ML17264B043

Application for Amend to License DPR-18,revising Administrative Controls W/Respect to RCS Pressure & Temp Limits Rept

ML17264B043
Person / Time
Site:	Ginna
Issue date:	09/29/1997
From:	MECREDY R C ROCHESTER GAS & ELECTRIC CORP.
To:
Shared Package
ML17264B042	List: ML17264B041 ML17264B043 ML17264B044 ML17264B045
References
NUDOCS 9710020173
Download: ML17264B043 (13)

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UNITEDSTATESOFAMERICANUCLEARREGULATORYCOMMISSIONIntheMatterofRochesterGasandElectricCorporation(R.E.GinnaNuclearPowerPlant))))DocketNo.50-244)APPLICATIONFORAMENDMENTPursuanttoSection50.90oftheregulationsoftheU.S.NuclearRegulatoryCommission(NRC),RochesterGasandElectricCorporation(RG&E),holderofFacilityOperatingLicenseNo.DPR-18,herebyrequeststhattheTechnicalSpecificationssetforthinAppendixAtothat~~license,beamended.ThisrequestforchangeistorevisetheAdministrativeControlswithrespecttotheReactorCoolantSystem(RCS)PressureandTemperatureLimitsReport(PTLR)tomakethenecessarychangesinorderplacethisdocumentunderlicenseecontrol,makeseveralchangestothePTLR,andtorevisetheLTOPenabletemperaturemethodology.Adescriptionoftheamendmentrequest,necessarybackgroundinformation,justificationoftherequestedchanges,andanosignificanthazardsandenvironmentalconsiderationsareprovidedinAttachmentI.Thisevaluationdemonstratesthattheproposedchangesdonotinvolveasignificantchangeinthetypesorasignificantincreaseintheamountsofeffluentsoranychangeintheauthorizedpowerlevelofthefacility.Theproposedchangesalsodonotinvolveasignificanthazardsconsideration.97<0Dggg05000244020%73970929PDRADPDRp

AmarkedupcopyoftheGinnaStationTechnicalSpecificationswhichshowtherequestedchangesissetforthinAttachmentII.TheproposedrevisedtechnicalspecificationsareprovidedinAttachmentIII.TherevisedPTLRisprovidedinAttachmentIV.AttachmentVcontainsaredlinedversionofthelowtemperatureoverpressureprotection(LTOP)setpointmethodologywithrespecttothecurrentlyapprovedversion.AttachmentVIcontainsafinalversionoftheLTOPsetpointmethodology.AttachmentVIIcontainsthefirstuseoftheLTOPenabletemperaturemethodologywhileAttachmentVIIIcontainsa'copyofWCAP-14684asreferencedwithinthePTLR.AttachmentIXcontainsresponsestoNRCquestionsconcerningtheGinnaStationLTOPanalysis.WHEREFORE,ApplicantrespectfullyrequeststhatFacilityOperatingLicenseNo.DPR-18,andAttachmentAtothatlicense,beamendedintheformattachedheretoasAttachmentIII.RochesterGasandElectricCorporationByRobertC.MecredyVicePresidentNuclearOperationsSubscribedandsworntobeforemeonthis29thdayofSeptember1997.NotaryPublicDEBORAHA.PIPERNINotaryPublicmtheStateofNmYorkONTARIOCOUNTYCommasonExpiresNov.23,19,3.3

~I AttachmentIR.E.GinnaNuclearPowerPlantLicenseAmendmentRequestRevisionofReactorCoolantSystem(RCS)PressureandTemperatureLimitsReport(PTLR)AdministrativeControlsRequirementsThisattachmentprovidesadescriptionofthelicenseamendmentrequest(LAR)andthenecessaryjustificationstosupportarevisiontotheGinnaStationPTLRandrelatedrequirementscontainedwithintheAdministrativeControlssectionoftechnicalspecifications.Thisattachmentisdividedintosixsectionsasfollows.SectionAsummarizesallchangestotheGinnaStationTechnicalSpecificationswhileSectionBprovidesthebackgroundandhistoryassociatedwiththechangesbeingrequested.SectionCprovidesthejustificationsassociatedwiththeseproposedchanges.AnosignificanthazardsconsiderationevaluationandenvironmentalconsiderationoftherequestedchangestotheGinnaStationTechnicalSpecificationsareprovidedinSectionsDandE,respectively.SectionFlistsallreferencesusedinthisattachment.A.DESCRIPTIONOFTECHNICALSPECIFICATIONCHANGESThisLARproposestorevisetheGinnaStationTechnicalSpecificationstoreflectanewPTLRintheAdministrativeControlssection.ThechangeissummarizedbelowandshowninAttachmentII.1.AdministrativeControls5.6.6ItemcwillberevisedtoicplacethereferencetotheMay23,1996NRCletterwithanewNRCreferencethatapprovesthefirstuseofthePTLRmethodologyincludedasAttachmentVItothisLAR.Inaddition,Reference1isrevisedtoreferencethisLARasthesourceforthelowtemperatureoverpressureprotection(LTOP)methodologywhileReference2isrevisedtoreferencethefinalNRCapprovedWCAP-14040-NP-AwhichisthebasisforthenewP/Tcurves.Reference3isnolongerrequiredandisthereforedeleted.Finally,atypographicalerrorinitemdiscorrected.

