ML21246A257
| ML21246A257 | |
| Person / Time | |
|---|---|
| Site: | General Atomics |
| Issue date: | 08/12/1999 |
| From: | Alexander Adams Office of Nuclear Reactor Regulation |
| To: | Asmussen K General Atomics |
| Marlayna Doell, 301-415-3178 | |
| Shared Package | |
| ML21246A250 | List: |
| References | |
| TAC M98498, TAC M98499 | |
| Download: ML21246A257 (24) | |
Text
summarasaromes
- 1. NRCApprova Letter orte TRIGA Decommissioning Pan, ate August 12,199
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NUCLEAR REGULATORY WASHINGTON, D.C.
COMMISSION 205550001 o # August12, 1999 Dr.Keith E. Asmussen, Director Licensing,Safety andNuclear Compliance GeneralAtomics P.O.Box85608 SanDiego, California 92186-9784
SUBJECT:
ISSUANCEOF AMENDMENT NO.36TOAMENDED FAClLITY LICENSE NO.R-38AND AMENDMENT NO.45 TO FACILITY LICENSE NO.R-67 -
GENERAL ATOMICS (TAC NOS.M98498AND M98499)
DearDr.Asmussen:
TheCommission hasissued theenclosed Amendment No.36 to AmendedFacility License No.R-38for theGeneral Atomics TRIGAMark IResearch Reactor andAmendmentNo.45 to FacilityLicense No.R-67for theGeneral Atomics TRIGA MarkF Research Reactor. The amendment consists ofchanges tothefacility license andtechnicalspecifications (TSs) in response toyour application ofApril18,1997, as supplemented on November 20,1998, andJanuary 28and29,February 3,April 22,May 3 and 12,andJune15 (applicable to MarkIonly), 16(applicable toMarkF only) and22,1999.
Theamendment approves thedecommissioning plan for theGeneral Atomics TRIGA MarkIandTRIGAMarkF Research Reactors. Theamendmentalso authorizes the approved decommissioning planto beincluded asa supplement tothe Safety Analysis Report pursuant to 10 CFR50.82(b)(5).
A copyofthesafety evaluation supporting AmendmentNos.36and45 isalso enclosed.
Sincerely, t2#'d ,
Alexander Adams,Jr., SenirP oject Manager EventsAssessment, Generic Communications and Non-Power Reactors Branch DivisionofRegulatory Improvement Programs OfficeofNuclear Reactor Regulation Docket Nos.50-89and 50-163
Enclosures:
- 1. Amendment Nos.36and45
- 2. Safety Evaluation ccw/enclosures: Seenextpage
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General Atomics Nos.50-89/163 Docket cc:
Mr.Steve Hsu Radiologic Health Branch State Department ofHealth Service P.O Box942732 Sacramento, CA 94234-7320 Mr.B.M. Murray Vallecitos NuclearCenter General ElectricCompany 6705Vallecitos Road Sunol, CA 94586
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R j NUCLEAR REGULATORY COMMISSION WASHANGTON, D.C.205554001
% 5 GENERAL ATOMICS DOCKETNO.50-89 AMENDMENT TO AMENDED FACILITY LICENSE AmendmentNo.36 License No.R-38 1 TheU.S.Nuclear Regulatory Commission (theCommission) hasfoundthat A. Theapplication foran amendment toAmended FacilityLicense No.R-38filed by GeneralAtomics (the licensee)on April18, 1997, as supplemented on November 20,1998,andJanuary 28 and29, February 3,April 22,May 3 and 12,andJune15and22,1999,conforms to the standards andrequirements of theAtomic Energy Actof1954,asamended (the Act), andtheregulations of theCommission asstated inChapter IofTitle 10 of the Code ofFederal Regulations (10CFR),
B. Thefacility willbedecommissioned inconformity withthe application, the provisionsoftheAct,andtherules andregulations oftheCommission; C. There isreasonable assurance that(i) theactivities authorized bythis amendment canbeconducted withoutendangering thehealth andsafety ofthepublic and(ii) suchactivitieswill beconducted incompliance withtheregulations ofthe Commission; D. Theissuance ofthis amendment notbeinimical will tothecommon defense and securityorto thehealth andsafety ofthepublic; E. This amendment isissuedinaccordance with theregulations oftheCommission as statedin10 CFRPart 51,andall applicable requirements havebeensatisfied; and F. Prior noticeofthis amendment was notrequired by 10CFR2.105,and publicationofnotice forthis amendment isnotrequired by 10CFR2.106.
