ML17264A866

Application for Amend to License DPR-18,revising RCP PT & Administrative Control Requirements

ML17264A866
Person / Time
Site:	Ginna
Issue date:	04/24/1997
From:	MECREDY R C ROCHESTER GAS & ELECTRIC CORP.
To:
Shared Package
ML17264A865	List: ML17264A863 ML17264A866 ML17264A867 ML17264A868
References
NUDOCS 9705020088
Download: ML17264A866 (18)

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UNITEDSTATESOFAMERICANUCLEARREGULATORYCOMMISSIONIntheMatterofRochesterGasandElectricCorporation(R.E.GinnaNuclearPowerPlant))))DocketNo.50-244)APPIICATIONFORAMENDMENTTPERATINGLICENEPursuanttoSection50.90oftheregulationsoftheU.S.NuclearRegulatoryCommission(NRC),RochesterGasandElectricCorporation(RG&E),holderofFacilityOperatingLicenseNo.DPR-18,herebyrequeststhattheTechnicalSpecificationssetforthinAppendixAtothatlicense,beamended.ThisrequestforchangeistorevisetheAdministrativeControlswithrespecttotheReactorCoolantSystem(RCS)RCSPressureandTemperatureLimitsReporttomakethenecessarychangesinorderplacethisdocumentunderlicenseecontrolandtorevisetheLTOPenabletemperaturemethodology.Adescriptionoftheamendmentrequest,necessarybackgroundinformation,justificationoftherequestedchanges,andnosignificanthazardsandenvironmentalconsiderationsareprovidedinAttachmentI.Thisevaluationdemonstratesthattheproposedchangesdonotinvolveasignificantchangeinthetypesorasignificantincreaseintheamountsofeffluentsoranychangeintheauthorizedpowerlevelofthefacility.Theproposedchangesalsodonotinvolveasignificanthazardsconsideration.'97050200SS9704~+PDRADQCK05000244PPDR

AmarkedupcopyoftheGinnaStationTechnicalSpecificationswhichshowtherequestedchangesissetforthinAttachmentII.TheproposedrevisedtechnicalspecificationsareprovidedinAttachmentIII.TherevisedPTLRisprovidedinAttachmentIV.AttachmentVcontainsaredlinedversionofthelowtemperatureoverpressureprotection(LTOP)setpointmethodologywithrespecttothecurrentlyapprovedversion.AttachmentVIcontainsafinalversionoftheLTOPsetpointmethodology.AttachmentVIIcontainsthefirstuseoftheLTOPenabletemperaturemethodologywhileAttachmentVIIIcontainsacopyofWCAP-14684asreferencedwithinthePTLR.WHEREFORE,ApplicantrespectfullyrequeststhatFacilityOperatingLicenseNo.DPR-18,andAttachmentAtothatlicense,beamendedintheformattachedheretoasAttachmentIII.RochesterGasandElectricCorporationByRobertC.MecredyVicePresidentNuclearOperationsSubscribedandsworntobeforemeonthis24thdayofApril1997.NotaryPublicDEBORAHA.PIPERNlNotaryPubiic)ntheStateofNewYorkONTARIOCOUNTYCouutuauonExpiresNov.23,19.~

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AttachmentIR.E.GinnaNuclearPowerPlantLicenseAmendmentRequestRevisionofReactorCoolantSystem(RCS)PressureandTemperatureLimitsReport(PTLR)AdministrativeControlsRequirementsThisattachmentprovidesadescriptionofthelicenseamendmentrequest(LAR)andthenecessaryjustificationstosupportarevisiontotheRCSpressureandtemperature(P/T)limitsandlowtemperatureoverpressureprotection(LTOP)limitscontainedinthePTLRasreferencedbytheAdministrativeControls.Thisattachmentisdividedintosixsectionsasfollows.SectionAsummarizesallchangestotheGinnaStationTechnicalSpecificationswhileSectionBprovidesthebackgroundandhistoryassociatedwiththechangesbeingrequested.SectionCprovidesthejustificationsassociatedwiththeseproposedchanges.AnosignificanthazardsconsiderationevaluationandenvironmentalconsiderationoftherequestedchangestotheGinnaStationTechnicalSpecificationsareprovidedinSectionsDandE,respectively.SectionFlistsallreferencesusedinthisattachment.A.DESCRIPTIONOFTECHNICALSPECIFICATIONCHANGESThisLARproposestorevisetheGinnaStationTechnicalSpecificationstoreflectanewPTLRintheAdministrativeControlssection.ThechangeissummarizedbelowandshowninAttachmentII,1.AdministrativeControls5.6.6ItemcwillberevisedtoreplacethereferencetotheMay23,1996NRCletterwithanewreferencethatapprovesthefirstuseofthePTLRmethodologyincludedasAttachmentVItothisLAR.Inaddition,reference1.isrevisedtoreferencethisLARasthesourceforthePTLRmethodologywhilereference2.isrevisedtoreferencethefinalNRCapprovedWCAP-14040-NP-AwhichisthebasisforthenewP/Tcurves.Reference3.isnolongerrequiredandisthereforedeleted.Finally,atypographicalerrorinitemdiscorrected.

