ML21246A262

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Triga Decommissioning Plan Safety Evaluation
ML21246A262
Person / Time
Site: General Atomics
Issue date: 08/12/1999
From: Alexander Adams, Rozier Carter
Idaho National Engineering & Environmental Lab (INEEL), Office of Nuclear Reactor Regulation
To:
General Atomics
Marlayna Doell, 301-415-3178
Shared Package
ML21246A250 List:
References
Download: ML21246A262 (36)
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++*o SAFETYEVALUATION BYTHEOFFICEOFNUCLEARREACTORREGULATION SUPPORTING AMENDMENTNO.36TO AMENDED FACILITY LICENSE NO.R-38 AND AMENDMENTNO45 TO FACILITY LICENSE NO.R-67 GENERAL ATOMICS DOCKETNOS.50-89 AND 50-163

1.0 INTRODUCTION

Byletter datedApril 18,1997,assupplemented byletters dated November 20,1998, andJanuary28and29,February 3,April 22,May3 and12,andJune 15,16,and22, 1999,General Atomics(GAorthelicensee) submitted theGA TRIGA Reactor Facility Decommissioning Plan(DP).

Thelicensee alsoapplied forterminationof Amended Facility License No.R-38fortheGATRIGAMarkIResearch Reactor andFacilityLicense No.R-67 fortheGATRIGAMarkFResearch Reactor (Docket Nos.50-89and50-163, respectively) pursuantto 10CFR50.82(b)(1).

2.0 EVALUATION 2.1 Introduction Thestaff hasreviewed andevaluated thelicensee's DPandapplication foramendment to Facility Licenses No.R-38andNo.R-67toauthorize dismantlement anddisposal ofthe componentsandmaterials fromthelicensee's two TRIGAnon-power reactors.The licensee alsoapplied fortermination ofthetwo NRClicenses, andrequested unrestricted useofthesite.

Thelicensee's DPisasupplement totheSafety Analysis Reportinaccordance with 10CFR50.82(b)(5).

Thelicensee maymakechanges totheDPinaccordance withthe regulations in10CFR50.59(a) through(c) asallowed by10CFR50.59(e).

- 2 TheDPincluded theinformationrequired by10CFR50.82(b)(4),

namely, (i) thechoiceof thealternative fordecommissioning withadescription ofactivities
involved, (ii) a description of the controls andlimits onprocedures andequipment toprotectoccupational andpublic health and safety, (iii) adescription oftheplanned final radiation survey,(iv) an updated costestimate, comparison ofthatestimate withpresentfunds setaside for decommissioning, and plans forassuringtheavailability ofadequate fundsforcompletion ofdecommissioning, and (v) a description oftechnical specifications (TSs),

quality assurance provisions andphysical security planprovisions inplaceduring decommissioning Thelicensee also submitted anupdatedenvironmental reportas required by10CFR51.53(d).

Thelicensee planstoremoveanddecontaminate theradioactive materials sothatthe residual radiological condition ofthesite meets theestablishedcriteria forrelease for unrestricted use.Because thetermsofa settlement agreement ofalawsuit concerning spentnuclear fuelandnuclear wasteattheIdaho National EngineeringandEnvironmental Laboratory (INEEL) severely constrain domesticspent nuclear fuelreceipts attheINEEL, reactorfuelwill remain onsite during somedecommissioning activities.Until thefuelhas beenappropriately removed,applicable license restrictions mustremain

ineffect, and somedecommissioning activities mustbedelayed.

Termination ofthetwo non-power reactorfacility licenses requires NRCtodetermine in accordance with10CFR50.82(b)(6) that(i) thedecommissioning has beenperformed in accordance withtheapproved decommissioning planand(ii) theterminal radiation survey andassociated documentation demonstrate thatthefacility andsiteare suitable for release inaccordance withthecriteria fordecommissioning in10CFRPart 20,SubpartE.

Thedecommissioning ofthesereactorsispartofGA'splans toconduct comprehensive decommissioning oftheGAsite.

Thelicensee hasalready decommissioned a number of otherfacilities underNRCspecial nuclear material andStateofCalifornia licenses.

Because ofthis,thelicensee hasdeveloped procedures andtechniques forcarryingout decommissioning activities andhasextensive experience inapplying their proceduresand techniques.

Thelicensee's performance during conduct oftheseother decommissioning activities hasbeenacceptable.

A "Notice ofApplication forDecommissioning Amendment"waspublished inthe FEDERALREGISTER onDecember 11,1997(62FR65288),inaccordance withthe requirements of10CFR50.82(b)(5).

2.2 m Thetwo non-power reactors arelocated intheTRIGAReactor Facility (TRF).

TheTRF occupies building No.21andanadjacent outdoor service yardonthegrounds ofthemain siteofGeneral Atomics Corporation, located inSanDiegoCounty,about21km (13miles) northofdowntownSanDiego, California (Figures 1, 2,3).

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- 3 TheTRF (Figures 4 and5)wasbuilt instagesovertheyears, starting withtheTRIGA MarkIreactor complex (License No.R-38) in1958(Figure 6).Subsequently, two other TRIGAreactors were added,called theTRIGAMarkF reactor(License No.R-67)

(Figure 7) andtheTRIGAMark Ill reactor(License No.R-100).

TheTRIGAMark111 reactorwas decommissioned and itsNRClicense terminated in1975.Someofthereactor structure andreactor poolremains with theresidual radioactive material possessed underan authorization fromtheState ofCalifornia.

Because theNRClicense fortheTRIGAMarkIll reactorhasalready beenterminated, onlytheTRIGAMarkIandTRIGAMarkFreactors aresubjects ofthis decommissioning reviewandevaluation.

Operations havebeenterminatedat the TRIGA MarkIandTRIGAMarkF reactors.

The TRIGAMarkIreactor license was amended onOctober29,1997,andtheTRIGAMarkF reactor license wasamendedonMarch22,

1995, toremoveauthority tooperatethe reactors.Thelicenses allow possession-only oftheremaining radioactive material.

All irradiated fuelisstored intheTRIGAMarkF reactor storage canalundertheTRIGAMarkF reactorlicense.

Someofthenonradioactive components(such asthe control console) oftheTRIGAMarkI reactorhavebeenremovedandshipped offsite tobereused inotherTRIGAreactors.

2.3 Thelicensee hasreviewed theoperating histories oftheTRF,andfound noreportsof spills orother eventsthatcouldsignificantly contaminate surfaces such asfloorsand walls.After anextensive characterization survey/program, discussedin the DP,the licensee verified theabsence ofcontaminated areasorcomponentsoutside of thereactor poolsandcoolant

loops, whichareinterconnected.

TheTRIGAMarkIreactor (250 kW) operated foratotal lifetime ofabout84MW-daysandtheTRIGAMarkF (1.5MW) operated foratotal lifetime ofabout4,200MW-days.Onthebasisoftheabove information, andexperience atpreviously decommissioned TRIGAreactors ofnearly identical

designs, thelicensee hasestimated thetypesandquantities ofradionuclides expected tobeencountered during decommissioning.

Thisinformation isgiven in Tables 1 and2.Thelicensee hasextensive experience workingwithradioactive componentsandmaterials, andeventhoughthecurrentinventories ofradionuclides are notrecorded

indetail, theyplantoinvestigate andprepare adequately before removing anddismantling components.TheTRIGAMarkIandTRIGAMarkF reactorscontain different typesofcomponentsintheregion ofthehighest neutronfluences nearthe cores.Thelicensee isawareofthesedifferences andisprepared toaddress them.

