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RochesterGasandElectric(RG&E)currentlyanticipatessubmittingtheproposedconversiontoImprovedTechnicalSpecifications(ITS)consistentwithNUREG-1431laterthismonth.Includedwithinthissubmittalareseveralchangestotheexistingtechnicalspecifications(TS)thataresupportedbyengineeringcalculationsorotherdocumentsthatwillrequireNRCStaffreviewandapprovalseparatefromtheconversionreview.Basedonrecentconversations,theNRChasrequestedthatRG&EprovidethesedocumentspriortotheITSsubmittaltoallowtheNRCStaffadditionaltimeforreview.Therefore,attachedarethefollowingdocuments:(a)"CriticalityAnalysisoftheR.E.GinnaNuclearPowerPlantFreshandSpentFuelRacks,andConsolidatedRodStorageCanisters,"datedJune1994.(b)WCAP-14040,"MethodologyUsedtoDevelopColdOverpressureMitigatingSystemSetpointsandRCSHeatupandCooldownLimitCurves,"Revision1,December1994.(c)RG&EMethodologyforDeterminingtheLowTemperatureOverpressureProtectionSystem(LTOPS)Setpoints.Thespentfuelpoolcriticalitystudyisrequiredtosupportanincreaseinallowedfuelenrichmentnecessarytosupportaconversion,to18monthfuelcycleswhichisplannedtobeginfollowingthe1996refuelingoutage.AnincreasedinfuelenrichmentaffectscurrentGinnaStationTS5.3.1.bandTS5.4.~GgQQ95OS<S00<49S0505PDRADGCK05000244PPDR,';oi TheremainingtwodocumentssupporttheincorporationofaPressureTemperatureLimitsReport(PTLR)whichisplannedtobeimplementedduringtheconversiontoITS.SinceGinnaStationutilizestheLTOPSforpreventingoverpressurizationoftheresidualheatremovalsystem,Section3.0ofWCAP-14040doesnotapplytotheinstalledsystem.Therefore,RG&Especificmethodologyisprovidedforyourreview.BoththeRG&Especificmethodologyandared-linemarkupofthemethodologyprovidedinWCAP-14040areprovided.AllitemsproposedtoberelocatedfromthecurrentGinnaStationTStothePTLRareaddressedbythesetwodocuments.TheitemsRG&EanticipatestoberelocatedtotheCoreOperatingLimitsReport(COLR)areprovidedinattachedTable1.Ascanbeseenfromthistable,NRCapprovedmethodologyexistsforallitemsproposedtoberelocatedsuchthatnodocumentsrequiresubmittaltotheNRCatthistime.ThecurrentscheduleforimplementationoftheITSforGinnaStationindicatesNRCStaffapprovaloftheproposednewTSbyNovember1995.Therefore,RG&ErequeststhatNRCreviewofthesethreedocumentsbecoordinatedtosupportthisschedule.Vertrulyyours,MDFK677AttachmentsRobertC.Mecedyxc:U.S.NuclearRegulatoryCommissionMr.AllenR.Johnson(MailStop14B2)PWRProjectDirectorateI-1Washington,D.C.20555U.S.NuclearRegulatoryCommissionRegionI475AllendaleRoadKingofPrussia,PA19406GinnaSeniorResidentInspector Table1R.E.GinnaProposedCOLRParametersGinnaITSCOLRParameterNRCApprovedMethodology3.1.1ShutdownMarginLimitsWCAP-9272-P-A,WestinghouseReloadSafetyEvaluationMethodology,July19853.1.33.1.33.1.53.1.63.2.13.2.23.2.3ModeratorTemperatureCoefficient-BOLlimitsModeratorTemperatureCoefficient-EOLLimitsShutdownBankInsertionLimitControlBankInsertion,Sequence,andOverlapLimitsHeatfluxhot.channelfactor(F<(Z)limits),K(Z)curve,andequationNuclearEnthalpyRiseHotChannelFactor(F~limit),powerfactormultiplierandequationAFDCAOClimitsandtarget,bandWCAP-9272-P-A,WestinghouseReloadSafetyEvaluationMethodology,July1985WCAP-9272-P-A,WestinghouseReloadSafetyEvaluationMethodology,July1985WCAP-9272-P-A,WestinghouseReloadSafetyEvaluationMethodology,July1985WCAP-9272-P-A,WestinghouseReloadSafetyEvaluationMethodology,July1985WCAP-9272-P-A,WestinghouseReloadSafetyEvaluationMethodology,July1985WCAP-9220-P-A,WestinghouseECCSEvaluationModel-1981Version,Rev.1,February1982WCAP-9272-P-A,WestinghouseReloadSafetyEvaluationMethodology,July1985WCAP-9272-P-A,WestinghouseReloadSafetyEvaluationMethodology,July1985WCAP-8385,PowerDistributionControlandLoadFollowingProcedures-TopicalReport,September1974 | RochesterGasandElectric(RG&E)currentlyanticipatessubmittingtheproposedconversiontoImprovedTechnicalSpecifications(ITS)consistentwithNUREG-1431laterthismonth.Includedwithinthissubmittalareseveralchangestotheexistingtechnicalspecifications(TS)thataresupportedbyengineeringcalculationsorotherdocumentsthatwillrequireNRCStaffreviewandapprovalseparatefromtheconversionreview.Basedonrecentconversations,theNRChasrequestedthatRG&EprovidethesedocumentspriortotheITSsubmittaltoallowtheNRCStaffadditionaltimeforreview.Therefore,attachedarethefollowingdocuments:(a)"CriticalityAnalysisoftheR.E.GinnaNuclearPowerPlantFreshandSpentFuelRacks,andConsolidatedRodStorageCanisters,"datedJune1994.(b)WCAP-14040,"MethodologyUsedtoDevelopColdOverpressureMitigatingSystemSetpointsandRCSHeatupandCooldownLimitCurves,"Revision1,December1994.(c)RG&EMethodologyforDeterminingtheLowTemperatureOverpressureProtectionSystem(LTOPS)Setpoints.Thespentfuelpoolcriticalitystudyisrequiredtosupportanincreaseinallowedfuelenrichmentnecessarytosupportaconversion,to18monthfuelcycleswhichisplannedtobeginfollowingthe1996refuelingoutage.AnincreasedinfuelenrichmentaffectscurrentGinnaStationTS5.3.1.bandTS5.4.~GgQQ95OS<S00<49S0505PDRADGCK05000244PPDR,';oi TheremainingtwodocumentssupporttheincorporationofaPressureTemperatureLimitsReport(PTLR)whichisplannedtobeimplementedduringtheconversiontoITS.SinceGinnaStationutilizestheLTOPSforpreventingoverpressurizationoftheresidualheatremovalsystem,Section3.0ofWCAP-14040doesnotapplytotheinstalledsystem.Therefore,RG&Especificmethodologyisprovidedforyourreview.BoththeRG&Especificmethodologyandared-linemarkupofthemethodologyprovidedinWCAP-14040areprovided.AllitemsproposedtoberelocatedfromthecurrentGinnaStationTStothePTLRareaddressedbythesetwodocuments.TheitemsRG&EanticipatestoberelocatedtotheCoreOperatingLimitsReport(COLR)areprovidedinattachedTable1.Ascanbeseenfromthistable,NRCapprovedmethodologyexistsforallitemsproposedtoberelocatedsuchthatnodocumentsrequiresubmittaltotheNRCatthistime.ThecurrentscheduleforimplementationoftheITSforGinnaStationindicatesNRCStaffapprovaloftheproposednewTSbyNovember1995.Therefore,RG&ErequeststhatNRCreviewofthesethreedocumentsbecoordinatedtosupportthisschedule.Vertrulyyours,MDFK677AttachmentsRobertC.Mecedyxc:U.S.NuclearRegulatoryCommissionMr.AllenR.Johnson(MailStop14B2)PWRProjectDirectorateI-1Washington,D.C.20555U.S.NuclearRegulatoryCommissionRegionI475AllendaleRoadKingofPrussia,PA19406GinnaSeniorResidentInspector