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- 2. Accordingly, thelicense isamended bychanges tothefollowing paragraphs which are hereby amended to read asfollows:
1.C.The facility will bedecommissioned inconformity with theapplication as amended, theprovisions oftheAct,andtherules andregulations ofthe Commission; 1.D.There isreasonable assurance that thereactor facilitycanbedecommissioned (i) without endangering thehealth andsafety ofthepublic and(ii) incompliance withtheregulations in thischapter; 1.E.General Atomics istechnically andfinanciallyqualified todecommission the facility inaccordance with the regulations inthis chapter;
- 3. Accordingly, thelicense isamendedby deleting paragraph2.B.(2) inits entirety.
- 4. Accordingly, thelicense isamended toapprove thedecommissioning plan described inthelicensee's application dated April 18,1997 assupplemented
, on November 20, 1998,andJanuary 28and FebruaryApril 29, 3, 22, May 3 and andJune15and 12, 22,1999,andauthorizes inclusion ofthedecommissioning plan asa supplement to theSafety Analysis Report pursuant to 10CFR50.82(b)(5). thelicense Also, is amended bychanges totheTechnical Specifications asindicated intheenclosure to this license amendment, andparagraph 2.C.(2) ofAmended Facility License No.R-38 ishereby amended to read asfollows:
(2)M TheTechnical Specifications contained inAppendix A, asrevisedthrough Amendment No. 36, are hereby incorporated in thelicense. Thelicensee shall decommission thefacility inaccordance withtheTechnical Specifications.
- 5. Thislicense amendment iseffective asofthedate ofissuance.
FORTHENUCLEAR REGULATORY COMMISSION
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Ledyard B.Marsh, Chief Events Assessment, Generic Communications and Non-Power Reactors Branch Division ofRegulatory Improvement Programs Office ofNuclear Reactor Regulation
Enclosure:
Appendix A, Technical Specifications Changes DateofIssuance: Augus t 12, 1999
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ENCLOSURE TO LICENSE AMENDMENT NO.36 AMENDED FACILITYLICENSE NO.R-38 DOCKET NO.50-89 thefollowing- pages ofAppendix Replace Specifications,"
A, "Technical withtheenclosed Therevisedpages areidentified byamendment pages. number.
Remove Insert coverpage cover page tableofcontents i 1 23 1 -8
, , t t TRIGAReactors Facility :
Facility License No.R-38 AUGUST12, 1999
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TABLE OFCONTENTS PageNo.
1.0 Definitions..........,..........................,................................. 1 2.0 Site ....................................................................................... 2 3.0 Reactor Building..................................................................... 2 4.0 Reactor Pool......................................................................... 2 5.-0 Reactor Fuel.-................................................................. 3 6.0 Control andSafety Systems ................................ 3 6.1Control Systems .........................,.......................,.. 3 6.2Safety Systems ............................................................,.,,. 3 7.0 Administrative Requirements..................................................... 3 7.1Organization .................................................................. 3 7.2Criticality andRadiation Safety Committee ................................ 4 7.3Written Procedures ............................................... 5 7.4Action tobeTaken intheEvent ofa Reportable Occurrence .... 6 7.5Facility Records -......................................................... 6 7.6Reporting Requirements ........................................................ 7 8.0 F~acility Operations..................................................................,..... 8 i
Amendment No.36
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APPENDIX A License No.R-38 TECHNICAL SPECIFICATIONS FOR THE TORREY PINES TRIGA MARK IREACTOR DATE:JANUARY 21,1972 1.0 DEFINITIONS 1.1Facility Facility meansthebuilding housing thedisassembled reactor plussystems, components,etc.
associated with possession anddecommissioning ofthereactor.