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Table1:List ofExpected Radionuclides Nuclide HalfLife Decay Notes (yr)

Mode "C

5730.

p-AP;fromnactivation ofgraphite reflector structure (TRIGA Mkionly) 5*Mn 0.86 e

, y AP;short-lived specie; fromn-activation ofSShardware 55Fe 2.73 e

AP;fromn-activation ofSShardware "Co 5.27 p,y AP;fromn-activation ofSShardware; expected tobepredominant AP specie present SSNi 76000.

e, y AP; from n-activation ofSShardware "Ni 100.

p-AP; from n-activation ofSShardware "Sr 29.1 p-FP;probable FP constituent; activity expected tobeproportional to thatof'"Cs "Nb 20000.

p,y AP;unlikely APinventory constituent; possible fromn-activation of SShardware, ifNbimpurities arepresent "Tc 213000.

D,y FP,andminor APinventoryconstituent; possible fromn-activation of SShardware, ifMoimpuritiesare present

'2sSb 2.76 p,y FP;relatively short-lived specie

"*Cs 2.07 E,y FP;minorFPinventory constituent "7Cs 30.17 D,y FP;expected tobepredominant FPspecie present "Ce 0.78 p,y FP;shortlived specie

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e, y FP,andminor APinventory constituent; possible fromnactivation of

concrete, ifEuimpurities exist inbiological shield structure Symbols/Abbreviations:

p- = Beta p+ = Positron e

= Electron Capture y

= Gamma-Ray 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 core components andother integral hardware orstructural members which aresituated adjacent to,orinclose proximity to,thereactor coreduring operations.

Specific items whichareconsidered tohave beenexposed toneutron activation include materials composedofaluminum,

steel, stainless-steel,
graphite, cadmium,lead, concrete andpossibly others.

Basedonearlier studies andexperience gained insimilar research reactor decommissioning

projects, andreactor-specific 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 soil volumes) isnotexpected foreither the TRIGAMarkInorMarkFReactors.

Table2 Sources ofRadiation Components withPotential Surface Contamination Purification System purification loopanddeionizer tank piping demineralizer OtherComponents cables andconduits pool deck plates rotaryrack drive reactor bridge structure pneumatic transfer system Components withInduced Radioactivity RotarySpecimenrack(TRIGA MarkIreactoronly)

Control rodguidetubesanddetector tubes Topgrid plate Bottomgridplate 3

Reflector Coresupport Fasteners andconnectors Pneumatic transfer systemterminus Reactor TankActivated Components Reactor pitliner Concrete Anchors Reinforcement bars Equipment UsedinDecommissioning Operations General ventilation system Localized ventilation system Confinement barriers Contaminated tools andequipment Contaminated clothing

- 4 Thefuel is stored inacanallocated offthepooloftheTRIGAMarkF reactor.Thereis sufficientwater above thefuel toprovide adequate shielding topersonnel working atfloor level.

This water iscurrently beingcirculated andpurified tolimit thecorrosion ofthefuel cladding andother submersed componentssothatcontained radioactive material isnot likely tomigrate to less contaminated areas.Thefuelwill continue tobestored and handled inaccordance with therequirements oftheTSs.TRIGAMarkFreactor componentswhosedismantlement couldimpactfuelsafety willbeleft inplaceuntil after thefuelhasbeenremoved from thestoragecanal inpreparation toshipoffsite.

Thestaff hasreviewed thelicensee's methods usedtoassessradiological conditions, how theywill plantolimit personal exposures astheydismantle, andhowtheywill perform additional radiation measurementsand surveys asthedismantlementproceeds.

Thestaff concludes thatthelicensee's plansareacceptable.

2.4 M Theregulations in10CFR50.82(b)(4)(i) require that the licensee discuss their choice of alternative fordecommissioning.

Thethreebasic approaches todecommissioning are (1)DECON,wherethelicensee dismantles anddecontaminates their facility without significant

delay, (2)SAFSTOR,wherethefacility isplaced and maintained ina condition thatallows thefacility tobesafely stored andsubsequentlydecontaminated tolevels that permit release forunrestricted use,and(3)

ENTOMB,whereradioactive contaminates are encased ina structurally long-lived

material, suchasconcrete,the entombed structureis appropriately maintained andcontinued surveillance iscarried outuntil the radioactivity decaystoa level permitting release ofthepropertyforunrestricted use.

Theregulations in10CFR50.82(b)(4)(i) further statethata decommissioning alternative isacceptable ifitprovides forcompletion ofdecommissioning without significant delay.

Thelicensee hasdecided todismantle anddispose ofreactor-related radioactivematerial assoonasfeasible (DECON option).

TheTRIGAMarkIreactorwill bedecommissioned without significant delay.Next,TRIGAMarkF reactor decommissioning activities thatcan besafely carried outwiththefuelintheTRIGAMarkFfuel storagecanal willbe completed.

After fuelisremoved offsite,TRIGAMarkF reactordecommissioning activities will becompleted.

SAFSTORisnotacceptable tothelicensee because itwouldrequire longtermmonitoring andlossofproperty use,andbecause thequantity ofradioactive materials atthesiteis relatively

small, readily removed,andthere isanavailable approved low-level radioactive wastedisposal site.

ThelongtermENTOMBdecommissioning option suffers fromthe samedisadvantages.

Furthermore, theTRFwasnotadequately designed orsited tobea longtermdepository ofradioactive material whichwouldresult fromeither theSAFSTOR orENTOMBoptions.

- 5 Thestaff concurs thatearly dismantlement andremovalofradioactive material toa planned and authorized disposal site isthepreferred methodtoachieve limited environmental impact andlongtermprotection ofthehealth andsafety ofthepublic.

The staff concludesthat thelicensee's choiceofdecommissioning alternative meetsthe requirements of10 CFR 50.82(b)(4)(i).

2.5 TheDPcontains anorganization

chart, Figure 8,thatdemonstrates thatGAmanagement isfully awarethateventhough reactor decommissioning islesshazardous thanreactor operation anduse,itsclose involvement andcontrol isstill needed.Therefore, a

decommissioning groupreporting tothe company VicePresident forResearch and Development isestablished, with responsibilities similar totheoperations groupwhenthe reactors wereinuse.Themanagementis aware andcommittedtoitsresponsibility to ensurecontinued compliance withall applicable regulations, andthatcontrols onany contractors alsoensurecompliance.

Decommissioning dealsmostlywithradioactive wasteandassociated personnel protection, sothe strong independent radiation protection program isstill

inplace, withadequate authority toensure protection ofbothworkers and thepublic.

Furthermore, manyofthepersonnel who were knowledgeable andinvolved during reactoroperations havebeenretained.

Their knowledge andexperience gives reasonable assurance thatdecommissioning activities will be carried outsafely andin accordance withtheregulations.

Because thedecommissioning groupisprominent intheGA management structure, the qualifications ofkeypositions

arehigh, andleadership positions arefilled byexperienced andwellqualified personnel, thestaff concludes thattheorganization and management structures areacceptable tosuccessfully andsafely complete thedecommissioning ofthe TRFatGA.

2.6 TheDPacknowledges thatGAisrequired toensurethatallactions bybothitsstaff and anycontractors complywithallapplicable regulations, forexample10CFR50.82for decommissioning activities, 10CFRPart20forradiation protection, 10CFRPart71for managementofradioactive waste,and10CFRPart73forphysical protection offuel materials.

Several NUREGandregulatory guidedocuments havebeenissued byNRCto helpdefine acceptable decommissioning actions andresults, including NUREG-5512, "Residual Radioactive Contamination FromDecommissioning,"

NUREG-5849,"Manualfor Conducting Radiological Surveys inSupport ofLicense Termination,"

Regulatory Guide 1.86,"Termination ofOperating Licenses forNuclear Reactors,"

andthe"Site Decommissioning Management Plan(SDMP)

Action PlanofApril 16,1992"(57FR 13389).

