Application Detection Capability EberlineRO-2 and 2A lonization chamber RO-2 Beta/gamma exposure rate measurements Eberline RO20 05,000mR/hr Minimum detection:
0.2mR/hr RO-2A 050R/hr RO-20 0-50R/hr Eberline Teletector6112D/B GM tube 01,000R/hr Telescoping detector with GMprobe forhigh range Ludium-M239F Floor Monitor 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 Canbeusedwith several types ofprobes-Information for HP-260 probe.
probe RM-14SA "Srefficiency
- 32%4n 0
5,000,000 cpm 15.5cm2 HP100BGS probe"Srefficiency 36%4n,100cm2 Ludium Model 12with 4368 GasProportional0500,000 cpm Beta-Gamma surface contamination measurements probe Canberra LowLevel GasProportional Detection capability Low-level a/psmear samples Alpha/Beta Counting System typically
<25dpm/100cm2 Ludium-177 znS()
0500,000 cpm Handheld alpha frisker (50 cm2area) scintill on Ludium Model 19pR Nal(TI)
Scintillator 05,000gR/hr Lowgammaexposure 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 6Decade scalar Beta laboratory measurement ofair samples andsmears pancake tube REGECanberra S-100 or HPGe Detection capability:
Gamma laboratory measurement
- ofwater, air, smear/media samples equivalent Gamma-ray s;0.18 pCi1370s/g (e.g.,Soil, asphalt, concrete,tar, vegetation) aggo spectroscopy system
- ~
4 Eberline Personnel GasProportional Detection capability:
Personnel contaminationmonitor/walk-in monitor with microprocessor 7
Contamination
<5,000 dpm/100cm2 control and radon rejectcapability.
Monitor PCM-2 SAICRADeCO H809V N/A 1-30cfm HighVolume air sampling for minimum detectioncapability "HiVol" SAICRADeCOHD-29A N/A 0.5-3.5 cfm Lowvolume airsampling for long term air sampling "Goose Neck" Technical Assoc.
GM 10-105 cpm Local airborne monitor with alarm capability FM5ABN2CHmodular air monitors Ametek MG4AirSampler N/A 5
- 4,000cc/min.
Lapel airsampler for useinchronic exposure situations TheTRDSDecommissioning Project willutilize theexisting GAHP Program forthe Project.
ThisProgram prescribes
- policy, method, andfrequency foreffluent monitoring, conduct ofradiological
- surveys, personnel monitoring, contamination control
- methods, and protective clothing usage.
Efflu.eert.Monitoring-Until suchtimeasthedecommissioning effort hasreached thepoint where theHEPAsystemisnolonger
- needed, theTRDSventilation systemexhaust points will becontinuously sampled downstream ofeachHEPAfiltration system byanisokinetic sample collection point(a grab-type sample) whichisincontinuous operation.
The particulate sample change-out frequency isapproximately weekly; sample mediaare analyzed forparticulates using laboratory counting systems inatimely mannerafter filter 3-5
PC000482/2 media change-out.
TheGAHPDepartment also operates several continuous environmental g$3 air sample stations onthemainGAsite tofurther assess thepotential forenvironmental
'S" airborne radiological effluents.
Anypotentially contaminated liquids that maybegenerated orstored atthefacility will be sampledand analyzed forradioactivity prior todisposal.
Ifthese liquids arefound to contain radioactivity, theywillbeevaluated fordisposal options inaccordance with applicable permits andState andFederal regulations.
RadiationSurves-Radiation, airborne radioactivity, andcontamination surveys during decommissioning will be conducted inaccordance withapproved HPprocedure(s).
The purposes ofthese surveys will beto(1) protect thehealth andsafety ofworkers, (2) protect thehealth andsafety ofthegeneral public,and(3) demonstrate compliance withapplicable
- license, federal, andstate requirements, aswellasDecommissioning Plancommitments.
HPpersonnel willverify thevalidity ofposted radiological warning signs during the conduct ofthese surveys.
Surveys will beconductedinaccordance withprocedures utilizing survey instrumentation andequipment suitableforthenatureandrange ofhazards anticipated.
Equipment andinstrumentation willbecalibrated and,whereapplicable, operationally tested prior touseinaccordance withproceduralrequirements.
Routine surveys areconducted ataspecified frequency toensure that contamination andradiation levels inunrestricted areas donotexceed
- license, federal,
- state, orsite limits.
HPstaff will also perform surveys during decommissioningwhenever workactivities create apotential toimpact radiological conditions.
-Externalmonitoring willbeconducted in accordance withtheprospective external exposure evaluation fortheTRDS.Prospectivegra external exposure evaluations will beperformed, ata minimum, onanannual
- basis, or W
whenever changes inworker exposures warrant.
Visitors totheTRDS willbemonitoredin accordance withrequirements specified inGA HP procedures, and according tothe radiological hazards ofareas tobeentered.
Internal monitoring will beconducted inaccordance withthe prospectiveinternal exposure evaluation fortheTRDS.This prospective internal exposure evaluation will be evaluated on anannual
- basis, ata minimum,orwhenever significant changes inplanned work evolutions warrantit.
A comprehensive airsampling program isconducted attheTRDS to evaluate worker exposures regardless ofwhether internal monitoring isspecified.
The results ofthis airsampling program will beutilized toensure validity ofspecified internal monitoring requirements forTRDSpersonnel.
Ifatanytimeduring the decommissioning, hazards that maynotbereadily detected bythepreceding measures areencountered, special measures orbioassay, asappropriate, will beinstituted toensure theadequate surveillance ofworker internal exposure.
Monitoring will berequired iftheprospective doseevaluation showsthat anindividual(s) doseislikely toexceed 10%oftheapplicable limits andforindividuals entering ahigh or veryhighradiation area.
Rh-The GArespiratory protection program provides direction foruse ofNational Institute forOccupational Safety andHealth/Mine Safety andHealth Administration (NIOSH/MSHA) certified equipment.
Thisprogram isadministered byGA HPinconsultation withGAIndustrial Hygiene.
NIOSH/MSHA approved equipment areairpurifying respirators whichincludes full face piece assemblies withairpurifying 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 flowfull-face
($j$
airline respirators forworkinareas withactual orpotential airborne radioactivity.
TheHP Manager will also ensure that therespiratory protection program meetstherequirements of 10 CFR Part 20,subpart H.
Maintenance-When respiratory protection equipment requires
- cleaning, thecartridges will beremoved.
Therespiratorwillbecleaned andsanitized after everyusewitha cleaner/sanitizer andthenrinsed thoroughly inplain warmwaterinaccordance withHP procedures.
Storage-Respiratory protective equipment will bekeptinproper working order.
When anyrespirator showsevidence ofexcessivewearorhasfailed inspection, itwill berepaired orreplaced.
Respiratoryprotective equipmentthat isnotinusewill bestored inaclean dry location.
Contamination Control-Contamination controlmeasures that will beemployed
- include, as appropriate, thefollowing:
e Worker training will incorporate methods andtechniquesforthecontrol ofradioactive materials, andproper useanddonning/doffing ofprotectiveclothing
- Procedures incorporate HPcontrols tominimize spreadofcontamination during work
- Radiological surveys will bescheduled andconducted byHP a Containment devices suchasdesigned barriers,containers andplastic bagswill beused toprevent thespread ofradioactive material a Physical decontamination ofTRDSareas oritems
$jjg e Physical barriers suchasHerculite
- sheeting, strippable paint, andtacky matstep-off A
pads tolimit contamination spread a
- Posting, physical areaboundaries andbarricades a Clean stepoffpads attheentrance point tocontaminated areas Personnel entries intoradiological contaminated areas will require theuse ofprotective clothing.
Thisclothing willconsist ofa suitable combination ofitems such asthe following, dependent upontheconditions outlined intheWAorRWP:
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 suit disposable outerclothing
- Faceshield 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 willbe minimized byutilizing engineering controls suchasthefollowing:
3-7
PC-000482/2 Ventilation devices-in-placeorportable HEPAfilters orTRDSventilation systems, ggg localexhaust byuseofvacuums
%$9 a
Containment devices-designed containment
- barriers, containers, plastic
- bags, tents, and glove-bags a
Source term reduction-application offixatives prior tohandling, misting ofsurfaces to minimize dustandresuspension W-Monitoring fortheintake ofradioactive material is required by10CFR 20.1502(b) iftheintake islikely toexceed 0.1ALI(annual limit on intake) during the year foranadult worker orthecommitted effective doseequivalent is likely toexceed 0.10 rem (1.0mSv)fortheoccupationally exposed minorordeclared pregnant woman.Airsampling willbeperformed inareas whereairborne radioactivity is present orlikely.
Prospective estimates ofworker intakes andair concentrationsusedtoestablish monitoring requirements will bebased onconsideration ofthefollowing:
a Thequantity ofmaterial(s) handled e TheALIforthematerial(s) being handled e Therelease fraction fortheradioactive material(s) based uponits physical formanduse Thetypeofconfinement being usedfor thematerial(s) being handled e Other factors that maybeapplicable
~
HPpersonnel will usetechnical judgment indetermining the situations that necessitate air sampling regardless ofgeneralized, prospective evaluations done fortheTRDS.
aea Prior toidentifying thelocation foranairsampler, the purpose oftheradiologicalair
$A*
sample will beidentified.
Various reasons exist forcollecting air samples.
Thefollowing areafewexamples:
a Estimation ofworker intakes
- Verification ofconfinement ofradioactive materials a Early warning ofabnormal airborne concentrations ofradioactive materials e Determining theexistence ofcriteria forposting anAirborne Radioactivity Area (ARA).
Smoketubes andbuoyant markers maythenbeusedtodetermine airflowpatternsin the area.
Airflowpatterns maybereevaluated ifthere arechanges attheTRDSthat mayimpact thevalidity ofthesampling locations.
Suchfactors might include thefollowing:
a Changes intheworkprocess a
Changes intheventilation system e
Useofportable ventilation that rnight alter earlier assessments After identifying thepurpose fortheairsample andflowpatterns areestablished, air sample locations areestablished asfollows:
e Forverification ofconfinement ofradioactive materials:
Locate samplers intheair flow nearthepotential oractual release point.
Morethanonesampling point maybeappropriate whenthere aremorethanone potential oractual release points.
3-8
PC000482/2 e Forestimationofaworker intake:
Samplerintakes will belocated asclose totheworkers breathing zones aspractical without interfering withtheworkorworker General workplace airsampler intakes will notbeplaced inornearventilation exhaust ducts unless their purposeistodetect systemleakage during normal operation, andif quantitative measurements ofworkplace concentrations arenotrequired.
Locations or number ofair samplers willbechanged whendictated bymodifications toFacility structure, changes in work processes, orelimination ofpotential sources.
Asufficient inventoryand variety ofoperable andcalibrated portable andsemi-portable air sampling equipment will be maintained toallow foreffective collection, evaluation, and control ofairborne radioactive material andtoprovide backup capability forinoperable equipment.
Airsampling equipment willbecalibrated atprescribed intervals orprior touse against certified equipment having known valid relationships tonationally recognized standards.
Table 3-1lists anticipated air sampling equipment.
Whentheworkbeing performed isa continuous
- process, a continuous sample witha weekly exchange frequency isappropriate.
For situations whereshort-lived radionuclides areimportant considerations, theexchange frequency will beadjusted accordingly.
Longer sample exchange frequencies maybeapproved by HP management forsituations where airborne radioactive material andnuisance dustare expected toberelatively low.Grab sampling forcontinuous processes mayalsobeapproved byHPmanagementbased upon consideration ofvariability oftheexpected source term for the facilityandprocess.
Grab sampling istheappropriate meansofairborne sampling forprocessesconducted intermittently, andforshort duration radiological workthatinvolves apotentialforairborne 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 mayalsobeidentified by,radionuclide, physical properties, volatility, andradioactivity.
Worker exposure tosignificant external deep-dose radiation fields isconsidered unlikely during this project duetothenature ofthecontaminants and/or theworkprecautions and techniques employed.
Workerexposure to airborne radioactivity mayoccurduring decontamination operations/work evolutions whichmayinvolve abrasives ormethods that volatilize loose and/or fixed contamination.
Exposure ofthepublic toexternal orinternal radiation fromthis Decommissioning Project isnotconsidered credible because ofthecontainment provided bytheFacility andthe access control provided fortheFacility andtheareasurrounding it.
Thetype(s) ofexposure controls usedtakes into account thecurrent state oftechnology and theeconomics ofimprovements inrelation tothebenefits.
Control ofpotential sources of radiation exposure toworkers andpublic asaresult ofdecommissioning activities will be achieved
- through, butnotlimited to,theuseofadministrative, engineering, andphysical controls.
3-9
PC-000482/2 Administrative controls consist ofbutarenotlimited to:
a Administrative doselimits that arelower than regulatory limits e
Training e
Radiological surveys Physical barriers suchas radiological warning rope/ribbon, incombination with radiological warning tape,lockable doors/gates aswellasinformation signs andflashing lights orotherapplicable barriers mayalso beused.
Engineering controls may consist ofbutarenotlimited to:
e HEPAventilation/enclosures e Protective clothing/equipment a
Access restrictions/barriers e Confinement Subcontractor personnel maybeusedfor certain requiredworkduring theTRDS Decommissioning Project.
Subcontractorswho willworkwithlicensed radioactive materials will berequired to:
e Attend andcomplete appropriate radiation safetycourse a Provide required exposure history information
- Readandsign anapplicable RWPandcomply with instructions sh a
Follow allspecial instructions given byHP
%59 a
Beescorted byacognizant authorized person listed onthe WA, unless specifically designated asanAuthorized Individual inthecurrent TRDSWA.
3.1.3Radioactive Material Controls GA'sradiation protection program establishes radioactive material controlsthat ensure the following:
e Prevention ofinadvertent radioactive material (licensed material) release touncontrolled areas.
e Assurance thatpersonnel arenotexposed inadvertently toradiation fromlicensed radioactive materials.
a Mmimization of theamountofradioactive wastematerial generated during decommissioning.
Allmaterials leaving theTRDSRestricted Areawill beradiologically surveyed toensure thatradioactive materials (i.e.,
licensed materials) arenotinadvertently removed.
Decommissioning Project andGAHealth Physics procedures will beused toensure that all potentially radioactive orcontaminated items removed fromtheTRDSsite aresurveyed.
Theperformance ofthese surveys will incorporate theguidance presented inU.S.NRC Circular No.81-07,"Control ofRadioactively Contaminated Material,"
andU.S.NRC Information Notice No.85-92, "Surveys ofWastes Before Disposal FromNuclear Reactor Facilities,"
(References 10-20 and10-21).
Thefollowing survey methods will beused:
3-10
PC000482/2 e W
- Direct frisking withaportable Geiger-Mueller detector ff$)
(e.g.,LudlumModel44-9orEberline ModelHP-210,orequivalent) having a
V minimum level ofdetection abovebackground oflessthanorequal to5,000 dpm/100 cm2 Sme.arjS.amplai
- Analysis with aGeiger-Mueller detector (e.g.,
Ludium Model44-9 orEberline ModelHP-210, orequivalent) having aminimum level ofdetection above background ofless than orequal to1,000 dpm/100 cm2 a
Bulk Materials (e.g.,sandandsoil)
- Analysis ofrepresentative sample(s) witha high resolution gamma spectroscopy systemhaving lowerlimits ofdetection, above system background, calibrated toavalue ofless than orequal to0.18pCi/gram for
' Cs(i.e.,
5180 pCi/kg).