B.BACKGROUNDDuringtheconversiontoimprovedstandardtechnicalspecifications(ISTS)forGinnaStation,RG&EproposedtorelocatetheLTOPandRCSP/TlimitstothePTLR(Ref.1).AssociatedwiththischangewastheadditionofareferencetotheAdministrativeControlssectionoftechnicalspecificationsrelatedtothePTLRdocumentingthemethodologyusedforallchangestotheselimits.However,theonlyNRCapprovedmethodologywouldbe"new"withrespecttodeterminationofboththeLTOPandRCSP/Tlimits.Duetotimeconstraints,RG&EinformedtheNRCthatuseofthisnewmethodologywouldbeburdensomeandinstead,RG&Ewishedtoretaintheexistingvalues.TheNRCagreedwiththisconcernandallowedtheexistinglimitstoberelocatedtothePTLRbutrequiredchangestotheselimitstobereviewedandapprovedbytheNRCasdocumentedinReference2.SubsequenttotheconversiontoISTS,theNRCcompleteditsreviewofthelatestreactorvesselcapsuledataandtheassociatedimpactonthepressurizedthermalshockevaluationforGinnaStation(Ref.3).IncorporationofthisinformationintothePTLRrequiredareassessmentoftheP/TcurvesandLTOPsetpointsthatareincludedinthePTLR.However,thefluencefactormethodologyusedfortheGinnaStationPTSevaluationwasanearlierversionthanthatrequiredbyWCAP-14040-NP-A(Ref.4)whichwastobethebasisfortheP/Tmethodology.Sinceanupdateoftheassociateddocumentscouldnotbecompletedinthetimeframerequiredtosupportstart-upfromthe1996refuelingoutage,theNRCapprovedaPTLRforuseatGinnaStationuntilDecember31,1996usinganestimatedfluencefactorvalue(Ref.5).Subsequenttothis,whileattemptingtocloseoutthefluencefactormethodologies,theNRCquestionedRG&E'sapproachfordeterminingLTOPenabletemperature.Specifically,theNRCidentifiedthatthedeterminationoftheLTOPenabletemperaturerequiredconsiderationofRCSliquidtemperaturemeasurementaccuracyperthemethodologycurrentlyspecifiedinSpecification5.6.6.Uponfurtherevaluation,RG&Eagreedtoaddressthisconcernbyfirstsubmittingareliefrequest(Ref.6)andthenbyrequestinganexemptiontoregulations(Ref.7).Subsequently,theNRCidentifiedthattheliquidtemperatureaccuracyquestionshouldbeinsteadaddressedbyanewLARwhichupdatedthemethodologyinSpecification5.6.6.ToallowRG&Esufficienttimetoaddressthisissue,thePTLRexpirationdatewaschangedtoJuly1,1997(Ref.8).