TheDPnotesthatthelicensee isawareof,andintends tousetheseandotherapplicable guidance andregulations.

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- 6 Thestaff considers thelicensee's information,

plans, andcommitments aresufficient to give reasonable assurance thata well-planned andcompliant decommissioning oftheTRF atGAwill result.

2.7 W TheDPdiscusses GA's plans fortrainingbothmanagersandworkers intheir respective roles.

GA overtheyearshas conducted training programs foroutside groupsand individuals insuchtopics asreactor operation andradiation protection.

Therefore, thereis still considerable interest atthe management level andexperience andcompetenceatthe workerlevels toprovide all needed training in-house. Therecontinues tobegeneral employee radiological training forall.

There areestablishedprograms toincrease workers' knowledge inhandling radiological

waste, including surveying,classifying, packaging,
shipping, andpreparing documentation.There isa continuing training programforhealth physicists inallaspectsofradiation protection.

Asuniqueequipment isintroduced to perform dismantlement andsegmenting ofcomponents, operators willbetrained.

Ifany workinvolving hazardous ormixedwastesisanticipated, workers willbetrained as necessary.

Training inapplicable topicswillbeconducted forall contractorsand subcontractors.

Senior staff who havebothworkandteaching experience willbe responsible forpreparing andconducting thetraining.

OnthebasisofGA'smanagementcommitment,historical activities atthesite,andthe planning stated intheDP,thestaff concludes there isreasonable assurance thatthe individual membersoftheworkforceandstaff will betrained acceptably to implement the TRFdecommissioning whileprotecting thehealth andsafety ofthepublic.

2.8 m GA planstousetheexisting companyHealthPhysics (HP)

Programwhile conducting the TRFdecommissioning Thisprogramemphasizes compliance with10CFRPart20in handling radioactive materials, andincludes apolicy toensurethatallradiation exposures areaslowasreasonably achievable (ALARA).

Thequalification requirements forthe position ofManager, health

physics, andthekeystaff membersensurevery knowledgeable andexperienced personnel.

Overtheyears, GAhasdealt withsomevery complexradiological

issues, including thedecommissioning ofotherfacilities attheGA
site, sotheexisting staff should bewellprepared tosuccessfully manageprotecting personnel andtheenvironment during TRFdecommissioning.

TheHPprogramaddresses all aspectsofradiation andexposure management,including methodsofexposure reduction, radiation workpermits,

surveys, personal dosimetry, control andstorageof radioactive
material, respiratory protection, equipment andinstrumentation, effluent monitoring,
audits, quality
control, radiological accident
analyses, andgen'eral industrial safety.

inorder toconduct aneffective ALARAprogram, themeasurementinstruments andmethodsofanalysis should beappropriate andofhighquality.

TheDPdiscusses the typesofinstruments, selection

criteria, andcalibration program thatwillbeinplace during decommissioning.

TheDPdiscusses confinement andcontrol ofpossible airborne

- 7 radioactive material tobegenerated asa result ofcertain dismantlement activities, and concludesthat thiscontrol,alongwithaccesscontrol tothefacilities, will ensurethat membersofthe public will receive negligible (less than0.1person-rem) radiation exposure fromreactor-related radiation duetodecommissioning activities.

TheGAstaff has predicted theradiation exposures oftheworkers onthedecommissioning project tobe lessthan20 person-rem.

Details oftheestimated occupation exposure areprovided in Table3.

Onthebasis ofbothprior history andthedocumentedHPprogram atGA,thestaff concludes thatGA management has made radiationprotection a highpriority, andthe planning issufficient toprovide reasonable assurance thattheworkers,thepublic, andthe environment willbeprotected fromsignificant radiological risk related totheGATRF decommissioning project.

2.9 m TheGA managementhasemphasized andpromoted a safe workingenvironment inthe past,andtheDPincludes discussions andcommitments tocontinue thosepolicies and practices during theTRFdecommissioning.

TheDPcites specific guidancetobe

employed, asfoundinOSHAregulations andstateofCalifornia regulations, andinthe general GA Quality Assurance Plan.Thestaff considers these plans acceptable tocontrol industrial risks.

2.10 M Theregulations in10CFR50.82require thelicensee tosubmitanupdated cost estimate forthechosenalternative fordecommissioning, acomparison ofthat estimate with presentfundssetaside fordecommissioning, andplansforassuring theavailability of adequatefundsforcompletion ofdecommissioning.

Thelicensee estimates that decommissioning thetwo reactorswill costabout$5.6million.

Theestimate is reasonable, basedonprevious decommissioning projects ofsimilar reactor facilities.

GA hastraditionally useda parentcompanyguaranty tomeet thedecommissioning funding regulations.

Because ofotherdecommissioning commitments andfinancial

factors, in 1996,GA'sparentcompany,General AtomicTechnologies Corporation, couldnolonger qualify toprovide aguarantyofthefull amountofthecostofdecommissioning thetwo reactors andotherfacilities underGA'snuclear material license.

Byletter datedMay20, 1996,GAproposed analternative meansofproviding decommissioning funding assurance thatcombined a limited parentcompanyguaranty(for anagreed uponamountthatisless thanthetotal costofdecommissioning) witha sinking fundintowhichmoneyis contributed annually

. Ofthemoneyplacedinthesinking fund,partofthemoneyand interest canbeusedtopayforcurrent decommissioning costs.Theremaining money muststayinthefundwiththefundbalance growing eachyearuntil thefundbalance

TABLE 3 OCCUPATIONAL RADIATION DOSEESTIMATES FORTRIGAREACTORS DECOMMISSIONING TASKS N

1 TRIGAReactor FacilityD&D 2

NRC/State approval ofDecommissioning Plan 3

Decommission MkiReactor 4

Radiological Survey 112 2

0.0002 0.0448 0.04 5

RemoveReactor Components abovePool 80 4

0.0002 0.064 0.06 6

RemoveReactor Components inPool 7

Grapple/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 j Discharge/Filter asnecessary 40 3

0.0002 0.024 0.05 13 Install Confinement Barrier aroundReactor Pit 40 3

0.0003 0.036 0.04 14 lAlTankRemoval 15 Cut/Remove insections 80 4

0.0025 0.8 16 Segregate cleansections 64 4

0.0025 0.64 17 Package LLWsections 56 4

0.002 0.448 1.89 8

Concrete Liner 19 Demolish activated portion 120 4

0.002 0.96 I

20 Remove/Package 112 4

0.002 0.896 21 Survey remaining Concrete 32 2

0.0005 0.032 22 ! Demolish remaining portion toexpose Soil 80 4

0.0005 0.16

[

23 Survey Soil presumed tobeclean 40 2

0.0002 0.016 24

! Shore/Cover Pit 40 4

0.0002 0.032 2.10 25Aey/RemoveStorage

Wells, ifcontaminated 160 4

0.0003 0.192 0.19 26 [Dismantle Barrier/Package forLLWdisposal 40 4

0.0002 0.032 0.03 27

! Decontaminate MkiReactor Roomsurfaces 80 4

0.0002 0.064 0.16 28 lDecommission remaining

areas, exceptMkF 29 lRemoveHotDrainLines 104 4

0.0003 0.1248 l

30

[ Removecontaminated

sections, exc.

fromMkFRoom 80 4

0.0003 0.096 31

' Reroute services toisolate MkFRoom 224 4

0.0002 0.1792 32 lRemoveMakeUpWaterTank 80 4

0.0002 0.064 33 Dismantle/Dispose ofremaining equipment inYard 160 3

0.0003 0.144 34

, ShiLLWtoNTS l80 4

0.0003 0.096 0.70 (CONTINUED)

TABLE3.

OCCUPATIONAL RADIATION DOSEESTIMATES FORTRIGAREACTORS DECOMMISSIONING TASKS,(CONTINUED)

Task' TaskDescription Duralian 319. vg,0cee TotaicoseSubtotal Total No.

