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'1f iAttachmentVR.E.GinnaNuclearPowerPlantProposedGinnaStationTechnicalSpecifications DesignFeatures4.04.0DESIGNFEATURES4.1SiteLocationThesitefortheR.E.GinnaNuclearPowerPlantislocatedonthesouthshoreofLakeOntario,approximately16mileseastofRochester,NewYork.Theexclusionareaboundarydistancesfromtheplantshallbeasfollows:DirectionN(includingoffshore)NNENEENEEESESESSESSSWSWWSWWWNWNWNNWDistancem8000800080008000747640503450450450503915945701800080004.2ReactorCore4.2.1FuelAssembliesThereactorshallcontain121fuelassemblies.EachassemblyshallconsistofamatrixofzircaloyorZIRLOcladfuelrodswithaninitialcompositionofnaturalorslightlyenricheduraniumdioxide(UO,)asfuelmaterial.Limitedsubstitutionsofzircaloy,ZIRLO,orstainlesssteelfillerrodsforfuelrods,inaccordancewithNRCapprovedapplicationsoffuelrodconfigurations,maybeused.FuelassembliesshallbelimitedtothosefueldesignsthathavebeenanalyzedwithapplicableNRCstaffapprovedcodesandmethodsandshownbytestsorcyclespecificanalysestocomplywithallfuelsafetydesignbases.Alimitednumberofleadtestassembliesthathavenotcompletedrepresentativetestingmaybeplacedinnonlimitingcoreregions.I(continued)R.E.GinnaNuclearPowerPlant4.0-1AmendmentNo.Q 4 | '1f iAttachmentVR.E.GinnaNuclearPowerPlantProposedGinnaStationTechnicalSpecifications DesignFeatures4.04.0DESIGNFEATURES4.1SiteLocationThesitefortheR.E.GinnaNuclearPowerPlantislocatedonthesouthshoreofLakeOntario,approximately16mileseastofRochester,NewYork.Theexclusionareaboundarydistancesfromtheplantshallbeasfollows:DirectionN(includingoffshore)NNENEENEEESESESSESSSWSWWSWWWNWNWNNWDistancem8000800080008000747640503450450450503915945701800080004.2ReactorCore4.2.1FuelAssembliesThereactorshallcontain121fuelassemblies.EachassemblyshallconsistofamatrixofzircaloyorZIRLOcladfuelrodswithaninitialcompositionofnaturalorslightlyenricheduraniumdioxide(UO,)asfuelmaterial.Limitedsubstitutionsofzircaloy,ZIRLO,orstainlesssteelfillerrodsforfuelrods,inaccordancewithNRCapprovedapplicationsoffuelrodconfigurations,maybeused.FuelassembliesshallbelimitedtothosefueldesignsthathavebeenanalyzedwithapplicableNRCstaffapprovedcodesandmethodsandshownbytestsorcyclespecificanalysestocomplywithallfuelsafetydesignbases.Alimitednumberofleadtestassembliesthathavenotcompletedrepresentativetestingmaybeplacedinnonlimitingcoreregions.I(continued)R.E.GinnaNuclearPowerPlant4.0-1AmendmentNo.Q 4 | ||
