ML17263A641

Application for Amend to License DPR-18,revising TS Administrative Controls Section 6.0 Consistent W/Improved TS

ML17263A641
Person / Time
Site:	Ginna
Issue date:	05/13/1994
From:	MECREDY R C ROCHESTER GAS & ELECTRIC CORP.
To:
Shared Package
ML17263A642	List: ML17263A641 ML17263A643 ML17309A543
References
NUDOCS 9405170066
Download: ML17263A641 (36)

Text

UNITEDSTATESOFAMERICANUCLEARREGULATORY COMMISSION IntheMatterof))Rochester GasandElectricCorporation

)(R.E.GinnaNuclearPowerPlant))DocketNo.50-244APPLICATION FORAMENDMENT TOOPERATING LICENSEANDUALITYASSURANCE PROGRAMPursuanttoSection50.90oftheregulations oftheU.S.NuclearRegulatory Commission (NRC),Rochester GasandElectricCorporation (RGEE),holderofFacilityOperating LicenseNo.DPR-18,herebyrequeststhattheTechnical Specifications setforthinAppendixAtothatlicensebeamended.ThisrequestforchangeinTechnical Specifications istorevisetheAdministrative Controlsesectionconsistent withImprovedTechnical Specifications.

Severalrequirements arealsorelocated tootherprogramsanddocuments inaccordance withthecriteriacontained intheNRCFinalPolicyStatement onTechnical Specifications Improvements forNuclearPowerReactors.

Adescription oftheamendment request,necessary background information, justification oftherequested change,safetyevaluation andnosignificant hazardsandenvironmental considerations areprovidedinAttachment A.Thisevaluation demonstrates thattheproposedchangesdonotinvolveasignificant changeinthetypesorasignificant increaseintheamountsofeffluents oranychangeintheauthorized powerlevelofthefacility.

Theproposedchangesalsodonotinvolveasignificant hazardsconsideration.

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AmarkedupcopyofthecurrentGinnaStationTechnical Specifications whichshowtherequested changesissetforthinAttachment B.TheproposedrevisedTechnical Specifications areprovidedinAttachment C.AmarkedupcopyofStandardTechnical Specifications isprovidedinAttachment Dwhichshowsallapplicable changes.WHEREFORE, Applicant respectfully requeststhatAppendixAtoFacilityOperating LicenseNo.DPR-18beamendedintheformattachedheretoasAttachment C.Rochester GasandElectricCorporation ByRbertC.HecredyVicePresident NuclearProduction Subscribed andsworntobeforemeonthis13thdayofHay1994.NotaryPublic

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Attachment AR.E.GinnaNuclearPowerPlantLicenseAmendment RequestUpgradeofAdministrative ControlsTechnical Specification

6.0 Thisattachment

providesadescription oftheamendment requestandnecessary justification fortheproposedchanges.Theattachment isdividedintosevensectionsasfollows.SectionAidentifies allchangestothecurrentGinnaStationTechnical Specifications whileSectionBprovidesthebackground andhistoryassociated withthechangesbeingrequested.

SectionCprovidesdetailedjustification fortheproposedchangesincluding acomparison toImprovedTechnical Specifications asapplicable.

Asafetyevaluation, significant hazardsconsideration evaluation, andenvironmental consideration oftherequested changesareprovidedinSectionsD,E,andF,respectively.

SectionGlistsallreferences usedinthisattachment.'.

DESCRIPTION OFAMENDMENT REQUESTThisLicenseAmendment Request(LAR)proposestoreviseGinnaStationTechnical Specification (TS)6.0assummarized below.Attachment BcontainsamarkedupcopyofthecurrentGinnaStationTechnical Specifications showingtherequested changes.TheTechnical Specifications following theproposedchangesisprovidedinAttachment C.Notethatformatissuesandminorwordingchangesareexcludedfromthediscussion below:2.3.5.Technical Specification TableofContentsi.Revisedtosupportproposedchanges.Technical Specification 3.1.4.3.ai.Deletedspecialreportrelatedtoexceeding I-131equivalent activitylimits.Technical Specification 3.5.5.3Deleted"Semiannual" fromthenameoftheRadioactive EffluentReleaseReport.Technical Specification 3.6Revisedbasestoreplacereference toTS6.8withtheQualityAssurance Program.Technical Specification 3.15.1.3i.Revisedreference tospecialreporttechnical specification section.

Technical Specification 3.16.1TS3.16.1.3isrevisedtoreplacereferences toTable6.9.2withtheOffsiteDoseCalculation Hanual(ODCH).TS3.16.1.4isrevisedtodelete"Semiannual" andadd"Release" tothenameoftheRadioactive EffluentReleaseReport.Technical Specification 6.1TS6.1.1isrevisedtoincludeastatement thatthePlantHanagershallapproveeachproposedtest,experiment ormodification tostructures, systemsorcomponents thataffectnuclearsafety.Addedanewrequirement (TS6.1.2)whichoutlinestheShiftSupervisor's (SS)responsibilities andwhocanbedesignated toassumethecontrolroomcommandfunctionwhentheSSisabsent.Technical Specification 6.2TS6.2.l.aisrevisedtoincludearequirement forfunctional descriptions

'fdepartmental responsibilities andrelationships andjobdescriptions ofkeypersonnel positions.

TS6.2.1.b,6.2.1.c,6.2.2.a,6.2.2.b,6.2.2.c,6.2.2.d,6.2.2.fandTable6.2-1aredeleted.V.Vl.TS6.2.2.aisreplacedwithastatement definingwhennon-licensedoperators arerequiredtobeassignedtotheshiftcrew.Thisrequirement currently existsinTable6.2-1.TS6.2.2.bisreplacedwithastatement definingtheconditions anddurations thatoperating shiftcrewcompositions maybelessthanthatspecified in10CFR50.54(k),

(l),and(m),andintheTechnical Specifications.