Es..

rem/hr2 wom m

wom 35 Decommission MkFReactor 36 Radiological Survey 120 2

0.002 0.48 0.48 37 RemoveReactor Componentsin Pool 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 CanalWater 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 reteLiner 52 Demolish activated portion 112 4

0.002 0.896 53 i

Remove/Package 120 4

0.002 0.96 54 Survey remaining Concrete 40 2

0.0005 0.04 55 l Demolish remaining portion toexpose Soil 80 4

0.0005 0.16 l

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 l ShipLLWtoNTS 72 4

0.0002 0.0576 0.06

~

v 62RSoil 112 2

0.0002 0.0448 0.04 UPrepareSurveyReport 64 iSubmittal forRelease toUnrestricted Use

- 8 represents the difference betweentheremaining GAcostofdecommissioning thesiteand theparent company guaranty. TheNRCagreed toGA'sproposal ina letter datedJuly9, 1996.TheNRC staff hasreviewed GA'sfinancial statements annually toverify thatthe licensee ismeeting therequirements ofthelimited parentcompanyguaranty.As partof thereview forthis licensing

action, thestaff reviewed financial records associated with thesinking fundand verified thattheconditions ofmaintaining thesinking fundhavebeen met. Thestaff concludes that GAismeeting theconditions oftheir alternative meansof providing decommissioning funding assurance andthatthereisreasonable assurance that sufficient fundswill beavailable fordecommissioning theGAreactors.

2.11 TheDPprovides a proposed schedule(Figure 9),estimatedinventories ofradioactive

nuclides, approximate distribution ofradioactive material bycomponentandlocation, dismantlement actions tobetaken, estimates of radioactive wastestobeproduced, and projected workerradiation dosesforcompletion of thedecommissioning.

Allcomponents oftheTRIGAMarkIreactorthatcurrently remain will beremoved, segmented and packaged forshipment asradioactive waste,asnecessary.

Thebiological shield structure will bedecontaminated asnecessary, butitisnotexpected thatbiologicalshield decontamination willresult insignificant building structural changes.

Thenremoval ofthe TRIGAMarkFreactorcomponentswillbestarted.

However, until allfuelisremovedfrom thestoragecanal,dismantlement ofcomponentsthatcould pose a risktofuelintegrity or security willbedelayed.

After fuelremoval,dismantlement anddecontamination as necessary oftheTRIGAMarkF reactorwillresume.TheTRIGAMark Ireactor accumulated onlyabouttwo percentasmanymegawattdaysastheTRIGA MarkF reactor.Because theTRIGAMarkIreactorwill bedecommissioned first, it can beusedto develop additional expertise indecommissioning technics ina lowerdoseenvironment thantheTRIGAMarkF.Thisexpertise willcontribute toefficient decommissioning ofthe TRIGAMarkFreactor.

Thestaff considers thatGAhasconducted sufficient

planning, radiological characterizations, andradiation exposure predictions sothatthereisreasonable assurance thatdecommissioning will becompleted asplanned intheDP.Thestaff hasalso examined GA'splans toconduct decommissioning activities attheTRIGAMarkFreactor withreactorfuel presentintheTRIGAMarkFstoragecanalandconcludes thatthelimited activities planned bythelicensee canbecarried outwithout significant riskoffueldamage orrelease offission products

7M M

9M 7

SCHEDULE FOR TRGA REACTOR FACLTY D&D Tas#

Tas Name g

g Y

RGA REACTOR FACLTY D&D O

i RC/Sae Approva o

DPan jDecommission Mark Reacor%F Remove Reaco Componens inPoo Gae/Hos/Suve Disassembe asnecessa 5'

Demois acivaed

oion2, Remove

/Pacage 0'O Suve Soiesume o

e cea Soe

/Covepi@

Suvey/Remove Soae

Waa, icon Diamane Baie/Pacage oLLW disposa 2jDeconamin MiReaco Room suaces 2QDeco remaining
areas, excep MkF Remove HoDain Lines Remove conaminae secions exc.

om MF Room Reoue sevices oisoae MF Room jRemove Maeup Wae Tan Diaman oemainin eqp inad Ship heLLW oNTS Radioogica Suve

'Remove Reaco Componens abovePoob 3

iDeconaminae oPacae asW@

[Reaco TankWaee Suve/Same/A o

Discae

/Fie asnecessa nsa Coninemen Barier around Reacor Pi Auminum Tan Remova u/Remove insecion 3

1Pacae LW secions o

M Concee Linev M

Concee Demoish emainin oion asnecessa i0/30/9

Task#

Task Name 2Y sy4Y7 9Ml M

M 5MF7M M

M'M 2SM 7M 29M 3M 33M 5M 37M 39M 4M 43M 3Remove Reacor Componens nPoo

,,+G 4

LDisassembe asnecessa 4Deconaminae oPacae as W

4DOE Appova oShip Fue 4

Ship Fue Sored inMkF Cana Reacor Tank

&Sorage Cana Waer m

4Suve/Sampe/Ana 4Dischage/Fie asnecessa g

nsa Coninemen Barrie around Reaco Pi o

4Tank Remova 4Cu/Remove insecions Q

gD 49Segegae ceansecion 0

5Pacage LLWsecion O

.3 Concee Liner" Demois acivaed poion@

5Remove/ackage O

Suve emainin con 5'

5Demois emainin poion asnece 5Suve Soipesume o

ecean f

iShoe/Cove pi 7

Dismane Barier/Packag or LLWdisp Deconamin MF Reaco Roomsua S

j SCHEDULE FOR TRGA REACTOR FACLTY D&D Y'

Suvey Soi

~

Pepae Suvey Repo Submia orReease oUnresric Use 0/30/98 3Decommission Mark FReacor oogica Suve

,Pacage conaminaed oos and equipmen Ship LLW oNTS

- 9 2.12 Assurance Overtheyears, GA hasconducted manyactivities thatrequired maintaining control of licensed materials and controlled accesstofacilities.

Therefore, theyhaveapproved security plansandprocedures

inplace, andhavemaintained astaff withsecurity experience.

GA plansto continue withthesesameprocedures, asapplicable, toprotect theradioactive high enriched uranium fuel fromlossordiversion, andtomaintain restrictions toprotectbothworkers andthepublic fromunplanned radiation exposures.

Because ofGA'sexperience inthis area andtheir NRCapproved security plan,thestaff considers their plansandprovisions to beacceptable.

Thelicensee continues tohaveanNRC approved Radiological Contingency Planinplace to respond toemergencies.

Thelicensee updates theplanasneeded.Theplanwas last updated onOctober 9,1998,undertheprovisions of10CFR50.54(q)Thestaff concludes thattheRadiological Contingency Plan issufficient forresponding to emergencies thatmayarise during decommissioning and fuel storage.

Becausethelicensee continues tohaveirradiated fuelon

site, GAismaintainingthe qualifications ofNRC-licensed reactor operators.

Withthe permanent shutdownofthe

reactors, thelicensee amendedtheir TRIGAReactors Facility Operator Requalification Program tofocusonfuelhandling safety andactivities.

TheNRC staff reviewed the changes totherequalification programandapproved thechanges on March 3,1998.

Thelicensee prepared aquality assurance program fortheTRFdecommissioning project.

TheprogramisbasedontheGAcorporate quality assurance program which meets the requirements of10CFRPart71,Subpart H,"Quality Assurance,"

andtheguidance of ASME-NQA-1-1989,"Quality Assurance ProgramRequirements forNuclear Facilities" and ANS-15.8,"Quality Assurance Program Requirements forResearch Reactors."The GA corporatequality assurance program wasreviewed andaccepted bytheNRCSpent Fuel Project Office.