Materials will bereleased if nodiscernable facility-related activity isdetected within the capability ofthesurvey methods presented above.
Inevaluation ofequipment and materials forfixed orsmearable licensed radioactive materials, items painted with other than original manufacturer's paint will notbereleased unless clear process knowledge demonstrates that thepaint wasapplied
- toaclean, non-radioactive surface prior to usein the TRDS RestrictedAreaor approval from Decommissioning Project Health
- Physics, has beenobtained andanacceptable survey course forthis situation hasbeenapproved. If thepotential exists forcontamination on inaccessible
- surfaces, theequipment will beassumed tobeinternally contaminated unless (1) theequipment isdismantled allowing accessfor surveys, (2) appropriate tool orpipe monitors withacceptable detection capabilities areutilized thatwouldprovide sufficient confidence that nolicensed materials werepresent, or(3) itmayreadily beconcluded that surveys fromaccessible areasarerepresentative of the inaccessible surfaces (i.e.,
- ggg, surveying theinternal surface frombothendsofa straight pipe froma nonradioactive
%Pf process system with cotton 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 bytheNRCoranAgreement
- 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 arebased onthenature ofthe workinvolved ineachtask
- item, theexpected number ofpersons tobeassigned toeach
- task, andtheindividual task duration periods asshownontheoverall project Schedule for TRDSD&D(see Figure 2-1).
h 3-11
PC-000482/2 TABLE 32:OCCUPATIONAL RADIATION DOSEESTIMATES FORTRIGAREACTORS DECOMMISSIONiNG TASKS Task
'TasIt Description DurationANo.
vg,Dose.Rat
' Total Dose Subtotal Total No.
C A
A
. P bra. persons?
'.Premlhr'persrem persrem' persrem 1
TRIGAReactor Facility D&D l
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 lGrapple/Hoist/Survey 72 3
0.005 1.08 8
Disassemble asnecessary 72 3
0.005 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 lRemove/Package 112 4
0.002 0.896 W
21 Surveyremaining Concrete 32 2
0.0005 0.032 22 Demolish remaining portion toexpose Soil 80 4
0.0005 0.16 23 Survey Soilpresumed 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 forLLWdisposal 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.
fromMkFRoom 80 4
0.0003 0.096 31 Reroute services toisolate MkFRoom 224 4
0.0002 0.1792 32 RemoveMake-Up WaterTank 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
' 111 /Durationj jNo;j'.yg,jDose RatETotal'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 toShipFuel 42 ShipFuelstored 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 aroundReactor 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 ShipLLWtoNTS 72 4
0.0002 0.0576 0.06 62 SurveySoil 112 2
0.0002 0.0448 0.04 63 Prepare SurveyReport 64 Submittal forRelease toUnrestricted Use 3-13
PC000482/2 This estimateisprovided forplanning purposes only.
Detailed exposure estimates and exposure controlsshall bedeveloped inaccordance withtherequirements oftheGA tid ALARA program during detailed planning ofthedecommissioning activities.
Areadose rates used forthis estimate arebased onprocess knowledge andcurrent survey maps (where available).
Thedoseestimate tomembersofthepublic asaresult ofdecommissioning activities is estimated tobe negligible.
Thisisbecause site perimeter controls will restrict members of thepublic from the areawheredecommissioningactivities aretaking place.
Thisis consistent with theestimate given forthe"reference research reactor" inthe"Final Generic Environmental Impact Statement ondecommissioning ofnuclear facilities" (NUREG-0586)
(Ref.
10-22).
Thedose tothepublic during decommissioning (DECON) andtruck transport transportation ofradioactive wastefromthereference research reactor referred to intheFinal Generic ImpactStatement isestimated tobe"negligible (less than0.1man-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 that ithasacontractual obligation toaccept alloftheTRIGAreactor fuel ataDOEdesignated fuel storage facility (see Contract DE-CR01-83NE4436).
Adate forshipment hasnotyetbeendetermined andisthe subject of ongoing negotiation.
Thecurrent fuel status isasfollows:
TRIGAMarkF Reactor-All reactor fuel elements havebeen removed from theTRIGA MarkFreactor core/shroud andplaced intheFuelStorage Canal.
TRIGAMarkIReactor-All reactor fuel elements havebeenrelocated tothe TRIGA Mark FFuelStorage Canal.
3.2.2Radioactive WasteProcessing Theprocesses ofdecontamination, remediation, anddismantlement oftheTRDSwill result insolid andliquid lowlevel radioactive waste,mixed waste,andhazardous waste.
Limited soil remediation isanticipated whichwill result insolid radioactive waste.Thiswastewill behandled (processed andpackaged),
- stored, anddisposed ofinaccordance with applicable sections oftheCodeofFederal Regulations (CFR),California Codeof Regulations (CCR),SanDiegoCounty andCityRegulations, disposal site Waste Acceptance
- Criteria, respective State Administrative
- Codes, GALicenses andPermits, and theapplicable implementing plans andprocedures.
Radioactive wasteprocessing includes wasteminimization orvolume reduction, radioactive andhazardous wastesegregation, wastecharacterization, neutralization, stabilization, solidification andpackaging.
3.2.3Radioactive WasteDisposal Lowlevel radioactive wastewill beprocessed andpackaged fordisposal attheNevada Test Site under thetermsofanagreement with DOE.Thevolume oflowlevel radioactive waste A
isestimated at4,000 cu.ft.Mixedlowlevel wastemaybetreated atGA'sNuclear Waste W
3-14
PC000482/2 o,
Processing Facility orprepared forshipment tooff-site commercial processing anddisposal facilities suchasEnvirocare ofUtah.
Lowlevel mixed wasteisexpected tobeminimal, v
less than50cu.ft.
10CFR 61,Licensing Requirements for LandDisposal 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 WasteCertification Officials, WastePackaging personnel, andWaste Characterization personnel toassure conformance toapplicable 10 CFR61requirements as stated inthespecific implementing procedures andplans.
Quality Assurance conducts audits and surveillances pertheQuality Assurance Program Document basedon ASME-NQA-1-1989, whichconfirms conformance withDisposal Site Acceptance Criteria and applicable 10CFR61requirements.
10 CFR 71,Packaging and Transportation ofRadioactive
- Material, establishes requirements forpackaging, shipment preparation, andtransportation oflicensed material.
Theradioactive wastethat will bepackaged andshippedwill beLSAmaterial.
GAisa USNRCandState ofCalifornia Licenseeto receive, possess,use,andtransfer licensed by-product andsourcematerials.
10CFR 71 requirements willbemetthrough the implementation ofProject andGA'sNuclear Waste Processing Facility (NWPF)
Packaging andShipping Procedures.
Training will beprovided forWastePackaging Personnel and WasteShipping Personnel toassure conformanceto applicable 10CFR71requirements.
LSNC'sNuclear Material Accountability Departmentprovides compliance oversight and off-site shipment notices.
Quality Assurance will confirm conformance to10CFR71 a
Subpart H(Quality Assurance) requirements through the implementation oftheGAQuality A
Assurance ManualandQuality Assurance Program Document.
10CFR71applicable Quality Assurance requirements apply
- todesign, purchase, fabrication,
- handling, shipping,
- storing, cleaning,
- assembly, inspection,
- testing, operation, maintenance,
- repair, and modification ofcomponents ofpackaging which areimportant tosafety.
10CFR20.2006, Transfer forDisposal andManifests, establishes requirements for controlling transfers oflow-level radioactive wasteintended fordisposal ataland 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 fortransport.
Theserequirements will bemetthrough theimplementation of Project andNWPFPackaging andShipping Procedures withtheoversight ofGA's LSNC's Nuclear Material Accountability Department.
Radiological andmixed wasteswill 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, asrequired, certification
- plans, qualification statements, assessments, wastestreamanalysis, evaluations andprofiles, transportation
- plans, and wastestreamvolumeforecasts.
Wastecharacterization, wastedesignation, waste traceability, wastesegregation, wastepackaging, wasteminimization, andquality assurance andtraining requirements ofthedesignated disposal sites will beincorporated in implementing procedures toassure conformance todisposal site requirements.
g Generator State (California) andTreatment/Storage/Disposal Facility States (Nevada,
- Utah, W
etc.)
requirements forradioactive andmixed wastemanagement will beincorporated into 3-15
PC000482/2 plans andprocedures toassure conformance withapplicable state regulations,
- licenses, and permits.
Applicablestateregulations include California Hazardous WasteManagement@$
Regulations (CaliforniaCodeofRegulations, Title 22),andUtahDepartment of Environmental Quality Rules(R313) forthecontrol ofionizing radiation reflected in Envirocare's Utah RadioactiveMaterial
- License, UT2300249.
TheProject will conform to GACAL-DHS, Radiological Health Branch (CAL-RHB)
License No.0145-80 topossess andusesource andbyproductmaterials asdirected byCCR,Title 17.GAwillalso conform tothe CAL-EPA requirements(EPA IDNumberCAD067638957) which permit/authorize GA tooperateasagenerator ofhazardous waste,totreat hazardous waste onsite under California's Tiered Permit program Conditional Authorization (CA) or Conditional Exemption (CE) tiers, andtomanage radioactive mixed wastesunderInterim Status granted bytheState ofCalifornia Department ofToxic Substances Control (CAL-DTSC).
TheProject will also conform totheGAHealth Permit tomanagehazardous materials issued bytheCounty ofSanDiegoDepartment ofHealth Services Hazardous Materials Management Division (SD-DHS-HMMD).
Project Plans andProcedures will also incorporate Metropolitan Industrial Waste Program(MIWP) requirements forthedischarge ofindustrial wastewaters into thesanitary sewersystem managed bytheCity ofSanDiego (San Diego Metropolitan Water District).
Radioactive wastewill bestaged indesignated controlled areas inaccordance withUSNRC 10CFR19and20requirements, CAL-DHS 17 CCR requirements, andtherequirements ofGA'sSpecial Nuclear Material License and State ofCaliforniaRadioactive Material License.
Mixed wasteswill bestaged indesignated controlled areas perEPA40CFR requirements, CAL-DHS22CCR,10CFR19and 20, andperlocal andstatepermits.
Measures will beimplemented through plans andprocedures tocontrol thespread of contamination, limit radiation
- levels, prevent unauthorized
- access, prevent unauthorized material
- removal, prevent tampering, andprevent weather damage.
Thedesignatedgy controlled areas will beapproved byWAs,Radiological Work Permits, and/or Hazardous%&F WorkPermits Radioactive andmixed wastematerial will bepackaged forshipment per 10 CFR, 40CFR, 49CFR,17CCR,22CCR,andthedesignated Disposal Site Criteria and placedin permitted interim storage (staged) until shipped.
Thequantity ofwastepackages staged for shipment will beafunction ofwastegeneration andpackaging
- rate, shipment preparation rate,shipment rate,anddisposal site acceptance rate.Tomeetthis objective,shipments will bescheduled throughout thelife oftheProject todesignated treatment,
- storage, and disposal facilities.
Radioactive material storage areas will becontained inside posted restricted areas according toexisting GAprocedures andconsistent with10CFR20.
3.2.4General Industrial Safety Program Industrial Safety andIndustrial Hygiene personnel, withProject Management, shall be responsible toensure that theProject meetsoccupational health andsafety requirements of Project personnel andthegeneral public.
Primary functional responsibility istoensure compliance withtheOSHAof1973asimplemented 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 ofworkareasandactivities toidentify andcorrectanyunsafe conditions andworkpractices; providing industrial hygiene services asrequired; administering theHazardous Work Authorization Program; andadvising Project 3-16
PC000482/2 management onindustrial safety matters andontheresults ofperiodic safety inspections.
(j[
The Project issupported byGAIndustrial Safety andIndustrial Hygiene personnel.
All personnel working ontheTRDSDecommissioning Project will receive Health and Safety training inorder torecognize andunderstand thepotential risks involving personnel healthand safety associated withtheworkattheTRDS.TheHealth andSafety training implemented atGAistoensurecompliance withtherequirements oftheUSNRC(10 CFR),the EPA (40 CFR),andbothOSHAandCAL-OSHA(29 CFRandCCRTitle 8).
Workers andregular visitors will befamiliarized withplans, procedures, andoperation of equipment toconduct themselves safely.
Inaddition, eachworker mustbefamiliar with procedures that provide forgoodquality control.
Section 2.5,Training
- Program, provides additional information.
3.3 Radiological AccidentAnalyses Thepotential radiological accidents for the decommissioning oftheTRDSwill bemainly associated withthe approximately250 TRIGA fuel elements stored inanexisting Fuel Storage Canalwithin theformer Mark F reactor poolcomplex.
Thisfuel storage may remain ineffect during apartofthe decommissioning ofthebuildings andfacilities related totheMarkIandMarkF reactors if arrangements toremovethefuel offsite aredelayed.
Factors considered inassessing potential radiological accidents are:
1)Fuel storage andremoval 2)Seismicity a
3)Fire o
4)Other considerations FuelStorage Thespent TRIGAfuel elements will bestored inracks inthestorage canalassociated with theMarkF reactor pool.
Thestorage canal is15feetdeepwith adequate radiation protection provided bythedepth ofwateroverthestored fuel.
ThePossession-Only-License conditions setforth inRefs.
10.2 and10.3 requires thatfuel bemovedandstored inaccordance withtheexisting Technical Specifications andGA procedures, until removed fromthesite.
Theproposed decommissioning action doesnot poseanyadditional criticality orfission product release risk.
Operations toremove MarkF reactor equipment notassociated withfuel storage will beconducted soastoavoid possible disruption oftheFuel Storage Canal while itisbeing used tostorefuel.
Aspreviously stated inSection 2.3.1.2, GAplans toperform limited decommissioning tasks ontheTRIGAMark Freactor prior toremoval offuel fromtheFSC.These
- actions, whichinclude thesurvey,
- handling, removal, sectioning, packaging, anddisposal of hardware items notassociated with orrequired forfuel
- storage, will necessarily becarried outinproximity totheirradiated TRIGAfuel situated intheFSCportion oftheTRIGA MarkFpool.
Inorder toprotect thesecurity ofstored fuel materials intheFSCduring such operations, several administrative andengineering controls will beapplied during this work,including thefollowing existing oradditional measures:
ff 1)Allexisting protective deckplates covering theFSCwill beinstalled andsecured in W
place during anydecommissioning-related activities.
317
PC000482/2 2)Allwork,including decommissioningrelated activities, occurring intheTRIGAMark 4,
F Reactor Roomwill beperformed by,orunder thedirect supervision of,currently$$E licensed Senior Reactor Operator(s).
3)Prior tothestart ofdecommissioning-related workinvolving theTRIGAMarkFpool, all unnecessary equipmentandmaterials shall beremoved fromtheTRIGAMarkF Reactor Room (refertoFigure 2.5),
andaStaging Areaonthenorth side oftheTRIGA MarkFpool shall becleared andprepared forreceipt ofhardware items removed from thepool.