eportingRequirements5.65.6ReportingRequirements5.6.5COLR(continued)b.TheanalyticalmethodsusedtodeterminethecoreoperatinglimitsshallbethosepreviouslyreviewedandapprovedbytheNRC,specificallythosedescribedinthefollowingdocuments:1.WCAP-9272-P-A,"WestinghouseReloadSafetyEvaluationMethodology,"July1985.(MethodologyforLCO3.1.1,LCO3.1.3,LCO3.1.5,LCO3.1.6,LCO3.2.1,LCO3.2.2,LCO3.2.3,andLCO3.9.1.)2.WCAP-13677-P-A,"10CFR50.46EvaluationModelReport:WCOBRA/TRACTwo-LoopUpperPlenumInjectionModelUpdatestoSupportZIRLOŽCladdingOption,"February1994.(MethodologyforLCO3.2.1.)3.WCAP-8385,"PowerDistributionControlandLoadFollowingProcedures-TopicalReport,"September1974.(HethodologyforLCO3.2.3.)4.WCAP-12610-P-A,"VANTAGE+FuelAssemblyReferenceCoreReport,"April1995.(MethodologyforLCO3.2.1).5.WCAP11397-P-A,"RevisedThermalDesignProcedure,"April1989.(MethodologyforLCO3.4.1whenusingRTDP.)6.WCAP-10054-P-AandWCAP-10081-A,"WestinghouseSmallBreakECCSEvaluationModelUsingtheNOTRUMPCode,"August1985.(MethodologyforLCO3.2.1)7.WCAP-10924-P-A,Volume1,Revision1,"WestinghouseLarge-BreakLOCABest-EstimateMethodology,Volume1:ModelDescriptionandValidationResponsestoNRCguestions,"andAddenda1,2,3,December1988.(HethodologyforLCO3.2.1)(continued)R.E.GinnaNuclearPowerPlant5.0-20AmendmentNo.g lirI eportingRequirements5.65.6ReportingRequirements5.6.5COLR(continued)8.WCAP-10924-P-A,Volume2,Revision2,"WestinghouseLarge-BreakLOCABest-EstimateMethodology,Volume2:ApplicationtoTwo-LoopPWRsEquippedwithUpperPlenumInjection,"andAddendum1,December1988.(MethodologyforLCO3.2.1)9.WCAP-10924-P-A,Volume1,Revision1,Addendum4,"WestinghouseLarge-BreakLOCABest-EstimateMethodology,Volume1:ModelDescriptionandValidation,Addendum4:ModelRevisions,"March1991.(MethodologyforLCO3.2.1)c~Thecoreoperatinglimitsshallbedeterminedsuchthatallapplicablelimits(e.g.,fuelthermalmechanicallimits,corethermalhydrauliclimits,EmergencyCoreCoolingSystems(ECCS)limits,nuclearlimitssuchasSDH,transientanalysislimits,andaccidentanalysislimits)ofthesafetyanalysisaremet.d.TheCOLR,includinganymidcyclerevisionsorsupplements,shallbeprovideduponissuanceforeachreloadcycletotheNRC.5.6.6ReactorCoolantSstemRCSPRESSUREANDTEMPERATURELIMITSREPORTPTLRa0b.RCSpressureandtemperaturelimitsforheatup,cooldown,criticality,andhydrostatictestingaswellasheatupandcooldownratesshallbeestablishedanddocumentedinthePTLRforthefollowing:LCO3.4.3,"RCSPressureandTemperature(P/T)Limits"ThepoweroperatedreliefvalveliftsettingsrequiredtosupporttheLowTemperatureOverpressureProtection(LTOP)System,andtheLTOPenabletemperatureshallbeestablishedanddocumentedinthePTLRforthefollowing:LCO3.4.6,"RCSLoops-MODE4";LCO3.4.7,"RCSLoops-MODE5,LoopsFilled";LCO3.4.10,"PressurizerSafetyValves";andLCO3.4.12,"LTOPSystem."(continued)R.E.GinnaNuclearPowerPlant5.0-21AmendmentNo.g | eportingRequirements5.65.6ReportingRequirements5.6.5COLR(continued)b.TheanalyticalmethodsusedtodeterminethecoreoperatinglimitsshallbethosepreviouslyreviewedandapprovedbytheNRC,specificallythosedescribedinthefollowingdocuments:1.WCAP-9272-P-A,"WestinghouseReloadSafetyEvaluationMethodology,"July1985.