Thisstatement currently existsinTable6.2-1.TS6.2.2.eisrenumbered andrevisedtoallowtheindividual qualified inradiation protection procedures tobeabsentfornotmorethan2hours.TS6.2.2.gisrenumbered andrevisedtoreference aNRCapprovedprogramforcontrolling overtime.

viii.Addedanewrequirement (newTS6.2.2.e)whichdefinestheresponsibilities andqualifications ofthe'ShiftTechnical Advisor(STA).

l,y 9.Technical Specification 6.3i.TS6.3.1isrevisedtodeletereference totheSTAfunctionandstandardize thereference toRegulatory Guide1.8.10.Technical Specification 6.4i.Deletedentiresection.ll.Technical Specification 6.5i.Deletedentiresection.'2.

Technical Specification 6.6i.Deletedentiresection.13.Technical Specification 6.7i.TSSectionisnow6.8.ii.TS6.7.aisrevisedtoupdatereference to10CFR5036(c)(1)(i)(A) iii.TS6.7.band6.7.darerevisedtoreplacethereference to.NSARBwith"offsitereviewfunction" andSeniorVicePresident, Production andEngineering, with"corporate executive responsible foroverallplantnuclearsafety."iv.TS6.7.cisrevisedtoreplacereference toPORCwith"onsitereviewfunction."

14.Technical Specification 6.8i.TSSectionisnow6.4.ii.TS6.8.l.aisrevisedtoreference Revision2ofRegulatory Guide1.33,AppendixA,insteadofRevision0.iii.TS6.8.l.b,6.8.l.c,6.8.1.d,6.8.l.e,6.8.l.f,6.8.1.g,6.8.l.h,6.8.l.i,6.8.2,and6.8.3aredeleted.iv.TS6.4.l.bisaddedwhichrequireswrittenemergency operating procedures whichimplement therequirements ofNUREG-0737 andNUREG-0737, Supplement 1.v.TS6.4.l.cisaddedwhichrequireswrittenprocedures forallprogramsspecified innewTS6.5.15.Technical Specification 6.9i.TSSectionisnow6.6.

ii.TS6.9.1.1,6.9.1.5,6.9.2.1,6.9.2.3,6.9.2.4,6.9.2.5,andTable6.9-2aredeleted.iii.TS6.9.1.2isrevisedtorequiredocumentation ofallchallenges tothepressurizer poweroperatedreliefvalvesorthepressurizer safetyvalves.iv.TS6.9.1.3isrevisedtodeletealldiscussion relatedtoformatandcontentoftheAnnualRadiological Environmental Reportincluding deletionofTable6.9-1.References to10CFR50,AppendixI,SectionsIV.B.2,IV.B.3,andIV.Careaddedandthesubmittal dateischangedfromHay1stofeachyeartoNay15th.V.TS6.9.1.4isrevisedtodeletealldiscussion relatedtoformatandcontentoftheRadiological EffluentReleaseReport.References to10CFR50.36aand10CFR50,AppendixI,SectionsIV.B.1areaddedandthesemiannual submittal requirement ischangedtoanannualreport.vi.TS6.9.2.2isrevisedtoupdatethereferences to10CFR20andspecifyarequiredsubmittal date.16.Technical Specification 6.10i.Deletedentiresection.17.Technical Specification 6.11i.Deletedentiresection.18.Technical Specification 6.12i.Removedpreviously deletedsection.19.Technical Specification 6.13i.TSSectionisnow6.7.ii.Revisedentiresectionconsistent withnew10CFR20.20.Technical Specification 6.14i.Removedpreviously deletedsection.21.Technical Specification 6.15Significantly revisedentiresectionandmovedtheOffsiteDoseCalculation HanualtonewTS6.5.1.22.Technical Specification 6.16i.Deletedentiresection. 23.Technical Specification 6.17i.Deletedentiresection.24.NewTechnical Specification Section6.5i.AddednewTS6.5.1whichdefinestheOffsiteDoseCalculation Manual.ii.AddednewTS6.5.2whichdefinesthePostAccidentSamplingProgram.BACKGROUND 1.HistoryOnFebruary6,1987,theNRCissuedaninterimPolicyStatement onTechnical Specification Improvements forNuclearPowerReactorswhichproposedcriteriafordefiningthescopeofwhatshouldbecontained withintechnical specifications.

Thesecriteriaweredeveloped asaresultofeffortswithintheNRCandnuclearindustrytorelocatemanyexistingrequirements toothermoreappropriate programsanddocuments inordertostreamline thetechnical specifications.

Therelocated requirements wouldthenbecontrolled byotherexistingregulations (e.g.,10CFR50.59).Thisrelocation wouldresultinmoreconcisetechnical specifications whichfocusedonthemostimportant requirements withoutanyreduction insafety.Following issuanceoftheinterimPolicyStatement, theNRCandnuclearindustrybegandevelopment ofnewstandard(orimproved) technical specifications whichimplemented theproposedcriteria, providedgreateremphasisonhumanfactorsprinciples, andcontained detailedbasesforeachretainedspecification.

TheendproductofthiseffortwasthereleaseoffiveNUREGsinSeptember 1992whichcontained theImprovedTechnical Specifications (ITS)foreachofthefourNSSSvendors(twoNUREGswereissuedforBWRs).TheseNUREGscontained alloftheimprovements discussed aboveandalsoso-called "line-item" improvements whicharegenericrefinements tothetechnical specifications thatwereidentified subsequent totheinterimPolicyStatement.

TheNUREGswerethenfollowedbyafinalPolicyStatement whichbecameeffective onJuly22,1993,andencouraged licensees toimplement theITS.InresponsetothereleaseoftheITSandthecontinued publication ofnew"line-item" improvements, RGEEbeganconsideration ofimplementing NUREG-1431(Reference 1)whichcontained thenewtechnical specifications forWestinghouse plants.Following discussions withtheNRCstaff,RGLEdecidedtoinitiateaTechnical Specification Improvement Program(TSIP)andimplement theITSforGinnaStation(Reference 2).Thisprogramwillconsistofrelocating currentrequirements inaccordance withthefinalPolicyStatement onTechnical Specifications andreformatting theremaining requirements consistent withNUREG-1431.

Ingeneral,newrequirements contained inNUREG-1431 thatarenotinthecurrentGinnaStationTechnical Specifications willnotbeadded.

IIsa Basedondiscussions withtheNRCstaff,thefirststepintheTSIPisconversion oftheAdministrative Controlssectionoftechnical specifications.