ThepurposeofthisLARistocompleteimplementationofGenericLetter96-03forGinnaStationandtorespondtotheJuly1,1997timelimitontheexistingPTLR.GenericLetter96-03requiresthatlicenseesreferencetheP/TandLTOPmethodologiesinthetechnicalspecificationsandprovideaproposedPTLRusingthemethodologyforNRCreview.Sections1,2,and4ofWCAP-14040-NP-A(Ref.4)havebeengenericallyapprovedforusebytheNRCforP/TlimitsandisbeingproposedastheP/Tlimitmethodology.ThecurrentLTOPmethodologyforGinnaStation(Ref.1)replacedthatprovidedinSection3ofWCAP-14040duetoRG&EspecificissuesandwaspreviouslyreviewedbytheNRCandfoundtobeacceptable(Ref.5).However,theLTOPenabletemperaturemethodologyisbeingrevisedtoclarifythespecificRCStemperatureaccuracyrequirementsandallowtheuseofASMEXICodeCaseN-514.AredlinedversionofthemethodologyshowingallchangesfromthepreviousNRCapprovedversionisprovidedinAttachmentVwhileafinalversionisprovidedinAttachmentVItothisLAR.Therefore,thisLARprovidesaproposedPTLR(andsupportingdocumentationasprovidedinWCAP-14684)andincludesareferencetoWCAP-14040-NP-AandthisLARintheAdministrativeControlsasthebasisforthemethodology.Itshouldbenotedthat'venthoughthetechnicalspecificationsdonotrequirereactorvesselmaterialinformationtobelocatedwithinthePTLR,thisinformationisprovidedconsistentwithGenericLetter96-03.ThisincludesarevisedRT~valuebasedontheattachedWCAP-14684.TherevisedRT~valuealsoincludeschangesmadeasaresultofadditionalsurveillancecapsulechemistryanalyses.C.JUSTIFICATIONOFCHANGESThissectionprovidesthejustificationforallchangesdescribedinSectionAaboveandshowninAttachmentII.Thejustificationsareorganizedbasedonwhetherthechangeis:morerestrictive(M),lessrestrictive(L),administrative(A),ortherequirementisrelocated(R).Thejustificationslistedbelowarealsoreferencedinthetechnicalspecification(s)whichareaffected(seeAttachmentII).C.1~dAdministrativeControlsSection5.6.6.cisrevisedtoreplacereferencetotheMay23,1996submittalwithanewreferencethatapprovesthefirstuseofthePTLRmethodology.Inaddition,theAdminstrativeControlscontentisrevisedconsistentwithGL96-03andthereferencesforPTLRmethodologywithrespecttoRCSP/Tlimitsisupdated.ThesechangesareadministrativeinnaturesincetheRCSP/TlimitswerepreviouslyrelocatedfromtechnicalspecificationstothePTLR.TheonlychangebeingrequestedistoupdatethePTLRconsistentwithgenericallyapprovedWCAP-14040-NP-AusedintheAdministrativeControlssection.

Spe4 2.AtypographicalerrorinAdministrativeControlsSection5.6.6.discorrectedtoprovideconsistencywithNUREG-1431.C.2AdministrativeControlsSection5.6.6.cisrevisedtoreplacethepreviouslyapprovedLTOPmethodology(Ref.1)withthatprovidedinAttachmentVI(AttachmentVprovidesa"red-line"comparisontothepreviouslyapprovedmethodologytoshowalldifferences).TheproposednewLTOPmethodologyallowstheLTOPenabletemperaturetobedeterminedusingASMESectionXICodeCaseN-514.ThiscodecaseallowstheLTOPenabletemperaturetobethehigherof:(1)aRCStemperatureof200'F,or(2)attheRCStemperaturecorrespondingtoareactorvesselmetaltemperatureatthe1/4thicknessfromtheinsidevesselsurfaceofRT~Y+50'F.ThisdiffersfromthecurrentspecifiedmethodologythatwasbasedonBranchTechnicalPositionRSB5-2whichrequiresusingaLTOPenabletemperatureofeither:(1)aRCStemperatureof200F,or(2)attheRCStemperaturecorrespondingtoareactorvesselmetaltemperatureatthe1/4thicknessfromtheinsidevesselsurfaceofRT~~+90'F,whicheverofthetwoisgreater.EffectivelyreducingtheLTOPenabletemperatureby40'FisacceptableduetothemargininherentintheASMESectionXI,AppendixGcalculationsusedinthedeterminationoftheRT~~value.ThiswasrecognizedbyASMEintheirapprovalofCodeCaseN-514onFebruary12,1992andincorporatingitintothe1993AddendatoASMECodeSectionXI,AppendixG.InstrumenterrormuststillbeaddressedwhendeterminingtheRCStemperaturecorrespondingtotheRT>>~+50Fenabletemperaturesetpoint.Therearenotanymorerestrictive(M),orrelocated(R)changesassociatedwiththisLAR.D.SIGNIFICANTHAZARDSCONSIDERATIONEVALUATIONTheproposedchangestotheGinnaStationTechnicalSpecificationsasidentifiedinSectionAandjustifiedinSectionChavebeenevaluatedwithrespectto10CFR50.92(c)andshowntonotinvolveasignificanthazardsconsiderationasdescribedbelow.ThissectionisorganizedbasedonSectionCabove.