(MethodologyforLCO3.1.1,LCO3.1.3,LCO3.1.5,LCO3.1.6,LCO3.2.1,LCO3.2.2,LCO3.2.3,andLCO3.9.1.)2.WCAP-13677-P-A,"10CFR50.46EvaluationModelReport:WCOBRA/TRACTwo-LoopUpperPlenumInjectionModelUpdatestoSupportZIRLOŽCladdingOption,"February1994.(MethodologyforLCO3.2.1.)3.WCAP-8385,"PowerDistributionControlandLoadFollowingProcedures-TopicalReport,"September1974.(HethodologyforLCO3.2.3.)4.WCAP-12610-P-A,"VANTAGE+FuelAssemblyReferenceCoreReport,"April1995.(MethodologyforLCO3.2.1).5.WCAP11397-P-A,"RevisedThermalDesignProcedure,"April1989.(MethodologyforLCO3.4.1whenusingRTDP.)6.WCAP-10054-P-AandWCAP-10081-A,"WestinghouseSmallBreakECCSEvaluationModelUsingtheNOTRUMPCode,"August1985.(MethodologyforLCO3.2.1)7.WCAP-10924-P-A,Volume1,Revision1,"WestinghouseLarge-BreakLOCABest-EstimateMethodology,Volume1:ModelDescriptionandValidationResponsestoNRCguestions,"andAddenda1,2,3,December1988.(HethodologyforLCO3.2.1)(continued)R.E.GinnaNuclearPowerPlant5.0-20AmendmentNo.g lirI eportingRequirements5.65.6ReportingRequirements5.6.5COLR(continued)8.WCAP-10924-P-A,Volume2,Revision2,"WestinghouseLarge-BreakLOCABest-EstimateMethodology,Volume2:ApplicationtoTwo-LoopPWRsEquippedwithUpperPlenumInjection,"andAddendum1,December1988.(MethodologyforLCO3.2.1)9.WCAP-10924-P-A,Volume1,Revision1,Addendum4,"WestinghouseLarge-BreakLOCABest-EstimateMethodology,Volume1:ModelDescriptionandValidation,Addendum4:ModelRevisions,"March1991.(MethodologyforLCO3.2.1)c~Thecoreoperatinglimitsshallbedeterminedsuchthatallapplicablelimits(e.g.,fuelthermalmechanicallimits,corethermalhydrauliclimits,EmergencyCoreCoolingSystems(ECCS)limits,nuclearlimitssuchasSDH,transientanalysislimits,andaccidentanalysislimits)ofthesafetyanalysisaremet.d.TheCOLR,includinganymidcyclerevisionsorsupplements,shallbeprovideduponissuanceforeachreloadcycletotheNRC.5.6.6ReactorCoolantSstemRCSPRESSUREANDTEMPERATURELIMITSREPORTPTLRa0b.RCSpressureandtemperaturelimitsforheatup,cooldown,criticality,andhydrostatictestingaswellasheatupandcooldownratesshallbeestablishedanddocumentedinthePTLRforthefollowing:LCO3.4.3,"RCSPressureandTemperature(P/T)Limits"ThepoweroperatedreliefvalveliftsettingsrequiredtosupporttheLowTemperatureOverpressureProtection(LTOP)System,andtheLTOPenabletemperatureshallbeestablishedanddocumentedinthePTLRforthefollowing:LCO3.4.6,"RCSLoops-MODE4";LCO3.4.7,"RCSLoops-MODE5,LoopsFilled";LCO3.4.10,"PressurizerSafetyValves";andLCO3.4.12,"LTOPSystem."(continued)R.E.GinnaNuclearPowerPlant5.0-21AmendmentNo.g | ||
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Issue date: | 11/24/1998 |
From: | ROCHESTER GAS & ELECTRIC CORP. |
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AttachmentIVR.E.GinnaNuclearPowerPlantIncludedpages:4.0-15.0-205.0-21Mark-upofExistingGinnaStationTechnicalSpecifications98i207008398ii24PDRADQCK05000244PPGR J