ThissectionwasselectedsinceRG&Epreviously submitted aLARrelatedtothePlantOperations ReviewCommittee (PORC)membership requirements whicharecontained intheAdministrative Controlssection(Reference 3).ThatLARhasnotbeenapprovedbytheNRCandissuperseded bythissubmittal.

Theremaining sectionsoftechnical specifications willbeconverted atalaterdate.Subsequent totheissuanceoftheNUREGs,theNRCproposedthatthecontentoftheITSAdministrative Controlssectionbesignificantly reducedtoeliminate duplication withotherregulatory requirements (Reference 4).Thenuclearindustryevaluated theproposedchangesandformallysubmitted revisions totheITSAdministrative Controlssectionbasedontheinformation providedbytheNRCandadditional researchandstudy(Reference 5).RG&Ehasevaluated thenuclearindustryproposedchangesanddecidedtosubmitaLARwhichimplements theITSformatfortheAdministrative Controlssection(GinnaStationTechnical Specification Section6)andrelocates requirements consistent withReference 5.Administrative controlsthatarecontained inNUREG-1431 whicharerelatedtorequirements thatwillbeaddressed duringtheconversion oftheremaining GinnaStationTechnical Specifications arenotincludedwiththisLAR.Examplesofrequirements whicharenotaddedatthistimeincludetheSafetyFunctionDetermination, Explosive GasandStorageTankRadioactivity Monitoring, andtheBasesControlPrograms.

Inaddition, acurrentrequirement foraddressing SafetyLimitViolations isretainedwithintheAdministrative Controlssectioninordertopreventtheneedtoreviseadditional Technical Specification sections.

TheSafetyLimitViolation requirement willberelocated toGinnaStationTechnical Specification Section2duringtheconversion oftheremaining sections.

2.HardwareModifications Therearenoplantmodifications whicharerequiredtoimplement thechangesrequested inthisLAR.Section6oftheTechnical Specifications addresses theadministrative controlswhichareinplacetoassurethatGinnaStationisoperatedinasafemanner.Thesecontrolstypically consistofprogramsandperiodicreporting requirements.

Revisingthecurrentadministrative

controls, removingcurrentcontrolswhichduplicate requirements contained withintheCodeofFederalRegulations, orrelocating controlstootherprogramsdoesnotrequireanyplantmodifications.

Anychangestoplantprocedures, theUpdatedFinalSafetyAnalysisReport(UFSAR),orthegAProgramwhicharenecessary tosupportthechangesrequested bythisLARwillalsonotresultinanyplantmodifications. C.JUSTIFICATION Reformatting thecurrentAdministrative Controlssectionwillprovideasignificant humanfactorsimprovement bylocatingsimilarrequirements

,-,within thesamesectionandprovideastandardstructure.

Thereareseveraltypesofchangesthatarebeingrequested bythisLARinordertoperformthereformatting.

Thetechnical andsignificant administrative changes,andthebasisforthesechanges,aresummarized below.SincetheupgradeoftheAdministrative Controlssectionisbeingperformed consistent withtheITS,amarkedupcopyofSection5.0ofNUREG-1431 isprovidedinAttachment D.Thisattachment showsallproposedchangeswithrespecttoITSforWestinghouse plants.Acrossreference isprovidedintheleftmarginofeachITSspecification thathasbeenchangedbyuseofacirclecontaining sectionnumbersfrombelow.Requirements contained withinthecurrentGinnaStationTechnical Specifications areidentified as"TS";withintheproposedfinalGinnaStationTechnical Specifications (i.e.,Attachment C)as"newTS";andwithinNUREG-1431 as"ITS."Relocation ofRequirements WithinTechnical Specification Section6Manycurrentrequirements aremovedtosupportconsolidation ofsimilaradministrative controlswithinthesamesection.Sincetherequirements areonlybeingrelocated withinthetechnical specifications, thereisnoreduction insafety.Thefollowing GinnaStationrequirements wererelocated withintheAdministrative ControlsSection6:TS6.2.l.c-theresponsibilities ofthePlantManageraredeletedsincethisisaddressed bynewTS6.1.1.TS6.3.1-thecurrentrequirements forShiftTechnical Advisors(STAs)aremovedtonewTS6.2.2.e.Thereference totheRGKEletterdatedDecember30,1980,wasreplacedwithastatement requiring theSTAsto"meetthequalifications specified withinaNRCapprovedSTAtrainingprogram."

Thischangeisdifferent thanthewordingcontained inNUREG-1431 whichrequirestheSTAtomeet,thequalifications specified intheCommission PolicyStatement onEngineering Expertise onShift(i.e.,GenericLetter86-04).ThecurrentSTAprogramatGinnaStationisdiscussed inReferences 6and7andhasbeenreviewedandapprovedbytheNRC.SincetheSTAprogramdoesnotmeetalltherequirements contained withinGL86-04,theproposedwordingisconsidered moreappropriate andconsistent withthecurrenttechnical specifications.

Thedeletionofthespecificreference toanRG&Elettereliminates theneedtorevisetechnical specifications iftheSTAprogramislaterrevised.

Jf,ikt iii.TS6.4-therequirements foraTrainingProgramaredeletedsinceTS6.3specifies thatallmembersoftheGinnaStationstaffmustmeetorexceedtheminimumrequirements ofANSIStandardN18.1-1971.ThisANSIStandardrequiresaretraining andreplacement trainingprogramwhichensures"safeandefficient operation ofthefacility."