Table1R.E.GinnaProposedCOLRParametersGinnaITSCOLRParameterNRCApprovedMethodology3.1.1ShutdownMarginLimitsWCAP-9272-P-A,WestinghouseReloadSafetyEvaluationMethodology,July19853.1.33.1.33.1.53.1.63.2.13.2.23.2.3ModeratorTemperatureCoefficient-BOLlimitsModeratorTemperatureCoefficient-EOLLimitsShutdownBankInsertionLimitControlBankInsertion,Sequence,andOverlapLimitsHeatfluxhot.channelfactor(F<(Z)limits),K(Z)curve,andequationNuclearEnthalpyRiseHotChannelFactor(F~limit),powerfactormultiplierandequationAFDCAOClimitsandtarget,bandWCAP-9272-P-A,WestinghouseReloadSafetyEvaluationMethodology,July1985WCAP-9272-P-A,WestinghouseReloadSafetyEvaluationMethodology,July1985WCAP-9272-P-A,WestinghouseReloadSafetyEvaluationMethodology,July1985WCAP-9272-P-A,WestinghouseReloadSafetyEvaluationMethodology,July1985WCAP-9272-P-A,WestinghouseReloadSafetyEvaluationMethodology,July1985WCAP-9220-P-A,WestinghouseECCSEvaluationModel-1981Version,Rev.1,February1982WCAP-9272-P-A,WestinghouseReloadSafetyEvaluationMethodology,July1985WCAP-9272-P-A,WestinghouseReloadSafetyEvaluationMethodology,July1985WCAP-8385,PowerDistributionControlandLoadFollowingProcedures-TopicalReport,September1974 | ||
3.3.1OTaTOPaTCOLRParameterNRCApprovedMethodologyWCAP-8745-P-A,DesignBasesfortheThermalOverpower~TandThermalOvertemperature~TTripFunctions,September19863.4.13.5.1DNBpressurizerpressurelimit,RCSTavglimit,andRCStotalflowlimitAccumulatorboronconcentrationWCAP-8567-P-A,ImprovedThermalDesignProcedure,February1989WCAP-11397-P-A,RevisedThermalDesignProcedure,April1989WCAP-9272-P-A,WestinghouseReloadSafetyEvaluationMethodology,July19853.5.4RWSTboronconcentrationWCAP-9272-P-A,WestinghouseReloadSafetyEvaluationMethodology,July19853.7.123.9.1SpentFuelPoolBoronConcentrationMODE6/RefuelingBoronConcentrationWCAP-11596-P-A,PHOENIX-P/ANCNuclearDesignSystemforPressurizedWaterReactorCores,June1988WCAP-9272-P-A,WestinghouseReloadSafetyEvaluationMethodology,July1985 AttachmentACriticalityAnalysisoftheR.E.GinnaNuclearPowerPlantFreshandSpentFuelRacks,andConsolidatedRodStorageCanisters 0/ | 3.3.1OTaTOPaTCOLRParameterNRCApprovedMethodologyWCAP-8745-P-A,DesignBasesfortheThermalOverpower~TandThermalOvertemperature~TTripFunctions,September19863.4.13.5.1DNBpressurizerpressurelimit,RCSTavglimit,andRCStotalflowlimitAccumulatorboronconcentrationWCAP-8567-P-A,ImprovedThermalDesignProcedure,February1989WCAP-11397-P-A,RevisedThermalDesignProcedure,April1989WCAP-9272-P-A,WestinghouseReloadSafetyEvaluationMethodology,July19853.5.4RWSTboronconcentrationWCAP-9272-P-A,WestinghouseReloadSafetyEvaluationMethodology,July19853.7.123.9.1SpentFuelPoolBoronConcentrationMODE6/RefuelingBoronConcentrationWCAP-11596-P-A,PHOENIX-P/ANCNuclearDesignSystemforPressurizedWaterReactorCores,June1988WCAP-9272-P-A,WestinghouseReloadSafetyEvaluationMethodology,July1985 AttachmentACriticalityAnalysisoftheR.E.GinnaNuclearPowerPlantFreshandSpentFuelRacks,andConsolidatedRodStorageCanisters 0/}} | ||
}} | |||
Revision as of 13:27, 18 May 2018
| ML17263B045 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 05/05/1995 |
| From: | MECREDY R C ROCHESTER GAS & ELECTRIC CORP. |