Secured 1.2Facility Facility secured shallmeanthat condition where nodecommissioning activities arein inthefacility.
progress 1.3h Facility shall operation meananycondition whereinthe facility isnotsecured.
1.4W activities Decommissioning shall meanthose activitiesrequired to remove the facility from safely andreduce service residual radioactivity toa level that permits the ofthefacility release tounrestricted useandtermination ofthelicense. These activities will thehandling, involve surveying, packaging, anddispositioning of radioactive inthe materials facility.
1.5W Decommissioning statusmeansthat the facilitylicense hasbeenamended to authorization withdraw tooperate thereactor andauthorizes possession onlyofthe andthat reactor, thefuelhasbeenremoved from thereactor andismaintained ina safeandsecuremanner inanapproved location outside the Mark Ifacility.
1.6 Operat A systemordevice shallbeconsidered operable whenit iscapable ofperforming its functions intended ina normal manner.
1.7 Operating meansa component Operating orsystem isperforming its intended function.
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1.8 Abnormal Occurrence Anabnormal occurrence isanobserved inadequacy inthe implementation ofeither administrative orprocedural controls, such thatthe inadequacy caused, or- could have caused,the existence ordevelopment ofa condition which resulted, orcould
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have resulted, in afacility conditionoutside the requirements ofthe Technical Specifications.
1.9 Measured Value Themeasured value isthe magnitude ofthat variable asit appears ontheoutput ofa measuring channel.
1.10Measuring Channel A measuring channel isthe combination ofsensor, interconnecting cables orlines, amplifiers, andoutput device which is connectedfor thepurpose ofmeasuring the value ofa variable.
1.11Channel Calibration A channel calibration consists ofcomparing a measured value from themeasuring channel with a corresponding known value of theparameter sothat the measuring channel output canbeadjusted torespond, with acceptable accuracy, toknown values ofthemeasured variable.
2.0SE A minimum radius of120feet from theapproximate center ofthe TRIGA ReactorFacility buildingshall define the exclusion area.
3.0REACTOR BUILDING Until such time asall decommissioning activitieshave been completed inthe facility, the followingventilation requirements shallapply:
3.1 Controls for the ventilating system shall belocated inthe facility.
3.2 Thereactor roomventilation shallbeseparate from the rest ofthe building ventilation.
3.3 During decommissioning tenting activities, oranequivalent confinement barrier shall beplaced around the work areaandanassociated airventilationHEPAsystem shall beoperating toensure the work area ismaintained ata negative pressure with respect tothe surrounding areas andtheexhaust pathway tothe environment is controlled andmonitored.
4.0REACTOR POOL 4.1 Until drained asa part ofdecommissioning, the minimum levelofthe pool water shall be12inches below thereference point atthe topofthepool. Thereference point is marked onastraight edgeaffixed tothe liner atthe top ofthe pool. This point is located 9 1/2 inches from the top flange ofthepool liner.
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4.2 Until such time asthe poolwater isdrained asa partofdecommissioning, thepool water shall besampled conductivity for atleastweekly. Theconductivity ofthe coolant shall not exceed 5 micro-mhos percentimeter averaged over anyone calendar month.
5.0REACTOR FUEL Noreactor fuel elements orcontrol elements with fuelfollowers shall belocated in, stored in, ormoved into,the reactor corestructure orreactor facility.
6.0CONTROL ANDSAFETYSYSTEMS 6.1 Controj.Systems, Thepoison section ofthecontrol rods whichmayremain inthefacility contains borated graphite orstainless steel, B4C powder or boron or its compounds insolid form, cadmium, ortherare earthpoisons insolid formclad withthematerials authorized for fuel-element cladding.The control rods maycontain flux traps and maybeequipped with non-fuel followers.