Thestaff reviewed theprogramfortheTRFdecommissioning projectand concludes thattheprogramisacceptable forTRIGAreactordecommissioning activities.

2.13m Thelicensee hasconsidered possible accidents during decommissioning thatcouldcause radiation exposures orunplanned releases ofradioactive material.

Mostoftheaccidents postulated anddiscussed intheDPcouldimpactthestored fuel.

Theseinclude:

1 fuel storageandhandling;

2. seismicity;
3. fire;
4. otherconsiderations.

- 10 M

Thefuelwill bebothstored andmovedbyexperienced licensed reactor operators inaccordance withTSsandprocedures previously ineffect during reactor operations.

Also,emergencyprocedures thataddress postulated stored fuel accidentswill remain ineffect.

However,thelicensee hasproposed some dismantlement and removal ofcomponents, internal totheTRIGAMarkF reactorpool whilefuelisstill stored inthecanal.

Thelicensee hasplanned special precautions to avoiddropping such components andotherwise damaging thefuel.Ifprecautions were notsufficient andsomefuel elements weredamaged, anyreleased fission products and fissile nuclides wouldbeprimarily retained inthepoolwater,tobedecontaminated later.

Because thefuelhasundergone a period ofdecayofatleast several

years, many significant short-lived fission products either nolonger exist orhavehadtheir inventories decreased significantly.

Dosestothe staff andmembersofthepublic fromfuelcladding failure willbewithin previously accepted values forfailures during reactor operation.

Seismici.ty SanDiegoCountyisconsidered to beoneofthemoderate seismic risk regions insouthern California.

Therefore, a seismic event ofmagnitude close tosevenon theRichter scale isnotlikely during thefewyears while fuelwillstill bestored inthe canal.

Intheeventofadamaging quake,watercould be lostfromtheTRIGAMarkF reactorpoolandthestoragecanal.Thewaterisusedfor shielding, notfuelcooling, and currently iscirculated through cleanup systems,sotheconcentration ofradioactivity wouldfall within NRCregulations forrelease fromthefacility.

The primaryissue wouldbe forGAstaff toshield thereactorfuel.

Therefore, nosignificant release ofradioactive material wouldoccurunless fuelcladding wereruptured.

This would notbelikely, becausethereislittle heavymaterial thatcouldcollapse ontothefuel with damaging effect.

Inaddition, protective deckplates coverthefuel storage canal.

Fire.

Thelicensee hasconsidered howfires during decommissioning couldimpact fuel integrity.

However,accumulation offlammable materials will bemonitored and

avoided, andaslongasthereactorpoolisintact, thefuelisprotected fromthereactor room region under15feetofwater.

Otherconsiderations.

Thelicensee hasaddressed thepossibility ofradiological accidents duetomishandling radioactive componentsother thanfuel.

TheGAstaff has considerable experience withsuchactivities, andarecommitted tosufficient preplanning andprecautionary procedures tokeepthelikelihood ofsucheventsacceptably low.

Thestaff considers thatwiththehistory ofGA'sradiological experience andproposed preplanning, thereisreasonable assurance thatsignificant radiological risk toworkers and thepublic will beacceptably low.

- 11 2.14 TheDPaddresses thevarioussourcesofsolid andliquid radioactive wastes,andtheir managementand disposal.

Thereisnosourceofairborne wasteother thanparticulate dustresulting from dismantling proceduressuchasmetalcutting andconcretedemolition, whichwillbecontrolled bytemporary barriers andlocal airhandling andfilters.

Several componentsfromeach ofthereactors, including thereactor tanks,weremade radioactive byneutronirradiation during reactoroperations.

Thesewillberemoved, segmented asnecessary,

packaged, andshippedoffsite, allinaccordance withapplicable regulations.

GAhasan arrangement with theDepartmentofEnergy(DOE) toshipthelow level radioactive wastetotheNevada waste disposal site.

Someoftheconcreteinthe biological shield isradioactive intheregion close tothereactorcores.Somedemolition andremoval will beexpected toreduce the residual contamination downtolevels that meettherelease criteria.

Thisradioactive waste willalsobeshipped totheDOEorother licensed disposal facility.

Thepoolwaterwill beanalyzed carefully andwhenit is sufficiently clean tocomplywith 10CFRPart20limits, itwillbereleased intotheGAsanitary waste stream.GA maintains a radioactive wasteprocessing facility thatcanbe used todecontaminate liquid radioactive materials ifnecessary.

Theusedreactorfuelwill bereturned toDOE.Muchofthis fuelis highly radioactive with fission

products, andalsomanyoftheelements contain highenriched uranium.

GAplans tocontinue adequate protective custodyuntil DOEmakesarrangements and retrieves the fuel.

Atthiswriting, DOEprojects thatthisaction isnotlikely tooccur before 2003.

TheDPcontains adiscussion oftheGA radioactive material controls program to ensure thatradioactive material isdisposed inaccordance with10CFRPart20,SubpartK, "WasteDisposal."

Thisdiscussion includes information ontheradiation detection instruments tobeusedtosurveymaterial leaving theGAsiteandthesensitivity that theseinstruments willpossess.Thelicensee mayalsotransfer material fromthereactor licenses tootherGAradioactive materials licenses foradditional processing orforfinal disposal.

Considering thediscussions intheDPandGA'sexperience wi'th managing radioactive materials, thestaff concludes thatthereisreasonable assurance thattheradioactive wastesproduced bydemolition, dismantlement, anddecontamination willbehandled,

packaged, anddisposed offsite inaccordance withallapplicable regulations, andinaccord withALARAprinciples inprotecting thehealth andsafety ofthepublic andtheworkers.

- 12 2.15 License Conditions Thelicensee has proposed changes tothelicense conditions commensuratewithfacility decommissioning.

Inaddition tothechanges proposed bythelicensee, theNRCstaff has amendedseverallicense conditions commensuratewithdecommissioning status.The NRCstaff discussedthese changes withthelicensee whohadnoobjections tothe changes.

TRIGAMar.kj.

Thelicenseehas requested thatlicense condition 2.B.(2) bedeleted inits entirety.

Thislicense condition authorizes possessionofspecial nuclear material.

With theTRIGAMarkIreactorfuel permanently transferred totheTRIGAMarkFlicense for storageintheTRIGAMarkFfuel storage canal, thislicense condition isnolonger needed.

Thestaff hasamendedlicense conditions 1.C.,

1.D.,1.E.,and2.C.(2) tochange reference topossession ofthereactor todecommissioning ofthereactor.Theselicense conditions havebeenamendedtoreadasfollows:

1.C.

Thefacility will bedecommissionedin conformity withtheapplication asamended,theprovisions oftheAct,and the rulesandregulations of theCommission; 1.D.

Thereisreasonable assurance thatthereactor facility canbe decommissioned (i) without endangering thehealth and safety ofthepublic and(ii) incompliance withtheregulations inthis chapter; 1.E.

General Atomicsistechnically andfinancially qualified todecommission the facility inaccordance withtheregulations inthis chapter; 2.C.(2)

M TheTechnical Specifications contained inAppendix A,asrevised through AmendmentNo.36,areherebyincorporated inthelicense.

Thelicensee shall decommission thefacility inaccordance withtheTechnical Specifications.

Becausethesechanges tothelicense conditions reflect thechangeinstatusofthereactor toactive decommissioning, thesechanges areacceptable tothestaff.

TRIGAMarlLF.

Thelicensee hasrequested thatlicense conditions 3 and4 bedeleted fromthelicense ittheir entirety.

License condition 3contained requirements forrecord retention andlicense condition 4 contained requirements forreports.Theserequirements havebeenupdated toreflect thedecommissioning statusofthereactorandplaced inthe amendedTSs.

