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{{#Wiki_filter:ReportingRequirementsD.O5.6ReportingRequirements5.6.5COLR(continued)XN-NF-81-58(P)(A)Supplements1and2Revision2"RODEX2FuelRodThermal-MechanicalResponseluationModel,"May1986.24.XN-NF-4(P)(A)."RODEX2A(BWR)FRodThermal-MechanicasponseEvaluationMo,"August1986.'V0LllQIOlC+d00aa0-~P00CLIVloChC25.26.27.2.30~17.el'N-NF-82-06(P)(A)aements2~4and5Revision1,"QualifiofExxonNuclearFuel'for.ExtendedBurnup,"ober8.XN-NF-85-92A)."ExxonNuclearaniumDioxide/oliniaIrradiationExamiionandThermalConduvity."November1986.-90-082(P)(A)Revision1andRevision1Supplement1,"ApplicationofANFDesignMethodoforFuelAssembl'yReconstitution,"May1995.ANF-91-048(P)(A)."AdvancedNuclearFuelsCorporationMethodologyforBoilingWaterReactorsEXEMBWREvaluationModel."January1993.-CC-33(P)(A)Supplement2,"HUXY:AGenerMulitupCodewith10CRF50A'eatupOption,"Janl.XN-CC-33(P)sion1.".eneralizedMult'tupCodewith10CFR50Appe'eatupionUsersManual,"November1975:XN-NF-80-19(P)(A).Volumes2.2A.2B;and2C"Exxon'uclearMethodologyforBoilingWaterReactors:EXEMBWRECCSEvaluationModel."September1982.XN-NF-80-19(P)(A).Volumes3Revision2"ExxonNuclearMethodologyforBoilingWaterReactorsThermex:ThermalLimitsMethodologySummaryDescription,"January1987.XN-NF-79-71(P)(A)Revision2,Supplements1,.2.and3."ExxonNuclearPlantTransientMethodologyforBoilingt"r61OmcontinuSUSQUEHANNA-UNIT25.0-24Amendment151990i2i0326990ii2PDRADQCK-05000388P'.PDR 0\PlnftP'tIC a'DistributionSheetDistri58.txt~/~PonePriority:NormalFrom:EsperanzaLomosbogActionRecipients:RidsNrrPMRSchaafRidsNrrLAMObrienRidsNrrDlpmLpdi1Copies:000OKOKOKInternalRecipients:RidsRgn1MailCenterRidsOgcRpRidsNrrWpcMailRidsNrrDssaSrxbRidsManagerRidsAcrsAcnwMai+Center+FILECENTER-01~ACRS000OKOKOKOKOK0OKPaperCopyPaperCopyExternalRecipients:NOACPaperCopyTotalCopies:Item:ADAMSDocumentLibrary:MLADAMS"HQNTAD01ID:003700504:1
{{#Wiki_filter:Reporting Requirements D.O5.6Reporting Requirements5.6.5COLR(continued)
XN-NF-81-58(P)(A)
Supplements 1and2Revision2"RODEX2FuelRodThermal-Mechanical ResponseluationModel,"May1986.24.XN-NF-4(P)(A)."RODEX2A(BWR)FRodThermal-Mechanica sponseEvaluation Mo,"August1986.'V0LllQIOlC+d00aa0-~P00CLIVloChC25.26.27.2.30~17.el'N-NF-82-06(P)(A) aements2~4and5Revision1,"QualifiofExxonNuclearFuel'for.
ExtendedBurnup,"ober8.XN-NF-85-92 A)."ExxonNuclearaniumDioxide/oliniaIrradiation ExamiionandThermalConduvity."November1986.-90-082(P)(A)
Revision1andRevision1Supplement 1,"Application ofANFDesignMethodoforFuelAssembl'y Reconstitution,"
May1995.ANF-91-048(P)(A).
"Advanced NuclearFuelsCorporation Methodology forBoilingWaterReactorsEXEMBWREvaluation Model."January1993.-CC-33(P)(A)
Supplement 2,"HUXY:AGenerMulitupCodewith10CRF50A'eatupOption,"Janl.XN-CC-33(P) sion1.".eneralized Mult'tupCodewith10CFR50Appe'eatupionUsersManual,"November1975:XN-NF-80-19(P)(A).
Volumes2.2A.2B;and2C"Exxon'uclearMethodology forBoilingWaterReactors:
EXEMBWRECCSEvaluation Model."September 1982.XN-NF-80-19(P)(A).
