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{{#Wiki_filter: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  
{{#Wiki_filter:UNITEDSTATESOFAMERICANUCLEARREGULATORY COMMISSION IntheMatterofRochester GasandElectricCorporation (R.E.GinnaNuclearPowerPlant))))DocketNo.50-244)APPLICATION FORAMENDMENT PursuanttoSection50.90oftheregulations oftheU.S.NuclearRegulatory Commission (NRC),Rochester GasandElectricCorporation (RG&E),holderofFacilityOperating LicenseNo.DPR-18,herebyrequeststhattheTechnical Specifications setforthinAppendixAtothat~~license,beamended.ThisrequestforchangeistorevisetheAdministrative ControlswithrespecttotheReactorCoolantSystem(RCS)PressureandTemperature LimitsReport(PTLR)tomakethenecessary changesinorderplacethisdocumentunderlicenseecontrol,makeseveralchangestothePTLR,andtorevisetheLTOPenabletemperature methodology.
Adescription oftheamendment request,necessary background information, justification oftherequested changes,andanosignificant hazardsandenvironmental considerations areprovidedinAttachment I.Thisevaluation demonstrates thattheproposedchangesdonotinvolveasignificant changeinthetypesorasignificant increaseintheamountsofeffluents oranychangeintheauthorized powerlevelofthefacility.
Theproposedchangesalsodonotinvolveasignificant hazardsconsideration.
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  
AmarkedupcopyoftheGinnaStationTechnical Specifications whichshowtherequested changesissetforthinAttachment II.Theproposedrevisedtechnical specifications areprovidedinAttachment III.TherevisedPTLRisprovidedinAttachment IV.Attachment Vcontainsaredlinedversionofthelowtemperature overpressure protection (LTOP)setpointmethodology withrespecttothecurrently approvedversion.Attachment VIcontainsafinalversionoftheLTOPsetpointmethodology.
~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.
Attachment VIIcontainsthefirstuseoftheLTOPenabletemperature methodology whileAttachment VIIIcontainsa'copyofWCAP-14684 asreferenced withinthePTLR.Attachment IXcontainsresponses toNRCquestions concerning theGinnaStationLTOPanalysis.
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).
WHEREFORE, Applicant respectfully requeststhatFacilityOperating LicenseNo.DPR-18,andAttachment Atothatlicense,beamendedintheformattachedheretoasAttachment III.Rochester GasandElectricCorporation ByRobertC.MecredyVicePresident NuclearOperations Subscribed andsworntobeforemeonthis29thdayofSeptember 1997.NotaryPublicDEBORAHA.PIPERNI NotaryPublicmtheStateofNmYorkONTARIOCOUNTYCommasonExpiresNov.23,19,3.3  
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).
~I Attachment IR.E.GinnaNuclearPowerPlantLicenseAmendment RequestRevisionofReactorCoolantSystem(RCS)PressureandTemperature LimitsReport(PTLR)Administrative ControlsRequirements Thisattachment providesadescription ofthelicenseamendment request(LAR)andthenecessary justifications tosupportarevisiontotheGinnaStationPTLRandrelatedrequirements contained withintheAdministrative Controlssectionoftechnical specifications.
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.
Thisattachment isdividedintosixsectionsasfollows.SectionAsummarizes allchangestotheGinnaStationTechnical Specifications whileSectionBprovidesthebackground andhistoryassociated withthechangesbeingrequested.
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.
SectionCprovidesthejustifications associated withtheseproposedchanges.Anosignificant hazardsconsideration evaluation andenvironmental consideration oftherequested changestotheGinnaStationTechnical Specifications areprovidedinSectionsDandE,respectively.
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,
SectionFlistsallreferences usedinthisattachment.
A.DESCRIPTION OFTECHNICAL SPECIFICATION CHANGESThisLARproposestorevisetheGinnaStationTechnical Specifications toreflectanewPTLRintheAdministrative Controlssection.Thechangeissummarized belowandshowninAttachment II.1.Administrative Controls5.6.6Itemcwillberevisedtoicplacethereference totheMay23,1996NRCletterwithanewNRCreference thatapprovesthefirstuseofthePTLRmethodology includedasAttachment VItothisLAR.Inaddition, Reference 1isrevisedtoreference thisLARasthesourceforthelowtemperature overpressure protection (LTOP)methodology whileReference 2isrevisedtoreference thefinalNRCapprovedWCAP-14040-NP-A whichisthebasisforthenewP/Tcurves.Reference 3isnolongerrequiredandistherefore deleted.Finally,atypographical errorinitemdiscorrected.