eht'~i",iC}t~l.aOh D.1EvaluinofAdminirativehanTheadministrativechangesdiscussedinSectionC.1donotinvolveasignificanthazardsconsiderationasdiscussedbelow:OperationofGinnaStationinaccordancewiththeproposedchangesdoesnotinvolveasignificantincreaseintheprobabilityorconsequencesofanaccidentpreviouslyevaluated.TheproposedchangesreviseAdministrativeControlsSection5.6.6.ctoupdatethereferencetotheNRC'sapprovalofthefirstuseofthePTLRmethodology,updatetheRCSP/TmethodologytothefinalNRCapprovedversion,andtocorrectatypographicalerror.ThesechangescompleteimplementationofGenericLetter96-03byreferencingNRCapprovedmethodologywithintheAdministrativeControls.Assuch,thesechangesareadministrativeinnatureanddonotimpactinitiatorsoranalyzedeventsorassumedmitigationofaccidentortransientevents.Therefore,thesechangesdonotinvolveasignificantincreaseintheprobabilityorconsequencesofanaccidentpreviouslyanalyzed.2.OperationofGinnaStationinaccordancewiththeproposedchangesdoesnotcreatethepossibilityofanewordifferentlandofaccidentfromanyaccidentpreviouslyevaluated.Theproposedchangesdonotinvolveaphysicalalterationoftheplant(i.e.,nonewordifferenttypeofequipmentwillbeinstalled)orchangesinthemethodsgoverningnormalplantoperation.Theproposedchangeswillnotimposeanynewordifferentrequirements.Thus,thischangedoesnotcreatethepossibilityofanewordifferentkindofaccidentfromanyaccidentpreviouslyevaluated.3.OperationofGinnaStationinaccordancewiththeproposedchangesdoesnotinvolveasignificantreductioninamarginofsafety.TheproposedchangeswillnotreduceamarginofplantsafetybecausethemethodologyhavebeenshowntoensurethattheP/TandLTOPlimitsinthePTLRcontinuetomeetallnecessaryrequirementsforreactorvesselintegrity.ThesechangesareadministrativeinnaturesincethelimitswerepreviouslyrelocatedtothePTLRunderaseparateLAR.Assuch,noquestionofsafetyisinvolved,andthechangedoesnotinvolveasignificantreductioninamarginofsafety.Basedupontheaboveinformation,ithasbeendeterminedthattheproposedadministrativechangestotheGinnaStationTechnicalSpecificationsdonotinvolveasignificantincreaseintheprobabilityorconsequencesofanaccidentpreviouslyevaluated,doesnotcreatethepossibilityofanewordifferentkindofaccidentpreviouslyevaluated,anddoesnotinvolveasignificantreductioninamarginofsafety.Therefore,itisconcludedthattheproposedchangesmeettherequirementsof10CFR50.92(c)anddonotinvolveasignificanthazardsconsideration.

D.2vlinfRriivhnThelessrestrictivechangesdiscussedinSectionC.2donotinvolveasignificanthazardsconsiderationasdiscussedbelow:OperationofGinnaStationinaccordancewiththeproposedchangesdoesnotinvolveasignificantincreaseintheprobabilityorconsequencesof.anaccidentpreviouslyevaluated.TheproposedchangerevisesAdministrativeControlsSection5.6.6toreplacetheLTOPenabletemperaturemethodologywithuseofASMESectionXICodeCaseN-514.ThiscodecaseeffectivelyreducestheLTOPenabletemperaturebyupto40'Foverthecurrentmethodology.However,asshowninSectionC.2,sufficientmarginremainswithintheLTOPenabletemperaturecalculationtoensurethatthereactorvesselremainsintactfollowingallanalyzedevents.Therefore,thesechangesdonotinvolveasignificantincreaseintheprobabilityorconsequencesofanaccidentpreviouslyanalyzed.2.OperationofGinnaStationinaccordancewiththeproposedchangesdoesnotcreatethepossibilityofanewordifferentkindofaccidentfromanyaccidentpreviouslyevaluated.Theproposedchangesdonotinvolveaphysicalalterationoftheplant(i.e.,nonewordifferenttypeofequipmentwillbeinstalled)orchangesinthemethodsgoverningnormalplantoperation.Theproposedchangeswillnotimposeanynewordifferentrequirements.Thus,thischangedoesnotcreatethepossibilityofanewordifferentkindofaccidentfromanyaccidentpreviouslyevaluated.3.OperationofGinnaStationinaccordancewiththeproposedchangesdoesnotinvolveasignificantreductioninamarginofsafety.TheproposedchangeswillnotreduceamarginofplantsafetybecausethemethodologyhasbeenshowntoensurethattheLTOPlimitsinthePTLRcontinuetomeetallnecessaryrequirementsforreactorvesselintegrity.TheASMECodespecificallyrecognizesthatCodeCaseN-514providesnecessarymarginsuchthatthechangedoesnotinvolveasignificantreductioninamarginofsafety.Basedupontheaboveinformation,ithasbeendeterminedthattheproposedlessrestrictivechangetotheGinnaStationTechnicalSpecificationsdonotinvolveasignificantincreaseintheprobabilityorconsequencesofanaccidentpreviouslyevaluated,doesnotcreatethepossibilityofanewordifferentkindofaccidentpreviouslyevaluated,anddoesnotinvolveasignificantreductioninamarginofsafety.Therefore,itisconcludedthattheproposedchangesmeettherequirementsof10CFR50.92(c)anddonotinvolveasignificanthazardsconsideration.