- 13 Thestaff has amended license conditions 1.B.,1.C.,1.D.,1.E.,and2.C.2tochange referenceto possession ofthereactor todecommissioning ofthereactor.Theselicense conditions have been amended toreadasfollows:

1.B.

Thereactor hasbeenconstructed inconformity withConstruction Permit No..

CPRR-59 andwill bedecommissionedinconformity withthe application, as

amended, andinconformity withtheActandtherules and regulationsof the Commission; 1.C.

Thereisreasonable assurance thatthereactor canbedecommissioned at thedesignated location without endangering thehealth andsafety ofthe public; 1.D.

General Atomics istechnically and financially qualified todecommission the reactor; 1.E.

Thedecommissioning ofthereactorin the manner proposed inthe application will notbeinimical tothecommon defense andsecurity ortothe health andsafety ofthepublic; 2

m TheTechnical Specifications contained inAppendixA, as revised through AmendmentNo.45,areherebyincorporated inthelicense.

Thelicensee shall decommission thefacility inaccordance withtheTechnical Specifications.

Becausethesechanges tothelicense relocate conditions fromthelicense tothe TSs and reflect thechangeinstatusofthereactor toactive decommissioning, these changes are acceptable tothestaff.

2.16 M GAwill maintain TSstoensurecontrol ofimportant aspectsoftheofthe decommissioning oftheTRF.Thelicensee hasproposed changes totheTSfortheTRIGA MarkIandTRIGAMarkFreactorlicenses.

Thechanges totheTSsfall intofivemajor categories:

1 Editorial changesthathavenoimpact onTScontentorintent.

- 14 2.

Changes thatdelete reference toreactoroperation andconduct ofexperiments, ora reactor condition, equipmentrequirement orfuelrequirement whichisnolonger applicable or required forsafety related functions.

FortheTRIGAMarkIreactorthese changes reflect thefactthatauthority tooperatethereactorandpossessfuelhas beenpermanently removed fromthelicense.

FortheTRIGAMarkFreactorthese changes reflectthe fact thatauthority tooperatethereactorandmaintain fuelonthe reactorgridplate have been permanently removedfromthelicense.

Because ofthe permanentchanges to the

licenses, thesedeletions havenoimpact onreactoror decommissioning safety.
3. Requirements associated with the reactor thathavebeenaddedorrevised toapplyto thefacility instead ofthereactorto reflect thefactthatthefacility, andnotjustthe reactor,isbeingdecommissioned.
4. Newrequirements thatareaddedtotheTSs tocapture important requirements ofthe DP.
5. Changesthatareproposed toprovide clarification to existing requirements toimprove consistency orclarity.

inaddition, changesweremadetotheadministrative requirements sections ofboth licenses tomakethesesections oftheTSssimilar.

Overtheyears, theadministrative requirements forthetwo reactors havenotbeenconsistently changed.

Forexample,the TRIGAMarkITSscontains arequirement forthesubmission ofanannual report where theTRIGAMarkFTSscontains noannualreporting requirement (although the licensee has submitted anannual reportfortheTRIGAMarkFvoluntarily).

Thelicensee has proposed similar reporting requirements forbothlicenses.

Whenthetwo reactor's operating licenses wereamendedtopossession-only to remove theauthorization tooperatethereactor,onlyminimal changesintheTSstorequirements directly related toreactoroperation wereproposed bythelicensee, andapproved byNRC.

Manyspecifications wereleft intheTSsthatwerenotneededforafacility inpossession-onlystatus,butbecauseoftheir

wording, wouldnotbeeffective again.Thelicensee now wantstoremovethesemeaningless TSstocreatea precise setofTSs.

TRIGAMarkj.Because fuelisnotnow permitted intheMarkI,allspecifications related

tofuel, reactorcore,reactivity, reactor safety systems,reactoroperating conditions, control instrumentation, experiments, andsurveillances related tothesetopics areno longer applicable.

Theproposed specifications arediscussed andevaluated below.

Coverpageandtable ofcontents Editorial changes weremadetothesesections to reflect otherchanges madetotheTSs.

TS 1.0 Definitions:

Thelicensee hasproposed several new definitions related to thedecommissioning statusofthefacility.

- 15 A new definition 1 1for"Facility" reads asfollows:

Facility means thebuilding housing thedisassembled reactorplussystems, components, etc.associatedwithpossession anddecommissioning ofthe reactor.

A new definition 1.2 for "Facility Secured" readsasfollows:

Facility secured shall mean thatcondition wherenodecommissioning activities areinprogress inthefacility.

A new definition 1.3for"Facility Operation" readsasfollows:

Facility operation shall meananycondition whereinthefacility isnot secured.

A new definition 1.4for"Decommissioning Activities" readsasfollows:

Decommissioning activities shall meanthoseactivities requiredtoremove thefacility safely fromservice andreduce residual radioactivity toalevel thatpermits therelease ofthefacility tounrestricted use andtermination of thelicense.

Theseactivities will involve thehandling, surveying, packaging, anddispositioning ofradioactive materials inthefacility.

A new definition 1.5for"Decommissioning Status" readsasfollows:

Decommissioning statusmeansthatthefacility license hasbeenamended to withdraw authorization tooperatethereactorandauthorizes possession onlyofthereactor,andthatthefuelhasbeenremovedfromthereactor and ismaintained ina safeandsecuremannerinanapproved location outside theMarkIfacility.

Thedefinitions of"Facility Secured" and"Facility Operation" replace similar definitions forthereactor toreflect thefactthatthescopeofdecommissioning activities involve notjustthereactorbutthereactorfacility.

Thenew definitions of "Facility,"

"Decommissioning Activities" and"Decommissioning Status" helptodefine thescopeoftheTSstodecommissioning andareusedintheTSstodetermine equipment operability requirements.

- 16 A new definition (1.7) for"operating" hasbeenaddedtotheTSsbecause some pieces of equipment mustbeoperating during theconduct ofdecommissioning activities.

This definition usesthestandard non-powerreactorwordingofthe definition.

The licensee hasproposed changing thedefinition of"Reportable Occurrence"to "Abnormal Occurrence"(old definition 1.10,new definition 1.8).

The definition was changed torefer tofacility conditions instead ofthereactorandto removeconditions that referred tofuel.Thesechanges wererequested because of thechangeofthefacility todecommissioning status.

Definitions for"Reactor Shutdown,"

"ReactorSecured,"

"Reactor Operation,"

"Standard Control Rod,""Transient Control Rod,""ColdCritical,"

"Experiment,"

"Experimental Facilities,"

"Reactor Safety Systems,""Experiment Safety Systems,"

"Standard Thermocouple,"

and"Standard TRIGACore"havebeenproposed for removal fromthedefinitions because they refertoequipment orconditions thatare meaningless fora permanently shut

down, defueled facility indecommissioning status.

Thedefinitions havebeenrenumbered appropriately toreflectthechanges proposed bythelicensee.

TS3.0 Reactor Building:

Thisisa new specification that provides ventilation requirements tocontrol possible airborne radioactive materials when decommissioning activities areinprogress.

TS4.0 Reactor Pool:Thisspecification isa revision oftheprevious TS 3.0, "Reactor Pool."Therevised version continues a requirement that the pool benearly full ofwateratalltimesuntil drained aspartofthedecommissioningprocess to provide shielding ofradioactive components.Thespecification also requires high pool waterquality tolimit corrosion ofsubmergedradioactive materials that could promote thespreadofcontamination.

TS5.0 Reactor Fuel:Thisspecification replaces previous TSs4.0,"Reactor Core,"

and6.0,"FuelStorage."

Thisspecification makesexplicit thatfuelpossession or storageisnotauthorized intheTRIGAMarkIfacility.