Requirements forlicensedoperatortrainingareaddressed by10CFR55.TS6.8.l.b,6.8.l.c,and6.8.l.f-therequirements forwrittenprocedures whichaddressrefueling operations, surveillance andtestactivities ofsafetyrelatedequipment, andFireProtection programimplementation aredeletedsincethesearespecified inRegulatory Guide1.33,AppendixA,Revision2(newTS6.4.l.a).V.TS6.8.l.g-therequirement forwrittenprocedures fortheradiological environmental monitoring programisdeletedsincethisisaddressed inthespecification fortheOffsiteDoseCalculation Hanual(newTS6.5.1).TheOffsiteDoseCalculation Hanualisrequiredtocontain"themethodology andparameters usedin...theconductoftheradiological environmental monitoring program."

vi.TS6.8.l.h-therequirement forwrittenprocedures fortheOffsiteDoseCalculation HanualismovedtonewTS6.5.1.TS6.9.1.5and6.9.2.4-therequirement forreporting pressurizer poweroperatedreliefvalveandpressurizer safetyvalvechallenges ismovedtotheHonthlyOperating ReportSpecification (newTS6.6.4).viii.TS6.15-theOffsiteDoseCalculation Hanualisrevisedconsistent withNUREG-1431 andITSTraveller BWOG-09andmovedtonewTS6.5.1.Elimination ofDuplicated Regulatory Requirements Severaladministrative controlscurrently duplicate otherregulatory requirements.

Theremovalofthesetypeofadministrative controlseliminates theneedtochangetechnical specifications whentherearerulechanges.Asanexample,therecentrevisions to10CFR20willrequireRG3Etorevisethetechnical specifications.

Sincealllicensees mustmeettheapplicable requirements contained intheCodeofFederalRegulations, orhaveNRCapprovedexemptions, therearesufficient regulatory controlsinplacetoallowelimination ofduplicated requirements fromtechnical specifications.

Theimplementation oftheserequirements arecontained inprocedures andotherlicenseecontrolled documents.

Thefollowing requirements wereremovedfromtheAdministrative ControlsSection6(orrevisedasnoted)sincetheyduplicate existingregulatory requirements:

TS3.1.4.3.a and6.9.2.3-reporting requirements forexceeding theprimarycoolantspecificactivitylimitslistedinTS3.1.4.l.aand3.1.4.l.barespecified in10CFR50.73(2)(i)(A).

TS6.2.2.a,6.2.2.b,6.2.2.c,6.2.2.d,andTable6.2-1requiredoperating crewcompositions arespecified in10CFR50.54(k),

(l),and(m)andnewTS6.2.2.a,6.2.2.b,and6.2.2.e.TS6.6-requirements forreportable eventsarespecified in10CFR50.72,10CFR50.73,andotherregulations.

TS6.8.l.d-therequirement forwrittenprocedures whichimplement theSecurityPlanarespecified in10CFR50.54(p)(l) and10CFR73.55(b)(3).

Elimination ofthisrequirement isconsistent withGenericLetter93-07(Reference 8).TS6.8.l.e-therequirement forwrittenprocedures whichimplement theEmergency Planarespecified in10CFR50.54(q)and50.54(t),

and10CFR50,AppendixE,SectionV.Elimination ofthisrequirement isconsistent withGenericLetter93-07(Reference 8).TS6.9.1.3andTable6.9-1-theformatandcontentoftheAnnualRadiological Environmental Reportiscontained intheOffsiteDoseCalculation Hanualspecification (newTS6.5.1)andthereferenced Radiological Assessment BranchTechnical

Position, Revision1,November1979.References to10CFR50,AppendixI,SectionsIV.B.2,IV.B.3,andIV.Cwereaddedtosupportdeletionofthereportformatandcontentandthesubmittal datewaschangedfromHay1stofeachyeartoHay15thconsistent withNUREG-1431.

TS6.9.1.4-theformatandcontentoftheRadiological

'.EffluentReleaseReportiscontained inOffsiteDoseCalculation Hanualspecification (newTS6.5.1).References to10CFR50.36aand10CFR50,AppendixI,SectionIV.B.1wereaddedconsistent withNUREG-1431.

Thesemiannual submittal requirement isalsochangedtoanannualreportinaccordance with10CFR50.36a(a)(2).

TS6.9.2.1-reporting requirements relatedtosealedsourcesarespecified in10CFR30.50.TS6.9.2.5-licenseesubmittals areaddressed by10CFR50.4.TS6.11-therequirement foraRadiation Protection Programisspecified in10CFR20.1101.

Ey~I'\ xi.TS6.17-changestotheRadioactive WasteTreatment systemsarecontrolled by10CFR50.59.NRCnotification ofsignificant changestothesesystemsisaddressed by10CFR50.59(b)(2).

3.Relocation ofCurrentAdministrative ControlRequirements ToOtherControlled Documents Therelocation ofcertainrequirements contained intheAdministrative Controlssectiontootherlicenseecontrolled documents (i.e.,gAProgramandplantprocedures),

doesnoteliminate theprogram.Instead,therequirements arerelocated toothermoreappropriate documents andprogramswhichhavesufficient controlsinplacetomanageimplementation andfuturechanges(e.g.,10CFR50.54(a)(3) and10CFR50.59).Therelocation oftheseitemswillenableRGKEtomoreefficiently maintaintherequirements underexistingregulations andreducetheneedtorequesttechnical specification changesforissueswhichdonotaffectpublicsafety.Thefollowing sectionswererelocated fromtheAdministrative ControlsSection6tothegAProgramorplantprocedures:

TS3.16.1.3andTable6.9-2-Reporting levelsforradioactivity concentrations inenvironmental sampleswillbeaddressed inandimplemented byprocedure RD-15.0,OffsiteDoseCalculation Hanual(Reference 9).Relocating thereporting levelstotheOffsiteDoseCalculation Manualisconsistent withtherequiredcontentofthismanualasspecified innewTS6.5.1.ChangestotheOffsiteDoseCalculation Hanualisalsoaddressed bynewTS6.5.1whichprovidessufficient controlwithrespecttomaintaining appropriate reporting levelsforradioactivity concentrations.

TS6.2.1.b,6.7.band6.7.d-theresponsibilities oftheSeniorVicePresident, Production andEngineering.

NewTS6.2.I.arequiresthat"linesofauthority, responsibility andcommunication shallbeestablished anddefinedthroughout thehighestmanagement levels."Specifying management positions bytitlewithinthetechnical specifications createsalicenseeandNRCburdenwhentitlesarechangedorresponsibilities areshifted.Theresponsibilities ofkeyorganization positions arespecified intheGinnaStationgAProgram.SincechangestothegAProgramarecontrolled by10CFR50.54(a)(3),

equivalent controlisprovided.