6.2 Safety Systen)s Until suchtime asdecommissioning arecompleted activities inthefacility, radiation monitoring systems shall beoperating asfollows:
- a. Anarea radiation monitoring system capableofactivating anevacuation alarm.
- b. Whenthe facility isnotsecured, a continuous monitoring system for airborne activityhaving a readout andaudible alarmwhich canbeheard inthefacility.
These systems shall becalibrated annually andtheirsetpoints verified monthly. For periods oftime for maintenance orrepair tothe above systems, orduring periods of other forced outages, theintent ofthis specificationshall besatisfied ifthe installed system(s) isreplaced with appropriate alternate orportable radiation monitoring system(s)..
Following maintenance or modification of theradiation monitoring systems, the affected systemshall be verified tobe operable before returning ittoroutine operation.
7.0 ADMINISTRATIVE REQUIREMENTS 7.1 Organization Thefacility shall beunder the supervision ofthePhysicist-in-Charge orhis designated alternate, both ofwhom shall belicensed senior operators ofthe facility.
Theminimum qualification for the shall Physicist-in-Charge include a Bachelor's degree orequivalent academic education andthree years experience inactivities related toreactor operations. Heshall beresponsible toaVice President whose duties include responsibility for research anddevelopment, orhis designated 3
Amendment No.36
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alternate, for safe possession ofthe reactor andits associated equipment andfor limiting exposure of personnel anddispersal ofradioactive material. Thereactor shall berelatedtothe Corporate structure asshown inthe following chart:
VicePreskient nesearchanevelopmeni via'P'Saklant l
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- Direct Reporting FacAny Functional Support/Oversight 7.2 M
- a. There shall bea Criticality andRadiation Safety Committee (CRSC). TheCRSC ora subcommittee thereof shall review activities ofthe facility toassure criticality andradiation safety. This Committee shall becomposed ofatleast four members selected bytheCognizant Vice President, ora designee, considering their experience andeducation with regard tothe various aspects ofnuclear physics, chemistry, radiological health andstatistics, aswell as appropriate experience inother disciplines such asmetallurgy andengineering.
Subcommittees shall beappointed bytheChairman ofthe CRSC.The subcommittee assigned theresponsibility for reviewing facility operations shall nothavethereon person(s) whoaredirectly involved with the facility.
- b. TheCriticality andRadiation Safety Committee shall beinaccordance with a written charter including provisions for:
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1 Holding meetings oraudits atleast annually; special meetings maybecalled bysubcommittees ofthe CRSC orbythe Chairman ofthe CRSCattimes whensuch meetings aredeemed appropriate.
2.Having a quorum whena majority ofthe members attend.
- 3. Preparing minutes oraudit findings ofthe CRSCmeetings bythe Chairman or hisdesignee. Evidence ofapproval ofthe participating members ofthe CRSC shallbeobtained before distribution.
- c. TheCriticality andRadiation Safety Committee, orsubcommittee, shallreview andapprove safety standardsassociated withpossession oftheFacility. The CRSCora subcommittee thereof shall audit theFacility annually, butatintervals nottoexceedfifteen (15) months.
- d. Theresponsibilitiesof the Committee ordesignated subcommittee thereof include, but arenot limited to, the following:
- 1. Review andapproval ofall proposed changes tothe facility, procedures, andTechnical Specifications;
- 2. Determination ofwhether a proposed change, test, orexperiment would constitute anunreviewed safety question ora change inthe Technical Specifications;
- 3. Review ofFacility records;
- 4. Review ofabnormal performance ofplant equipment andother anomalies; and
- 5. Review ofunusual orabnormal occurrences andincidents which are Reportable Occurrences under 10CFR20and10CFR50.
7.3 Written Procedures instructions Written shallbeineffect for the following items. Theinstructions shall beadequate toassure the safe possession ofthereactor butshall notpreclude the useofindependent judgment andaction should thesituation require such:
- a. Testing andcalibration ofinstrumentation, controls,radiation monitors and radiation protectionsystems necessary tomeetthe requirements ofthe Technical Specifications.