BACKGROUND Duringtheconversion toimprovedstandardtechnical specifications (ISTS)forGinnaStation,RG&EproposedtorelocatetheLTOPandRCSpressureandtemperature (P/T)limitstothePTLR(Ref.1).Associated withthischangewastheadditionofareference totheAdministrative Controlssectionoftechnical specifications relatedtothePTLRdocumenting theNRCapprovalofthemethodology usedinthePTLR.However,theonlyNRCapprovedmethodology wouldbe"new"withrespecttodetermination ofboththeLTOPandRCSP/TlimitsatGinnaStation.Duetotimeconstraints, RG&EinformedtheNRCthatuseofthisnewmethodology wouldbeburdensome andinstead,RG&Ewishedtoretaintheexistingvalues.TheNRCagreedwiththisconcernandallowedtheexistinglimitstoberelocated tothePTLRbutrequiredchangestotheselimitstobereviewedandapprovedbytheNRCasdocumented inReference 2.Subsequent totheconversion toISTS,theNRCcompleted itsreviewofthelatestreactorvesselcapsuledataandtheassociated impactonthepressurized thermalshock(PTS)evaluation forGinnaStation(Ref.3).Incorporation ofthisinformation intothePTLRrequiredareassessment oftheP/TcurvesandLTOPsetpoints thatareincludedinthePTLR.However,thefluencefactormethodology usedfortheGinnaStationPTSevaluation wasanearlierversionthanthatrequiredbyWCAP-14040-NP-A (Ref.4)whichwastobethebasisfortheP/Tmethodology.
Sinceanupdateoftheassociated documents couldnotbecompleted inthetimeframerequiredtosupportstart-upfromthe1996refueling outage,theNRCapprovedaPTLRforuseatGinnaStationuntilDecember31,1996usinganestimated fluencefactorvalue(Ref.5).Subsequent tothis,whileattempting tocloseoutthefluencefactormethodologies, theNRCquestioned RG&E'sapproachfordetermining LTOPenabletemperature.
Specifically, theNRCidentified thatthedetermination oftheLTOPenabletemperature requiredconsideration ofRCSliquidtemperature measurement accuracyperthemethodology currently specified inSpecification 5.6.6.Uponfurtherevaluation, RG&Eagreedtoaddressthisconcernbyfirstsubmitting areliefrequest(Ref.6)andthenbyrequesting anexemption toregulations (Ref.7).Subsequently, theNRCidentified thattheliquidtemperature accuracyquestionshouldbeinsteadaddressed byanewLARwhichupdatedthemethodology inSpecification 5.6.6andincorporated anexemption to10CFR50.60(Ref.8).ToallowRG&Esufficient timetoaddressthisissue,thePTLRexpiration datewaschangedtoDecember31,1997(Ref.9).
ThepurposeofthisLARistocompleteimplementation ofGenericLetter96-03forGinnaStationandtorespondtotheDecember31,1997timelimitontheexistingPTLR.GenericLetter96-03requiresthatlicensees reference theP/TandLTOPmethodologies inthetechnical specifications andprovideaproposedPTLRusingthemethodology forNRCreview.Sections1,2,and4ofWCAP-14040-NP-A (Ref.4)havebeengenerically approvedforusebytheNRCforP/TlimitsandisbeingproposedastheP/Tlimitmethodology forGinnaStation.ThecurrentLTOPmethodology forGinnaStation(Ref.1)replacedthatprovidedinSection3ofWCAP-14040 duetoRGBspecificissuesandwaspreviously reviewedbytheNRCandfoundtobeacceptable (Ref.5).However,theLTOPenabletemperature methodology isbeingrevisedtoclarifythespecificRCStemperature accuracyrequirements andallowtheuseofASMEXICodeCaseN-514fortemperature determination (Ref.8).AredlinedversionoftheLTOPmethodology showingallchangesfromthepreviousNRCapprovedversionisprovidedinAttachment Vwhileafinalversionisprovidedin.Attachment VItothisLAR.Therefore, thisLARprovidesaproposedPTLR(andsupporting documentation asprovidedinWCAP-14684) andincludesareference toWCAP-14040-NP-A andthisLARintheAdministrative Controlsasthebasisforthemethodology.
Itshouldbenotedthateventhoughthetechnical specifications donotrequirereactorvesselmaterialinformation tobelocatedwithinthePTLR,thisinformation isprovidedconsistent withGenericLetter96-03.ThisincludesarevisedRT~,valuebasedontheattachedWCAP-14684.
TherevisedRT~valuealsoincludeschangesmadeasaresultofadditional surveillance capsulechemistry analyses.
C.JUSTIFICATION OFCHANGESThissectionprovidesthejustification forallchangesdescribed inSectionAaboveandshowninAttachment II.Thejustifications areorganized basedonwhetherthechangeis:morerestrictive (M),lessrestrictive (L),administrative (A),ortherequirement isrelocated (R).Thejustifications listedbelowarealsoreferenced inthetechnical specification(s) whichareaffected(seeAttachment II).
C.1Administrative ControlsSection5.6.6.cisrevisedto:(1)replacereference totheMay23,1996submittal withanewreference thatapprovesthefirstuseofthePTLRmethodology ascontained inAttachment VItothisLAR;(2)updatetheAdminstrative Controlscontentconsistent.
withGL96-03;and,(3)updatethereferences forPTLRmethodology withrespecttoRCSP/Tlimits.Item(1)onlychangesthedateoftheNRCapprovalofthePTLR,including thePTLRmethodology sinceGinnaStationcurrently hasaNRCapprovedPTLR.Item(2)makestheGinnaStationTechnical Specifications consistent withISTSinorderforthelicenseetomakefuturechangeswithoutNRCreviewandapproval.
Item(3)updatesthePTLRmethodology usedforP/Tlimitstoreference WCAP-14040-NP-Ainsteadofreferencing WCAP-14040 andtheassociated NRCapprovalletter(i.e.,WCAP-14040-NP-A includestheNRCapprovalletterandallNRCrequiredchanges).
Thesethreechangesareadministrative innaturesincetheRCSP/Tlimitswerepreviously relocated fromtechnical specifications tothePTLR;onlyminordetailsarebeingclarified.