TS6.2.1;d-thecapability oftraining, healthphysicsandqualityassurance tohavedirectaccesstoresponsible corporate management tosupportmitigation oftheirconcerns.

NewTS6.2.l.arequiresthat"linesofauthority, responsibility andcommunication shallbeestablished anddefinedthroughout thehighestmanagement levels."Theorganizational structure isspecified intheGinnaStationgAProgram.SincechangestothegAProgramarecontrolled by10CFR50.54(a)(3),

equivalent controlisprovided. 1V~TS6.5,6.6.l.b,6.7.b,6.7.cand6.7.d-theReviewandAuditfunctions, including thecompositions, meetingfrequencies, andresponsibilities ofthePORC,NSARBandgA.Thenecessary changestothegAProgramtosupportrelocation arebeingrequested separately.

ChangestothegAProgramarecontrolled by10CFR50.54(a)(3) whichprovidesequivalent control.v.V1~TS6.8.l.iand6.16-TheProcessControlProgramisaddressed inandimplemented byprocedure RD-16.0,ProcessControlProgram(Reference 10).Thisprogramensurescompliance with10CFR20,10CFR61,and10CFR71whichregulatetheprocessing andpackaging ofsolidradioactive wastes.Thefailuretomeettheseregulations issufficiently addressed withintheCodeofFederalRegulations.

SincetheProcessControlProgramonlyensurescompliance withexistingregulations, itisacceptable torelocatethisprogramtoplantprocedures whichareunderthecontrolof10CFR50.59.TS6.8.2and6.8.3andBasesforTS3.6-controlofchangestowrittenprocedures andtheuseandapprovaloftemporary procedure changes.Thenecessary changestothegAProgramtosupportrelocation arebeingrequested separately.

ChangestothegAProgramarecontrolled by10CFR50.54(a)(3) whichprovidesequivalent control.TS6.10-RecordRetention requirements.

Thesearecurrently specified inthegAProgram.ChangestothegAProgramarecontrolled by10CFR50.54(a)(3) whichprovidesequivalent control.AdditionofNewITSAdministrative ControlRequirements Thereareseveralrequirements contained inNUREG-1431 whicharenotcurrently intheGinnaStationTechnical Specifications.

Thefollowing NUREG-1431 (ITS)requirements wereaddedtothecurrentGinnaStationAdministrative Controlssectioninordertoprovideamorecompletespecification:

ITS5.1.1(TS6.1.1)-PlantManagerresponsibilities relatedtoapproving eachproposedtest,experiment ormodifications tosystems,structures orcomponents thataffectnuclearsafety.ITS5.1.2(TS6.1.2)-ShiftSupervisor responsibilities andallowedabsencesfromthecontrolroom.1V.ITS5.2.l.a(TS6.2.l.a)-arequirement for,functional descriptions ofdepartmental responsibilities andrelationships andjobdescriptions ofkeypersonnel positions.

ITS5.2.l.c(TS6.2.2.e)-allowstheindividual qualified inradiation protection procedures tobeabsentfornotmorethan2hours.

'III v.ITS5.7.l.l.a(TS6.4.l.a)-requireswrittenprocedures inaccordance withRevision2ofRegulatory Guide1.33,AppendixA,insteadofthecurrentreference toRevision0.vi.ITS5.7.l.l.b(TS6.4.l.b)-requireswrittenemergency operating procedures whichimplement therequirements ofNUREG-0737 andNUREG-0737, Supplement l.vii.ITS5.7.l.l.g(TS6.4.l.c)-requireswrittenprocedures forallprogramsspecified inTS6.5.rviii.ITS5.7.2.6(TS6.5.2)-requiresaPostAccidentSamplingPro'gram.

ITSAdministrative ControlsDeferredUntilConversion ofRemaining TSSectionsSeveralITSAdministrative Controlrequirements werenotaddedsincetheywillbeaddressed duringtheconversion of.theremaining technical specifications sections.

Theiradditionisdelayedsincetheyarecurrently addressed elsewhere withintheGinnaStationTechnical Specifications oraredirectlyrelatedtotheconversion oftheremaining sections.

Thefollowing NUREG-1431 administrative controlrequirements (orissues)willbeevaluated duringtheconversion oftheremaining chapters:

TheuseofModes1through6.Thiswasreplacedwiththecurrentnomenclature ofRefueling,'old

Shutdown, HotShutdown, andOperating (seeTS1.2).Thenumbering oftheAdministrative Controlssectionremains6.0(versus5.0)untiltheconsolidation ofTechnical Specifications Sections3.0and4.0.ill~1V.ITS5.6,Technical Specifications BasesControl-thisprogramwillbeimplemented following conversion oftheremaining chapters.

ITS5.7.1.1.e,gualityAssurance forEffluentandEnvironmental Monitoring

-therequirements foreffluentandenvironmental monitoring areaddressed byTS3.16,Radiological Environmental Monitoring, andTS4.10,Radiological Environmental Monitoring Surveillances.

TheGinnaStationTechnical Specifications currently require(andthegAProgramwillrequire)independent auditsatleastonceperyeartoensure"theconformance offacilityoperation toallprovisions contained withinTechnical Specifications."

Therefore, sufficient qualityassurance oftheseactivities exists.v~"ITS5.7.2.4,PrimaryCoolantSourcesOutsideContainment

-thecontrolofleakagefromsystemsthatcouldcontainhighlyradioactive fluidsandwhichexitcontainment isaddressed byTS4.4.3,Recirculation HeatRemovalSystems. V1.V11.ITS5.7.2.5,InPlantRadiation Monitoring Program-thecapability todetermine airborneiodineconcentrations invitalareasunderaccidentconditions isaddressed byTS3.5.4andTable4.1-5.ITS5.7.2.7,Radioactive EffluentControlsProgram-therequirement toprovidelimitations onliquidandgaseousreleasesisaddressed byTS3.9,PlantEffluents, andTS4.12,EffluentSurveillance.

V111~1X.ITS5.7.2.8,Radiological Environmental Monitoring Program-therequirement tomonitor,sample,andreportradiation andradionuclides intheenvironment isaddressed byTS3.16,Radiological Environmental Monitoring, andTS4.10,Radiological Environmental Monitoring Surveillances.