| To: | JOHNSON A R NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML17263B047 | List: |
| References | |
| RTR-NUREG-1431 NUDOCS 9505150014 | |
| Download: ML17263B045 (8) | |
Text
PRIORIT'YZREGULAT(<NAORMNEetHVTSVREMTION4STEM(RZDS)ACCESSIONNBR:9505150014DOC.DATE:95/05/05NOTARIZED:NOFACIL:50-244RobertEmmetGinnaNuclearPlant,Unit1RochesterGAUTHi,NAMEAUTHORAFFILIATIONMECREDY,R.C.RochesterGas&ElectricCorp.RECIP.NAMERECIPIENTAFFILIATIONJOHNSON,A.R.DocumentControlBranch(DocentControlDesk)JOHNSON,A.R.ProjectDirectorateI-1(PDl-1)(Post941001)
SUBJECT:
ForwardslisteddoucmentsforNRCreview6approvalpriorsubmittalofimprovedTSconsistentw/NUREG-1431.DISTRIBUTIONCODE:A001DCOPIESRECEIVED:LTRENCLSIZE:TITLE:ORSubmittal:GeneralDistributionDOCKETI05000244toPNOTES:LicenseExpdateinaccordancewith10CFR2,2.109(9/19/72).05000244PINTERNARECIPIENTIDCODE/NAMEPDl-1LAJOHNSON,AECEDRCH/HICBNRR/DSSA/SRXBOGC/HDS3COPIESLTTRENCL111111111110RECIPIENT1DCODE/NAMEPD1-1PDNRR/DE/EMCBNRR/DSSA/SPLBNUDOCS-ABSTRACTCOPIESLTTRENCL11111111YEXTERNAL:NOAC11NRCPDR11DUNNOTETOALL"RIDS"RECIPIENTS:.PLEASEHELPUSTOREDUCEWASTE!CONTACTTHEDOCL'MENTCONTROLDESK,ROOIIIPI-37(EXT.504-20S3)TOELIMIYATEYOURNAMEFROiIDISTRIBUTIOY.LISTSFORDOCUKIEYTSYOUDON"I'EED!TOTALNUMBEROFCOPIESREQUIRED:LTTR12ENCL11 4NDROCHESTERGASANDELECTRICCORPORATION~89EASTAYENUE,ROCHESTER,N.YId6d9-0001AREACODE7165'-2700ROBERTC.MECREDYVicePresidentkucteorOperationsMay5,1995U.S.NuclearRegulatoryCommissionDocumentControlDeskAttn:AllenR.JohnsonProjectDirectorateI-1Washington,D.C.20555
Subject:
TechnicalSpecificationImprovementProgramRochesterGas&ElectricCorporationR.E.GinnaNuclearPowerPlantDocketNo.50-244
DearMr.Johnson,
RochesterGasandElectric(RG&E)currentlyanticipatessubmittingtheproposedconversiontoImprovedTechnicalSpecifications(ITS)consistentwithNUREG-1431laterthismonth.Includedwithinthissubmittalareseveralchangestotheexistingtechnicalspecifications(TS)thataresupportedbyengineeringcalculationsorotherdocumentsthatwillrequireNRCStaffreviewandapprovalseparatefromtheconversionreview.Basedonrecentconversations,theNRChasrequestedthatRG&EprovidethesedocumentspriortotheITSsubmittaltoallowtheNRCStaffadditionaltimeforreview.Therefore,attachedarethefollowingdocuments:(a)"CriticalityAnalysisoftheR.E.GinnaNuclearPowerPlantFreshandSpentFuelRacks,andConsolidatedRodStorageCanisters,"datedJune1994.(b)WCAP-14040,"MethodologyUsedtoDevelopColdOverpressureMitigatingSystemSetpointsandRCSHeatupandCooldownLimitCurves,"Revision1,December1994.(c)RG&EMethodologyforDeterminingtheLowTemperatureOverpressureProtectionSystem(LTOPS)Setpoints.Thespentfuelpoolcriticalitystudyisrequiredtosupportanincreaseinallowedfuelenrichmentnecessarytosupportaconversion,to18monthfuelcycleswhichisplannedtobeginfollowingthe1996refuelingoutage.AnincreasedinfuelenrichmentaffectscurrentGinnaStationTS5.3.1.bandTS5.4.