2.Administrative ControlsSection5.6.6.c.l isrevisedtoreplacethepreviously approvedLTOPmethodology (Ref.1)withthatprovidedinAttachment VItothisLAR(Attachment Vprovidesa"red-line" comparison tothepreviously approvedmethodology toshowalldifferences).
Theonlydifference intheproposednewLTOPmethodology fromthatapprovedpreviously istoprovideadditional clarifications consistent withNRCandRG&Ecommunciations andtoallowtheLTOPenabletemperature andpressurelimitstobedetermined usingASMESectionXICodeCaseN-514.Thiscodecasedesignates theallowable reactorcoolantpressureboundarypressureduringLTOPeventstobe110%ofthatspecified by10CFR50,AppendixG.Useofthiscodecaserequiresanexemption to10CFR50.60whichwasgrantedtoRG&EinReference 8.Therefore, thischangeincorporates theuseofCodeCaseN-514intotheLTOPmethodology specified withintheAdminstrative ControlssectionofTechnical Specifications consistent withReference 8.3.Atypographical errorinAdministrative ControlsSection5.6.6.discorrected toprovideconsistency withNUREG-1431.
Therearenotanymorerestrictive (M),lessrestrictive (L),orrelocated (R)changesassociated withthisLAR.
D.SIGNIFICANT HAZARDSCONSIDERATION EVALUATION TheproposedchangestotheGinnaStationTechnical Specifications asidentified inSectionAandjustified inSectionChavebeenevaluated withrespectto10CFR50.92(c)andshowntonotinvolveasignificant hazardsconsideration asdescribed below.Thissectionisorganized basedonSectionCabove.D.1Theadministrative changesdiscussed inSectionC.1donotinvolveasignificant hazardsconsideration asdiscussed below:Operation ofGinnaStationinaccordance, withtheproposedchangesdoesnotinvolveasignificant increaseintheprobability orconsequences ofanaccidentpreviously evaluated.
TheproposedchangesreviseAdministrative ControlsSection5.6.6.ctoupdatethereference totheNRC'sapprovalofthefirstuseofthePTLRmethodology, updatetheRCSP/Tmethodology tothefinalNRCapprovedversion,allowuseofASMECodeCaseN-514forLTOPenabletemperature methodology, andtocorrectatypographical error.Thesechangescompleteimplementation ofGenericLetter96-03byreferencing NRCapprovedmethodology withintheAdministrative Controls.
TheupdatedRCSP/Tmethodology hasbeengenerically approvedbytheNRCwhiletheuseofASMECodeCaseN-514forLTOPenabletemperature methodology waspreviously approvedforuseatGinnaStationbytheNRC.Assuch,thesechangesareadministrative innatureanddonotimpactinitiators oranalyzedeventsorassumedmitigation ofaccidentortransient events.Therefore, thesechangesdonotinvolveasignificant increaseintheprobability orconsequences ofanaccidentpreviously analyzed.
2.Operation ofGinnaStationinaccordance withtheproposedchangesdoesnotcreatethepossibility ofanewordifferent kindofaccidentfromanyaccidentpreviously evaluated.
Theproposedchangesdonotinvolveaphysicalalteration oftheplant(i.e.,nonewordifferent typeofequipment willbeinstalled) orchangesinthemethodsgoverning normalplantoperation.
Theproposedchangeswillnotimposeanynewordifferent requirements.
Thus,thischangedoesnotcreatethepossibility ofanewordifferent kindofaccidentfromanyaccidentpreviously evaluated.
3.Operation ofGinnaStationinaccordance withtheproposedchangesdoesnotinvolveasignificant reduction inamarginofsafety.Theproposedchangeswillnoteduceamarginofplantsafetybecausethemethodology havebeenshowntoensurethattheP/TandLTOPlimitsinthePTLRcontinuetomeetallnecessary requirements forreactorvesselintegrity.
Thesechangesareadministrative innaturesincethelimitswerepreviously relocated tothePTLRunderaseparateLAR.Assuch,noquestionofsafetyisinvolved, andthechangedoesnotinvolveasignificant reduction inamarginofsafety.Basedupontheaboveinformation, ithasbeendetermined thattheproposedadministrative changestotheGinnaStationTechnical Specifications donotinvolveasignificant increaseintheprobability orconsequences ofanaccidentpreviously evaluated, doesnotcreatethepossibility ofanewordifferent kindofaccidentpreviously evaluated, anddoesnotinvolveasignificant reduction inamarginofsafety.Therefore, itisconcluded thattheproposedchangesmeettherequirements of10CFR50.92(c)anddonotinvolveasignificant hazardsconsideration.
E.ENVIRONMENTAL CONSIDERATION RG&Ehasevaluated theproposedchangesanddetermined that:1.Thechangesdonotinvolveasignificant hazardsconsideration asdocumented inSectionDabove;2.Thechangesdonotinvolveasignificant changeinthetypesorsignificant increaseintheamountsofanyeffluents thatmaybereleasedoffsitesincenospecifications relatedtooffsitereleasesareaffected; and3.Thechangesdonotinvolveasignificant increaseinindividual orcumulative occupational radiation exposuresincenonewordifferent typeofequipment arerequiredtobeinstalled asaresultofthisLAR.Accordingly, theproposedchangesmeettheeligibility criteriaforcategorical exclusion setforthin10CFR51.22(c)(9).
Therefore, pursuantto10CFR51.22(b),
anenvironmental assessment oftheproposedchangesisnotrequired.
F.REFERENCES LetterfromR.C.Mecredy,RG&E,toA.R.Johnson,NRC,