BACKGROUNDDuringtheconversiontoimprovedstandardtechnicalspecifications(ISTS)forGinnaStation,RG&EproposedtorelocatetheLTOPandRCSpressureandtemperature(P/T)limitstothePTLR(Ref.1).AssociatedwiththischangewastheadditionofareferencetotheAdministrativeControlssectionoftechnicalspecificationsrelatedtothePTLRdocumentingtheNRCapprovalofthemethodologyusedinthePTLR.However,theonlyNRCapprovedmethodologywouldbe"new"withrespecttodeterminationofboththeLTOPandRCSP/TlimitsatGinnaStation.Duetotimeconstraints,RG&EinformedtheNRCthatuseofthisnewmethodologywouldbeburdensomeandinstead,RG&Ewishedtoretaintheexistingvalues.TheNRCagreedwiththisconcernandallowedtheexistinglimitstoberelocatedtothePTLRbutrequiredchangestotheselimitstobereviewedandapprovedbytheNRCasdocumentedinReference2.SubsequenttotheconversiontoISTS,theNRCcompleteditsreviewofthelatestreactorvesselcapsuledataandtheassociatedimpactonthepressurizedthermalshock(PTS)evaluationforGinnaStation(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,theNRCidentifiedthattheliquidtemperatureaccuracyquestionshouldbeinsteadaddressedbyanewLARwhichupdatedthemethodologyinSpecification5.6.6andincorporatedanexemptionto10CFR50.60(Ref.8).ToallowRG&Esufficienttimetoaddressthisissue,thePTLRexpirationdatewaschangedtoDecember31,1997(Ref.9).

ThepurposeofthisLARistocompleteimplementationofGenericLetter96-03forGinnaStationandtorespondtotheDecember31,1997timelimitontheexistingPTLR.GenericLetter96-03requiresthatlicenseesreferencetheP/TandLTOPmethodologiesinthetechnicalspecificationsandprovideaproposedPTLRusingthemethodologyforNRCreview.Sections1,2,and4ofWCAP-14040-NP-A(Ref.4)havebeengenericallyapprovedforusebytheNRCforP/TlimitsandisbeingproposedastheP/TlimitmethodologyforGinnaStation.ThecurrentLTOPmethodologyforGinnaStation(Ref.1)replacedthatprovidedinSection3ofWCAP-14040duetoRGBspecificissuesandwaspreviouslyreviewedbytheNRCandfoundtobeacceptable(Ref.5).However,theLTOPenabletemperaturemethodologyisbeingrevisedtoclarifythespecificRCStemperatureaccuracyrequirementsandallowtheuseofASMEXICodeCaseN-514fortemperaturedetermination(Ref.8).AredlinedversionoftheLTOPmethodologyshowingallchangesfromthepreviousNRCapprovedversionisprovidedinAttachmentVwhileafinalversionisprovidedin.AttachmentVItothisLAR.Therefore,thisLARprovidesaproposedPTLR(andsupportingdocumentationasprovidedinWCAP-14684)andincludesareferencetoWCAP-14040-NP-AandthisLARintheAdministrativeControlsasthebasisforthemethodology.ItshouldbenotedthateventhoughthetechnicalspecificationsdonotrequirereactorvesselmaterialinformationtobelocatedwithinthePTLR,thisinformationisprovidedconsistentwithGenericLetter96-03.ThisincludesarevisedRT~,valuebasedontheattachedWCAP-14684.TherevisedRT~valuealsoincludeschangesmadeasaresultofadditionalsurveillancecapsulechemistryanalyses.C.JUSTIFICATIONOFCHANGESThissectionprovidesthejustificationforallchangesdescribedinSectionAaboveandshowninAttachmentII.Thejustificationsareorganizedbasedonwhetherthechangeis:morerestrictive(M),lessrestrictive(L),administrative(A),ortherequirementisrelocated(R).Thejustificationslistedbelowarealsoreferencedinthetechnicalspecification(s)whichareaffected(seeAttachmentII).