4)Hardware itemsto be hoisted andremoved fromtheTRIGAMarkFpool areprimarily aluminum-construction pieces suchasthereactor
- shroud, grid-plates, beamtubes, neutron/gamma radiation detectors, andetc.,withno single itemorcomponent expected toexceed 200lbs.
5)Hardware items removed from the TRIGA MarkFpool shall besecurely grappled and rigged with appropriately-certified lifting equipment.
6)Hardware items removed fromthe TRIGA Mark Fpoolshall behoisted nohigher than decklevel which isoverthepool, using the installed 3Toncapacity Electric Hoist or equivalent, andshall beimmediately translated inanortherlydirection totheStaging Areaforsubsequent processing.
During decommissioning-related work,limit controls shall beinstalled onthe'IRIGA MarkF Electric Hoist topreventtranslation ofloads overtheFSC.
SAsmi.city SanDiegoCounty hasbeenconsidered oneofthemoremoderate seismic risk regions in Southern California.
Thehistorical pattern ofseismic activity has generally been characterized by a broadscattering ofsmallmagnitude earthquakes, whereas the surrounding regions arecharacterized byahigh rateofseismicity withmany moderate-to-large-magnitude earthquakes.
Arecent study(see Appendix B,Ref.5.8) estimated theprobabilities oflargeearthquakes occurring inCalifornia onthemajor strands oftheSanAndreas fault system.
Inaddition to theprincipal traces oftheSanAndreas
- fault, earthquakes occurring onthe other major faults ofthesystem(San
- Jacinto, Imperial, etc.)
werealso considered.
Thestudy estimated that theprobability ofamagnitude 7orgreater earthquake occurring inthenext30yearsin Southern California (along theSouthern SanAndreas,
- Imperial, orSanJacinto faults) is 0.5orgreater.
- However, aquake ofmagnitude close to7 onthese fault lines isnot expected tosignificantly impact theGAsite because ofintervening distance.
Current information (see Appendix B,Ref.5.9)
- however, indicates theRoseCanyon, Coronado Bank,SanDiegoTrough,
- LaNacion, andElsinore fault zonesarecapable of generating strong ground motion intheSanDiego area.
Possible Richter magnitudes for earthquakes onthese faults canbeashigh as7.0,7.5,7.5,6.3and7.5,respectively.
Passing approximately 3miles (5km)westoftheGAsite, theRoseCanyon fault isthe nearest active fault.
Thepresence ofthree small,local faults wasconfirmed bytheWoodward-Clyde Consultants field reconnaissance ofthesite(see Appendix B,Ref.5.11).
Anunnamed fault inthenorthern portion ofthesite trends easttowestthrough proposed lots 25,26, w
31,and32.TheSalk fault ismapped inthesouthern portion ofthesite andalso trends east ff towest.A northerly trending fault islocated inthesoutheastern areaandcrosses the 3-18
PC000482/2 Ae Genesee Avenuecanyon.
Allofthese faults aremapped asbeing overlain byearly Pleistocene formations which have notbeendisplaced.
Therefore, thefaults on-site arenot considered active.
Decommissioning activities willinvolve decontamination andremediation.
Plans and specifications foranyremediationwhich could affect thestructural integrity ofthebuilding would bereviewed byastructural engineer toassure that these alterations would notrender the buildingunsafe.
Decommissioning will notposeadded risk toworkers during aseismic event.
Ei.re TheTRDSwill notcontain combustible material insufficient quantity tosupport amajor fire.
Itispossible forasmall fire tooccurasaresult ofanelectrical
- fault, asanexample.
Portable extinguishers anddetection will beprovided asneeded.
There should beno radiological hazard asaresult offire.
Other Considerations Radiological accidents could occur duringremoval andpackagingofactivated components andequipment.
- However, this riskisvery low considering theadministrative precautions whichwill betaken during decommissioning.GA experience inD&Dprojects, including thehandling ofactivated/contaminated components and control ofjobactivities utilizing written andapproved procedures, will ensure the safe conduct oftheproject.
Consequences ofapoolleak arelowbecause thepool water iscontinuously treated and g,
contains negligible radioactivity.
Themainfunction ofthe pool istoprovideshielding for A%y' workers positioned nearorovertheFSCduring anyrequiredhandling, inventory related, ortraining operations.
Thewaterisnotrequired forfuel cooling.
Any failure tomeet shielding requirements would result inworker restrictions onapproach to theFSCuntil the requirement could bemet.Theother potential consequence would bedue to flowing water carrying loose contamination toanewlocation within thefacility, outside the facility, or into thesoil.
Since loose contamination isminimal, therisk ofspread ofcontamination is low.Thereisnopotential forairborne contamination fromsuch anevent.
3-19
PC000482/2 4.
PROPOSED FINALRADIATIONSURVEYPLAN Theintended course ofaction forTRDSdecommissioning, based uponconsideration ofsite and facility radiological characterization
- results, istostrive todecontaminate structural materials tothe extent practicable in balance withradioactive wasteminimization considerations, anddismantle TRDSsystems tothe extent necessary forremediation, andpackaging forburial those materials that cannot reasonablybe decontaminated.
Assuch,theFinal Release Survey Plan(and subsequent Final Survey Report) discussed inthis section deals with release ofthebuilding structure ofthe TRDSremaining after decontamination andremediation
- actions, andtheTRDSproperty to unrestricted use.This sectionwill alsodiscussthesurvey methods that will beutilized.
4.1 Description ofFinal Radiation SurveyPlan Thepurpose oftheFinal Radiation Survey istodemonstrate that theradiological condition oftheTRDSsite structure areator below established release criteria (see Section 2.8) in anticipation ofU.S.
NRCapproval to terminate theTRIGAReactor licenses andtorelease theTRDSforunrestricted use.TheFinal Release Survey Plan(and report) will deal with release oftheTRDSstructure andsite tounrestricted use.
GA hasdeveloped itsFinal Release Survey Plan usingtheguidance provided in NUREG/CR-5849 (draft)
(Ref.
10.10).
4.1.1Means forEnsuring thatallEquipment,
- Systems, Structures, andSiteare Included intheSurveyPlan Everyitemthat istoberemoved fromtheTRDSwillbe evaluated forability to decontaminate andradiologically surveyed toensure that radioactive (i.e.,
licensed) materials arenotinadverently removed fromthefacility (see Section 3.1.3). Whenitis impractical ornotpossible todecontaminate anitemsuchthat it exhibits nodiscernable facility<elated activity whensurveyed following methods presented inSection 3.1.3,the itemwillbe treated as radioactive waste.Thesystematic approach to TRDS decommissioning will ensure that every itemorstructural component inthe
'IRDS is specifically evaluated forrelease before beginning theFinal Release Survey. The Final Release Survey will treat theTRDSas"affected" toensure 100%survey coverageprior to requesting TRDSreactor license termination andrelease oftheproperty for unrestricted use.
4.1.2Means forEnsuring thatSufficient DataisIncluded toAchieve Statistical Goals GAhasdeveloped the'IRDSFinal Release Survey Planusing theguidance presented in NUREG/CR-5849.
By using this
- guidance, theProject will satisfy theU.S.NRC recommended statistical goals.
4.2 Background
SurveyResults TheFinal Release Survey Guideline values forresidual activity aretaken tobelevels above thenaturally occurring background radiation.
Thefinal release measurements will consist ofacombination ofgeneral arearadiation values andareasurveys.
Inaddition, adetailed micro-R radiation survey oftheremaining structure andsite will beperformed and compared tobackground measurements.
4-1
PC-000482/2
Background
radiation asencountered atanylocation includes contributions duetoboth a
natural radiationsources andmanmade sources.
Natural radiation sources include terrestrial NEE radioactivity duetonaturally occurring radioisotopes insoils andconstruction
- media, airborne radioactivity (principally radon andradonprogeny) fromtheradioactive decay of certain of these naturallyoccurring radioisotopes, andcosmic radiation fromhighspeed particleinteractions intheearth's atmosphere.
Manmade background radiation asitwould impact theFinal Release Survey wouldprimarily consist ofatmospheric fall-out offission products dueto weapons testing andreactor accidents andanycontribution that might exist asaresult ofother licensees' activities.
Thegeneral area background radiation aswouldbemeasured withthemicro-R meteris influenced byanumber of
- factors, principallythenaturally occurring radioactivity insoils andother nearby materials, radon andradon progeny concentrations
- intheair, andextent ofcosmic radiation (whichvaries withelevation).Duetothenumber ofinfluences, the natural background varies appreciably fromlocation tolocation, day-to-day (even timeof day)andseason-to-season asrelated tochanging weather conditions andmaterials inthe surroundings.
Thesite andfacility characterization study included measurements toestablish background radioactivity
- insoils, concrete, andasphaltthat were considered representative ofthose that wouldbeencountered intheFinal ReleaseSurvey.
Oneoftheprincipal constituents of global
- fallout, 137CS, which isfound principallyas a result ofatmosphericweapons testing andreactor accidents isalso theprincipal fission product contaminant attheTRF.l"Cs has beenseentobepersistent intheupper 15cm(6in.)of soil withconcentrations decreasing beyond this depth(Ref.
10.12).
Release criteria (e.g.,
Regulatory Guide1.86) wereestablished asanincrement inexcess A
ofbackground values.
Therefore, theFinal Release Survey will include theestablishment W
ofbackground arearadiation levels using theguidance ofNUREG/CR-5849.
- Asphalt, concrete andother construction material background values will beestablished bytaking measurements onunaffected facilities and/or portions oftheGAproperty representative of unaffected TRDSconstruction materials.
4.3 FinalRelease Criteria-Residual Radiation andContamination Levels Thecriteria forrelease oftheTRDSfacility/site tounrestricted use,after completion of the decommissioning activities described inthis
- plan, arepresented inSection 2.8.
In
- summary, they are:1)those given intheU.S.NRCRegulatory Guide1.86, "Termination ofOperating Licenses forNuclear Reactors,"
and2)anexposure rateduetoresidual radionuclides
- asaresult offacility operation
- notinexcess of5micro R/hrabove natural background measured at1meterfromthesurface.
(Ref.
"Action PlantoEnsure Timely Cleanup ofSite Decommissioning Management Plan Sites,"
FRVol.57No.74April 16, 1992).
4.4 Measurements forDemonstrating Compliance withRelease Criteria 4.4.1Instrumentation-Type, Specifications, andOperating Conditions Instrumentation utilized during theFinal Release Survey (and equipment andmaterials survey) will beselected basedupontheneedtoensure that site residual radiation will not exceed therelease criteria.
Inorder toachieve this
- goal, instrumentation that issensitive to theisotopes ofconcern andcapable ofmeasuring levels below 75%oftheguideline values a
forthose isotopes willbeselected.
Instrumentation selected willbebaseduponthe recommendations ofNUREG/CR-5849.
Instrumentation that isavailable fortheFinal 4-2
PC000482/2 Release Survey, andtheir respective detection range capability waspresented inTable 3-1 of thisplan.
Instrumentation that isusedinthesurveys will becalibrated against sources and standards that areNISTtraceable andrepresentative oftherepresentative isotopes encountered attheTRDS.Instruments will beoperationally tested
- daily, orprior toeach use,whichever isless frequent.
Instruments will notbeusedinconditions that arenotin conformance withmanufacturer recommendations.
4.4.2 Measurement Methodology forConduct ofSurveys Theentire TRDS site willbetreated asan"affected" areainaccordance withthedef'mition provided inNUREG/CR-5849.
Theyard areawascharacterized during facility radiological characterization scoping survey. This Decommissioning Planpresumes that theTRDShas beendecontaminated tothe extent practicable prior totheFinal Release Survey.
TheTRDS structure andsite will bemethodically remediatedasnecessary prior toconduct oftheFinal Release Survey.
Thecharacterization resultsandthecontinuous feedback fromremediation surveys will bethebasis for remediation efforts.
Theonlyradionuclides identifiedin the TRFandadjacent yards during radiological characterization efforts were137Cs (predominant nuclide),60Co andto'alesser extent(in onlyonesoil sample)
- Cs.These isotopes arereadilydetectable usingp-ysensitive instrumentation.
Furthermore, allofthese isotopes arereadily detectable withgamma spectrometry techniques aswell.
Tosupport thefinal
- survey, portions ofthe TRDS will begriddedinto areasthat are10 metersby 10meters.Eachgridwillbesurveyed initially witha surface scanning instrument systemtoascertain locations ofanyelevated concentrations.
Inaddition, systematic measurements maybeperformed within each grid atlocationsequidistant an between thecenterandeachofthefour grid block corners.
g Ifanylocation within agrid requires remediation inorder tosupport adecision infavor of release tounrestricted use,theentire affected grid will bescanned again after completion of remediation efforts.
4.4.3 FixedContamination SurveyProtocol Thesurfaces ofequipment andmaterials will besurveyed inaccordance withProject and GAHPprocedures forrelease ofequipment andmaterials tounrestricted use.
Direct frisk will beperformed witheither a portable Geiger-Mueller, ora gasflow proportional
- detector, asdictated bytheminimum detectable activities ofthe instrument/probe, orbeta-scintillator forthecontaminants ofconcern andtheassociated release criteria.
Inany situations whereprocess knowledge wouldsuggest apotential foralpha
- activity, survey withalpha detection instruments orcounters willalsobeemployed.
Inevaluation of equipment andmaterials forfixed orsmearable licensed materials, items painted withother thanoriginal manufacturer's paint will notbereleased unless (1) clear process knowledge demonstrates that thepaint wasapplied toaclean non-radioactive surfaceprior touseinthe restricted area,(2) thepaint isremoved or(3)
Health Physics approved paint sampling survey demonstrates that radiation levels under thepaint arebelow therelease criteria.
Ifthe potential exists forcontamination oninaccessible
- surfaces, theequipment will beassumed tobeinternally contaminated unless (1) theequipment isdismantled allowing access for
- surveys, (2)appropriate tool orpipe monitors withacceptable detection capabilities are utilized that would provide sufficient confidence that nolicensed materials werepresent, or (3) itmayreadily beconcluded that surveys fromaccessible areas arerepresentative ofthe inaccessible surfaces (i.e.,
surveying theinternal surface fromboth endsofastraight pipe fromanonradioactive process system withcottonswabswouldberepresentative ofthe
/
inaccessible areas).
Theresults ofcontamination surveys will berecorded either onsurvey 4-3
PC-000482/2 maps orspecial release logs.
Results ofallsurveys willbecompared toaverage and maximum criteria prior toanymaterial being released.
4.4.4Removable Contamination SurveyProtocol Removable contamination will beassayed bycollection of100cm2smears fromsurfaces, oraspracticable. Thesmearsamples will beevaluated using suitable hand-held instruments orlowlevel beta counting systems.
As discussed inSection 4.4.3, smearswillbe evaluated for alpha contaminants ifprocess orsurvey information recommends
- this, though TRDSDecommissioning HealthPhysics personnel routinely evaluates a portion ofits positive smears for alpha contamination.
Survey evaluations arerecorded inthesame mannerdescribed inSection 4.4.3.