==Subject:==
==Subject:==
TechnicalSpectjicatt'onsImprovementProgram,ReactorCoolantSystem(RCS)PressureandTemperatureLimitsReport(PTLR),datedDecember8,1995.  
Technical Spectjicatt'onsImprovement Program,ReactorCoolantSystem(RCS)PressureandTemperature LimitsReport(PTLR),datedDecember8,1995.  


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


==Subject:==
==Subject:==
R.E.Ginna-AcceptanceforReferencingofPressureTemperatureLimitsReport(TACNo.M92320),datedDecember26,1995.LetterfromA.R.Johnson,NRC,toR.C.Mecredy,RG&B,
R.E.Ginna-Acceptance forReferencing ofPressureTemperature LimitsReport(TACNo.M92320),datedDecember26,1995.LetterfromA.R.Johnson,NRC,toR.C.Mecredy,RG&B,


==Subject:==
==Subject:==
R.E.GinnaNuclearPowerPlant-PressurizedThermal'ShockEvaluation(TACNo.M93827),datedMarch22,1996.WCAP-14040-NP-A,MethodologyUsedtoDevelopColdOverpressureMitigatingSystemSetpointsandRCSHeatupandCooldownLimitCurves,January1996.LetterfromG.S.VissingNRC,toR.C.Mecredy,RG&E,
R.E.GinnaNuclearPowerPlant-Pressurized Thermal'Shock Evaluation (TACNo.M93827),datedMarch22,1996.WCAP-14040-NP-A, Methodology UsedtoDevelopColdOverpressure Mitigating SystemSetpoints andRCSHeatupandCooldownLimitCurves,January1996.LetterfromG.S.VissingNRC,toR.C.Mecredy,RG&E,


==Subject:==
==Subject:==
IssuanceofAmendmentNo.6'4toFacilityOperatingLicenseNo.DPR-I8,R.E.GinnaNuclearPowerPlant(TACNo.M94770),datedMay23,1996.LetterfromR.C.Mecredy,RG&B,toG.S.Vissing,NRC,
IssuanceofAmendment No.6'4toFacilityOperating LicenseNo.DPR-I8,R.E.GinnaNuclearPowerPlant(TACNo.M94770),datedMay23,1996.LetterfromR.C.Mecredy,RG&B,toG.S.Vissing,NRC,


==Subject:==
==Subject:==
RequesttoUseASMECodeCaseN-514intheDeterminationofLowTemperatureOverpressureProtection(LTOP)EnableTemperature,datedDecember18,1996.LetterfromR.C.Mecredy,RG&E,toG.S.Vissing,NRC,
RequesttoUseASMECodeCaseN-514intheDetermination ofLowTemperature Overpressure Protection (LTOP)EnableTemperature, datedDecember18,1996.LetterfromR.C.Mecredy,RG&E,toG.S.Vissing,NRC,


==Subject:==
==Subject:==
RequestforExemprionto10CFR50.60toUseAmericanSocietyofMechanicalEngineers(ASME)CodeCaseN-514intheDeterminationofLowTemperatureOverpressureProtection(LTOP)EnableTemperature,datedFebruary10,1997.LetterfromG.S.Vissing,NRC,toR.C.Mecredy,RG&B,
RequestforExemprion to10CFR50.60toUseAmericanSocietyofMechanical Engineers (ASME)CodeCaseN-514intheDetermination ofLowTemperature Overpressure Protection (LTOP)EnableTemperature, datedFebruary10,1997.LetterfromG.S.Vissing,NRC,toR.C.Mecredy,RG&B,