- b. Emergency andabnormal conditions including provisions for evacuation, reentry,recovery, andmedical support.
- c. Maintenance ofsystems necessary for maintaining thereactor inaccordance withthelicense.
- d. Actions tobetaken tocorrect specific andforeseen potential malfunctions of systems orcomponents, including responses toalarms andabnormal changes.
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- e. Decommissioning activities (consistent with anapproved Decommissioning Plan).
Changes which alter the original intentofthe above procedures shallbemadeonly with the approval oftheCriticality andRadiation Safety Committee (CRSC).
Temporary changes tothe procedures that donot change their original anddo intent notconstitute an unreviewed madeby the Physicist-in-Charge.
safety All question such (as temporary defined in10CFR50.59) changes shall maybe bedocumented and subsequently reviewed andapproved bytheCRSC.
7.4 Action tobeTaken inthe Event ofanAbnormal Occurrence Inthe event ofanabnormal occurrence, asdefined inSection 1.8 ofthe Specifications, thefollowing action shall betaken:
- a. ThePhysicist-in-Charge or designated alternate shall benotified andcorrective action taken with respect to the operation involved.
- b. ThePhysicist-in-Charge orother person notified under Section 7.4a shallnotify theChairman oftheCRSCandthe Vice President, orhis designated alternate, identified inSection 7.1
- c. A report shallbemadetothe CRSCwhich shall includeananalysis ofthe cause oftheoccurrence, efficacy ofcorrective action, andrecommendations formeasures toprevent orreduce theprobability ofrecurrence.
- d. A report shallbemadetotheNRCinaccordance with Section 7.6ofthese Specifications.
7.5 FacilityRecords Inaddition tothe requirements ofapplicable regulations, andinnoway substituting therefore, records andlogs shall beprepared ofatleast thefollowing items and retained for a period ofatleast five (5)years:
- a. Normal reactor operation andfacility status;
- b. Principal maintenance activities;
- c. Abnormal orreportable occurrences;
- d. Equipment andcomponent surveillance activities required bythe Technical Specifications;
- e. Gaseous andliquid radioactive effluents released totheenvirons;
- f. Off-site environmental monitoring surveys;
- g. Fuel inventories andtransfers;
- h. Facility radiation andcontamination surveys; 6
Amendment No.
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I. Experiments performed with the reactor orinsupport ofdecommissioning; j . Radiation exposures forall personnel;
- k. Updated, corrected, andas-built drawings ofthe facility (these shall beretained forthe lifetime ofthe facility).
I. Decommissioning/dismantlement activities.
7.6 W Inaddition tothe requirements ofapplicable regulations, andinnowaysubstituting therefor, reports shall bemade tothe NRCasfollows:
- a. A report 24hours bytelephone orfacsimile within tothe NRCOperations Center:
1.Anyaccidental release of radioactivity above permissible limits in unrestricted areas, whether or not therelease resulted in property damage, personal injury, orexposure;
- 2. Anyabnormal occurrences asdefined inSection1.8 ofthese Specifications.
- b. A report within10days inwriting tothe Document Control Desk, USNRC ,
Washington, D.C. 20555:
- 1. Anyaccidental release ofradioactivity above permissible limits in unrestricted areas, whether ornottherelease resulted inproperty damage, personal injury,orexposure; the written report (and, to theextent possible, the preliminary telephone orfacsimile report) shall describe, analyze andevaluate safety implications, andoutline the corrective measures taken orplanned toprevent reoccurrence ofthe event.
- 2. Anyabnormal occurrence asdefined inSection 1.8 ofthese Specifications.
- c. A report within30days inwriting tothe Document Control Desk, USNRC ,
Washington, D.C. 20555:
1 Anysignificant changes infacility organization orpersonnel for which minimum qualifications arespecified inthese specifications.
- d. Commencing in2000, a routine report inwriting tothe Document Control Desk, U.S. Nuclear Regulatory Commission byApril 15ofeach year, providing the following information:
- 1. A brief narrative summary of: (1) actions taken for decommissioning of the facility, (2) current facility status, (3) any changes tothe decommissioning schedule, and(4) a summary ofradioactive material shipments.
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- 2. Discussion ofthe major maintenance operations performed the during period, including the e ffects, ifa ny, on the s afepossession ofthe reactor, andthe reasons for anycorrective maintenance required.
- 3. A summary ofeach change, if such changes have beenmade, tothe facility,orprocedures, andexperiments tests, carried outunder the conditions of Section 50.59 ofCFRPart 50.
- 4. A summary ofthe nature andamount ofradioactive effluents released or discharged tothe environs beyond theeffective ofthe control licensee asmeasured atorprior tothe point ofsuch releaseor discharge.
- 5. A description of any environmental surveys performed the outside facility.
- 6. A summary ofradiation exposures received byfacility personnel and visitors, including thedates andtime ofsignificant exposure, anda brief summary ofthe resultsof radiation andcontaminationsurveys performed within the facility.
OPERATIONS 8.0 FACILITY activities Thefollowing shallbeconducted inthe facility:
a)and Maintenance, security monitoring, activities control asdefined ofradioactive inapproved material, protection procedures (seeSection ofpersonnel, 7.3).
b) Decommissioning inaccordance with the facility license andconsistent with an Decommissioning approved Plan.
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pt,AB REG
/ % UNITEDSTATES
- B NUCLEARREGULATORY COMMISSION
/ WASHINGTON,D.C.20555-0001
'+4; # July29, 1999 Dr.KeithE. Asmussen, Director Licensing, Safety andNuclearCompliance General Atomics P.O.Box85608 SanDiego, California 92186-9784
SUBJECT:
ENVIRONMENTAL ASSESSMENT RELATED TOISSUANCE OFAMENDMENT NO.36TOAMENDED FACILITY LICENSE NO.R-38ANDAMENDMENT NO.45 TO FACILITY LICENSE NO.R-67 GENERAL ATOMICS (TAC NOS.M98498 AND M98499)
DearDr.Asmussen:
Enclosedisa copyoftheEnvironmental Assessment andFinding ofNo Significant Impact related toyourapplication for amendment toAmended FacilityLicense No.R-38for the GeneralAtomics TRIGAMarkIResearch Reactorand Facility License No.R-67forthe GeneralAtomics MarkF Research Reactor dated April 18, 1997, assupplementedon November 20,1998,andJanuary 28and29,February 3, April 22,May 3 and12,and June15,16,and22,1999 Theproposed amendment would approve the decommissioning plan fortheGeneral Atomics TRIGAMarkI and Mark F Research Reactors.
Theassessment isbeing forwarded totheOffice oftheFederal Register forpublication.
Sincerely,
- wd Alexander Adams,Jr., S ni Project Manager Events Assessment, Generic Communications and Non-Power Reactors Branch Division ofRegulatory improvement Programs Office ofNuclear Reactor Regulation DocketNos.50-89 and 50-163
Enclosure:
Environmental Assessment ccw/enclosure:
Seenextpage RECElVED AUG031999 UCENSING
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General Atomics Nos.50-89/163 Docket cc:
Mr.Steve Hsu Radiologic Health Branch State Department ofHealth Service P.O. Box942732 Sacramento, CA 94234-7320 Mr.B.M. Murray Vallecitos Nuclear Center General Company Electric 6705Vallecitos Road Sunol, CA 94586
7590-01-P UNITED STATESNUCLEAR REGULATORY COMMISSION GENERAL ATOMICS DOCKET NOS.50-89 AND 50-163 GENERAL ATOMICS TRIGA MARKIAND MARKF RESEARCH REACTORS ENVIRONMENTAL ASSESSMENT AND FINDING OFNOSIGNIFICANT IMPACT TheU.S.Nuclear Regulatory Commission (the Commission) isconsidering issuance amendment ofa license to Amended Facility License No.R-38andFacility License toGeneral No.R-67,issued Atomics (GAorthelicensee), fordecommissioning oftheGA TRIGAMarkIandTRIGAMarkF Research Reactors, located at General Atomics inSan SanDiego Diego, county, California.