C.1AdministrativeControlsSection5.6.6.cisrevisedto:(1)replacereferencetotheMay23,1996submittalwithanewreferencethatapprovesthefirstuseofthePTLRmethodologyascontainedinAttachmentVItothisLAR;(2)updatetheAdminstrativeControlscontentconsistent.withGL96-03;and,(3)updatethereferencesforPTLRmethodologywithrespecttoRCSP/Tlimits.Item(1)onlychangesthedateoftheNRCapprovalofthePTLR,includingthePTLRmethodologysinceGinnaStationcurrentlyhasaNRCapprovedPTLR.Item(2)makestheGinnaStationTechnicalSpecificationsconsistentwithISTSinorderforthelicenseetomakefuturechangeswithoutNRCreviewandapproval.Item(3)updatesthePTLRmethodologyusedforP/TlimitstoreferenceWCAP-14040-NP-AinsteadofreferencingWCAP-14040andtheassociatedNRCapprovalletter(i.e.,WCAP-14040-NP-AincludestheNRCapprovalletterandallNRCrequiredchanges).ThesethreechangesareadministrativeinnaturesincetheRCSP/TlimitswerepreviouslyrelocatedfromtechnicalspecificationstothePTLR;onlyminordetailsarebeingclarified.2.AdministrativeControlsSection5.6.6.c.lisrevisedtoreplacethepreviouslyapprovedLTOPmethodology(Ref.1)withthatprovidedinAttachmentVItothisLAR(AttachmentVprovidesa"red-line"comparisontothepreviouslyapprovedmethodologytoshowalldifferences).TheonlydifferenceintheproposednewLTOPmethodologyfromthatapprovedpreviouslyistoprovideadditionalclarificationsconsistentwithNRCandRG&EcommunciationsandtoallowtheLTOPenabletemperatureandpressurelimitstobedeterminedusingASMESectionXICodeCaseN-514.ThiscodecasedesignatestheallowablereactorcoolantpressureboundarypressureduringLTOPeventstobe110%ofthatspecifiedby10CFR50,AppendixG.Useofthiscodecaserequiresanexemptionto10CFR50.60whichwasgrantedtoRG&EinReference8.Therefore,thischangeincorporatestheuseofCodeCaseN-514intotheLTOPmethodologyspecifiedwithintheAdminstrativeControlssectionofTechnicalSpecificationsconsistentwithReference8.3.AtypographicalerrorinAdministrativeControlsSection5.6.6.discorrectedtoprovideconsistencywithNUREG-1431.Therearenotanymorerestrictive(M),lessrestrictive(L),orrelocated(R)changesassociatedwiththisLAR.

D.SIGNIFICANTHAZARDSCONSIDERATIONEVALUATIONTheproposedchangestotheGinnaStationTechnicalSpecificationsasidentifiedinSectionAandjustifiedinSectionChavebeenevaluatedwithrespectto10CFR50.92(c)andshowntonotinvolveasignificanthazardsconsiderationasdescribedbelow.ThissectionisorganizedbasedonSectionCabove.D.1TheadministrativechangesdiscussedinSectionC.1donotinvolveasignificanthazardsconsiderationasdiscussedbelow:OperationofGinnaStationinaccordance,withtheproposedchangesdoesnotinvolveasignificantincreaseintheprobabilityorconsequencesofanaccidentpreviouslyevaluated.TheproposedchangesreviseAdministrativeControlsSection5.6.6.ctoupdatethereferencetotheNRC'sapprovalofthefirstuseofthePTLRmethodology,updatetheRCSP/TmethodologytothefinalNRCapprovedversion,allowuseofASMECodeCaseN-514forLTOPenabletemperaturemethodology,andtocorrectatypographicalerror.ThesechangescompleteimplementationofGenericLetter96-03byreferencingNRCapprovedmethodologywithintheAdministrativeControls.TheupdatedRCSP/TmethodologyhasbeengenericallyapprovedbytheNRCwhiletheuseofASMECodeCaseN-514forLTOPenabletemperaturemethodologywaspreviouslyapprovedforuseatGinnaStationbytheNRC.Assuch,thesechangesareadministrativeinnatureanddonotimpactinitiatorsoranalyzedeventsorassumedmitigationofaccidentortransientevents.Therefore,thesechangesdonotinvolveasignificantincreaseintheprobabilityorconsequencesofanaccidentpreviouslyanalyzed.2.OperationofGinnaStationinaccordancewiththeproposedchangesdoesnotcreatethepossibilityofanewordifferentkindofaccidentfromanyaccidentpreviouslyevaluated.Theproposedchangesdonotinvolveaphysicalalterationoftheplant(i.e.,nonewordifferenttypeofequipmentwillbeinstalled)orchangesinthemethodsgoverningnormalplantoperation.Theproposedchangeswillnotimposeanynewordifferentrequirements.Thus,thischangedoesnotcreatethepossibilityofanewordifferentkindofaccidentfromanyaccidentpreviouslyevaluated.