==Subject:==
==Subject:==
ExemptionfronttheRequirementsof10CFRPart50.60,AcceptanceCriteriaforFracturePreventionMeasuresforLightwaterNuclearPowerReactorsforNormalOperation-R.E.GinnaNuclearPlant(TACNo.M98993),datedJuly28,1997.LetterfromG.S.Vissing,NRC,toR.C.Mecredy,RG&E,
Exemption fronttheRequirements of10CFRPart50.60,Acceptance CriteriaforFracturePrevention MeasuresforLightwater NuclearPowerReactorsforNormalOperation
-R.E.GinnaNuclearPlant(TACNo.M98993),datedJuly28,1997.LetterfromG.S.Vissing,NRC,toR.C.Mecredy,RG&E,


==Subject:==
==Subject:==
R.E.Ginna-AcceptanceofRequesttoExtendTimeforApprovalofRevisionofPressureandTemperatureLimitsReport(PTLR)(TACNo.M97313),datedDecember10,1996.
R.E.Ginna-Acceptance ofRequesttoExtendTimeforApprovalofRevisionofPressureandTemperature LimitsReport(PTLR)(TACNo.M97313),datedDecember10,1996.
AttachmentIIMarkedUpCopyofR.E.GinnaNuclearPowerPlantTechnicalSpecificationsIncludedPages:5.0-22}}
Attachment IIMarkedUpCopyofR.E.GinnaNuclearPowerPlantTechnical Specifications IncludedPages:5.0-22}}

Revision as of 12:41, 29 June 2018

Application for Amend to License DPR-18,revising Administrative Controls W/Respect to RCS Pressure & Temp Limits Rept
ML17264B043
Person / Time
Site: Ginna Constellation icon.png
Issue date: 09/29/1997
From: MECREDY R C
ROCHESTER GAS & ELECTRIC CORP.
To:
Shared Package
ML17264B042 List:
References
NUDOCS 9710020173
Download: ML17264B043 (13)
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Text

UNITEDSTATESOFAMERICANUCLEARREGULATORY COMMISSION IntheMatterofRochester GasandElectricCorporation (R.E.GinnaNuclearPowerPlant))))DocketNo.50-244)APPLICATION FORAMENDMENT PursuanttoSection50.90oftheregulations oftheU.S.NuclearRegulatory Commission (NRC),Rochester GasandElectricCorporation (RG&E),holderofFacilityOperating LicenseNo.DPR-18,herebyrequeststhattheTechnical Specifications setforthinAppendixAtothat~~license,beamended.ThisrequestforchangeistorevisetheAdministrative ControlswithrespecttotheReactorCoolantSystem(RCS)PressureandTemperature LimitsReport(PTLR)tomakethenecessary changesinorderplacethisdocumentunderlicenseecontrol,makeseveralchangestothePTLR,andtorevisetheLTOPenabletemperature methodology.

Adescription oftheamendment request,necessary background information, justification oftherequested changes,andanosignificant hazardsandenvironmental considerations areprovidedinAttachment I.Thisevaluation demonstrates thattheproposedchangesdonotinvolveasignificant changeinthetypesorasignificant increaseintheamountsofeffluents oranychangeintheauthorized powerlevelofthefacility.

Theproposedchangesalsodonotinvolveasignificant hazardsconsideration.

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AmarkedupcopyoftheGinnaStationTechnical Specifications whichshowtherequested changesissetforthinAttachment II.Theproposedrevisedtechnical specifications areprovidedinAttachment III.TherevisedPTLRisprovidedinAttachment IV.Attachment Vcontainsaredlinedversionofthelowtemperature overpressure protection (LTOP)setpointmethodology withrespecttothecurrently approvedversion.Attachment VIcontainsafinalversionoftheLTOPsetpointmethodology.

Attachment VIIcontainsthefirstuseoftheLTOPenabletemperature methodology whileAttachment VIIIcontainsa'copyofWCAP-14684 asreferenced withinthePTLR.Attachment IXcontainsresponses toNRCquestions concerning theGinnaStationLTOPanalysis.

WHEREFORE, Applicant respectfully requeststhatFacilityOperating LicenseNo.DPR-18,andAttachment Atothatlicense,beamendedintheformattachedheretoasAttachment III.Rochester GasandElectricCorporation ByRobertC.MecredyVicePresident NuclearOperations Subscribed andsworntobeforemeonthis29thdayofSeptember 1997.NotaryPublicDEBORAHA.PIPERNI NotaryPublicmtheStateofNmYorkONTARIOCOUNTYCommasonExpiresNov.23,19,3.3

~I Attachment IR.E.GinnaNuclearPowerPlantLicenseAmendment RequestRevisionofReactorCoolantSystem(RCS)PressureandTemperature LimitsReport(PTLR)Administrative ControlsRequirements Thisattachment providesadescription ofthelicenseamendment request(LAR)andthenecessary justifications tosupportarevisiontotheGinnaStationPTLRandrelatedrequirements contained withintheAdministrative Controlssectionoftechnical specifications.