DesignFeatures4.04.0DESIGNFEATURES4.1SiteLocationThesitefortheR.E.GinnaNuclearPowerPlantislocatedonthesouthshoreofLakeOntario,approximately16mileseastofRochester,NewYork.Theexclusionareaboundarydistancesfromtheplantshallbeasfollows:DirectionN(includingoffshore)NNENEENEEESESESSESSSWSWWSWWWNW'WNNWDistancem800080008000,8000747640503450450450503915945701800080004.2ReactorCore4.2.1FuelAssembliescHo<z.irc~loyjZ%<~~>~c"~ANThereactorshallcontain121fuelasseblies.Eachassemblyshallconsistofamatrixofzircalloycladfuelrodswithaninitialcompositionofnaturalorslightlyenricheduraniumdioxide(UO,)asfuelmaterial.Limitedsubstitutionsofzircon~urnaoorstainlesssteelfillerrodsforfuelrods,inaccorancewithapprovedapplicationsoffuelrodconfigurations,mayeuse.FuelassembliesshallbelimitedtothosefueldesignsthathavebeenanalyzedwithapplicableNRCstaffapprovedcodesandmethodsandshownbytestsoranalysestocomplywithallfuelsafetydesignbases.Alimitenumberofleadtestassembliesthathavenotcompletedreprsentativetestingmaybeplacedinnonlimitingcore.regions.eyeesp~(continued)R.E.GinnaNuclearPowerPlant4.0-1AmendmentNo.61 11 ReportingRequirements5.65.6ReportingRequirements5.6.5COLR(continued)b.TheanalyticalmethodsusedtodeterminethecoreoperatinglimitsshallbethosepreviouslyreviewedandapprovedbytheNRC,.specificallythosedescribedinthefollowingdocuments:"1.WCAP-9272-P-A,"WestinghouseReloadSafetyEvaluationMethodology,"July1985.(MethodologyforLCO3.1.1,LCO3.1.3,LCO3.1.5,LCO3.1.6,LCO3.2.1,LCO3.2.2,LCO3.2.3,andLCO3.9.1.)2.3.WCAP-9220-P-A,"WestinghouseECCSEvaluationModel-1981Version,"Revision1,February1982.(HethodologforLCO3.2.1.)WCAP-8385,"PowerDistributionControlandLoadFollowingProcedures-TopicalReport,"'September1974.(MethodologyforLCO3.2.3.)4.WCAP-8567-P-A,"ImprovedThermalDesignProcedure;"February1989.(HethodologyforLCO3.4.1wheusinP.5.WCAP11397-P-A,"RevisedThermalDesignProcedure,"April1989.(MethodologyforLCD3.4.1'henusingRTDP.)~n6.'CAP-'10054-P-AandWCAP-1008+"WestinghouseSmallBreakECCSEvaluationModelUsingtheNOTRUMPCode,"August1985.(MethodologyforLCO3.2.1)p~U~'"~c.i>>.WCAP-10924-P-A,Volume1,.1,andAdden1,2,3,"WestinghouseLarge-BreakLOCABest-EstimateMethodology,Vo1:ModelDescriptionanda>aso,"December1988.(HethodologyforLCO3.2;1)C.t.l8.WCAP-10924-P-A,Volume2,.2,andnda"WestinghouseLarge-BreakLOCABest-stimateMethodology,Volume2:ApplicationtoTwo-LoopPWRsEquippedwithUpperPlenumInjection,"December8.