ITS5.7.2.10,Pre-Stressed ConcreteContainment TendonSurveillance ProgramandITS5.9.2.d,SpecialReportrelatedtoabnormaldegradation observedbythePre-Stressed Containment TendonSurveillance Program-requirements relatedtocontainment tendondegradation areaddressed byTS4.4.4,TendonStressSurveillance.

X.X1~X11.X111.X1V.ITS5.7.2.11,Inservice Inspection Program-requirements foraninservice inspection programareaddressed byTS4.2,Inservice Inspection.

ITS5.7.2.12,Inservice TestingProgram-requirements foraninservice testingprogramareaddressed byTS4.2.1.6.ITS5.7.2.13,SteamGenerator TubeSurveillance ProgramandITS5.9.2.e,SpecialReportforSteamGenerator TubeSurveillance Program-requirements forasteamgenerator tubesurveillance programareaddressed byTS4.2.1and4.2.1.4.ITS5.7.2.15,Ventilation FilterTestingProgram-testingrequirements forEngineered SafetyFeaturefilterventilation systemsisaddressed byTS4.5.2.3,AirFiltration System.ITS5.7.2.16,Explosive GasandStorageTankRadioactivity Monitoring Program-thecontrolandmonitoring ofpotentially explosive gasmixturesinradioactive systemsisaddressed byTS3.5.5and3.9.2.5.XV.XV1.ITS5.7.2.17,DieselFuelOilTestingProgram-thecontrol,monitoring, andsamplingrequirements ofdieselfueloilisaddressed byTS4.6.I.d.ITS5.8.1,SafetyFunctionDetermination Program-thisprogramwillbeimplemented following conversion oftheremaining chapters.

ITS5.9.1.6,CoreOperating LimitsReport-thisreportisonlyrequiredfollowing removalofexistingtechnical specification coreoperating limitsandwillbeutilizedfollowing conversion oftheremaining sections.

xviii.ITS5.9.1.7,ReactorCoolantSystemPressureandTemperature LimitsReport-thisreportisonlyrequiredfollowing removal'ofexistingtechnical specification RCSpressureandtemperature limitsandwillbeutilizedfollowing conversion oftheremaining sections.

ITS5.9.2.b,SpecialReportfollowing fourormorevalidfailuresofanindividual emergency dieselgenerators inthelast25demands-Thisrequirement iscurrently notspecified intheelectricpowersectionsofTechnical Specifications andwillbeaddressed duringtheirconversion.

XX.ITS5.9.2.c,SpecialReportrelatedtoPostAccidentMonitoring (PAM)Instrumentation

-therequirement foraspecialreportiscurrently specified inTSTable3.5-6.ITSAdministrative ControlsNotAddedThefollowing NUREG-1431 administrative controlrequirements werenotaddedtothetechnical specifications basedonITSTraveller BWOG-09orissuesspecifictoGinnaStation:ITS5.1.1(TS6.1.1)-therequirement forPlantManagerapprovalofproposedtests,experiments ormodifications tobecontained inapprovedadministrative procedures wasnotadded.Thiswouldonlyduplicate atechnical specification requirement withinprocedures anddoesnotprovideanybenefittosafety.Also,PlantManagerapprovalof"proposed changes"wasdeletedsincehisapprovalisalreadyrequired"priortoimplementation" whichprovidessufficient controlofunitchanges.ITS5.1.2(TS6.1.2)-therequirement foranannualmanagement directive toallstationpersonnel relatedtotheshiftsupervisor controlroomcommandfunctionwasnotadded.Amanagement directive isnotnecessary sincetheauthority andresponsibility ofeachunitorganization isspecified inthegAProgramandaddressed byTS6.2.l.a.ITS5.2.2.f-therequirement fortheOperations ManagertoholdanSROlicensewasnotaddedsincethequalifications ofthispositionareaddressed inANSIStandardN18.1-1971 (seeTS6.3). v.V1.ITS5.3.1(TS6.3)-arequirement forqualifications ofstaffnotcoveredbyRegulatory Guide1.8wasnotadded.Thisrequirement wasnotconsidered necessary sinceallactivities whichaffectnuclearsafetyarecontrolled byothertechnical specification requirements, existingregulations, andthegAProgram.Also,Revision1ofRegulatory Guide1.8wasnotrevisedtoRevision2inordertomaintainconsistency withthecurrentgAProgramandexistingprocedures.

ITS5.7.2.9-therequirement foraComponent CyclicorTransient LimitProgramwasnotadded.Thetrackingofcyclicandtransient occurrences withinaspecified programtoensurethatcomponents aremaintained withinthedesignlimitsisnotconsidered necessary duetoexistingprogramssuchassurveillance testingandtheISIprogram.Maintaining recordsoftransient andoperational cyclesiscurrently requiredbyTS6.10.gandthegAProgram.ITS5.7.2.14-therequirement forcontrolling andmonitoring secondary waterchemistry wasnotaddedsincethisrequirement isspecified asacondition totheGinnaStationOperating LicensedatedDecember10,1984(seeReference 12).ITS5.7.2.18-therequirement foraFireProtection Programwerenotaddedconsistent withBWOG-09.Theadministrative controlforthisprogramwasoriginally addedtoensurethattheunitwascapableofproviding alternate/dedicated safeshutdowninaccordance with10CFR50,AppendixRfollowing afire.ChangestotheFireProtection ProgrammaybemadewithoutpriorNRCapprovalonlyifthosechangeswouldnotadversely affecttheabilitytoachieveandmaintainsafeshutdownintheeventofafire.Thisrequirement isspecified asacondition totheGinnaStationOperating LicensedatedDecember10,1984(seeReference 13).Changestoplantprocedures thatimplement theFireProtection Programareaddressed under10CFR50.59.ITS5.9.2.a-therequirement foraspecialreportfollowing theactuation andinjection ofanEmergency CoreCoolingSystem(ECCS)aboveNode4wasnotaddedconsistent withBWOG-09.Reporting requirements relatedtoECCSactuations areaddressed by10CFR50.73(a)(2)(iv) whichspecifies aLicenseeEventReportwithin30days.OtherChangestoTechnical Specification Section6Thefollowing revisions totheAdministrative ControlsSection6.0areminorchangesonlyanddonotinvolveanytechnical issues:ReformatoftheentireSection6.0consistent withthestructure ofNUREG-1431.

r Renumbering ofremaining Section6.0requirements consistent withtheformatofNUREG-1431 andITSTraveller BWOG-09.1V~v.V1.Updateofreferences tosectionsoftheCodeofFederalRegulations.