~GgQQ95OS<S00<49S0505PDRADGCK05000244PPDR,';oi TheremainingtwodocumentssupporttheincorporationofaPressureTemperatureLimitsReport(PTLR)whichisplannedtobeimplementedduringtheconversiontoITS.SinceGinnaStationutilizestheLTOPSforpreventingoverpressurizationoftheresidualheatremovalsystem,Section3.0ofWCAP-14040doesnotapplytotheinstalledsystem.Therefore,RG&Especificmethodologyisprovidedforyourreview.BoththeRG&Especificmethodologyandared-linemarkupofthemethodologyprovidedinWCAP-14040areprovided.AllitemsproposedtoberelocatedfromthecurrentGinnaStationTStothePTLRareaddressedbythesetwodocuments.TheitemsRG&EanticipatestoberelocatedtotheCoreOperatingLimitsReport(COLR)areprovidedinattachedTable1.Ascanbeseenfromthistable,NRCapprovedmethodologyexistsforallitemsproposedtoberelocatedsuchthatnodocumentsrequiresubmittaltotheNRCatthistime.ThecurrentscheduleforimplementationoftheITSforGinnaStationindicatesNRCStaffapprovaloftheproposednewTSbyNovember1995.Therefore,RG&ErequeststhatNRCreviewofthesethreedocumentsbecoordinatedtosupportthisschedule.Vertrulyyours,MDFK677AttachmentsRobertC.Mecedyxc:U.S.NuclearRegulatoryCommissionMr.AllenR.Johnson(MailStop14B2)PWRProjectDirectorateI-1Washington,D.C.20555U.S.NuclearRegulatoryCommissionRegionI475AllendaleRoadKingofPrussia,PA19406GinnaSeniorResidentInspector Table1R.E.GinnaProposedCOLRParametersGinnaITSCOLRParameterNRCApprovedMethodology3.1.1ShutdownMarginLimitsWCAP-9272-P-A,WestinghouseReloadSafetyEvaluationMethodology,July19853.1.33.1.33.1.53.1.63.2.13.2.23.2.3ModeratorTemperatureCoefficient-BOLlimitsModeratorTemperatureCoefficient-EOLLimitsShutdownBankInsertionLimitControlBankInsertion,Sequence,andOverlapLimitsHeatfluxhot.channelfactor(F<(Z)limits),K(Z)curve,andequationNuclearEnthalpyRiseHotChannelFactor(F~limit),powerfactormultiplierandequationAFDCAOClimitsandtarget,bandWCAP-9272-P-A,WestinghouseReloadSafetyEvaluationMethodology,July1985WCAP-9272-P-A,WestinghouseReloadSafetyEvaluationMethodology,July1985WCAP-9272-P-A,WestinghouseReloadSafetyEvaluationMethodology,July1985WCAP-9272-P-A,WestinghouseReloadSafetyEvaluationMethodology,July1985WCAP-9272-P-A,WestinghouseReloadSafetyEvaluationMethodology,July1985WCAP-9220-P-A,WestinghouseECCSEvaluationModel-1981Version,Rev.1,February1982WCAP-9272-P-A,WestinghouseReloadSafetyEvaluationMethodology,July1985WCAP-9272-P-A,WestinghouseReloadSafetyEvaluationMethodology,July1985WCAP-8385,PowerDistributionControlandLoadFollowingProcedures-TopicalReport,September1974
3.3.1OTaTOPaTCOLRParameterNRCApprovedMethodologyWCAP-8745-P-A,DesignBasesfortheThermalOverpower~TandThermalOvertemperature~TTripFunctions,September19863.4.13.5.1DNBpressurizerpressurelimit,RCSTavglimit,andRCStotalflowlimitAccumulatorboronconcentrationWCAP-8567-P-A,ImprovedThermalDesignProcedure,February1989WCAP-11397-P-A,RevisedThermalDesignProcedure,April1989WCAP-9272-P-A,WestinghouseReloadSafetyEvaluationMethodology,July19853.5.4RWSTboronconcentrationWCAP-9272-P-A,WestinghouseReloadSafetyEvaluationMethodology,July19853.7.123.9.1SpentFuelPoolBoronConcentrationMODE6/RefuelingBoronConcentrationWCAP-11596-P-A,PHOENIX-P/ANCNuclearDesignSystemforPressurizedWaterReactorCores,June1988WCAP-9272-P-A,WestinghouseReloadSafetyEvaluationMethodology,July1985 AttachmentACriticalityAnalysisoftheR.E.GinnaNuclearPowerPlantFreshandSpentFuelRacks,andConsolidatedRodStorageCanisters 0/