Thisattachment isdividedintosixsectionsasfollows.SectionAsummarizes allchangestotheGinnaStationTechnical Specifications whileSectionBprovidesthebackground andhistoryassociated withthechangesbeingrequested.

SectionCprovidesthejustifications associated withtheseproposedchanges.Anosignificant hazardsconsideration evaluation andenvironmental consideration oftherequested changestotheGinnaStationTechnical Specifications areprovidedinSectionsDandE,respectively.

SectionFlistsallreferences usedinthisattachment.

A.DESCRIPTION OFTECHNICAL SPECIFICATION CHANGESThisLARproposestorevisetheGinnaStationTechnical Specifications toreflectanewPTLRintheAdministrative Controlssection.Thechangeissummarized belowandshowninAttachment II.1.Administrative Controls5.6.6Itemcwillberevisedtoicplacethereference totheMay23,1996NRCletterwithanewNRCreference thatapprovesthefirstuseofthePTLRmethodology includedasAttachment VItothisLAR.Inaddition, Reference 1isrevisedtoreference thisLARasthesourceforthelowtemperature overpressure protection (LTOP)methodology whileReference 2isrevisedtoreference thefinalNRCapprovedWCAP-14040-NP-A whichisthebasisforthenewP/Tcurves.Reference 3isnolongerrequiredandistherefore deleted.Finally,atypographical errorinitemdiscorrected.

BACKGROUND Duringtheconversion toimprovedstandardtechnical specifications (ISTS)forGinnaStation,RG&EproposedtorelocatetheLTOPandRCSpressureandtemperature (P/T)limitstothePTLR(Ref.1).Associated withthischangewastheadditionofareference totheAdministrative Controlssectionoftechnical specifications relatedtothePTLRdocumenting theNRCapprovalofthemethodology usedinthePTLR.However,theonlyNRCapprovedmethodology wouldbe"new"withrespecttodetermination ofboththeLTOPandRCSP/TlimitsatGinnaStation.Duetotimeconstraints, RG&EinformedtheNRCthatuseofthisnewmethodology wouldbeburdensome andinstead,RG&Ewishedtoretaintheexistingvalues.TheNRCagreedwiththisconcernandallowedtheexistinglimitstoberelocated tothePTLRbutrequiredchangestotheselimitstobereviewedandapprovedbytheNRCasdocumented inReference 2.Subsequent totheconversion toISTS,theNRCcompleted itsreviewofthelatestreactorvesselcapsuledataandtheassociated impactonthepressurized thermalshock(PTS)evaluation forGinnaStation(Ref.3).Incorporation ofthisinformation intothePTLRrequiredareassessment oftheP/TcurvesandLTOPsetpoints thatareincludedinthePTLR.However,thefluencefactormethodology usedfortheGinnaStationPTSevaluation wasanearlierversionthanthatrequiredbyWCAP-14040-NP-A (Ref.4)whichwastobethebasisfortheP/Tmethodology.

Sinceanupdateoftheassociated documents couldnotbecompleted inthetimeframerequiredtosupportstart-upfromthe1996refueling outage,theNRCapprovedaPTLRforuseatGinnaStationuntilDecember31,1996usinganestimated fluencefactorvalue(Ref.5).Subsequent tothis,whileattempting tocloseoutthefluencefactormethodologies, theNRCquestioned RG&E'sapproachfordetermining LTOPenabletemperature.

Specifically, theNRCidentified thatthedetermination oftheLTOPenabletemperature requiredconsideration ofRCSliquidtemperature measurement accuracyperthemethodology currently specified inSpecification 5.6.6.Uponfurtherevaluation, RG&Eagreedtoaddressthisconcernbyfirstsubmitting areliefrequest(Ref.6)andthenbyrequesting anexemption toregulations (Ref.7).Subsequently, theNRCidentified thattheliquidtemperature accuracyquestionshouldbeinsteadaddressed byanewLARwhichupdatedthemethodology inSpecification 5.6.6andincorporated anexemption to10CFR50.60(Ref.8).ToallowRG&Esufficient timetoaddressthisissue,thePTLRexpiration datewaschangedtoDecember31,1997(Ref.9).

ThepurposeofthisLARistocompleteimplementation ofGenericLetter96-03forGinnaStationandtorespondtotheDecember31,1997timelimitontheexistingPTLR.GenericLetter96-03requiresthatlicensees reference theP/TandLTOPmethodologies inthetechnical specifications andprovideaproposedPTLRusingthemethodology forNRCreview.Sections1,2,and4ofWCAP-14040-NP-A (Ref.4)havebeengenerically approvedforusebytheNRCforP/TlimitsandisbeingproposedastheP/Tlimitmethodology forGinnaStation.ThecurrentLTOPmethodology forGinnaStation(Ref.1)replacedthatprovidedinSection3ofWCAP-14040 duetoRGBspecificissuesandwaspreviously reviewedbytheNRCandfoundtobeacceptable (Ref.5).However,theLTOPenabletemperature methodology isbeingrevisedtoclarifythespecificRCStemperature accuracyrequirements andallowtheuseofASMEXICodeCaseN-514fortemperature determination (Ref.8).AredlinedversionoftheLTOPmethodology showingallchangesfromthepreviousNRCapprovedversionisprovidedinAttachment Vwhileafinalversionisprovidedin.Attachment VItothisLAR.Therefore, thisLARprovidesaproposedPTLR(andsupporting documentation asprovidedinWCAP-14684) andincludesareference toWCAP-14040-NP-A andthisLARintheAdministrative Controlsasthebasisforthemethodology.