Standardization ofreportnameswithinTechnical Specifications.

Removalofpreviously deletedsectionswithinTechnical Specifications.

ITS5.l.1(newTS6.1.1)-thewordingwasrevisedtorequirethePlantHanagertoapprovechangesto"structures, systemsorcomponents" thataffectnuclearsafetyconsistent withGinnaStationterminology.

vii.ITS5.1.2(newTS6.1.2)-replaced"valid"licensewith"active"licenseconsistent withITSTraveller BWOG-09andstandardnomenclature atGinnaStation.1X.X.ITS5.2.2.e-revisedtheovertimerequirement forunitstaffwhoperformsafetyrelatedfunctions torequirecontrolinaccordance withanNRCapprovedprogram.RG&Ecurrently utilizesastaffworkinghourcontrolprogramwhichslightlydiffersfromtheNRCPolicyStatement onWorkingHours(GenericLetter88-12).Thisprogramwaspreviously reviewedandapprovedbytheNRC(Reference ll).Theproposedwordingisconsidered moreappropriate andconsistent withthecurrenttechnical specification.

TS6.9.1.1(ITS5.9.1.1)-deletedtherequirement sinceaStartupReportismoreappropriately addressed intheNRCSafetyEvaluation Reportauthorizing anOperating License,increased licensedpowerlevel,installation ofanewnuclearfueldesignormanufacturer, ormodifications whichsignificantly alterthenuclear,thermal,orhydraulic performance oftheplant.The'Startup Reportisrequiredtobesubmitted within90daysfollowing completion oftheaboveactivities anddoesnotrequireNRCapproval.

Therefore, inclusion oftherequirement forthisreportinTechnical Specifications isnotnecessary toassuresafeplantoperation.

ITS5.9.1.2.a(newTS6.6.1)-Asubmittal dateof"onorbeforeApril30ofeachyear"wasaddedtotheOccupational Radiation ExposureReportconsistent with10CFR20.2206(7)(c). xi.ITS5.11(newTS6.7)-replacedreferences to"healthphysics"with"radiation protection" throughout section.Alsoreplacedthe">1000mrem/hr"with"Z1000mrem/hr"inITS5.11.3tomakeitconsistent withITS5.11.2.Inaddition, deletedtherequirement fortheRadiation Protection ManagertosignRadiation WorkPermits(RWPs)asspecified inITS5.11.I.a.TheissuanceofRWPsisaddressed inprocedures underthecontrolof10CFR50.59.Specifying management positions bytitlewithinthetechnical specifications createsalicenseeandNRCburdenwhentitlesarechangedorresponsibilities areshifted.8.RetainedAdministrative ControlRequirements NotInITSGinnaStationTechnical Specification 6.7liststherequiredactionsintheeventthataSafetyLimitisviolated.

Thisrequirement willberelocated toTechnical Specification

2.0 duringtheconversion

oftheremaining sectionstoeliminate theneedtoreviseadditional technical specifications iftherequirement weretoberelocated now.SAFETYEVALUATION Thechangesrequested inthisLARinvolveeither1)therelocation ofexistingrequirements withinthetechnical specifications orotherRGSEcontrolled documents, 2)elimination ofspecifications duplicated byregulatory requirements, 3)additionofnewcontrolsinaccordance withNUREG-1431, or4)administrative changesonly.Thesechangesareconsistent withtheFinalPolicyStatement onTechnical Specifications Improvements forNuclearPowerReactorsandNUREG-1431.

Therefore, thesafetyimpactofmakingthesechangeshasbeenpreviously considered andfoundacceptable bytheNRC.TheAdministrative Controlssectionwasalsoconverted totheITSformat;however,notallNUREG-1431 requirements wereimplemented.

Theseadditional requirements werenotaddedsincetheyarecurrently addressed elsewhere withintheGinnaStationTechnical Specifications, aredirectlyrelatedtotheconversion oftheremaining

sections, orarenotconsidered necessary toprovideacompletespecification.

Theimpactofnotimplementing alloftheNUREG-1431 requirements wasevaluated asfollows:Thereisnoincreaseintheprobability orconsequences ofanaccidentormalfunction ofequipment important tosafetypreviously evaluated intheUFSARrelatedtonotimplementing alloftheNUREG-1431 administrative controls.

Therequirements whichwerenotaddedasidentified insectionC.5andC.6abovearecurrently addressed byexistingtechnical specifications andregulations, theGinnaStationlicense,plantprocedures, orthegAProgram.Therefore, thereisnoincreaseintheprobability orconsequences ofanaccidentormalfunction ofequipment bynotaddingtheserequirements totheTechnical Specifications. Thepossibility ofanewordifferent kindofaccidentoramalfunction ofadifferent typethanpreviously evaluated intheUFSARisnotcreatedbynotimplementing alloftheNUREG-1431 administrative controls.

TheAdministrative Controlssectioncontainsthoserequirements thatarenotcoveredbyothertechnical specifications whichareconsidered necessary toassuresafeoperation ofthefacility.

Thesecontrolstypically supplement existingregulations anddonotaffecttheaccidentanalysescontained intheUFSAR.Sincetheaffectedrequirements identified insectionC.5andC.6abovearecurrently addressed byexistingtechnical specifications andregulations, theGinnaStationlicense,plantprocedures, orthegAProgram,anewordifferent kindofaccidentormalfunction isnotcreatedbynotaddingthemtotheTechnical Specifications.

Thereisnoreduction inthemarginofsafetyasdefinedinthebasisforanyTechnical Specification relatedtonotimplementing alloftheNUREG-1431administrative controlssincetheserequirements arecurrently notcontained intheGinnaStationTechnical Specifications.