'Et\Ab E.ENVIRONMENTALCONSIDERATIONRG&Ehasevaluatedtheproposedchangesanddeterminedthat:1.ThechangesdonotinvolveasignificanthazardsconsiderationasdocumentedinSectionDabove;2.Thechangesdonotinvolveasignificantchangeinthetypesorsignificantincreaseintheamountsofanyeffluentsthatmaybereleasedoffsitesincenospecificationsrelatedtooffsitereleasesareaffected;and3.ThechangesdonotinvolveasignificantincreaseinindividualorcumulativeoccupationalradiationexposuresincenonewordifferenttypeofequipmentarerequiredtobeinstalledasaresultofthisLAR.Accordingly,theproposedchangesmeettheeligibilitycriteriaforcategoricalexclusionsetforthin10CFR51.22(c)(9).Therefore,pursuantto10CFR51.22(b),anenvironmentalassessmentoftheproposedchangesisnotrequired.F.REFERENCESLetterfromR.C.Mecredy,RG&E,toA.R.Johnson,NRC,

Subject:

TechnicalSpectJicationsImprovementProgram,ReactorCoolantSystem(RCS)PressureandTemperatureLimitsReport(PTLR),datedDecember8,1995.2.LetterfromL.B.Marsh,NRC,toR.C.Mecredy,RG&E,

Subject:

R.E.Ginna-AcceptanceforReferencingofPressureTemperatureLimitsReport(TACNo.M92320),datedDecember26,1995.3.LetterfromA.R.,Johnson,NRC,toR.C.Mecredy,RG&E,

Subject:

R.E.GinnaNuclearPowerPlant-PressurizedThermalShockEvaluation(TACNo.M93827),datedMarch22,1996.4.WCAP-14040-NP-A,MethodologyUsedtoDevelopColdOverpressureMitigatingSystemSetpointsandRCSHeatupandCooldownLimitCurves,January1996.5.LetterfromG.S.VissingNRC,toR.C.Mecredy,RG&E,

Subject:

IssuanceofAmendmentNo.64toFacilityOperatingLicenseNo.DPR-I8,R.E.GinnaNuclearPowerPlant(TACNo.M94770),datedMay23,1996.6.LetterfromR.C.Mecredy,RG&E,toG.S.Vissing,NRC,

Subject:

RequesttoUseASMECodeCaseN-514intheDeterminationofLowTemperatureOverpressureProtection(LTOP)EnableTemperature,datedDecember18,1996.

0 LetterfromR.C.Mecredy,RG&E,toG.S.Vissing,NRC,

Subject:

RequestforExemptionto10CFR50.60toUseAmericanSocietyofMechanicalEngineers(ASME)CodeCaseN-514intheDeterminationofLowTemperatureOverpressureProtection(LTOP)EnableTemperature,datedFebruary10,1997.LetterfromG.S.Vissing,NRC,toR.C.Mecredy,RG&E,Subject;R.E.Ginna-AcceptanceofRequesttoExtendTimeforApprovalofRevisionofPressureandTemperatureLimitsReport(PTLR)PACNo.M97313),datedDecember10,1996.-8-