4.5 MethodstobeEmployed for Reviewing, Analyzing, andAuditing Data 4.5.1Laboratory/Radiological Measurements Quality Assurance During decommissioning survey activities, many direct andindirect measurements and sample mediasamples willbe collected,
- measured, andanalyzed forradiological contaminants.
Theresults ofthese surveyswill beutilizedtoevaluate thesuitability ofthe material oritemforrelease tounrestricted
- use, or whether decontamination ofstructures, components, andthesurrounding site have achieved thedesiredresult.
Sample collection,
- analysis, andtheassociated documentation will adhere towrittenprocedures andmeetthe guidance oftheU.S.
NRC,aswellascomply withrecognized industryrecommendations andgoodpractices.
Outside (i.e.,
non-GA) laboratories selected toanalyze TRDS decommissioning samples shall beapproved bytheGAQuality Assurance organization and listed ontheQAApproved Suppliers List maintained bythe GA Quality Assurance Group.
Organizations that perform radiological monitoring measurements recognize theneedto establish quality assurance programs toassure that radiological monitoring measurements arevalid.
These programs areestablished forthefollowing reasons:
(1) to readily identify deficiencies inthesampling andmeasurement processes tothose individuals responsible forthese activities sothat promptcorrective action canbetaken, and(2) to routinely monitor thesurvey andlaboratory measurement results inorder toassure that results and conclusions arevalid.
4.5.2Supervisory andManagement ReviewofResults Radiological surveys areconducted byHealth Physics Technician staff members whoare trained andqualified.
Inaddition, radiological surveys andsample results arereviewed bya senior level member oftheHealth Physics staff other thantheindividual that performed the survey.
Final Radiation Survey data isalso reviewed bytheHPManager andtheTRDS Decommissioning Project Manager.
4-4
PC000482/2 5.
TECHNICALSPECIFICATIONS Currently applicable Technical Specifications fortheGATRIGAMarkIReactor aresetforth in Amendment No. 35toFacility License No.R-38(TRIGA MarkIReactor)-General Atomics (TAC No.M97502),
IssuedbytheUSNRC,dated October 29,1997(Reference 10.2).
Currently applicable Technical Specifications fortheGA'IRIGA MarkF Reactor aresetforth in Amendment No.43 to Facility License No.R-67(TRIGA MarkF Reactor)--General Atomics (TAC No.M90380),
Issued bytheUSNRC,dated March22,1995(Reference 10.3)
Asdecommissioning progresses, further requests forchanges totheTechnical Specifications will besubmitted inanapplicationfor amendment tothelicense pursuant to10CFR50.59.
=
51
PC000482/2 6., PHYSICALSECURITYPLAN AllGAradiation restrictedareas aresecured fromunauthorized entry.
During non-working
- hours, all nuclear facilities arelocked.
GAmaintains 24hoursecurity watchmen topatrol thesite.
Existing physical security andmaterial control andaccounting plans approved bytheNuclear Regulatory Commission, asmaybeamended, will continue tobeimplemented.
These existing plansmeet therequirements in10CFR70.38fordecommissioning, andwill be maintained asrequired by the MkF Possession OnlyLicense amendment (Ref.
10.3),
andtheMkI Possession Only License amendment (Ref.
10.2).
Compliance withParts 50and73 ofthephysicalsecurity plan isassured because allofthe elements oftheplan aremaintained until thefuel isremoved offsite.
Decommissioning activities will beconducted with thefuel intheFSC andall physical security andsurveillance inplace.
Once isolation ofcommonservices hasbeen implemented, thesecurity oftheMarkFreactor andcontrol roomscanbemaintained without impact ondecommissioning activities intheMarkIreactor room.
Workers will belimited innumber and appropriately trainedbefore entry tothesite.
Oversight will beprovided during anyentry into theMarkFroom forpurposes ofreactor equipment removal not associated withtheFSCorfuel.
6-1
PC000482/2 7.
EMERGENCYPLAN GAhas a Radiological Contingency Plan,supplemented byprocedures specific tothe'IRF, as requiredby the USNRC andState ofCalifornia.
Training ontheRadiological Contingency Planis provided tothe Emergency
Response
andRecovery Director andAlternates.
Emergency
Response
Teammembers receive trainingappropriate forresponding toemergencies.
7-1
PC-000482/2 8.
ENVIRONMENTAL REPORT TheEnvironmental Report isprovided asAppendix B.
c 8-1
PC-000482/2 9.
CHANGESTO THE DECOMMISSIONING PLAN Asthedecommissioning progresses, changes totheTechnical Specifications uptotermination of the license will beviaaRequest forLicense Amendment pursuant to10CFR50.90.
GArequests that other changestotheDecommissioning Planbeallowed without prior USNRC approval whichinvolve decommissioning activities unless anunreviewed safety questions is involved.
Anunreviewed safety question involves:
1 Theincrease ofprobability ofoccurrence ortheincrease ofconsequences ofanaccident or malfunction ofequipment important tosafety compared tothat situation previously evaluated in theSAR,or 2.Thepossibility foranaccidentor malfunction ofadifferent typethan previously analyzed inthe SAR,or 3.Thereduction inmargin ofsafety asdefined intheSAR.
- Reports, records
- ofchange, andretention ofdocuments will beinaccordance with theapplicable portions of10CFR50.59.
9-1
PC-000482/2
- 10. REFERENCES 10.1 NUREG-1537 Rev.0,"Guidelines forPreparing andReviewing Applications forthe Licensing ofNon-Power Reactors".
10.2Amendment No.35toFacility License No.R-38(TRIGA MarkIReactor)-Genera Atomics(TAC No.M97502), Issued bytheUSNRC,dated October 29,1997.
10.3Amendment No.
43 toFacilityLicense No.R-67(TRIGA MarkF Reactor)-Genera Atomics (TAC No.
M90380),
Issued bytheUSNRC,dated March22,1995.
10.4USNRCLicense 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, 50-89 and 50-163; Decommissioning Financial Assurance,"dated May20,1996.
10.6Weiss,Seymour H.AndRobert C.Pierson LettertoDr.Keith E.Asmussen, "Financial Assurance forUSNRCLicenses SNM-696, R-38, R-67/Docket Nos.70-0734, 50-89, 50-163,"dated July 9,1996.
10.7ASME-NQA-1-1989, "Quality Assurance Program Requirements forNuclear Facilities" 10.8General Atomics Quality Assurance Program Approval by theUSNRCTransportation Storage Inspection
- Section, Spent FuelProject
- Office, Nuclear MaterialsSafety and Safeguards, Approval No.0030,Rev.6,July 9,1996.
b 10.9USNRCRegulatory Guide 7.10, "Establishing Quality Assurance Programs forPackaging UsedintheTransport ofRadioactive Material".
10.10NUREG/CR-5849, "Manual forConducting Radiological Surveys inSupport ofLicense Termination,"
Draft forComment, June1992.
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 Guide4.15,"Quality Assurance for Radiological Monitoring Programs (Normal Operations)-Effluent Streams andthe Environment,"
Revision 1,February 1979.
10.14"General Atomics Site Decommissioning 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, SanJose, CA;1989.
10.16ANSStandard 15.8, "Quality Assurance Program Requirements forResearch Reactors."
10.17GARadiological Contingency Plan.
10-1
PC000482/2 10.18 U.S. Atomic Energy Commission, Regulatory Guide1.86,"Termination ofOperating Licenses forNuclear Reactors,"
dated June1974.
10.19 U.S.
Nuclear RegulatoryCommission, "Action PlantoEnsure Timely Cleanup ofSite Decommissioning ManagementPlanSites,"
Federal Register/Vol.
57,No.74/Thursday,
- April16, 1992.
10.20U.S.
Nuclear Regulatory Commission, IECircular No.81-07, "Control ofRadioactively ContaminatedMaterial,"
May14,1981.
10.21U.S.Nuclear Regulatory Commission, IEInformation Notice No.85-92, "Surveys of Wastes Before Disposal From Nuclear Reactor Facilities,"
December 2,1985.
10.22U.S.Nuclear RegulatoryCommission, NUREG-0586, "Final Generic Environmental Impact Statement ondecommissioning ofnuclear facilities,"
August 1988.
10-2
PC000482/2 A1
PC000482/2 LISTOF TABLES AM Table A-1-TRF AreaClassificationsfor 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 usedforMediaSample Locations for Radiological ScopingStudy....................................................
A-7 Figure A-2-Grid MapofTRIGA Reactor Facility showing Radiological Measurement Results from RadiologicalScoping Study.............=..........,.........
A-8 Figure A-3-Schematic ofthe RoomLayout fortheTRIGAReactor
- Facility, Building 21 A-9 LISTOF SURVEY RESULTS Rm.21/102, Survey
- 21-97-00004
................A-10
-00005
....A-11
-00023
..............................................A-12
-00009
......................................................A-13
-00019
.........................A-14 Rm.21/105, Survey
- 21-97-00030
........................................................A-15
-00036
..............................................A-16
-00032
....................A-17
-00037
..........................................A-18 few
-00031
........................................................A-19 W
Rm.21/106, Survey
- 21-97-00029
=....................,.,
.................,.........A-20
-00038
...........................................................A-21
-00033
.<...........A-22
-00039
......................................................A-23
-00034
..........................................................A-24 Rm.21/107, Survey
- 21-97-00010
................................=................A-25
-00011.............................................................A-26
-00024
.........................................................A-27
-00012
........................................A-28
-00014 L
..............A-29 Rm.21/108, Survey
- 21-97-00025
............................=.........A-30
-00027
.,.....................................................A-31
-00040
..............................A-32
-00026
.=....
...........,....A-33
-00028...........................................................A-34 Rm.21/109, Survey
- 21-97-00046
................A-35
-00048
..............................................A-3
-00044
................................................................A
-00050
..........=.....................
,...A-38
-00045 Rm.21/110, Survey
- 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#21-97-00052..........................................A-50
-00054........................................................A-51
-00055............................................................A-52
-00059..........................................................A-53
-00058............................................................A-54 Rm.21/113, Survey
- 21-97-00051.............................................................A-55
-00053................................,........................A-56
-00056......<..................................A-57
-00060..................=................A-58
-00057..................n......................A-59 Rms.21/114
& 115,Survey
- 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 wasperformed ontheTRIGAReactor Facility (TRF) tosupport decommissioning planning.
Duetotheoperational status ofthe'IRIGAMarkIReactor, the radiological scoping characterization wasnotaninvasive study that involved defacing facility structures bycollection ofbuilding constructionmediasamples.
Outside theTRFmediasamples wereobtained for surrounding soils,asphalt, andconcrete.
TheTRFwasfirst evaluated from process knowledge andpastradiological surveillance.
Based uponthis evaluation, variousportions ofthecomplex andits associated yard areclassified aseither "affected" or"unaffected."
Affected areas areareas thathavepotential radioactive contamination (based onprocess knowledge) orknown radioactive contamination (based onpastradiological surveillance).
Unaffected areas areall areas notclassified asaffected.
Table A-1showsthe classifications ofareas within the facility.
TableA1-TRF AreaClassifications forCharacterization Affected Areas 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 FControl Room Room104-Office Room109-Mark IIIControl Room Restrooms Room110-Mark IIIExerimental Area En andOffice Area Corridors Room111-MarkIIIReactor Electrical Pads
- A Room112-Thermal Stabilit X-Ra Room U
Room113-Thermal Stabilit Lab RoomI14-North En Room115-Decontamination Room AllYardArea/Roof MarkIShed CoolinTowerYardAreaStora eShed Machine Sho Sampling
- protocol, sample preparation, survey andmedia result documentation, andanalytical methods forthescoping study werebased uponRefs.
A-1through A-7.Pages A-10through A-68 arecopies ofthesurvey mapsfromthestudy.
W Agrid mapoftheTRF,including building surrounding areas (soils,
- asphalt, concrete) isprovided inFigure A-1.
Systematic media samples oftheTRFwereobtained atgrid intersections showninFigure A-2.In
- addition, onejudgment sample location wasusedtoobtain soil/asphalt samples based onprocess knowledge.
Thirty-two soil mediasamples, 21asphalt mediasamples, andoneconcrete media sample wereobtained forradiochemical analysis.
Thefirst approximate 6inch depth ofsoil inthe shape ofa4 inchdiameter
- cylinder, carved outbyacoring
- tool, wasobtained forsoil media samples.
Inonecase,location (X,1),nosoil could becollected duetothedepth oftheasphalt.
Asphalt andconcrete mediasamples wereobtained similarly using thecoring tool toproduce approximate
.6inchtall, 4 inchdiameter cylindrical samples ofasphalt/concrete.
Figure A-2 A
presents themedia sample radiological results entered onthegrid map,fortheTRF.
W A-4
PC000482/2 The results ofradiological analyses forsoil media samples including sample location andidentifica-tionnumber areprovidedinTable A-2.Theresults ofradiological analyses forasphalt/concrete mediasamples including sample location andidentification number areprovided inTable A-3.
FM Theradiological scoping surveyshowed thefacility areas tobewell maintained withonlyminor amountsofresidual radioactivity discovered.
Itisrecognized that components associated withthe TRIGAreactors, and some surrounding structural materials will beactivated asaresult ofreactor operations.
Inside ofthe facility
- itself, surveys ofaffected areasshowed verylittle residual radioactivity.
Rooms102 and 107,theMarkIandMarkF Reactor roomsrespectively, both showed several locations offixed radioactivity onthefloor
- surfaces, andRoom107also hadone location ofloose surface activity.
Figure A-3isaschematic oftheroomlayout fortheTRF.
