ML18040A969: Difference between revisions
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==References:== | ==References:== | ||
1.LetterPomVictorNerses(NRC)toRobertG.Byram(PP&L),"SusquehannaSteamElectricStation,Unit2PACNo.MA2434),"February17,1999.2.EMF-1997(P)(A)Revision0,"ANFB-10CriticalPowerCorrelation,"July1998,andEMF-1997(P)(A)Supplement1Revision0,"ANFB-10Cr'iticalPowerCorrelation:HighLocalPeakingResults,"July1998.3.ANF-I125(P)(A)andANF-1125(P)(A),Supplement1,"ANFBCriticalPowerCorrelation,"April1990.4.PL-NF-90-001-A,"ApplicationofReactorAnalysisMethodsforBWRDesignandAnalysis,"July1992,plusSupplements1-A(August1995)and2-A(July1996).5.'MF-97-010(P),Rev.1,"ApplicationofANFBtoATRlUMrM-10forSusquehannaReloads,"March1997.6.PLA-4595,"ResponsetoNRCRequestforAdditionalInformationonSiemens'eportEMF-97-'1'0,Revision1,"Mar'ch27,199'7.'.ANF-524(P)(A),Revision2andSupplement1,Revision2,"AdvancedNuclearFuelsCorporationCriticalPowerMethodologyforBoilingWaterReactors,"November1990.8.CENPD-300-P,"ReferenceSafetyReportforBoilingWaterReactorReloadFuel,"ABBCombustionEngineeringNuclearOperations,November1994.~iThepurposeofthisletteristoproposechangestotheSusquehannaSteamElectricStationUnit1TechnicalSpecifications,whicharesimilartothoserecentlyapprovedinFebruary1999forUnit2(Reference1).Reference2documentstheNRCapprovedcriticalpower'correlationapplicabletoSiemensPowerCorporation(SPC)ATRIUMŽ-10fuel(referredtoasANFB-10).ThisproposedchangeentailstheinclusionofReference2inSection5.6.5andtheinclusionofrevisedMCPRSafetyLimitsinSection2.1.1.2.AnadministrativechangetoSection5.6.5isincluded.AnumberofreferencesfromSection5.6.5areremovedinordertoincludeonlythosereferenceswhichdirectlysupportthegenerationoftheCoreOperatingLimitsandtoremovethereferencefortheABBLeadUseAssemblies(Reference8),whichwillbedischargedduringthenextUnit1outage.AssociatedBASESchangesarealsoincluded.9903290101.9'70312PDRADOCK05000387I'PPDRbpPOIi | 1.LetterPomVictorNerses(NRC)toRobertG.Byram(PP&L),"SusquehannaSteamElectricStation,Unit2PACNo.MA2434),"February17,1999.2.EMF-1997(P)(A)Revision0,"ANFB-10CriticalPowerCorrelation,"July1998,andEMF-1997(P)(A)Supplement1Revision0,"ANFB-10Cr'iticalPowerCorrelation:HighLocalPeakingResults,"July1998.3.ANF-I125(P)(A)andANF-1125(P)(A),Supplement1,"ANFBCriticalPowerCorrelation,"April1990.4.PL-NF-90-001-A,"ApplicationofReactorAnalysisMethodsforBWRDesignandAnalysis,"July1992,plusSupplements1-A(August1995)and2-A(July1996).5.'MF-97-010(P),Rev.1,"ApplicationofANFBtoATRlUMrM-10forSusquehannaReloads,"March1997.6.PLA-4595,"ResponsetoNRCRequestforAdditionalInformationonSiemens'eportEMF-97-'1'0,Revision1,"Mar'ch27,199'7.'.ANF-524(P)(A),Revision2andSupplement1,Revision2,"AdvancedNuclearFuelsCorporationCriticalPowerMethodologyforBoilingWaterReactors,"November1990.8.CENPD-300-P,"ReferenceSafetyReportforBoilingWaterReactorReloadFuel,"ABBCombustionEngineeringNuclearOperations,November1994.~iThepurposeofthisletteristoproposechangestotheSusquehannaSteamElectricStationUnit1TechnicalSpecifications,whicharesimilartothoserecentlyapprovedinFebruary1999forUnit2(Reference1).Reference2documentstheNRCapprovedcriticalpower'correlationapplicabletoSiemensPowerCorporation(SPC)ATRIUMŽ-10fuel(referredtoasANFB-10).ThisproposedchangeentailstheinclusionofReference2inSection5.6.5andtheinclusionofrevisedMCPRSafetyLimitsinSection2.1.1.2.AnadministrativechangetoSection5.6.5isincluded.AnumberofreferencesfromSection5.6.5areremovedinordertoincludeonlythosereferenceswhichdirectlysupportthegenerationoftheCoreOperatingLimitsandtoremovethereferencefortheABBLeadUseAssemblies(Reference8),whichwillbedischargedduringthenextUnit1outage.AssociatedBASESchangesarealsoincluded.9903290101.9'70312PDRADOCK05000387I'PPDRbpPOIi