TS6.0 Control andSafety Systems:Thisspecification describes non-fueled control rodsthatarepermitted toremainintheTRIGAMarkIfacility, andretains the requirements ofprevious specifications 5.2.3(a) and5.2.3(b) formonitors ofarea radiation andairborne radioactive

material, respectively, andcalibration requirements.

Theoperability andoperating requirements ofthesemonitors ischanged tofocus on facility decommissioning activities instead ofreactoroperation.

Requirements for reactorcontrol andsafety systemsareremovedfromtheTSduetothepermanent shutdownandremoval offuelfromthereactor.

- 17 a

TS 7.0 Administrative Requirements:

Thisspecification issimilar totheprevious TS 9.0, "Administrative Controls,"

withthefollowing exceptions:

a) thereare changes to the TStoaccommodate thechangefromanoperating orpossession-only reactortoa decommissioning reactor facility; b)theorganizational chart(Figure 8)is amendedtothat organization givenintheDP;c)changes areproposed toTS 9.3 "Written Procedures,"

todelete procedures forfuelelement andexperiment loading andaddprocedure requirements fordecommissioningactivities andtoaddthe requirement thattheCriticality andRadiation SafetyCommittee approvetemporary changes toprocedures; and d)changes areproposed toTS9.6,"Reporting Requirements" (renumbered as TS7.6),sothatreporting operating reactorrelated information aredeleted, andinformation related totheshutdownreactorbeing decommissioned isaddedtothe TS reporting requirements.

TS8.0 Facility Operations:

A new section isaddedtotheproposedTSsthat emphasizes thattheactivities tobeconducted inthefacility include maintenance, control ofradioactive materials, protection of personnel, assurance ofsecurity, and decommissioning inaccordance withthefacility license andtheapprovedDP.

TSson reactoroperations andexperiments aredeleted intheirentirety because the reactorwill neveroperateagainnorwill experimentsbe conducted.

Thestaff hasreviewed allproposed deletions, additions, andother changes totheTRIGA MarkITSs.Thechangesareconsistent withthechangeinstatus from eitheran operating reactorora nonoperating reactorinpossession-only toa facility in decommissioning status.Therequirements contained intheproposedTSs provide the samelevel ofmanagementcontrols andthesamequalifications fordecommissioning and radiation protection staff aspreviously existed during reactoroperations.

The TSs also includes a requirement tofollow theapproved DPduring decommissioning activities.

Basedontheseconsiderations, thestaff concludes thattheproposed TSsare commensuratewiththechangeinfacility statustodecommissioning andthatcompliance withtheproposed TSsprovides reasonable assurance thatthedecommissioning activities willbeconducted withdueregard toprotecting theenvironment andthehealth andsafety ofworkers, contractors,andthepublic.

Therefore, theproposed TSsfortheTRIGAMark Ireactorareacceptable tothestaff.

TRIGAMarkF.BecausefuelstorageinthecoreoftheTRIGAMarkF reactorandreactor operation arenotauthorized, TSSrelated tothereactor core,reactor safety

systems, reactor operating conditions, experiments andsurveillances related tothesetopics areno longer applicable.

However,fuelstorageinthestoragecanalandmanipulation offuelin thefuel storagecanal,intheTRIGAMarkF reactorpool,andinthereactor roomarenot prohibited andtheTSscontinue toreflect thisfact.Theproposed TSarediscussed and evaluated below.

Coverpageandtable ofcontents Editorial changesweremadetothesesections to reflect other changesmadetotheTSs.

- 18 TS 1.0 Definitions:

Thelicensee hasproposed several newdefinitions related to thedecommissioning statusofthefacility.

A new definition 1 1for"Facility" readsasfollows:

Facility means the building housing thedisassembled reactor plussystems, components,etc.

associated withpossession anddecommissioning ofthe

reactor, including fuel storage.

A new definition 1.2for"Facility Secured" readsasfollows:

Facility secured shall meanthat condition wherenodecommissioning activities orhandling offuel are inprogress inthefacility.

A new definition 1.3for"Facility Operation" reads asfollows:

Facility operation shall meananycondition wherein thefacility isnot secured.

A new definition 1.4for"Decommissioning Activities" reads asfollows:

Decommissioning activities shall meanthoseactivities required toremove thefacility safely fromservice andreduceresidual radioactivity toa level thatpermits therelease ofthefacility tounrestricted useand termination of thelicense.

Theseactivities will involve thehandling, surveying, packaging, anddispositioning ofradioactive materials inthefacility.

A new definition 1.5for"Decommissioning Status" readsasfollows:

Decommissioning statusmeansthatthefacility license hasbeenamendedto withdraw authorization tooperatethereactorandauthorizes possession onlyofthereactor,andthatthefuelhasbeenremovedfromthereactorand ismaintained ina safeandsecuremannerinanapproved location inthe facility.

Thedefinitions of"Facility Secured" and"Facility Operation" replace similar definitions forthereactortoreflect thefactthatthescopeofdecommissioning activities involve notjustthereactorbutthereactorfacility.

Thenewdefinitions of "Facility,"

"Decommissioning Activities" and"Decommissioning Status" helptodefine thescopeoftheTSstodecommissioning andareusedintheTSstodetermine equipment operability requirements.

Thedefinitions alsoaccountforthecontinued storageoffuelintheTRIGAMarkFfuel storagecanal.

- 19 A new definition (TS1.7) for"operating" hasbeenaddedtotheTSsbecause some pieces of equipment mustbeoperating during theconductofdecommissioning activities.

This definition usesthestandard non-power reactor wording ofthe definition. The licensee hasproposed a new definition (TS1.8) of"Abnormal Occurrence"similar tothedefinition intheTRIGAMarkITSstoprovide a basisfor reporting defined events totheNRC.Sucheventsaschangesinreactivity ofthe stored fuelandrelease offissionproducts fromfueled componentsareincluded inthe definition.

Thelicensee has proposed adding definitions for"Measured Value" (TS1.9),"Measuring Channel" (TS1,10),and"Channel Calibration" (TS1 11).

Thesedefinitions matchthose existing intheTRIGAMarkITSsandareusedin connection withsystemssuch as radiation monitoring equipment.

Thesechanges wererequested because ofthechange ofthefacility todecommissioning status.

Definitions for"Reactor Shutdown,""Reactor Secured," "Reactor Operation,"

"Standard Control Rod,""Transient Control Rod,"

"Experiment,"

"Reactor Safety Systems,"

"Experiment Safety Systems"and "Standard Thermocouple" havebeen proposed forremoval fromthedefinitions because theyrefer toequipment or conditions thataremeaningless fora permanently shut down,defueled facility in decommissioning status.

Thedefinitions havebeenrenumbered appropriately toreflect thechangesproposed bythelicensee.

TS3.0 Reactor Building:

Thisspecification hasbeenrevised to address ventilation conditions adequate tomaintain control ofairborne radioactive materials duringfuel storageanddecommissioning instead ofduring reactor operation.

TS4.0 Reactor Pool:Thisspecification hasbeenrevised toaddress the shielding andpoolwaterquality requirements during fuelstorageanddecommissioning instead ofduring reactoroperations.

Thelicensee hasaddeda proposed requirementto analyze thepoolwaterforradioisotope contentona quarterly basis whilefuelisin thepooltodetect fuelcladding failure.

TS5.0 Stored FuelDescription:

ThisTSpreviously addressed theoperable reactor core.Therevised version retains specifications forfuelelements possessed underthe

license, butalsoprohibits storageoffuel elements andfueled control rodsanyplace butthefuel storageareaoftheTRIGAMarkF.Thisproposed TSalsoprohibits fueled componentsfrombeingstored inthereactorportion ofthepool.