Basedontheabove,theproposedamendment doesnotinvolveanunreviewed safetyquestionandwillnotadversely affectorendangerthehealthandsafetyofthegeneralpublic.SIGNIFICANT HAZARDSCONSIDERATION EVALUATION TheproposedchangestotheGinnaStationTechnical Specifications donotinvolveasignificant hazardsconsideration asdiscussed below:Operation ofGinnaStationinaccordance withtheproposedchangesdoesnotinvolveasignificant increaseintheprobability orconsequences ofanaccidentpreviously evaluated.

Thechangesareconsistent

,withtheFinalPolicyStatement onTechnical Specifications Improvements forNuclearPowerReactorsandNUREG-1431andhavetherefore, beenpreviously evaluated bytheNRC.Implementation ofthesechangesisexpectedtoresultinasignificant humanfactorsimprovement andenableRGEEandtheNRCtofocusonthemostimportant requirements withoutanyreduction insafety.Thechangeswhichdonotduplicate NRCguidanceinNUREG-1431arecurrently addressed byexistingtechnical specifications andregulations, theGinnaStationlicense,plantprocedures, orthegAProgram.

II,g4Ce044 2.3.Operation ofGinnaStationinaccordance withtheproposedchangesdoesnotcreatethepossibility ofanewordifferent kindofaccidentfromanyaccidentpreviously evaluated.

TheAdministrative Controlssectioncontainsthoserequirements thatarenotcoveredbyothertechnic'al specifications whichareconsidered necessary toassuresafeoperation ofthefacility.

Themajorityofchangesareconsistent withtheFinalPolicyStatement onTechnical Specifications Improvements forNuclearPowerReactorsandNUREG-1431andhavetherefore, beenpreviously evaluated bytheNRC.Therequirements whichwerenotaddedonlysupplement existingregulations anddonotaffecttheaccidentanalysescontained intheUFSAR.Operation ofGinnaStationinaccordance withtheproposedchangesdoesnotinvolveasignificant reduction in,amarginofsafety.Allrequirements removedfromtechnical specifications arerelocated tootherprogramsanddocuments.

Thesealternative programsanddocuments arecontrolled byexisting'regulations whichprovideamoreappropriate vehicleforaddressing changesandcompliance.

Therewerenoadministrative controlrequirements whichwereremovedfromtechnical specifications andnotaddressed byotherregulations.

Therefore, thereisnosignificant reduction inamarginofsafety.Basedupontheaboveinformation, ithasbeendetermined thattheproposedchangestotheGinnaStationTechnical Specifications donotinvolveasignificant increaseintheprobability orconsequences ofanaccidentpreviously evaluated, doesnotcreatethepossibility ofanewordifferent kindofaccidentpreviously evaluated, anddoesnotinvolveasignificant reduction inamarginofsafety.Therefore, itisconcluded thattheproposedchangesmeettherequirements of10CFR50.92(c)anddonotinvolveasignificant hazardsconsideration.

ENVIRONMENTAL CONSIDERATION RG8Ehasevaluated theproposedchangesanddetermined that:Thechangesdonotinvolveasignificant hazardsconsideration asdocumented inSectionEabove;2.Thechangesdonotinvolveasignificant changeinthetypesorsignificant increaseintheamountsofanyeffluents thatmaybereleasedoffsitesincealladministrative controlsrelatedtooffsitereleasesareretainedoraddressed byexistingregulations; and3.Thechangesdonotinvolveasignificant increaseinindividual orcumulative occupational radiation exposuresincealladministrative controlsrelatedtomaintaining'adiation exposureaslowasreasonably achievable areretainedoraddressed byexistingregulations.

~4I Accordingly, theproposedchangesmeettheeligibi1itycriteriaforcategorical exclusion setforthin10CFR51.22(c)(9).Therefore, pursuantto10CFR51.22(b),

anenvironmental assessment oftheproposedchangesisnotrequired.

REFERENCES 2.NUREG-1431, StandardTechnical Specifications, kfestinghouse Plants,September 1993.LetterfromR.C.Hecredy,RG&E,toA.R.Johnson,NRC,

Subject:

Conversion toImprovedTechnical Specifications, datedFebruary28,1994.3.4,5.6.7.8.910.12.13.LetterfromR.C.Mecredy,RG&E,toA.R.Johnson,NRC,

Subject:

Application forAmendment toTechnical Specification 6.5.1,"PlantOperations ReviewCommittee (PORC)Function, "datedMarch23,1993.LetterfromW.T.Russell,NRC,toImprovedTechnical Specification OwnersGroupChairpersons,

Subject:

ContentofStandardTechnical Specifications, Section5.0,Administrative

Controls, datedOctober25,1993.ImprovedTechnical Specification Traveller BWOG-09.LetterfromR.W.Kober,RG&E,toH.Fairtile, NRC,

Subject:

PolicyStatement onEngineering Expertise onShift(GenericLetter86-04),datedHay14,1986.LetterfromR.CHecredy,RG&E,toA.R.Johnson,NRC,

Subject:

NUREG-0737,Item1.A.1.1,ShiftTechnical Advisor,datedOctober12,1989.GenericLetter93-07,

Subject:

Hodification oftheTechnical Specification Administrative ControlRequirements forEmergency SecurityPlans.GinnaStat'ionProcedure RD-15.0,OffsiteDoseCalculation Hanual.GinnaStationProcedure RD-16.0,ProcessControlProgram.LetterfromW.A.Paulson,NRC,toR.W.Kober, RG&E,

Subject:

PlantStaffirkingHoursandReporting Requirements forSafetyValveandReliefValveFailuresandChallenges, datedJanuary31,1984.LetterfromD.H.Crutchfield, NRC,toL.D.White,RG&E,

Subject:

IssuanceofAmendment No.33toProvisional Operating LicenseNo.DPR-18,datedJune13,1980.LetterfromA.R.Johnson,NRC,toR.C.Mecredy,RG&E,

Subject:

IssuanceofAmendment No.40toFacilityOperating LicenseNo.DPR-18,R.E.GinnaNuclearPowerPlant(TACNo.N83568),datedSeptember 21,1992.