ENVIRONMENTAL ASSESSMENT W:
Theproposed action wouldapprove thelicensee's decommissioning plan. GA submitted decommissioning their plan inaccordance with10CFR50.82(b) for theGA TRIGAMarkIandTRIGAMarkF Research Reactors which occupypartsoftheTRIGA Reactor within Facility GA'sTorrey Mesasite. TheTRIGAMarkIlicense wasamended on October29,1997,andtheTRIGAMarkF license was amended on March22,1995,to removeauthority tooperatethereactors. Fuel fromboth reactors havebeenplaced inthe TRIGAMarkF fuelstorage canal whichisinthesamepool astheTRIGAMarkF reactor.
Theproposeddecommissioning planwouldauthorize immediate dismantlement ofthe TRIGAMarkIResearch Reactor. To protect thestored fuel frompotential damagedueto
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decommissioning activities, only limited dismantlement oftheTRIGAMarkF Research Reactor will occur withfuel intheTRIGAMarkF fuel storage canal. Thiswouldbe followed by a period offuelstorage. After fuel isremoved'from theTRIGAMarkF fuel storage canal, dismantling becompleted will ontheTRIGAMarkF Research Reactor. The soonest that theDepartment of Energy canacceptfuel fromGA is2003.Domestic spent nuclear fuel receipts attheIdaho National Engineering andEnvironmental Laboratory have beenseverely constrained because of a settlement agreement ofa lawsuit concerning spentnuclear fuel andnuclear waste.The site willbedecontaminated to meet unrestricted release criteria. After theCommission verifies thattherelease criteria have beenmet, thereactor licensewillbeterminated.
Thelicensee will continue with their health physics program, andapproved emergency andsecurity planduring thedecommissioning andtheir operator requalification plan until fuel isremoved fromthefacility.
A "Notice ofApplication forDecommissioning Amendment" was published inthe FEDERAL REGISTER on December 11,1997(62 FR65288), inaccordance with the requirements of10CFR50.82(b)(5).
Theproposed action isinaccordance with thelicensee's application for amendment dated April 18,1997,assupplemented on November 20,1998,andJanuary 28and29, February 3,April 22,May 3 and12,andJune15,16,and22,1999.
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Theproposed action isneeded because ofGA'sdecision to cease reactor operations permanently attheTorrey Mesasite. As specified in10CFR50.82, any licensee may apply totheNRCfor authority to surrender a license voluntarily andto
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decommission theaffected facility. Oncethelicensee permanently ceases operation, 10CFR50.82(b)(1) requires thelicensee tomakeapplication forlicense termination within two years following permanent cessation ofoperations, andinnocaselater thanoneyear priortoexpiration ofthe operating license. GA isplanning to usethearea that wouldbe released forunrestricted use for other purposes.
TheCommission hascompleted its evaluation oftheproposed action and concludes that theradiological effectsofdecommissioning theTRIGAMarkIandMarkF Research Reactors will beminimal Thelicensee will continue withtheir health physics program, andapproved emergency andsecurity plans. Until fuel isremoved fromthesite, thelicensee will alsocontinue tomeet therequirements of their operator requalification plan.
All proposed operations inconnection withdecommissioningand decontaminating oftheGA reactors will becarefully planned andcontrolled, all contaminated components will beremoved, packaged, andshipped offsite inaccordance with theregulations, and radiological control procedures willbeinplace andimplemented toensure that releases of radioactive wastesfrom thefacility arewithin thelimits of10CFRPart 20 andareaslow asreasonably achievable (ALARA).
AII decontamination will beperformed bytrained personnel inaccordance with previously reviewed procedures andwill beoverseen byexperienced health physics staff.