TableA2-ResultsofRadiochemical AnalsesforTRFSoilMediaSam les Location
& Remarks SamleID GammaIsotoicResults(Ci/)
GridX,4, soil samlebeneath ashalt 21S-97-001 natural activit on)
Grid(X,5, soil samlebeneath ashalt 21S-97-002 0.04137Cs GridY,4, soil samlebeneath ashalt 21S-97-003 natural activi onl Grid2,5, soil samlebeneath ashalt 21S-97-004 0.04134C3 gjg137CS GridY,6, soil samlebeneath ashalt 21S-97-005 naturalactivi onl Gridz,6, soil samlebeneath ashalt 218-97-006 0.06"Co,0.37137C3 GridY+0.5,6.5
, soil samlebeneath ashalt 21S-97-007 0.26 137C3 Grid/Y,7, soil samlebeneath ashalt 21S-97-0080.03 "Co, 0.53137C3 GridX,6, soil samleonl 218-97-0090.45 "Co, 0.02134Cs, 1.24'37G
(
Grid(Y,5, soil samlebeneath ashalt 21S-97-010naturalactivit onl T"
- Grid(2,7, soil samleonl 21S-97-0119.24"Co,29.59 137C3
- GridW,4, soil samlebeneath ashalt 218-97-012natural activit onl Gridz,2, soil samleonl 21S-97-0130.43"Co,0.59l"Cs Grid2,1, soil samleonl 215-97-0140.69"Co,0.43 137Cs Gridz,0, soil samleonl 21S-97-0150.306"Co, 0.30l"Cs GridY,0, soil samleonl 21S-97-0160.16"Co,0.42137C3 GridA,1, soil samleonl 2lS-97-0170.956"Co, 1.26137C3 Grid(2,-1, soil samleonl 215-97-0180.11"Co,0.17l"Cs GridY,-1),soil samleonl 21S-97-0190.06"Co,0.20'"Cs GridX,-1, soil samleonl 21S-97-0200.22"Co,0.29137CS GridU,1, soil samleonl 21S-97-0210.11"Co,0.60137Cs GridA,4, soil samlebeneath ashalt 21S-97-0230.10'"Cs GridA,3, soil samlebeneath ashalt 21S-97-024natural activit onl GridA,2, soil samlebeneath concrete 21S-97-0250.04'"Cs GridV,2, soil samlebeneath ashalt 21S-97-026natural activit onl GridV,1, soil samlebeneath ashalt 21S-97-027natural activit onl Grid(X,0, soil samlebeneath ashalt 218-97-028natural activit onl GridX,3, soil samlebeneath ashalt 21S-97-0290.0613703 GridV,0, soil samlebeneath ashalt 21S-97-030natural activit onl GridW,0, soil samlebeneath ashalt 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 Analyses forTRF Asphalt/Concrete Media a
Sam les WE Location
& Remarks Sam leID GammaIsotoicResults(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-97-0040.48l"Cs GridY,7),ashalt samle 21B-97-0050.386"Co, 1.38137C3 GridY,6),ashalt samle 21B-97-0060.30137Cs Grid2,6, ashalt samle 21B-97-007 1.32l"Cs GridY+0.5,6.5
, ashalt samle 21B-97-008 2.90137Cs GridW,4, ashalt samle 21B-97-009 natural activit onl Grid(Y,5, ashalt samle 21B-97-010 0.4060Co, 0.16137C3 GridX,3, ashalt samle 21B-97-011 0.22137Cs GridA,4),ashalt samle 21B-97-012 0.316"Co, 0.25137C3 GridX,0),ashalt samle 21B-97-013 natural activi onl GridY,1),ashalt samle 21B-97-014 0.35137CS GridV,2, ashalt samle 21B-97-015 naturalactivit onl GridV,1, ashalt samle 21B-97-016 natural activit onl GridW,1, ashalt samle 21B-97-017 natural activit onl GridV,0, ashalt samle 21B-97-018 natural activionl GridW,0, ashalt samle 21B-97-019 natural activit onl GridX,1, ashalt samle 21B-97-0200.73137Cs GridA,3),ashalt samle 21B-97-021natural activit onl Grid(A,2),concrete samle 21C-97-001natural activit onl Unaffected Areas Theremaining roomsandareasofthe'IRFareconsidered unaffected areas.For these unaffected
- areas, radiological surveys consisted oflarge areamasslin smears ofthefloor and walls toroughly 2metersabove
- thefloor, at1m2intervals, floor monitor/surface scansurveys, and contamination surveys offloor drains andsinks.
No areas ofcontamination werediscoveredin surveys of unaffected areas.
A-6
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PC000482/2 TABLEOF CONTENTS 1.PURPOSE ANDNEEDFORACTION...........................................B4 2.FACILITY DESCRIPTION, PROPOSED ACTIONANDALTERNATIVES, ANDADMINISTRATIVE 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 3.1.1 Radioactive Materials...................................................................B-12 3.1.2 Hazardous Materials....................................................................B-14 3.1.3 Transportation................................................B-14 3.1.4 Cultural andHistorical Resources..........................<.......................B-15 3.1.5 Population andLand Use.....,..................................................B-15 3.1.6 Noise....................................................................B-15 3.1.7 Aesthetics........................................................................B-16 3.2Natural Environment.................................................................B-16 3.2.1 Topography, Geology andSeismicity.................
.................B-16 3.2.2 Climate andAirQuality
..............................................................B-17 3.2.3 Hydrology.............................................................................B-19 3.2.4 Biology
...................................................B-20 3.2.5 Socioeconomics andEnvironmental Justice.........................................B-21 4.POTENTIALENVIRONMENTALCONSEQUENCES OF PROPOSED ACTIONANDALTERNATIVES................................................B-21 4.1HumanHealth Effects....................................................................B-21 fo 4.1.1 Hazard Identification.........................................................B-21 C
4.1.2 Potential Exposures................................................B-22 4.1.3 Transportation...................................................................B-23 4.2Waste Disposal......,................................................................B-23 4.2.1 Hazardous Waste
....,............,=...........................B-23 4.2.2 Low-Level Radioactive andMixed Waste..............................................B-23 4.2.3 Non-Hazardous Solid Waste.....................................................B-24 4.3 Noise...................,..................,,..........................B-24 4.4Seismicity...........................................................................B-24 4.5~Air Quality
............................................................................B-24 4.6Regulatory Issues................=............................................B-25 4.7AreasNotAffected...........................................................................B-25 4.8Cumulative Effects..............................................,.....................B-25 4.9Alternatives toProposed Action........................................B-27 5.REFERENCES
...................................................................B-27 B2
PC000482/2 g
LISTOFFIGURES gyr Figure B-1-Regional Location......................=............B-5 Figure B-2-GA SiteandSurrounding Uses.............................................
B-6 Figure B-3-TRIGAReactor Facility Site andAdjacent 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 andRegulations...,
1 B3
PC 000482/2 APPENDIXB ENVIRONMENTAL REPORT Rh
- 1. PURPOSE AND NEEDFORACTION Asaresult ofnuclearresearch training andisotope production, activities conducted since 1958 forthe DOE andits predecessor
- agency, theAtomic Energy Commission (AEC),and commercialcustomers, theTRIGA*
Reactor Facility (TRF) hasbecome contaminated with varying amounts of radioactive materials andsmall amountsofhazardous materials.
GA decided toshutdown theTRFduetoreduced demandforirradiation services and continuing private industrial development aroundthesite.Decontamination and Decommissioning (D&D) oftheTRFwilleliminate thepotential forfuture inadvertent environmental releases.The goal oftheproposed D&Dactivities istoobtain fromthe United States Nuclear Regulatory Commission (USNRC) andtheState ofCalifornia Department ofHealth Services (CAL-DHS) release ofthesite for"unrestricted use."
The term"unrestricted use" means that there will benofuture restrictions ontheuseofthesite, other thanthose imposed bythe City of SanDiegozoning ordinances.
2.FACILITY,DESCRIPTION, PROPOSED ACTION AND ALTERNATIVES, AND ADMINISTRATIVECONTROLS 2.1 Facility Description TheTRFislocated within theGeneral Atomics (GA)
Torrey Mesa"MainSite,"
inSan
- Diego, CA. GAoccupies approximately 120acres (48hectares) ontwocontiguous areas approximately 13miles (21km)north ofdowntown San
- Diego, California whichis situated southwest oftheconvergence ofInterstates
- 5and805, and approximately onemile eastofthePacific Ocean.
Thetwolocations arereferred toas the "Main Site" andthe W
"Sorrento Valley Site',
orcollectively astheGAsite.
Figures B-1 through B-5depict the specific location ofGAandtheTRF.
TheTRFoccupies GABuilding 21andanoutdoor adjacent service yard.
The interior of Building 21hasapproximately 7,600ft 2offloor space consisting ofoffices, three reactor rooms,operating roomsandauxiliary areas.
Building 21issurrounded bya 43,800 ft2 fenced service yard.
TheTRIGAReactor Facility hashoused three TRIGAreactors, whichhavebeen variously usedsince 1958 toprovide controlled neutron andgammairradiation fordiverse laboratory research projects.
W TheTRIGAMkIReactor, situated inTRFRoom21/102, wasplaced in"Possession-Only-License" (POL)
- status, under Amendment No.35totheUSNRCLicense No.38,dated October 29,1997(Ref.
5.14),
andispresently inoperable.
AllTRIGAReactor fuel elements havebeen removed fromtheTRIGAMkIReactor
- pool, andtransferred/relocated totheTRIGAMkFFuel Storage CanalinRoom21/107.
- Moreover, anumberofadditional components andhardware
- items, previously installed aspartoftheTRIGAMkIReactor Control andInstrumentation
- systems, havebeen dismantled,
- surveyed, andremoved fromtheTRFforrecycle use;this partial B-4
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FigureB5-TRIGAReactor
- Facility, RoomDetail, PlanView B-9
PC-000482/2 dismantlement anddisassembly oftheTRIGAMkI systemswas performed by implementing instructions setforth
- inaplan, which wasprepared,
- reviewed, andapproved19 in accordance withtheadministrative provisions of10CFR50.59.
TheTRIGA MkF Reactor (situated inRoom21/107) was previously placed in "Possession-Only-License" (POL) status underUSNRCLicense No.R-67(Ref.),
as amended on March 22,1995, andisalsocurrently inoperable.
Allreactor fuel elements havebeen removed fromtheTRIGAMkFreactor core/shroud andplaced intheTRIGA MkFFuel Storage Canal. Thenon-fuel components oftheTRIGAMkFreactor, including thecore support structure, bridgeshroud, beamtubes, andassociated
- hardware, remain in the reactor pool.
TheFuel Storage Canal portion oftheTRIGAMkFreactor pool currently houses alloftheSpentNuclear Fuel(SNF) elements previously removed fromtheTRIGA MkI,MkFandMkIII Reactors.
Allrequiredprotection barriers andsecurity
(i.e.,
electrical
- service, domestic watersupply)
- storage, are maintained inaccordance withGA'sphysical protection plan.
AllTRFbuilding utility services required for facility operation andmaintenance under POL conditions areactive.
TRFbuilding airventilation andHEPA-filtered building exhaust
- systems, airsupply compressors, andlicense-required radiological monitoring instrumentation systemsarein normal continuous operation.
Allmanually-actuated andautomated fire alarm/suppression systems intheTRFare operational.
Allinstalled TRFsecurity andradiological alarm systems are active and normal.
Independent waterdemineralization systems serving theTRIGAMkI and TRIGA MkF Reactors remain fully operational.
A commonforced watercooling systemserving boththeTRIGAMkIandMkF Reactors remains fully operational.
2.2 Proposed Action andAlternatives TheProposed Action andtheAlternatives areasfollows:
a Proposed Action (DECON)-Decontamination andDecommissioning oftheTRF followed bytherelease ofthesite forunrestricted usebytheUSNRC.
e Alternative 1(SAFSTOR)-In safe
- storage, theTRFisplaced andmaintained ina condition that allows ittobesafely stored andsubsequently decontaminated toalevel permitting release oftheproperty bytheUSNRC.
e Alternative 2 (ENTOMB)-In entombment, radioactive materials areencased ina structurally long-lived material suchas concrete.
The entombed structure is appropriately maintained andsurveillance iscontinued until theradioactivity decays toa level permitting release oftheproperty bytheUSNRC.
Implementation oftheProposed Action will involve performance ofthefollowing tasks:
B10
PC000482/2 2.2. 1 Dismantle, decontaminateorpackage aslowlevel waste(LLW) theTRIGAMkIReactor
(
components, tank andpit.
2.2.2 Decontaminate anyremaining contaminated areas except theTRIGAMkFReactor and Control Rooms.
2.2.3 Reroute required utilityservices toisolate theTRIGAMkFReactor andControl Rooms.
2.2.4Obtain USDOE approval andship thespentTRIGAfuelfromtheTRIGAMkFFuel Storage Canal.
DOE iscontractually committed totake spentfuel atINEELbuttheactual shipping dateisuncertain.
TheDecommissioning Planhasbeenmodified todescribe the arrangements andshipment "schedule" both intheAppendix andinSection 2.3.2.
The shipping schedule andthe time requiredtocomplete Phase2 oftheplan,
- inturn, determines thedate for thelicense termination request.
2.2.5Dismantle, decontaminate orpackage asLLW,theTRIGAMkFcomponents, tank andpit.
2.2.6Ship theLLWgenerated asaresult ofdecommissioning activities.
2.2.7Perform final radiological survey andsubmit arequest totheUSNRCforrelease ofthe subject areas forunrestricted useandthe termination oftheTRIGAReactor licenses.
2.3Administrative Controls 2.3.
1 Tominimize therisks ofinadvertent
- exposure, contamination and/or radioactivereleases, all Decommissioning operations will beimplemented inaccordance with appropriate technical andadministrative
- controls, including:
' 2.3.2Performance ofall project workpursuant toapproved proceduresimplementing USNRC andCAL-DHS-approved Decommissioning Plan.
GAwill continueto be responsible for assuring anddemonstrating compliance with USNRCandCAL-DHSlicenses, aswell as other applicable
- federal, state orlocal
- laws, regulations, licenses and/or permits.
2.3.3Utilization ofcontainment structures,
- tents, andbagsunder negative pressure and/or appropriate contamination barriers toisolate operation areas arid prevent inadvertent release ofcontaminants.
2.3.4Employment ofmonitored, high-efficiency particulate air(HEPA) filtration systems for air ventilation intheworkareas.
2.3.5Maintenance ofemergency ventilation,
- power, andsupplies, asappropriate.
2.3.6Application ofALARAprinciples suchasemphasizing radiation protection forworkers and thegeneral
- public, employing personnel andareadosimetry, using personal protective equipment andclothing andconducting workthrough approved Radiological Work Authorization Permits.
Theterm"ALARA"meansaslowasreasonably achievable, taking into account thestate oftechnology andtheeconomics ofimprovements inrelation tothe benefits topublic health andsafety, andother societal andsocioeconomic considerations.
GAHealth Physics staff would havetheauthority tostopanyoperations which they believe mayinvolve
- unusual, unnecessary orexcessive radiological risk totheworker, the public ortheenvironment.
(g4 2.3.7Maintenance ofindustrial security access control totheworksite andfacility, torestrict
'ST unauthorized individuals fromtheworkarea.
B-11
PC-000482/2 2.3.8 Integration ofGAQuality Assurance andGAHealth andSafety requirements into Decommissioning Projectdocuments.
(j
- 3. DESCRIPTION OFTHE AFFECTEDENVIRONMENT 3.1ManMade Environment 3.1.1 Radioactive Materials Thepublic iscontinuously exposed toradiation fromnatural sources; primarily from cosmic radiation; external radiation fromnatural radioactive material intheearth andglobal fallout; andinternal radiation fromnatural radioactive materials taken into thebodyviaair, water,andfood.
Thepublic receives andaccepts therisks associated withradiation exposures frommedical X-rays, nuclear medicineprocedures, andconsumer products.
On
- average, amemberofthe public intheUnitedStates receives approximately 300mrem/yr fromnatural sources ofradiation; approximately 50mrem/yr frommedical procedures; and approximately 10mrem/yr from consumer products, foratotal of360mrem/yr (Ref.
5.1).
InSanDiego, atelevation nearsealevel, thebackground radiation fromnatural sources is about 240mrem/yr andthetotal background radiation isapproximately300mrem/yr.
Residual radioactive contamination resulting from pastTRIGAReactor operations is contained within theTRFBuilding whichiscontinuously monitoredunder anextensive surveillance andmaintenance program.
Existingmonitoring data,historical information, andcurrent surveys indicate that TRFbuilding contamination iscomprised ofcertain fission product andactivation product nuclides.
Some
'IRF reactorcomponents are contaminated withradionuclides.
Thisisprimarily the result of deposition andadherence of airborne andwater-soluble contaminants.
Theradionuclideslisted inTable B-1potentially exist intheTRF.