- 20 TS 6.0 ControlandSafety Systems:

Thisspecification describes thecontrol

rods, either fueled ornon-fueled thatarepermitted tobestored intheTRIGAMarkF storagecanal, andretains requirements forarearadiation monitors andairborne radioactivity monitors including calibration andoperability requirements.

The operability and operating requirements ofthesemonitors ischanged tofocuson facility decommissioning andfuel storageactivities instead ofreactor operation.

Requirements forreactor control andsafety systemsareremovedfromtheTSdueto thepermanentshutdown andremovaloffuelfromthereactor.

TS7.0 FuelStorage:

This specification hasbeenretained tolimit conditions of fuel storage.However,ithas been revised toinclude conditions ofstorageplacedon fueled control rods,aswellasfuel elements.

TS8.0 Administrative Requirements:

This sectionoftheTSfortheTRIGAMarkF wasmuchlesscomprehensive thanexisted fortheTRIGAMarkI.Thelicensee revised thissection oftheTSstobeconsistent withtheadministrativerequirements section oftheTRIGAMarkITSs.Thismeans that all management controls and requirements, reporting requirements, andretention ofrecords forbothreactor licenses wouldbethesame.Thisshould result inuniformity inadministrative requirements related todecommissioning thetwo reactor facilites.

Thelicensee proposed changes totheTSstoaccommodate the change froman operating orpossession-only reactor toadecommissioning reactor facility withfuelin storage.An organizational chart(Figure 8)identical tothatinthe TRIGA MarkITSs isaddedtotheseTSs.Organizational andCriticality andRadiation Safety Committee requirements betweenthetwo licenses aremadethesame.Changes are proposed in TS8.3,"Written Procedures,"

toclarify requirements forfuel handlingprocedures, addprocedure requirements fordecommissioning activities andaddtherequirement thattheCriticality andRadiation SafetyCommittee approve temporary changes to procedures.

Thelicensee hasproposed adding TS 8.4,"Action tobeTakeninthe EventofanAbnormal Occurrence,"

TS8.5,"Facility Records,"

andTS8.6, "Reporting Requirements."

Thesesections didnotexist intheTRIGAMarkFTSs.

Thesenew TSsaresimilar totherequirements intheTRIGAMarkITSs,withthe exception ofseveral additional requirements toaccountforthestorageoffuelunder theTRIGAMarkFlicense.

TS9.0 Facility Operations:

A new section isaddedtotheproposed TSsthat emphasizes thattheactivities tobeconducted inthefacility include maintenance, control ofradioactive materials, protection ofpersonnel, assurance ofsecurity, safe storageandhandling

offuel, anddecommissioning inaccordance withthefacility license andtheapprovedDP.

- 21

=

TSs on reactor operationsandexperiments aredeleted intheir entirety because the reactor will neveroperateagain norwill experiments beconducted.

Thestaff hasreviewed allproposeddeletions, additions, andother revisions totheTRIGA MarkFTSs.Thechanges areconsistentwiththechangeinstatusfromeither an operating reactorora nonoperating reactorinpossession-only toafacility in decommissioning status with temporary storageofusedfuel.

Therequirements contained intheproposed TSsprovide the samelevel ofmanagementcontrols andthesame qualifications fordecommissioning andradiationprotection staff aspreviously existed during reactoroperation.

TheTSs also includes a requirement tofollow theapproved DP during decommissioning activities.

Based onthese considerations,thestaff concludes thattheproposed TSsarecommensurate withthechangeinfacility statusto decommissioning withfuelstorageand that compliance withtheproposed TSsprovides reasonable assurance thatthedecommissioning andfuelstorageactivities will be conducted withdueregard toprotecting theenvironment andthehealth andsafety of

workers, contractors, andthepublic.

Therefore, the proposed TSsfortheTRIGAMarkF reactorareacceptable tothestaff.

2.17 m In1997,10CFRPart20,Subpart E,"Radiological Criteria for License Termination" becameeffective.

However,10CFR20.1401(b)(3) statesthat the criteria inthissubpart donotapplytosites whichsubmit asufficient decommissioningplan before

August20, 1998,andsuchdecommissioning planisapproved bytheCommission before
August20, 1999,andinaccordance withthecriteria identified intheSDMPAction Plan.

GAfalls underthisfacet oftheregulations.

TheSDMPAction Plancontains cleanup criteria todetermine whethersites have been sufficiently decontaminated sothattheymaybereleased forunrestricted usepursuant to 10CFR50.82.Thecleanup criteria areapplied onasite-specific basis withemphasis on residual contamination levels thatareALARA.Forreactorfacility structures, theSDMP Action Planrefers toRegulatory Guide1.86,"Termination ofOperating Licenses for Nuclear Reactors,"

Table1,forsurface contamination ofreactorfacility structures.

Reactorgenerated, gammaemitting isotopes thatmayexist inconcrete,components,and structures should beremovedsotheexposure rateislessthan5 microroentgen perhour abovenatural background atonemeterfromthesurface ofinterest.

TheDPcontains thesefacility release criteria whichmeettheregulations.

An extensive setofradiation measurementsandanalyses willberequired todemonstrate thattheGATRFhasbeendecontaminated sufficiently tocomplywiththeestablished criteria forlicense termination andrelease forunrestricted future use.TheDPdiscusses in detail themethods,instruments, principles, andguidance documents thatareplanned to beusedinacquiring anddocumenting thisinformation.

Thelicensee hasradiological characterization dataandotheroperating history thatindicate areasandcomponentsof concern, GAhascommitted tousing thebestinstruments reasonably available, andwill employstatistical sampling whenlarge areasofconcern arebeingsurveyed.

Thelicensee isawarethatrelease criteria relate tolocal natural background radiation

levels, so

- 22 appropriate effort isplanned todetermine thoselevels.

Thelicensee will comparethe evaluatedresidual radiation levels withtheaccepted release criteria initsfinal survey reportthat will be submitted toNRCtosupporttermination oflicense.

Thestaff finds the DPdiscussionsof the termination surveyplantobeincompliance withtheregulations and aretherefore acceptable.

3.0 ENVIRONMENTAL CONSlDERATION TheCommission hasprepared an Environmental Assessement andFinding ofNo Significant impact(EA),whichwas published intheFederaj Register onAugust5,1999, (64FR42730),Onthebasis ofthe EA andthissafety evaluation, theCommission has determined thatnoenvironmental impact statement isrequired andthatissuance ofthis amendmentapproving decommissioning will havenosignificant adverse effect orthe quality ofthehumanenvironment.

4.0 CONCLUSION

S Onthebasis ofthereviewandevaluation ofGeneral Atomics' DPandproposedchanges intheir TSs,thestaff concludes thatthelicensee isadequately cognizant ofitscontinuing responsibilities tocomplywithapplicable regulations andto protect theenvironmentand thehealth andsafety ofitsworkers, contractors, andthepublic from undueradiological riskuntil thereactorslicenses areterminated.

TheDPmeetsthe requirements of10CFR 50.82(b)(4) andprovides reasonable assurance thatthelicenseehas the resources to dismantle theTRIGAreactorfacilities, dispose ofthefuelandall the reactor-related radioactive

material, andtomeetcriteria fortermination ofthefacilitylicenses in accordance withapplicable regulations andNRCguidance.
Thestaff, therefore, findsthe licensee's plansandpreparations acceptable.

Thestaff hasconcluded, basedontheconsiderations abovethat:(1)thereisreasonable assurance thatthehealth andsafety ofthepublic will notbeendangered bytheproposed activities; (2)suchactivities will beconducted incompliance withtheCommission's regulations; and(3)theissuance ofthisamendmentwill notbeinimical tothecommon defense andsecurity orthehealth andsafety ofthepublic.

Principal Contributors:

R.E.Carter, INEEL A.Adams,Jr.,NRC Date:August12, 1999

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