No new postulated accidents havebeenidentified during decommissioning activities or storage ofthereactor fuel that would havegreater radiological impact thanpreviously evaluated accidents. TheGA staff hascalculated that thetotal doseto workers for the
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decommissioning project will beabout 20 person-rem over theperiod 1999to 2004 (assumingfuel isremoved fromthefacility in2003). TheGA staff estimates that the doseto members of thepublic fromdecommissioning activities will benegligible. These doses areconsistentwith those given inNUREG-0586,"Final Generic Environmental Impact Statement on Decommissioning ofNuclear Facilities," for thereference research reactor.
While onsite, fuel will bestored inapproved storage locations under the restrictions ofthefacility license. Thelicense will continue to maintain systemsnecessary forsafe storage ofthefuel.
Theproposed action willnotincrease theprobability orconsequences ofaccidents, no changes arebeing madeinthetypesofanyeffluentsthat may bereleased offsite, and there isno significant increase inoccupational orpublic radiation exposure. Therefore, there areno significant radiological environmental impacts associated with theproposed action. .... .
Withregard to potential non-radiological impacts, theproposed action does not involve anyhistoric sites. Hazardous materials suchasleadand asbestos will behandled anddisposed ofinaccordance with all applicable regulations and,therefore, will notresult
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inanysignificant release ofnon-radiological plant effluents andhasno other environmental impact. Therefore, there areno significant non-radiological environmental impacts associated with theproposed action.
Accordingly, theCommission concludes that there areno significant environmental impacts associated withtheproposed action.
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The alternatives totheproposed action for theGATRIGAresearch reactors are SAFSTOR,ENTOMB and no action. ENTOMB isthealternative inwhichradioactive contaminates areencased ina structurally long-lived material, suchasconcrete, the entombedstructure isappropriately maintained andcontinued surveillance iscarried out until theradioactivity decays to a level permitting releaseoftheproperty forunrestricted use.SAFSTOR isthealternative inwhich thefacility isplaced andmaintained ina condition that allows thefacility to besafely stored andsubsequently decontaminated to levels thatpermit release forunrestricted use.
TheENTOMBalterative could notbe putintoplace untilthefuel was removed from andwouldrequire thefacility thefacility to remain on sitefor an extended period oftime.
theSAFSTOR Likewise, alternative wouldrequire continued surveillance for an extended oftime.
period However,GA wantsto usethespace that will become available for other andwantstoenterinto purposes thedecommissioning activities assoort as possible. The ofnotdecommissioning alternative reactors wasreject.ed inNUREG-0586. The no action alternative wouldleave thefacility..in..its present configuration. Denial oftheapplication wouldresultinnosignificant change incurrent environmental impacts.
Theenvironmental impacts oftheproposed actionandthealternative actions are similar.
UseofResources:
Alternative Theaction doesnotinvolve theuseofresources different frompreviously committedforconstruction andoperation oftheGA TRIGAreactors.
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Inaccordance withits stated policy, onJuly 20,1999,thestaff consulted with the ofCalifornia State official, R.LupooftheRadiologic Health Branch oftheCalifornia Department ofHealthServices regarding theenvironmental impact oftheproposed action.
Thestateofficial hadno comments.
FINDING OFNOSIGNIFICANT IMPACT Onthebasis oftheenvironmental assessment, theCommission concludes that the proposedaction will nothavea significanteffect on thequality ofthehuman environment. Accordingly, theCommission hasdetermined notto prepare an environmental impact statement for theproposed action.
Forfurther details with respect tothis proposed action, see thelicensee's letter April dated 18,1997,assupplemented byletter dated November 20, 1998, and January28and29,February 3,April 22,May 3 and12,andJune 15, 16, and22,1999.
Thesedocuments areavailable for public inspection atthe..Commission's.Public Document Room,theGelman Building, 2120L Street, NW.,Washington, D.C. 20003-1527.
Dated atRockville, Maryland, this29th-day of July1999.
FORTHENUCLEAR REGULATORY COMMISSION Ledyard B.Marsh, Chief Events Assessment, Generic Communications and Non-Power Reactors Branch Division ofRegulatory Improvement Programs Office ofNuclear Reactor Regulation