(MethodologyforLCO3.2.1)(continued)R.E.GinnaNuclearPowerPlant5.0-20AmendmentNo.61 eportingRequirements5.65.6Reporting,Requirements.5:6.5(g~d~Revs'Sia~)~wcWCAP-10924-Polume1,1,Addenum4,"WethousOCABest-stimateMethodologyModelascriptionandValidationModelRevisions,"~ugus990Pldrdkl1%I(ethodologyforLCO3.2.1)COLR(continue9.WCAP-10924-P-A,Rev.2andWCAP-12071,"WestinghouseLarge-BreakLOCABestEstimateMethodology,Volume2:ApplicationtoTwo-LoopPWRsEquippedWithUpperPlenumInjection,Addendum1:ResponsestoNRCguestions,"December1988.HethodoloyforLCO3.2.1)C.Thecoreoperatinglimitsshallbedeterminedsuchthatall'pplicablelimits(e.g.,fuelthermalmechanicallimits,corethermalhydrauliclimits,EmergencyCoreCoolingSystems(ECCS)limits,nuclearlimitssuchasSDH,transientanalysislimits,andaccidentanalysislimits)ofthesafetyanalysisaremet.d.TheCOLR,includinganymidcyclerevisionsorsupplements,shallbeprovideduponissuanceforeachreloadcycleto"theNRC.5.6.6ReactorCoolantSstemRCSPRESSUREANDTEMPERATURELIMITS~RTPLa~b.RCSpressureandtemperaturelimitsforheatup,cooldown,criticality,andhydrostatictestingaswellasheatupandcooldownratesshallbeestablishedanddocumentedinthePTLRforthefollowing:LCO3.4.3,"RCSPressureandTemperature(P/T)Limits"ThepoweroperatedreliefvalveliftsettingsrequiredtosupporttheLowTemperatureOverpressureProtection(LTOP)System,andtheLTOPenabletemperatureshallbeestablishedariddocumentedinthePTLRforthefollowing:LCO3.4.6,"RCSLoops-MODE4";LCO3.4.7,"RCSLoops-MODE5,LoopsFilled";LCO3.4.10,"PressurizerSafetyValves";andLCO3.4.12,"LTOPSystem."(continued)R.E.GinnaNuclearPowerPlant5.0-21AmendmentNo.61 Ik INSERT1WCAP-13677-P-A,"10CFR50.46EvaluationModelReport:WCOBRA/TRACTwo-LoopUpperPlenumInjectionModelUpdatestoSupportZIRLOCladdingOption,"February1994.(MethodologyforLCO3.2.1).INSERT2WCAP-12610-P-A,"VANTAGE+FuelAssemblyReferenceCoreReport,"April1995.(MethodologyforLCO3.2.1).
'1f iAttachmentVR.E.GinnaNuclearPowerPlantProposedGinnaStationTechnicalSpecifications DesignFeatures4.04.0DESIGNFEATURES4.1SiteLocationThesitefortheR.E.GinnaNuclearPowerPlantislocatedonthesouthshoreofLakeOntario,approximately16mileseastofRochester,NewYork.Theexclusionareaboundarydistancesfromtheplantshallbeasfollows:DirectionN(includingoffshore)NNENEENEEESESESSESSSWSWWSWWWNWNWNNWDistancem8000800080008000747640503450450450503915945701800080004.2ReactorCore4.2.1FuelAssembliesThereactorshallcontain121fuelassemblies.EachassemblyshallconsistofamatrixofzircaloyorZIRLOcladfuelrodswithaninitialcompositionofnaturalorslightlyenricheduraniumdioxide(UO,)asfuelmaterial.Limitedsubstitutionsofzircaloy,ZIRLO,orstainlesssteelfillerrodsforfuelrods,inaccordancewithNRCapprovedapplicationsoffuelrodconfigurations,maybeused.FuelassembliesshallbelimitedtothosefueldesignsthathavebeenanalyzedwithapplicableNRCstaffapprovedcodesandmethodsandshownbytestsorcyclespecificanalysestocomplywithallfuelsafetydesignbases.Alimitednumberofleadtestassembliesthathavenotcompletedrepresentativetestingmaybeplacedinnonlimitingcoreregions.I(continued)R.E.GinnaNuclearPowerPlant4.0-1AmendmentNo.Q 4