Radioactive atomsundergo spontaneous nuclear transformations and release excessenergy intheformofionizing radiation.
Suchtransformations arereferred toas radioactive decay.
Asaresult oftheradioactive decay
- process, oneelement istransformed into another; the newlyformedelement, called a decayproduct, will possess physical and chemical properties different fromthose ofits
- parent, andmayalso beradioactive.A radioactive species ofaparticular element isreferred toasaradionuclide orradioisotope. Radiation emitted byradioactive substances cantransfer sufficient localized energy to atoms to removeelectrons fromtheelectric field oftheir nucleus (ionization).
Inliving tissue this energy transfer candestroy cellular constituents andproduce electrically charged molecules (i.e.,
freeradicals).
Extensive biological damage canlead toadverse health effect (Ref.
5.3).
Theadverse biological reactions associated withionizing radiation, andhence with radioactive materials, areskin
- injury, cancer, genetic mutation andbirth defects (Ref.
5.4).
B12
PC-000482/2 TableB1:List ofExpected Radionuclides Nuclide HalfLife Decay Notes (yr)
Mode "C
5730.
p-AP;fromn-activation ofgraphite reflector structure (TRIGA Mkionly) 54Mn 0.86 e, y AP;shortlived specie; fromnactivation ofSShardware 55Fe 2.73 e
AP;fromn-activation ofSShardware "Co 5.27 E,y AP; fromnactivationofSShardware; 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 fromn-activation of SShardware, ifNbimpurities are present "Tc 213000.
p,y FP,andminor APinventory constituent; possiblefromnactivation of
(
SShardware, ifMoimpurities arepresent "5Sb 2.76 p,y FP;relatively short-lived specie "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 from nactivation 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 HalfLife values andDecayModeinformation usedabovearetaken fromRef.
10.15.
Thelist ofexpected radionuclides provided above isbasedontheassumption that operations oftheTRIGAMarkIandMarkF Reactors haveresulted intheneutron activation ofreactor core components andother integral hardware orstructural members which aresituated adjacent to,orinclose proximity to,thereactor coreduring operations.
Specific items which areconsidered tohave beenexposed toneutron activation include materials composed ofaluminum,
- steel, stainless-steel,
- graphite, cadmium,
- lead, concrete andpossibly others.
Basedonearlier studies andexperience gained insimilar research reactor decommissioning
- projects, andreactor-specific calculations which considered measured values forneutron leakage
- fluence, integrated operating power histories, reactor core/pool structural configurations, andmaterial composition ofexposed pool structures, neutron activation of materials beyond theconcrete liner/biological shield structure (i.e.,
into surrounding soil volumes) isnotexpected foreither the TRIGAMarkInorMarkFReactors.
B-13
PC000 482/2 Major typesofionizing radiation include alpha particles, beta,andgammaorX-ray radiation.
Alpha particles expend their energy inshort distances andwill notusually 93 penetrate theouterlayer ofskin.
Alpha particles represent asignificant hazard onlywhen taken into thebody,wheretheir energy iscompletely absorbed bysmall volumes of tissues. Beta particles constitute external hazards iftheradiation iswithin afewcentimeters ofexposed skin surfaces andifthebetaenergy isgreater than70keV.Internally, beta particles deposit much less energy tosmall volumes oftissue and,consequently, inflict muchless damage thanalpha particles.
Gammaradiation areofthemostconcern as external hazards.
3.1.2Hazardous Materials Basedonpreliminary surveys andinspections ofthesubject workareas,thespecific hazardous materials ofconcern interms ofpotential exposure toproject
3.1.2.
1 Elemental Lead-The predominant hazardous material intheTRF,intermsofmass,is elemental lead(used primarily invarious radiation shielding applications).
Mostlead contained inthefacility consists
- ofsolid, non-dispersible
- bricks, fittings, liners and weights.
Leadisacumulative poison.Increasing amountscanbuild upinthebody eventually reaching apoint where symptomsand disability occur.
Theeffects ofexposure tolead dustthrough inhalation andingestionmay not develop quickly.
Symptoms may include decreased physical
- fitness, fatigue, sleep disturbance,
- headache, aching bones andmuscles, constipation, abdominal pains anddecreased appetite. Leadcanalso cause irritation totheskin andeyes.
Theseeffects arereported tobereversibleifexposure ceases.
Systemic effects arepossible ifa long-term exposure occurs andbirth defects havebeenreported.
(
3.1.2.2Asbestos-Asbestos ispresent inTRFconstruction materials(e.g., floor tiles, roofing material).
Asbestos isnotahazard unless itis"friable,"
that isinpowder orfiber form.
Inhalation ofthefibers cancauseasbestosis andlungcancer.
Gastrointestinal cancercan becaused byingestion.
Asbestos found tobepresent intheTRFwillbe removed bya licensed asbestos abatement contractor.
3.1.2.3Cadmium-Cadmium ispresent intheTRFintheformofmetal foil.
Inhalation or ingestion ofcadmium dust orfumescanaffect therespiratory
- system, kidneys,prostate andbloodSymptoms are:
pulmonary edema,dyspnea,
- cough, tight
- chest, substemal
- pain, headache,
- chills, muscular
- aches, nausea,
- diarrhea, anosmia, emphysema.
3.L3 Transportation Themainroadways inthevicinity oftheGAsite areshownonFigure B-2.Theyinclude Genesee Avenuebeyond thesouthern
- boundary, JohnJayHopkins Drive beyond aportion ofthewestern
- boundary, North Torrey Pines Roadfurther tothewest,andInterstate 5to theeast.
Genesee Avenue isasix-lane primary arterial.
North Torrey Pines Roadnorth of Genesee Avenueisasix-lane primary arterial.
North ofScience ParkRoad,NorthTorrey Pines Roadbecomes afour-lane primary arterial.
JohnJayHopkins Drive isafour-lane collector street which connects Genesee Avenue with North Torrey Pines Road.
TheGA site isgenerally accessed fromtheInterstate 5 freeway, exiting onGenesee Avenue andtraveling west,turning north onJohnJayHopkins Drive andeastonGeneral Atomics Court.
Thesite canbeentered through twoentrances shownonthemap(Figure B-2) fromGeneral Atomics Court andfromJohnHopkins Court.
Traffic ontothesite is controlled byaguard posted ataguard station andbypersonnel atanoffice reception area.
B-14
PC000482/2 Off-hour access isthrough akeycard gate atthesouth entrance.
Thenearest entrance tothe
()
GA site isapproximately 1,500 ft.(457 m)fromtheTRF.
3.1.4 Cultural andHistoricalResources Nosignificant archeological orcultural resources havebeenfound insurveys oftheGA site.
The mentions nohistorical structures orsites within theboundary oftheplant.
There isa state
- park, called Torrey Pines State
- Park, located onemile to thenorthwest ofthesite, whichcontains aunique species ofpine tree.
Nohistorical, archaeological orcultural properties arebelieved tobeunder consideration on orneartheTRF.
3.1.5Population andLand Use Thesite islocated within theTorrey PinesMesaareaandiscurrently zoned SR(Scientific Research).
TheUniversity Community Plan designatesopenspace andscientific research land usesforthesite.
Landusessurrounding theGAsite include scientific research and development parks tothenorth and to theeastacross Interstate 5,undeveloped land associated withTorrey Pines State Park, research anddevelopmentparks andahospital to the westandtheUniversity ofCaliforniaat San Diego (UCSD) tothesouth.
Surrounding land usesareshowngraphically onFigure B-2.
Thepresent population within theUniversity Census Tract Subregion, inwhich themain site
- lies, isprimarily ofanindustrial anduniversity campus makeup,withanestimated daytime total ofupto52,000 people (Ref.
5.5) including about 1,200 GAemployees.
The University Subregion contains sixCensus Tracts.
Theimmediate vicinityoftheFlintkote Avenuefacilities iszoned forindustrial activity.
y Estimates offuture growth indicate that theUniversity Subregioncould haveadaytime total
~'
of57,000 people byyear 2000,based uponfuture industrial growth in theSorrento Valley areaandanincreased number ofstudents ontheuniversity campus. Because ofterrain,
- zoning, andcurrent land use,mostfuture residential development will occur beyond atwo mileradius fromthesite.
Nearby sensitive humanpopulations include:
GAnon-radiological workers; Agouron Pharmaceuticals, located 0.25miles (0.4 km) tothe west; Children atadaycarecenter, located onJohnJayHopkins
- Drive, approximately 0.45 miles (0.7 km) tothewest; Scripps GreenHospital, located 0.5miles (0.8 km) tothewest; UCSDdormitories located about 0.9miles (1.5 km) tothesouth; and Aresidence along Torrey Pines Roadacross fromtheUCSDcampus (about 1.2miles or2kmtothesouthwest).
3.1.6Noise Within GAsite boundaries, theambient noise environment isgenerated byvehicular
- traffic, g
jet
- aircraft, general aviation aircraft andbuilding,
- heating, ventilating andairconditioning equipment.
B-15
PC000482/2 3.1.7 Aesthetics The TRF islocated against abackdrop ofcoastal bluffs interspersed withsteeply sloping canyons.
Itisintheinterior oftheGAsite andisnotvisible toadjacent neighbors.
- However, theTRFisvisible ata0.5mile(0.8 km)distance fromInterstate 5 totheeast andScripps Green Hospital tothewest.TheTRFwill bevisible fromfuture science-related development tothenortheast.
3.2 Natural Environment 3.2.
1 Topography, Geology and Seismicity 3.2.
1.1 Topography Site topography istypical ofcoastal SanDiego
- County, withbluffs andmesasinterspersed withcliffs andravines.
Themesa runs inanortherly direction paralleling thecoastand rising toaheight of400ft.
(122m) above sealevel between thesite andtheocean.
The topography ofthesite is characterizedby steeply slopingcanyons andrelatively level mesa areas.
ThemainGAsite isonTorrey Pines Mesa about onemile eastoftheoceanatan elevation of340ft.(105m) above sealevel.
3.2.
1.2Geology TheTRFhasbeenbuilt onmaterials that have been mapped asartificial fill (Ref.
5.6).
Areas immediately adjacent totheartificial fill are mapped asArdath Shale, amemberofthe LaJolla GroupofEocene
- Deposits, that ispredominantly weakly fissile,olive-gray shale.
Acrosssection ontheDelMarquadrangle shows subsurface formations approximately a
750ft.(228m)northeast oftheTRF.Based onthis cross
- section, theArdath shale deposit (MA intheTRFareaisapproximately 300ft.(91m)
- thick, isunderlain by approximately 500ft.
(150m)ofTorrey Sandstone overapproximately 250ft.(76m)ofDel Mar Formation.
3.2.
1.3Soils Soils present attheTRFhavebeenmapped asHuerhuero loam,5to9percent slopes and eroded (Ref.
5.7).
TheHuerhuero series soils havedeveloped insandy marine sediments andconsist ofmoderately welldrained loams that haveaclay subsoil.
A representative Huerhuero profile hasa surface layer that isbrownandpale-brown, strongly acid and mediumacid loamabout 12inches (0.3 m)thick, anupper subsurface layer that extends to a depth ofabout 41inches (1.0m)andisbrown,moderately alkaline clayandan underlying brown,mildly alkaline clayloamandsandy loamlayer that extends toadepth ofmorethan60inches (1.5m).
Small areasofLasFlores andOlivenhain soils and alluvium derived frommetabasic andmetasedimentary rocks areincluded inthearea.
Soils immediately downslope ofthe'IRFhavebeenmapped asAltamont
- Clay, 15to30 percent slopes (AtF)
Huerhuero loam,5 to9percent slopes anderoded.
TheAltamont series consists ofwell-drained clays that formed inmaterial weathered fromcalcareous shale.
Arepresentative Altamont profile hasasurface layer that isdark-brown andlight olive-brown, moderately alkaline heavy clay loamabout 8inches (0.2m)thick that lies oversoft calcareous shale.
Small areas ofLinne clay loamandareas wherethesoil isonly 10inches (0.2 m) overshale areincluded inthesurvey area(Ref.
5.7).
There maybelocalized areas ofsoil contamination.
Theextent ofcontamination will be defined through thesite characterization process.
B16
PC000482/2 3.2.1.4 Seismicity San Diego Countyhasbeenconsidered oneofthemoremoderate seismic risk regions in Southern California.
Thehistorical pattern ofseismic activity hasgenerally been characterized by a broadscattering ofsmall magnitude earthquakes, whereas the surrounding regions are characterizedbyahigh rateofseismicity withmanymoderate-to-large-magnitude earthquakes.
A recent study (Ref. 5.8) estimated theprobabilities oflarge earthquakes occurring in California onthemajor strands oftheSanAndreas fault system.
Inaddition totheprincipal tracesoftheSanAndreas
- fault, earthquakes occurring ontheother major faults ofthe system(San
- Jacinto, Imperial, etc.)werealsoconsidered.
Thestudy estimated that the probability ofa magnitude 7 or greater earthquakeoccurring inthenext30yearsin Southern California (along the Southern SanAndreas,
- Imperial, orSanJacinto faults) is 0.5orgreater.
- However, aquake of magnitude close to7 onthese fault lines isnot expected tosignificantly impact theGA site because ofintervening distance.
Current information (Ref.
5.9) however,indicates theRoseCanyon, Coronado Bank,San Diego
- Trough, LaNacion, andElsinore fault zones arecapable ofgenerating strong ground motion intheSanDiego area.
Possible Richter magnitudes forearthquakes onthese faults canbeashigh as7.0,7.5,7.5,6.3and7.5, respectively.
Passingapproximately 3miles (5km)westoftheGAsite, theRoseCanyon fault isthenearestactive fault.
Recent excavations (Ref.
5.10) showed definite evidence of Halocene (within thelast 10,000 years) activity.
Itisclear that SanDiego hasexperienced major earthquakes intherecent geologic past.
1 Thepresence ofthree small,local faults was confinnedby the Woodward-Clyde Consultants field reconnaissance ofthesite(Ref.
5.11).
Anunnamed fault inthenorthern portion ofthesite trends easttowestthrough proposed lots 25,26,31, and 32.TheSalk fault ismapped inthesouthern portion ofthesite andalso trends eastto west.
A northerly trending fault islocated inthesoutheastern areaandcrosses the GeneseeAvenue canyon.
Allofthese faults aremapped asbeing overlain byearly Pleistocene formations which have notbeendisplaced.
Therefore, thefaults on-site arenotconsidered active.
3.2.2Climate andAirQuality 3.2.2.1 Climatology TheTorrey Pines MesaandSorrento
- Valley, aswith mostofSanDiego County's coastal
- areas, hasasemi-arid Mediterranean climate characterized byhot,drysummersandmild, wetwinters.
Themeanannual temperature intheproject vicinity is610F(33.80C),
with summerhigh temperatures inthelow-90s (500C) andwinter lowsinthemid-30s (160C)
(Ref.
5.12).
Thedominating meteorologic feature affecting theregion isthePacific HighPressure
- zone, asemipermanent high pressure cell located overthePacific Ocean.
Thishigh pressure cell maintains clear skies formuchoftheyear, drives theprevailing westerly tonorthwesterly
- winds, andcreates twotypes oftemperature inversions (reversals ofthenormal decrease of temperature withheight) that acttodegrade local airquality.