3.OperationofGinnaStationinaccordancewiththeproposedchangesdoesnotinvolveasignificantreductioninamarginofsafety.TheproposedchangeswillnoteduceamarginofplantsafetybecausethemethodologyhavebeenshowntoensurethattheP/TandLTOPlimitsinthePTLRcontinuetomeetallnecessaryrequirementsforreactorvesselintegrity.ThesechangesareadministrativeinnaturesincethelimitswerepreviouslyrelocatedtothePTLRunderaseparateLAR.Assuch,noquestionofsafetyisinvolved,andthechangedoesnotinvolveasignificantreductioninamarginofsafety.Basedupontheaboveinformation,ithasbeendeterminedthattheproposedadministrativechangestotheGinnaStationTechnicalSpecificationsdonotinvolveasignificantincreaseintheprobabilityorconsequencesofanaccidentpreviouslyevaluated,doesnotcreatethepossibilityofanewordifferentkindofaccidentpreviouslyevaluated,anddoesnotinvolveasignificantreductioninamarginofsafety.Therefore,itisconcludedthattheproposedchangesmeettherequirementsof10CFR50.92(c)anddonotinvolveasignificanthazardsconsideration.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:

TechnicalSpectjicatt'onsImprovementProgram,ReactorCoolantSystem(RCS)PressureandTemperatureLimitsReport(PTLR),datedDecember8,1995.

LetterfromL.B.Marsh,NRC,toR.C.Mecredy,RG&B,

Subject:

R.E.Ginna-AcceptanceforReferencingofPressureTemperatureLimitsReport(TACNo.M92320),datedDecember26,1995.LetterfromA.R.Johnson,NRC,toR.C.Mecredy,RG&B,

Subject:

R.E.GinnaNuclearPowerPlant-PressurizedThermal'ShockEvaluation(TACNo.M93827),datedMarch22,1996.WCAP-14040-NP-A,MethodologyUsedtoDevelopColdOverpressureMitigatingSystemSetpointsandRCSHeatupandCooldownLimitCurves,January1996.LetterfromG.S.VissingNRC,toR.C.Mecredy,RG&E,

Subject:

IssuanceofAmendmentNo.6'4toFacilityOperatingLicenseNo.DPR-I8,R.E.GinnaNuclearPowerPlant(TACNo.M94770),datedMay23,1996.LetterfromR.C.Mecredy,RG&B,toG.S.Vissing,NRC,

Subject:

RequesttoUseASMECodeCaseN-514intheDeterminationofLowTemperatureOverpressureProtection(LTOP)EnableTemperature,datedDecember18,1996.LetterfromR.C.Mecredy,RG&E,toG.S.Vissing,NRC,

Subject:

RequestforExemprionto10CFR50.60toUseAmericanSocietyofMechanicalEngineers(ASME)CodeCaseN-514intheDeterminationofLowTemperatureOverpressureProtection(LTOP)EnableTemperature,datedFebruary10,1997.LetterfromG.S.Vissing,NRC,toR.C.Mecredy,RG&B,

Subject:

ExemptionfronttheRequirementsof10CFRPart50.60,AcceptanceCriteriaforFracturePreventionMeasuresforLightwaterNuclearPowerReactorsforNormalOperation-R.E.GinnaNuclearPlant(TACNo.M98993),datedJuly28,1997.LetterfromG.S.Vissing,NRC,toR.C.Mecredy,RG&E,

Subject:

R.E.Ginna-AcceptanceofRequesttoExtendTimeforApprovalofRevisionofPressureandTemperatureLimitsReport(PTLR)(TACNo.M97313),datedDecember10,1996.

AttachmentIIMarkedUpCopyofR.E.GinnaNuclearPowerPlantTechnicalSpecificationsIncludedPages:5.0-22