Itshouldbenotedthateventhoughthetechnical specifications donotrequirereactorvesselmaterialinformation tobelocatedwithinthePTLR,thisinformation isprovidedconsistent withGenericLetter96-03.ThisincludesarevisedRT~,valuebasedontheattachedWCAP-14684.

TherevisedRT~valuealsoincludeschangesmadeasaresultofadditional surveillance capsulechemistry analyses.

C.JUSTIFICATION OFCHANGESThissectionprovidesthejustification forallchangesdescribed inSectionAaboveandshowninAttachment II.Thejustifications areorganized basedonwhetherthechangeis:morerestrictive (M),lessrestrictive (L),administrative (A),ortherequirement isrelocated (R).Thejustifications listedbelowarealsoreferenced inthetechnical specification(s) whichareaffected(seeAttachment II).

C.1Administrative ControlsSection5.6.6.cisrevisedto:(1)replacereference totheMay23,1996submittal withanewreference thatapprovesthefirstuseofthePTLRmethodology ascontained inAttachment VItothisLAR;(2)updatetheAdminstrative Controlscontentconsistent.

withGL96-03;and,(3)updatethereferences forPTLRmethodology withrespecttoRCSP/Tlimits.Item(1)onlychangesthedateoftheNRCapprovalofthePTLR,including thePTLRmethodology sinceGinnaStationcurrently hasaNRCapprovedPTLR.Item(2)makestheGinnaStationTechnical Specifications consistent withISTSinorderforthelicenseetomakefuturechangeswithoutNRCreviewandapproval.

Item(3)updatesthePTLRmethodology usedforP/Tlimitstoreference WCAP-14040-NP-Ainsteadofreferencing WCAP-14040 andtheassociated NRCapprovalletter(i.e.,WCAP-14040-NP-A includestheNRCapprovalletterandallNRCrequiredchanges).

Thesethreechangesareadministrative innaturesincetheRCSP/Tlimitswerepreviously relocated fromtechnical specifications tothePTLR;onlyminordetailsarebeingclarified.

2.Administrative ControlsSection5.6.6.c.l isrevisedtoreplacethepreviously approvedLTOPmethodology (Ref.1)withthatprovidedinAttachment VItothisLAR(Attachment Vprovidesa"red-line" comparison tothepreviously approvedmethodology toshowalldifferences).

Theonlydifference intheproposednewLTOPmethodology fromthatapprovedpreviously istoprovideadditional clarifications consistent withNRCandRG&Ecommunciations andtoallowtheLTOPenabletemperature andpressurelimitstobedetermined usingASMESectionXICodeCaseN-514.Thiscodecasedesignates theallowable reactorcoolantpressureboundarypressureduringLTOPeventstobe110%ofthatspecified by10CFR50,AppendixG.Useofthiscodecaserequiresanexemption to10CFR50.60whichwasgrantedtoRG&EinReference 8.Therefore, thischangeincorporates theuseofCodeCaseN-514intotheLTOPmethodology specified withintheAdminstrative ControlssectionofTechnical Specifications consistent withReference 8.3.Atypographical errorinAdministrative ControlsSection5.6.6.discorrected toprovideconsistency withNUREG-1431.

Therearenotanymorerestrictive (M),lessrestrictive (L),orrelocated (R)changesassociated withthisLAR.

D.SIGNIFICANT HAZARDSCONSIDERATION EVALUATION TheproposedchangestotheGinnaStationTechnical Specifications asidentified inSectionAandjustified inSectionChavebeenevaluated withrespectto10CFR50.92(c)andshowntonotinvolveasignificant hazardsconsideration asdescribed below.Thissectionisorganized basedonSectionCabove.D.1Theadministrative changesdiscussed inSectionC.1donotinvolveasignificant hazardsconsideration asdiscussed below:Operation ofGinnaStationinaccordance, withtheproposedchangesdoesnotinvolveasignificant increaseintheprobability orconsequences ofanaccidentpreviously evaluated.

TheproposedchangesreviseAdministrative ControlsSection5.6.6.ctoupdatethereference totheNRC'sapprovalofthefirstuseofthePTLRmethodology, updatetheRCSP/Tmethodology tothefinalNRCapprovedversion,allowuseofASMECodeCaseN-514forLTOPenabletemperature methodology, andtocorrectatypographical error.Thesechangescompleteimplementation ofGenericLetter96-03byreferencing NRCapprovedmethodology withintheAdministrative Controls.