Whenabuoyant parcel of polluted
- airrises, itcools byexpansion.
Iftheairaround theparcel iswarm,asinan inversion, theparcel sinks backdowntoward its source andiseffectively prohibited from dispersing.
Insummer,amarine/subsidence inversion isformed whenthewarm,sinking
~
airmassinthePacific HighPressure zone isundercut byashallow layer ofcool marine air flowing onshore.
This inversion forms overtheentire coastal plain andallows formixing B-17
PC000482/2 below theinversion base at1,100 1,500ft.(457 m),butnotanyhigher.
During the winter offshoreflowregime, coldairpools inlowareas andairincontact withthecold ground coolswhile theairaloft remains warm.Anightly shallow inversion layer
[at about 800 ft. (244m))
forms between thetwoairmasses which cantrappollutants.
Inthesummer, whenthehigh pressure system isatits mostnortherly
- extent, eastward-travelingstorm andpressurecenters areblocked, resulting inlittle rainduetofrontal activity.
Themigration ofthis systemtoits mostsoutherly extent inthewinter allows the transient stormand pressure centers topassthrough thearea,resulting inwinter rains in southern California.
Thepredominant pattern is sometimes interrupted byso-called Santa Anaconditions, when high pressure overtheNevada-Utah areaovercomes theprevailing westerlies, sending
- strong, steady, hot,dry winds east overthemountains andouttosea.
Strong Santa Anas tend toblowpollutants outover the
- ocean, producingclear days.
- However, attheonsetor breakdown ofthese conditionsor if theSantaAnaisweak,airquality maybeadversely affected.
Inthese
- cases, emissionsfrom theSouthCoast AirBasin tothenorth areblown outovertheocean,andlowpressureover BajaCaliforniadrawsthis pollutant laden air masssouthward.
Asthehigh pressure
- weakens, prevailing northwesterlies reassert themselves andsendthis cloud ofcontamination ashore intheSanDiego AirBasin.
There isapotential forsuch anoccurrence about 45days oftheyear, buttheregion isadversely impacted ononlyabout five ofthem.
Whenthis impact does occur,thecombination of transported andlocally produced contaminants produces theworstairquality measurements recorded intheSanDiego basin.
3.2.2.2 Local Winds andDispersion Data Theprevailing daytimewinddirection iswesterly, althougheasterly windsasalmost as commonduring thewinter months.
During theday,the westerly winds developing from thePacific high-pressure system arereinforced bythesea-land breeze caused bythePacific Oceanresulting instronger average windvelocities
[6to9mph(10 to15 km/h)) than from theeasterly landbreeze
[1to7 mph(1.6 to11.6km/h)).
Thelandbreezes aremost commonduring stable conditions anddominate theflowtoward theocean during thenight andearly morning hours.
Theairflow ineither direction ischanneled effectively by topographical features ofthearea.
Strong winds areinfrequent; thestrongest recorded was 51mph(82 km/h) fromthesoutheast in1944.
Datafromanon-site meteorological system wereusedtoprovide atmospheric stabilityand windfrequency results.
Theon-site annual winddata areconsistent withthewindrose data fromtheMiramar Naval AirStation.
3.2.2.3 Precipitation Theaverage annual rainfall forthecity ofSanDiego is10.4in.(26.4 cm),
butrelatively large variations inmonthly andseasonal totals occur.
Theaverage monthly precipitation from1940through 1970ranges from2.15in.(5.5 cm) inFebruary to0.01in.(0.03 cm) inJuly.
Approximately 75%oftheannual precipitation occurs fromNovember through March.
Themaximumannual precipitation during thelast 60years was24.9in.(63.3 cm) occurring in1941.
3.2.2.4 AirQuality Under state regulations, thestudy areaiswithin theSanDiego AirBasin(SDAB).
The concentration ofpollutants within theSDABismeasured ateight stations maintained bythe C
B18
PC000482/2 County ofSanDiego AirPollution Control District (APCD) andtheCalifornia Air Resources Board(ARB).
Airquality ataparticular location isafunction ofthetypeand amount ofpollutants being emitted into theairlocally andthroughout thebasin andthe dispersal rates ofpollutantswithin theregion.
Theair quality monitoring station nearest the project area islocated inaschool ground atNinth andStratford Court intheCity ofDel Mar.Thisis four miles(6.4 km)north ofthesite.
Airquality measurements areexpressed asthe number of days onwhichairpollutant levels exceed stateandfederal clean air standards.
Under federal regulations, theGAfacility islocated inthesouthwestern portion oftheSan Diego Interstate Air Quality Control Region.
TheEnvironmental Protection Agency (EPA) hasdesignated this region as an"attainment area" forsulfur dioxide andnitric
- oxides, indicating that theconcentrations ofthese pollutants arebelowthefederal airquality standards.
Theregion wasclassified asa "nonattainment area" withrespect tocarbon
- monoxide, ozone,andsmall suspended particulates (PMio) someyears ago,butinrecent years only ozonefederal standards have been exceeded.
In1993 attheAPCDmonitoring station in Del Mar, ozoneexceeded thestate standard on 19daysandthefederal standard onthree days. This is characteristic oftheentire SDAB.
In1992and1993,themaximum24-hour measured levelofparticulatesless than10 microns insize intheSDABwasfound toexceed the state standardonseveral days.
Annual average measured PM10 levels weremarginal with statestandards.However, neither the24-hour northeannual federal standard for PMjo was exceeded.
3.2.3Hydrology 3.2.3.1 Groundwater TheTRFislocated within theSouthwestern portion oftheSoledad Basin.
TheSoledad Basin makes upthenorthwestern partoftheLosPenasquitos hydrographicsubunit andhas notbeendeveloped forwatersupply purposes.
No groundwater wells arepresent ator immediately adjacent totheTRF.Ground waterbeneath theTRFisapproximately 300 feet belowground surface.
Testborings ontheGAsite ranging fromapproximately6to 30 ft.
(1.8
- 9.1m)didnotencounter groundwater.
There iscurrently noreason tosuspect that anygroundwater contamination exists under theTRF.Further studies maybeconducted if warranted during D&Dactivities.
3.2.3.2 Surface Water Based onground surface elevations andsurface drainage
- patterns, surface run-off fromthe TRFControlled YardAreacurrently flows primarily northerly, across paved andunpaved surfaces intheservice yard.
TheTRFislocated within theLosPenasquitos Creek drainage basin.
Drainage runs through theSoledad Valley into LosPenasquitos
- Creek, which flows tothenorthwest and empties into thePacific Ocean.
Detention basins andsilt collection structures havebeen constructed forthedevelopment oftheTorrey Pines Science Parkthat surrounds and includes theGAsite toensure that adverse downstream impacts will notoccurfrom stormwater run-off.
Surface waterdownstream fromthesite cannotbeuseddomestically because ofits intermittent flowanddirty condition during periods following rainstorms orheavy run-offs.
No freshwater recreation areasexist within thelocal vicinity.
Agriculture isnot B-19
PC000482/2 prevalent because soils arenotwellsuited foragriculture, precipitation islimited, and groundwater quality (primarily inPenasquitos Valley) isconsidered marginal orinferior for (j irrigation.
Water useinthevicinity ofthesite islimited bytheephemeral nature ofmany streams andthehigh suspended solids content offlowduring thewinter.
Floodsdo not represent adanger tothesite asitissituated approximately 340ft.(103m) above thevalley flooronamesa.Also,drainage downstream fromthesite tothePacific Oceanis unrestricted. TheTRFisnotlocated within a100-Year Floodzone.
Wastewater collection services aresupplied totheGAsite bytheSanDiego Department of Public Utilities.
Wastewater fromthesite isdischarged through theCity's sewersystemto thePoint Lomatreatment plant. Anywastewaterreleased tothecity treatment system must meetthe requirements ofthe San DiegoIndustrial Waste Discharge Permit.
3.2.4Biology 3.2.4.1 Vegetation TheGAsite isprofessionally landscaped. The openspace surrounding theTRFandtheGA site isa combination ofdisturbed/developed
- lands, several eucalyptus groves andthree distinct typesofnative ornaturalized plantcommunities; coastal mixedchaparral, coastal sagescrub, andsouthern California grassland.No federally-listed endangered plant species areknowntoexist onorneartheGAsite (Ref.
5.13).
Themostsignificant natural areas inthevicinity ofthe site asTorreyPines Park,Torrey Pines State
- Reserve, andLosPenasquitos Lagoon andassociated marsh.These areas are located westandnorthwest ofthesite along the coast (Figure B-2). Inadditiontoprovidingg relatively undisturbed refuge-like
- habitats, theparkandreserve contain a rarespecies of tipp pine tree,thetorrey pine(Pinus torreyana).
Thisspecies is endemic to California, knownto
~~
occuronly inSanDiego County andonSanta RosaIsland.
3.2.4.2 Regional Wetlands Stormwater run-off fromtheTRFandtheGAsite flows into theLosPenasquitos Lagoon.
TheLosPenasquitos Lagoonandassociated marsharedesignated bythe California Department ofFish andGameasawetland area.
Thesaltwater marsh andlagoonsupport a
diverse fish fauna andamussel fauna ofabout 20species.
ThePacific little-neck cochral andcommonlittle-neck clamarethemostcommonmusselspecies.
A total of approximately 30species ofsalt-marsh plants occurs intheLosPenasquitos Lagoon.
The predominant vegetation inthemarshandlagoon ispickleweed (Solicormia).
Solicormia subterminalis occurs inthedrier areas; Solicormia virginica, inthelower-lying areas.
Pickleweed filters outmostofthesuspended material brought inbyupstream drainage.
3.2.4.3 Wildlife A1994survey oftheareaadjacent totheTRFconducted byNatural Resource Consultants identified several mammal,birds andreptile
- species, with themajority ofthese occurring in thebrushland habitats (coastal sagescrub andcoastal mixedchaparral).
Raptors utilize the grassland andtoalesser extent thebrushland habitats onthesite forforaging.
Raptors are protected inCalifornia andareconsidered sensitive duetothegeneral trend ofdeclining populations inmanyspecies andtheir importance intheecological structure ofbiological communities.
Twospecies observed inthebrushland habitats around
- thesite, black-tailed gnatcatcher (Polioptila melanuria californica) andtheorange-throated whiptail egg (Cnemidophorus hyperythrus beldingi) appear tobeexperiencing declines intheir U B20
PC000482/2 populations incoastal SanDiego County.
Theblack-tailed gnatcatcher isa species of special concernandislisted bytheCalifornia Department ofFishandWildlife Service as endangered.
The Torrey PinesPark,Torrey Pines State
- Reserve, andLosPenasquitos Lagoon and associated marsh areaprovides habitat forseveral species ofshorebirds andwaterfowl, as wellastwo federally listed endangered species
- ofbirds, thelight-footed clapper rail (Rallus longirostris levipes) andtheCalifornia least tern(Sterma albifrons browni).
These species havebeendeclining because.
ofhumandisturbance andwater pollution that destroyed nestingandfeeding habitats.
TheBelding's Savannah sparrow (Passerculus sandwichensis beldingi),
listed bythestate asendangered, isalso associated withthe pickleweed habitatofthelagoon.
It, too,hasbeendeclining because of humandevelopments affecting its habitat.Noneofthese unique wildlife species haveever beenobserved onthesite.
During thebiological survey conducted oftheadjacent area(Natural Resource Consultants, May10,1994),
atotal ofthree bird species wereobserved onthesite.
These include the housefinch (Carpodacus mexicanus),
common raven(Corvus corax),
andmourning dove(2enaida macroura).
A singlefence lizard (Seeloporus occidentalis) wasalso observed.
There arenowildlife species recognized asrareorendangered byanyresource protection agencies knowntohabitat within the TRF boundary.
3.2.5Socioeconomics andEnvironmental Justice Thesocioeconomic environment oftheGAfacility consists ofawell-established,
- diverse, middle-income community consisting ofresearch institutions, amedium-sized university, light
- industry, tourism, andresidences.
Thesetting isattractive, with thecoastline, Torrey Pines
- Park, andVillage ofLaJolla nearby.
Theroad system isadequate withboth interstate
~
highways andsecondary roads.
GAoperations donotconstitute a large percentage ofthe area's economy.
- 4. POTENTIALENVIRONMENTALCONSEQUENCES OF PROPOSED ACTION AND ALTERNATIVES This section discusses thepotential direct andcumulative effects ofthe proposed action on humanhealth andtheenvironment.
4.1HumanHealth Effects Types ofexposures that could lead tohumanhealth effects considered inthis report are worker andoff-site exposures tohazardous chemicals orradioactive materials during routine activities orpotential accidents
- onsite, orduring atransportation accident off-site (involving hazardous orradioactive wasteremoval).
Thissection identifies anddiscusses potential hazards that mayaffect workers on-site orpeople off-site during normal orroutine TRFDecommissioning activities.
Impacts ofthehazards relative tohumanhealth and safety aresummarized inSection 4.1.2.
4.1.1 HazardIdentification During theinitial site characterization andthefinal site
- survey, site workers wouldbe 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 withthese 6 materials.
Forthe Decommissioning activities, thekeyhazards wouldinvolve external radiation, inhalation of hazardous orradioactive materials, ordermal contact withthose materials during decontamination, dismantling,packaging anddisposal ofreactorandancillary equipment, the TRF structure, andcontaminated soil (if necessary).
Generally, the Decommissioning steps described inSection 2oftheDecommissioning Plan could involve the hazards asitemized below:
4.1.1.
1 Hazards-Hazards include:
e External radiation for workers working around radioactively contaminated equipment andmaterials.
e Dermal contact withboth radioactive and hazardousmaterials.
a Inhalation ofanyhazardous orradioactive materials.
e Possible confined spaces
- intents, bagsorsmall rooms withassociated oxygen content andasphyxiant concerns.
a Heavyequipment movementdangers.
Note:Noflammables orexplosive materials areexpectedto bepresent.
4.11.2Controls-For
- workers, project procedures andconformance with GA licenses and regulatory requirements including butnotlimited to:
e Radiological WorkPermits, WorkAuthorizations, andHazardousWork Authorization procedures, asrequired; a 29CFR1910.120 requirements forPPE,airmonitoring, workzone
- controls, medical surveillance andbio-assay
- program, personnel
- training, emergency
- response, and health andsafety plan; a personal dosimetry per10CFR20; a confmed space entry procedures per29CFR1910.146; a
HEPAfilter removal ofcontaminants; a
dust filter removal ofcontaminants.
4.1.2Potential Exposures Thecollective doseequivalent estimate toworkers fortheentire Decommissioning project is~20person-rem.
Thedecommissioning tasks willtakeapproximately 2 years.
Total person hours involving radiological exposure isestimated tobe6,000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />.
B-22
PC000482/2 Thepotentialexposures tothepublic asa result ofdecommissioning activities and gg radioactive wasteshipments isestimated tobenegligible.
Thisisconsistent withthe 6W estimate given forthe"reference research reactor" inthe"Final Generic Environmental Impact Statement ondecommissioning ofnuclear facilities" (NUREG-0586)
(Ref.
5.16).