PLA-5040DocumentControlDeskTheANFB-10correlationwillbeusedintheanalysisofATRIUMŽ-10fuelinplaceoftheANFBcriticalpowercorrelationandmethodologydescribedinReferences5and6.TheANFBcorrelation(Reference3)willcontinuetobeusedintheanalysisofSPC9x9-2fuel.TheANFB(for9x9-2)andANFB-10(forATRIUM~-10)correlationswillbeusedwithPP&L'sandSPC'sNRCapprovedmethods,andanalyseswillbeperformed(consistentwiththosemethods)togenerateCoreOperatingLimits.Therefore,PP&LwillnotbesubmittingachangetoitsNRC-approvedTopicalReports(Reference4)sincethemethodologyisthesameexceptANFB-10willbeusedtoanalyzeATRIUM-10fuel.SPCreportEMF-1997,gggA),Rev.0andSupplement1,Rev.0(proposed,toQe.addedtothe,.TechnicalSpecificationAdministrativeControlssection)describestheANFB-10criticalpowercorrelation,whichhasbeenapprovedby'theNRC.EnclosureAtothisletteristhe"SafetyAssessment"supportingthischange.EnclosureBisthe"NoSignificantHazardsConsiderationsandEnvironmentalAssessment"evaluationperformedinaccordancewiththecriteriaof10CFR50.92.EnclosureCtothislettercontainstheapplicablepagesoftheSusquehannaSESUnit1TechnicalSpecifications,markedtoshowtheproposedchangesaswellastheassociatedBASESchanges.TheproposedchangeshavebeenapprovedbytheSusquehannaSESPlantOperationsReviewCommittee,andreviewedbytheSusquehannaReviewCommittee.Toassistinyourreview,AttachmentsUnit1Cycle12CoreComposition.TechnicalSpecificationsforthoseSpecifications.DandEhavebeenprovided.AttachmentDprovidestheAttachmentEprovidesacross-referencetoapplicablereferencesspecifiedinSection5.6.5ofTechnical*'PP&LplanstoimplementtheproposedchangesinMay2000tosupportthestartupofUnit1Cycle12operation.Therefore,werequestNRCcompleteitsreviewofthischangebyFebruary11,2000withthechangeseffectiveuponstartupfollowingtheUnit111~RefuelingandInspectionOutagetosupportourscheduledimplementationdate.Anyquestionsregardingthisrequestshouldbedirectedto.Mr.R.R.Sgarroat(610)774-7552.'erytrulyyours,R..By PLA-5040DocumentControlDeskcopy:NRCRegionIMr.V.Nerses,NRCSr.ProjectManager-QWFNMr.S.L.Hansell,ActingNRCSr.ResidentInspector-SSESMr.D.J.Allard,Pa.DEP 0l | ||
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Revision as of 21:44, 2 May 2018
ML18040A969 | |
Person / Time | |
---|---|
Site: | Susquehanna ![]() |
Issue date: | 03/12/1999 |
From: | BYRAM R G PENNSYLVANIA POWER & LIGHT CO. |
To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
Shared Package | |
ML17164A990 | List: |
References | |
PLA-5040, NUDOCS 9903290101 | |
Download: ML18040A969 (4) | |
Text
RobertG.ByramSeniorVicePresidentGenerationandChiefNuclearOfficerTel.610.774.7502Fax610.774.5019E-mail:rgbyramepapl.cornBAR1:21999PPtLL,Inc.TwoNorthNinthStreetAllentown,PA18101-1179Tel.610.774.5151http:ltwww.pap!.corn/gsrLsQ~w+emU.S.NuclearRegulatoryCommissionAttn.:DocumentControlDeskMailStationP1-137Washington,D.C.20555SUSQUEHANNASTEAMELECTRICSTATIONPROPOSEDAMENDMENTNO.227TOLICENSENPF-14:ANFB-10CRITICAL.POWER.CORRELATIONAND.MCPRSAFETYLIMITSPLA-5040%1IDocketNo.50-387
References:
1.LetterPomVictorNerses(NRC)toRobertG.Byram(PP&L),"SusquehannaSteamElectricStation,Unit2PACNo.MA2434),"February17,1999.2.EMF-1997(P)(A)Revision0,"ANFB-10CriticalPowerCorrelation,"July1998,andEMF-1997(P)(A)Supplement1Revision0,"ANFB-10Cr'iticalPowerCorrelation:HighLocalPeakingResults,"July1998.3.ANF-I125(P)(A)andANF-1125(P)(A),Supplement1,"ANFBCriticalPowerCorrelation,"April1990.4.PL-NF-90-001-A,"ApplicationofReactorAnalysisMethodsforBWRDesignandAnalysis,"July1992,plusSupplements1-A(August1995)and2-A(July1996).5.'MF-97-010(P),Rev.1,"ApplicationofANFBtoATRlUMrM-10forSusquehannaReloads,"March1997.6.PLA-4595,"ResponsetoNRCRequestforAdditionalInformationonSiemens'eportEMF-97-'1'0,Revision1,"Mar'ch27,199'7.'.ANF-524(P)(A),Revision2andSupplement1,Revision2,"AdvancedNuclearFuelsCorporationCriticalPowerMethodologyforBoilingWaterReactors,"November1990.8.CENPD-300-P,"ReferenceSafetyReportforBoilingWaterReactorReloadFuel,"ABBCombustionEngineeringNuclearOperations,November1994.~iThepurposeofthisletteristoproposechangestotheSusquehannaSteamElectricStationUnit1TechnicalSpecifications,whicharesimilartothoserecentlyapprovedinFebruary1999forUnit2(Reference1).Reference2documentstheNRCapprovedcriticalpower'correlationapplicabletoSiemensPowerCorporation(SPC)ATRIUMŽ-10fuel(referredtoasANFB-10).ThisproposedchangeentailstheinclusionofReference2inSection5.6.5andtheinclusionofrevisedMCPRSafetyLimitsinSection2.1.1.2.AnadministrativechangetoSection5.6.5isincluded.AnumberofreferencesfromSection5.6.5areremovedinordertoincludeonlythosereferenceswhichdirectlysupportthegenerationoftheCoreOperatingLimitsandtoremovethereferencefortheABBLeadUseAssemblies(Reference8),whichwillbedischargedduringthenextUnit1outage.AssociatedBASESchangesarealsoincluded.9903290101.9'70312PDRADOCK05000387I'PPDRbpPOIi PLA-5040DocumentControlDeskTheANFB-10correlationwillbeusedintheanalysisofATRIUMŽ-10fuelinplaceoftheANFBcriticalpowercorrelationandmethodologydescribedinReferences5and6.TheANFBcorrelation(Reference3)willcontinuetobeusedintheanalysisofSPC9x9-2fuel.TheANFB(for9x9-2)andANFB-10(forATRIUM~-10)correlationswillbeusedwithPP&L'sandSPC'sNRCapprovedmethods,andanalyseswillbeperformed(consistentwiththosemethods)togenerateCoreOperatingLimits.Therefore,PP&LwillnotbesubmittingachangetoitsNRC-approvedTopicalReports(Reference4)sincethemethodologyisthesameexceptANFB-10willbeusedtoanalyzeATRIUM-10fuel.SPCreportEMF-1997,gggA),Rev.0andSupplement1,Rev.0(proposed,toQe.addedtothe,.TechnicalSpecificationAdministrativeControlssection)describestheANFB-10criticalpowercorrelation,whichhasbeenapprovedby'theNRC.EnclosureAtothisletteristhe"SafetyAssessment"supportingthischange.EnclosureBisthe"NoSignificantHazardsConsiderationsandEnvironmentalAssessment"evaluationperformedinaccordancewiththecriteriaof10CFR50.92.EnclosureCtothislettercontainstheapplicablepagesoftheSusquehannaSESUnit1TechnicalSpecifications,markedtoshowtheproposedchangesaswellastheassociatedBASESchanges.TheproposedchangeshavebeenapprovedbytheSusquehannaSESPlantOperationsReviewCommittee,andreviewedbytheSusquehannaReviewCommittee.Toassistinyourreview,AttachmentsUnit1Cycle12CoreComposition.TechnicalSpecificationsforthoseSpecifications.DandEhavebeenprovided.AttachmentDprovidestheAttachmentEprovidesacross-referencetoapplicablereferencesspecifiedinSection5.6.5ofTechnical*'PP&LplanstoimplementtheproposedchangesinMay2000tosupportthestartupofUnit1Cycle12operation.Therefore,werequestNRCcompleteitsreviewofthischangebyFebruary11,2000withthechangeseffectiveuponstartupfollowingtheUnit111~RefuelingandInspectionOutagetosupportourscheduledimplementationdate.Anyquestionsregardingthisrequestshouldbedirectedto.Mr.R.R.Sgarroat(610)774-7552.'erytrulyyours,R..By PLA-5040DocumentControlDeskcopy:NRCRegionIMr.V.Nerses,NRCSr.ProjectManager-QWFNMr.S.L.Hansell,ActingNRCSr.ResidentInspector-SSESMr.D.J.Allard,Pa.DEP 0l