TheupdatedRCSP/Tmethodology hasbeengenerically approvedbytheNRCwhiletheuseofASMECodeCaseN-514forLTOPenabletemperature methodology waspreviously approvedforuseatGinnaStationbytheNRC.Assuch,thesechangesareadministrative innatureanddonotimpactinitiators oranalyzedeventsorassumedmitigation ofaccidentortransient events.Therefore, thesechangesdonotinvolveasignificant increaseintheprobability orconsequences ofanaccidentpreviously analyzed.

2.Operation ofGinnaStationinaccordance withtheproposedchangesdoesnotcreatethepossibility ofanewordifferent kindofaccidentfromanyaccidentpreviously evaluated.

Theproposedchangesdonotinvolveaphysicalalteration oftheplant(i.e.,nonewordifferent typeofequipment willbeinstalled) orchangesinthemethodsgoverning normalplantoperation.

Theproposedchangeswillnotimposeanynewordifferent requirements.

Thus,thischangedoesnotcreatethepossibility ofanewordifferent kindofaccidentfromanyaccidentpreviously evaluated.

3.Operation ofGinnaStationinaccordance withtheproposedchangesdoesnotinvolveasignificant reduction inamarginofsafety.Theproposedchangeswillnoteduceamarginofplantsafetybecausethemethodology havebeenshowntoensurethattheP/TandLTOPlimitsinthePTLRcontinuetomeetallnecessary requirements forreactorvesselintegrity.

Thesechangesareadministrative innaturesincethelimitswerepreviously relocated tothePTLRunderaseparateLAR.Assuch,noquestionofsafetyisinvolved, andthechangedoesnotinvolveasignificant reduction inamarginofsafety.Basedupontheaboveinformation, ithasbeendetermined thattheproposedadministrative changestotheGinnaStationTechnical Specifications donotinvolveasignificant increaseintheprobability orconsequences ofanaccidentpreviously evaluated, doesnotcreatethepossibility ofanewordifferent kindofaccidentpreviously evaluated, anddoesnotinvolveasignificant reduction inamarginofsafety.Therefore, itisconcluded thattheproposedchangesmeettherequirements of10CFR50.92(c)anddonotinvolveasignificant hazardsconsideration.

E.ENVIRONMENTAL CONSIDERATION RG&Ehasevaluated theproposedchangesanddetermined that:1.Thechangesdonotinvolveasignificant hazardsconsideration asdocumented inSectionDabove;2.Thechangesdonotinvolveasignificant changeinthetypesorsignificant increaseintheamountsofanyeffluents thatmaybereleasedoffsitesincenospecifications relatedtooffsitereleasesareaffected; and3.Thechangesdonotinvolveasignificant increaseinindividual orcumulative occupational radiation exposuresincenonewordifferent typeofequipment arerequiredtobeinstalled asaresultofthisLAR.Accordingly, theproposedchangesmeettheeligibility criteriaforcategorical exclusion setforthin10CFR51.22(c)(9).

Therefore, pursuantto10CFR51.22(b),

anenvironmental assessment oftheproposedchangesisnotrequired.

F.REFERENCES LetterfromR.C.Mecredy,RG&E,toA.R.Johnson,NRC,

Subject:

Technical Spectjicatt'onsImprovement Program,ReactorCoolantSystem(RCS)PressureandTemperature LimitsReport(PTLR),datedDecember8,1995.

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

Subject:

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

Subject:

R.E.GinnaNuclearPowerPlant-Pressurized Thermal'Shock Evaluation (TACNo.M93827),datedMarch22,1996.WCAP-14040-NP-A, Methodology UsedtoDevelopColdOverpressure Mitigating SystemSetpoints andRCSHeatupandCooldownLimitCurves,January1996.LetterfromG.S.VissingNRC,toR.C.Mecredy,RG&E,

Subject:

IssuanceofAmendment No.6'4toFacilityOperating LicenseNo.DPR-I8,R.E.GinnaNuclearPowerPlant(TACNo.M94770),datedMay23,1996.LetterfromR.C.Mecredy,RG&B,toG.S.Vissing,NRC,

Subject:

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

Subject:

RequestforExemprion to10CFR50.60toUseAmericanSocietyofMechanical Engineers (ASME)CodeCaseN-514intheDetermination ofLowTemperature Overpressure Protection (LTOP)EnableTemperature, datedFebruary10,1997.LetterfromG.S.Vissing,NRC,toR.C.Mecredy,RG&B,

Subject:

Exemption fronttheRequirements of10CFRPart50.60,Acceptance CriteriaforFracturePrevention MeasuresforLightwater NuclearPowerReactorsforNormalOperation

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

Subject:

R.E.Ginna-Acceptance ofRequesttoExtendTimeforApprovalofRevisionofPressureandTemperature LimitsReport(PTLR)(TACNo.M97313),datedDecember10,1996.

Attachment IIMarkedUpCopyofR.E.GinnaNuclearPowerPlantTechnical Specifications IncludedPages:5.0-22

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