The estimated dose tothepublic during decommissioning (DECON) andtruck transport transportation ofradioactivewastefromthe"reference research reactor" asgiven inthe Final Generic Impact Statement is"negligible (less than 0.1man-rem)."
Theanticipated potential exposurestothepublic after license termination isalso negligible.
Thesite will have been' released tounrestricted use,with all areas having beenremediated tolevels nottoexceed 5pR/hrabovebackground andmeeting thesurface contamination criteria given inU.S.NRC Regulatory Guide1.86.
4.1.3Transportation Theprimary project impactsto the environment duetotransportation could occurwhen shipments ofwastetravel from the site.
Transportation wouldbeconducted inaccordance withapplicable USDOT,USEPA, and USNRC regulations.
During suchtransport, hazardous andradioactive materialswould beeffectively packaged toprevent significant radiation external tothetruck.
- Thus, the primary impacts areaccident riskand emissions/noise fromthetrucks themselves.
Thetruck routeinto orfromtheGAproperty coming from orgoing toSanDiego isalong Genesee Avenue westfromtheInterstate
- 5freeway, then alongJohnJ.Hopkins Drive to General Atomics Court tothegated GAentrance.
This entire routefromInterstate 5tothe GAgatecovers adistance ofabout 1-mile.
Truck shipments ofconcern consist ofhazardous wasteand radioactive wasteleaving the pgg4 site.
During TRFDecommissioning activities, short-term transportation effects would T
include employee
- trips, whichoccurunder existing conditions, a small numberof contractor
- trips, andless than12truck trips forhazardous andradiological wastetransfer.
- Traffic, circulation andparking effects areexpected tobeminor duetothe small increase in trips andtheshort duration ofthisaction andwouldnotsignificantly impact the surrounding roadways.
4.2WasteDisposal 4.2.
1 Hazardous Waste Small amountsofsolid andliquid hazardous wastefromTRFDecommissioning activities wouldbeaccumulated insatellite accumulation areas.
After accumulation forupto90days, thewastewouldbetransferred byalicensed contractor toauthorized off-site commercial treatment anddisposal facilities orrecyclers.
TheHazardous Onlywastewill beincluded aspartoftheregular "milkrun" shipments madebyGA'ssubcontractor.
4.2.2Low-Level Radioactive andMixedWaste Low-level radioactive waste,including anycontaminated
- soil, wouldbepackaged in accordance with theNevada TestSite Waste Acceptance Criteria.
Liquid wasteisfiltered or solidified andsolid wasteiscompacted, whenever
- possible, inaccordance withthe appropriate regulations.
Thewastewouldbeshipped toUSDOE's Nevada's TestSite for disposal.
Low-level radioactive wastegenerated during theTRFDecommissioning areexpected to consist oftwo(2) shipments (approximately 150ft3) ofirradiated hardware requiring a
B-23
PC000482/2 Type B container suchasthe10-142 cask,andfour(4) truck shipments (approximately 3850 ft3) of"strong tight" containers.
Mixed Waste generatedduring theTRFDecommissioning areexpected toconsist of primarily activated/contaminated lead andcadmium.
Estimated volumes ofactivated/con-taminated lead andcadmium are45cubic feet lead and5cubic feet cadmium.
General Atomicsexpects tomakeone(1) shipment toEnvirocare todisposition these wastes.
4.2.3 NonHazardous Solid Waste TRFDecommissioning activities will generate uncontaminated construction debris which would besenttoalocal sanitary landfill.
4.2.4SpentTRIGAFuelElements GAassumes that all ofthespentTRIGA Reactorfuel elements canbeshipped in5off-site transport
- trips, utilizing theGeneral Electric Co.ModelNo.2000shipping caskor appropriate equivalent package.
4.3 Noise During TRFDecommissioning activities, noise will begenerated byequipment suchas jackhammers, scabblers andconcrete saws.
Backhoes andother heavyequipment could also beused forpartial dismantling activities.
On-site workers will beoutfitted with earprotection devices.
The closestoff-site business isAgouron Pharmaceuticals, Inc.whichisapproximately0.25 miles away.Noisefrom A TRFDecommissioning activities would notimpact employeesor off-site businesses.
W 4.4Seismicity TRFDecommissioning activities wouldinvolve theremoval ofsurfacecontamination or possibly structural dismantlement activities.
Anydismantlement plans and specifications wouldbereviewed byastructural engineer toassure that activities would not render the TRFbuilding structurally
- unsafe, should anearthquake occur.
Decommissioning activities would notincrease therisk toTRFworkers during aseismic event.
4.5AirQuality Several Decommissioning-related activities could minimally impact airquality duetoboth mobile andstationary source emissions.
Asmall amountofmobile source emissions such ascarbon monoxide andnitrogen oxides could bereleased fromcontractors' trucks and cars.
However,theSanDiegoAirPollution District doesnotsetthresholds for determination ofsignificant emissions frommobile source emissions.
Duetothetemporary nature ofthetruck trips andthesmall
- number, mobile source emissions would below.
Stationary sourceemissions couldbe released during decontamination, building dismantlement andsolid remediation butareexpected tobenegligible.
Anyreleases from decontamination would occur within theTRF.Hazardous materials would belocated inside thebuilding.
Standard asbestos abatement procedures, under theoversight oftheSan Diego County AirPollution Control
- District, will beused toremoveanyasbestos.
Siteworkers wouldbeprotected during decontamination andsoil excavation activities through airmonitoring andtheuseofPPEandrespirators whenrequired.
B24
PC-000482/2 Theproposed action isonlya temporary potential source ofairemissions.
Negligible amounts ofmobile
- source, stationary
- source, andsoil remediation emissions wouldbe produced andwould notaffect regional attainment standards.
4.6 Regulatory Issues TableB-discusses the applicability ofvarious state andfederal regulations fortheproposed action.
4.7AreasNotAffected Theproposed action would notaffect thefollowing areas:
M-The proposed action wouldincrease thecompatibility ofGA withother science research activities on-going within theGAsite.
Future useofthe Building 21site could resultin the addition ofemployees ortenants atGA.
Cultural Resources-There arenocultural resources ontheGAsite.
Aeithst1tice.g--The proposed action would only be visible fromInterstate 5, located approximately 0.5mile(0.8 km)tothe east and Scripps Green
- Hospital, located 0.5mile (0.8 km)tothewest.TheTRFisnotcurrently visible toadjacent neighbors.
Temporary Decommissioning activities will becompatible with continuing industrial development of thesurrounding areas.
Theremaining site would beusedforother industrial-related purposes.
Biology-There arenoknownsensitive orendangered species ontheTRFsite.
Hyd.r.gl.ogy-The site elevation isapproximately 340feet above mean sealevel.
Itisnotin
- awetland, norisitina100-year flood plain.
4.8 Cumulative Effects No significant cumulative effects areexpected fromtheproposed
- action, as discussed below:
HumanHealth-The total doseestimated fordecommissioning workers is20person-rem fortheentire project evolution.
This estimate will beachieved byutilizing ALARApractices including planning ofworkactivities, utilization ofengineered safeguards,and minimization ofexposure times.
Thedecommissioning will beconducted under aWork Authorization systemusing written procedures toensure proper
- planning, training, and evaluation ofpotential risks.
Itshould benoted that atotal doseof20person-rem is consistent with18.6person-rem given inTable7.3-3"Summary ofradiation safety analyses fordecommissioning thereference research reactor" ofthe"Final Generic Environmental Impact Statement ondecommissioning ofnuclear facilities" (NUREG-0586)
(Ref.
5.16).
Thedose tomembers ofthepublic asaresult ofdecommissioning activities described in GA'sTRIGAfacility decommissioning plan areexpected tobenegligible.
Thedominant internal exposure pathway formembers ofthepublic isinhalation.
Thedose tothepublic isestimated tobenegligible because access totheareasurrounding thefacility isrestricted andbecause decontamination activities with potential forairborne activity will beconducted utilizing engineered safeguards such asHEPAequipped enclosures.
- Further, continued
($&
operation of thefacility HEPAsystemprovides additional protection forall m,.
decontamination activities conducted within thebuilding.
- Thus, potential airborne B25
PC000 482/2 TableB2-A licabilit ofEnvironmental Statutes andRe ulations tatute uation vauation ica I ationa nvironmen oicyct eevuation orpotenti environmenimpacts arecontaine in is es a
document.
GW n
ger pecies ct ocnti itats exist in eaect area, annoa erse mpacts o
o threatened orendangered species areexpected toresult from theproposed action.
as eans e uations e ro aconisnotoca wi inaweanorina ain.
o is an i ie co ination c
epropos action oesnot orimpact s
wi ienanywayor o
mod an bodies ofwater morethan10acres Insurface area.
arman roectionoI e
os a on snoa nmeorunue o
ationaistonc reserva on ereareno iso sites orareas n eocaono e ro a on.
o mencann lan eigiousree om ct eproposa onoesnointeere wi engto ave encans to o
exercise their traditional freedom.
i an cenic iversc eproposa on noin vewaerways esigna aswi o
scenicrivers.
esource an onserva on ecovery ct eproposaction mayinc e egenera on,pacgingan transportaties RCRA ofmixedwaste.
ompre ensive nvironmen esponse, yrequr reeasereporting wou epeorm ncompance wi es Comensation andLlabili ActCERCLA CERCLA reuirements.
er nsec cie, ungiciean entici e
epropo a onisnoinv in e is on,useorispo o any o
ActFIFRA insecticides, funicides orrodenticides.
oxic u stancesontroct estos may eencounter unng operations icwou e es roe ka edanddis 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 nnng ater epropose a on s exp oa su cewaer lesorwaer o
su lies.
Air emissions would bebelow waminlevels.
oise ontroct seeves coua verse ya e wo ersan s wi emi ga y
o providing ear protection for workers andrelocation ofstaff toareas awayfro theactivities.
Theublic is not ex ected tobelmacted from thenoise.
az ousaens ranspoon eproposa onw requ re s pmen o raoa vemaenasan mixe es (HMTA) wastes.
All waste will bepackaged and shipped inappropriate containers and dissedofatlicensed facilities ationmssions arsor azaous e
ass t a
are app eto icens actities. es AirPollutants NESHAPS Comliance with emission standard would be demonstrated.
tomicnergy cense requir mplancewe environmen an wo erproection es standard.
aiomia nvironmen uaI ct ro a on oesnottn eriscretiona review astate a enc o
Iomia ea an aety e, iv.
roposaction mu compywi wo ersaety regu ations.
es Ch ter7.6,Articles 13,14 Iomia ntegratasteanagement ct ransportation o ow everaloacvewasewou require es notification/consultation andmanifest.
iomia eo eguaonsia iv.,
cense requir omplancew environmen,wo er,a pu ic es Chater5,Subchter4,Radiation rotection standard radioactive will benegligible; and,therefore, thepotential internal dose tothe public isalso negligible.
Theestimate ofnegligible dosetomembersofthepublic canalsobeobtained from the estimate given forthereference research reactor inthe"Final Generic Environmental Impact Statement ondecommissioning nuclear facilities" (NUREG-0586)
(Ref.
5.16).
InSection 7.3.1 ofNUREG-0586, thedose tothepublic asaresult ofdecommissioning operations at thereference research reactor
- including truck transportation ofradioactive waste
- is "estimated tobenegligible (less than0.1person-rem)."
Thisestimate ofless than0.1 person-rem includes bothinternal (from inhalation andingestion) andexternal exposure doses.
WasteGeneration-The proposed action could generate approximately 4,000cubic feet of low-level radioactive wastefromTRFDecommissioning activities.
TheNevada TestSite is designated forthedisposal ofthis wasteandhassufficient capacity toreceive the waste.
Cultural Resources-No cultural resources would beimpacted bytheproposed action.
Popuullion.and.Lanti.le---Only temporary employment forafewcontractors wouldbe provided bytheproposed action.
Noincrease inpopulation would occur.
Landusewould notchange.
B-26
PC000482/2 Noise-TRF Decommissioningactivities wouldoccurinanindustrial areaandwould pgg largely occurwithin GA Building 21.Theproposed action wouldnot contribute Aff significantly tooff-site background noise levels duetotherelative isolation ofthework site.
Aesthetics-TRF Decommissioning activities would notbevisible tomostadjacent site neighbors, with the exceptionoftheareas ofInterstate 5andScripps GreenHospital, both located approximately 0.5miles (0.8 km)away.
Following release tounrestricted use,the TRFsite would be usedinamannerconsistent with theexisting GAsite land usepractices.
Traffic-The temporary contractor andwastetransport trips wouldcontribute an insignificant amountto the average number ofdaily trips designed forGenesee Avenue and JohnJayHopkins Drive.
-AllTRFDecommissioning activities would belocalized; stormwater runoff from exposedareasconsidered toberadiologically contaminated would becontainedand tested.
Rh-The SanDiego Air Basinisa non-attainment areaforcarbon
- monoxide, ozone,andsmall suspended particulates (PMw).
Theproposed action is temporary.
Asmall number ofvehicle tripswould begenerated during off-site shipment of wastematerials andwouldcontribute onlynegligible amountsofthese pollutants tothe basin.
Hyd.rology-No changes toanylandforms would occur andno radionuclides or hazardous materials would bereleased tostormwaterrun-off, resulting fromtheproposed action.
Bi.ologicd Resource.s-No biological resources havebeen identified on theTRFsite;
- moreover, TRFDecommissioning activities arenotexpected toeffect off-site biological resources.
4.9Alternatives toProposed Action This alternative poses essentially thesamepotential risks andenvironmental impactsas the proposed
- project, butpotentially foramuchgreater period oftime.
This alternative would necessitate continued surveillance andmaintenance oftheTRFovera substantial time period.
During this
- period, therisk ofenvironmental contammation wouldcontinue to exist.
- Moreover, development ofthelandaround theGAsite overthenextfewyears may significantly increase thelocal employment population density andincrease potential for public exposure.
Thisalternative isnotenvironmentally preferable.
Thisalternative wouldnecessitate continued surveillance andmaintenance oftheTRFover asubstantial timeperiod.
During this
- period, theriskofenvironmental contamination wouldcontinue toexist.
- Moreover, development oftheland around theGAsite overthe nextfewyears maysignificantly increase thelocal employment population density and increase potential forpublic exposure.
Thisalternative isnotenvironmentally preferable.
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5.6 Kennedy.
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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.
5.10Lindvall, S.C.,T.K.Rockwell, andC.E.Lindvall.
"The Seismic HazardofSanDiego, Revised:
Newevidence formagnitudes 6+Halocene earthquakes ontheRoseCanyon fault zone."
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5.11Woodward-Clyde Consultants.
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5.12SanDiego AirPollution Control District.
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5.14Amendment No.35toFacility License No.R-38(TRIGA MarkIReactor)-General Atomics (TAC No.M97502),
Issued bytheUSNRC,dated October 29,1997.
5.15Amendment No.43toFacility License No.R-67(TRIGA MarkF Reactor)-General Atomics (TAC No.M90380),
Issued bytheUSNRC,dated March 22,1995.
5.16U.S.Nuclear Regulatory Commission, NUREG-0586, "Final Generic Environmental Impact Statement ondecommissioning nuclear facilities,"
August 1988.
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