eportingRequirements5.65.6ReportingRequirements5.6.5COLR(continued)b.TheanalyticalmethodsusedtodeterminethecoreoperatinglimitsshallbethosepreviouslyreviewedandapprovedbytheNRC,specificallythosedescribedinthefollowingdocuments:1.WCAP-9272-P-A,"WestinghouseReloadSafetyEvaluationMethodology,"July1985.(MethodologyforLCO3.1.1,LCO3.1.3,LCO3.1.5,LCO3.1.6,LCO3.2.1,LCO3.2.2,LCO3.2.3,andLCO3.9.1.)2.WCAP-13677-P-A,"10CFR50.46EvaluationModelReport:WCOBRA/TRACTwo-LoopUpperPlenumInjectionModelUpdatestoSupportZIRLOŽCladdingOption,"February1994.(MethodologyforLCO3.2.1.)3.WCAP-8385,"PowerDistributionControlandLoadFollowingProcedures-TopicalReport,"September1974.(HethodologyforLCO3.2.3.)4.WCAP-12610-P-A,"VANTAGE+FuelAssemblyReferenceCoreReport,"April1995.(MethodologyforLCO3.2.1).5.WCAP11397-P-A,"RevisedThermalDesignProcedure,"April1989.(MethodologyforLCO3.4.1whenusingRTDP.)6.WCAP-10054-P-AandWCAP-10081-A,"WestinghouseSmallBreakECCSEvaluationModelUsingtheNOTRUMPCode,"August1985.(MethodologyforLCO3.2.1)7.WCAP-10924-P-A,Volume1,Revision1,"WestinghouseLarge-BreakLOCABest-EstimateMethodology,Volume1:ModelDescriptionandValidationResponsestoNRCguestions,"andAddenda1,2,3,December1988.(HethodologyforLCO3.2.1)(continued)R.E.GinnaNuclearPowerPlant5.0-20AmendmentNo.g lirI eportingRequirements5.65.6ReportingRequirements5.6.5COLR(continued)8.WCAP-10924-P-A,Volume2,Revision2,"WestinghouseLarge-BreakLOCABest-EstimateMethodology,Volume2:ApplicationtoTwo-LoopPWRsEquippedwithUpperPlenumInjection,"andAddendum1,December1988.(MethodologyforLCO3.2.1)9.WCAP-10924-P-A,Volume1,Revision1,Addendum4,"WestinghouseLarge-BreakLOCABest-EstimateMethodology,Volume1:ModelDescriptionandValidation,Addendum4:ModelRevisions,"March1991.(MethodologyforLCO3.2.1)c~Thecoreoperatinglimitsshallbedeterminedsuchthatallapplicablelimits(e.g.,fuelthermalmechanicallimits,corethermalhydrauliclimits,EmergencyCoreCoolingSystems(ECCS)limits,nuclearlimitssuchasSDH,transientanalysislimits,andaccidentanalysislimits)ofthesafetyanalysisaremet.d.TheCOLR,includinganymidcyclerevisionsorsupplements,shallbeprovideduponissuanceforeachreloadcycletotheNRC.5.6.6ReactorCoolantSstemRCSPRESSUREANDTEMPERATURELIMITSREPORTPTLRa0b.RCSpressureandtemperaturelimitsforheatup,cooldown,criticality,andhydrostatictestingaswellasheatupandcooldownratesshallbeestablishedanddocumentedinthePTLRforthefollowing:LCO3.4.3,"RCSPressureandTemperature(P/T)Limits"ThepoweroperatedreliefvalveliftsettingsrequiredtosupporttheLowTemperatureOverpressureProtection(LTOP)System,andtheLTOPenabletemperatureshallbeestablishedanddocumentedinthePTLRforthefollowing:LCO3.4.6,"RCSLoops-MODE4";LCO3.4.7,"RCSLoops-MODE5,LoopsFilled";LCO3.4.10,"PressurizerSafetyValves";andLCO3.4.12,"LTOPSystem."(continued)R.E.GinnaNuclearPowerPlant5.0-21AmendmentNo.g
.0~51J~(((,