Volumes3Revision2"ExxonNuclearMethodology forBoilingWaterReactorsThermex:ThermalLimitsMethodology SummaryDescription,"
January1987.XN-NF-79-71(P)(A)
Revision2,Supplements 1,.2.and3."ExxonNuclearPlantTransient Methodology forBoilingt"r61OmcontinuSUSQUEHANNA
-UNIT25.0-24Amendment 151990i2i0326 990ii2PDRADQCK-05000388 P'.PDR 0\PlnftP'tIC a'Distribution SheetDistri58.txt
~/~PonePriority:
NormalFrom:Esperanza LomosbogActionRecipients:
RidsNrrPMRSchaaf RidsNrrLAMObrien RidsNrrDlpmLpdi1 Copies:000OKOKOKInternalRecipients:
RidsRgn1MailCenter RidsOgcRp RidsNrrWpcMail RidsNrrDssaSrxb RidsManagerRidsAcrsAcnwMai+Center
+FILECENTER-01~
ACRS000OKOKOKOKOK0OKPaperCopyPaperCopyExternalRecipients:
NOACPaperCopyTotalCopies:Item:ADAMSDocumentLibrary:MLADAMS"HQNTAD01ID:003700504:1


==Subject:==
==Subject:==
SSES,ProposedAmendment194,InclusionofMCPRSafetyLimitsinTechnicalSpecificationsSection2.1.1.2Body:ADAMSDISTRIBUTIONNOTIFICATION.ElectronicRecipientscanRIGHTCLICKandOPENthefirstAttachmenttoViewtheDocumentinADAMS.TheDocumentmayalsobeviewedbysearchingforAccessionNumberML003700504.Page1 Distri58.txtA001-ORSubmittal:GeneralDistributionDocket:05000388Page2 RobertG.ByramSeniorVicePresidentandChiefNuclearOfficerTel.610.774.7502Fax610.774.5019E-mail:rgbyram@papl.cornPP&L,Inc.TwoNorthNinthStreetAllentovm,PA16101-1179Tel.610.774.5151IgIppMAR20,2000U.S.NuclearRegulatoryCommissionAttn:DocumentControlDeskMailStationOP1-17Washington,D.C.20555\SUSQUEHANNASTEAMELECTRICSTATIONPROPOSEDAMENDMENTNO.194TOLICENSENPF-22:MCPRSAFETYLIMITSPLA-5169DocketNo.50-388ThepurposeofthisletteristoproposechangestotheSusquehannaSteamElectricStationUnit2TechnicalSpecifications.ThisproposedchangeentailstheinclusionofUnit2Cycle11(U2C11)MCPRSafetyLimitsinSection2.1.1.2.ConsistentwiththepreviousUnit2reloadanalysis,theanalysismethodsdescribedinTechnicalSpecification5.6.5b.,asapprovedbytheNRC,areusedtogeneratetheSafetyLimitsandCoreOperatingLimitsfortheU2C11reload.EnclosureAtothisletteristhe"SafetyAssessment"supportingthischange.Enclosure8istheNoSignificantHazardsConsiderationsevaluationperformedinaccordancewiththecriteriaof10CFR50.92andtheEnvironmentalAssessment.EnclosureCtothislettercontainstheapplicablepageoftheSusquehannaSESUnit2TechnicalSpecifications,markedtoshowtheproposedchange.AttachmentDcontains"cameraready"versionoftherevisedTechnicalSpecificationpage.TheproposedchangehasbeenapprovedbytheSusquehannaSESPlantOperationsReviewCommitteeandreviewedbytheSusquehannaReviewCommittee.Toassistinyourreview,AttachmentEhasbeenprovided.AttachmentEprovidestheU2C11CoreComposition.  
SSES,ProposedAmendment 194,Inclusion ofMCPRSafetyLimitsinTechnical SpecificationsSection2.1.1.2Body:ADAMSDISTRIBUTION NOTIFICATION.
Electronic Recipients canRIGHTCLICKandOPENthefirstAttachment toViewtheDocumentinADAMS.TheDocumentmayalsobeviewedbysearching forAccession NumberML003700504.
Page1 Distri58.txt A001-ORSubmittal:
GeneralDistribution Docket:05000388Page2 RobertG.ByramSeniorVicePresident andChiefNuclearOfficerTel.610.774.7502 Fax610.774.5019 E-mail:rgbyram@papl.corn PP&L,Inc.TwoNorthNinthStreetAllentovm, PA16101-1179 Tel.610.774.51 51IgIppMAR20,2000U.S.NuclearRegulatory Commission Attn:DocumentControlDeskMailStationOP1-17Washington, D.C.20555\SUSQUEHANNA STEAMELECTRICSTATIONPROPOSEDAMENDMENT NO.194TOLICENSENPF-22:MCPRSAFETYLIMITSPLA-5169DocketNo.50-388ThepurposeofthisletteristoproposechangestotheSusquehanna SteamElectricStationUnit2Technical Specifications.
Thisproposedchangeentailstheinclusion ofUnit2Cycle11(U2C11)MCPRSafetyLimitsinSection2.1.1.2.Consistent withthepreviousUnit2reloadanalysis, theanalysismethodsdescribed inTechnical Specification 5.6.5b.,asapprovedbytheNRC,areusedtogeneratetheSafetyLimitsandCoreOperating LimitsfortheU2C11reload.Enclosure Atothisletteristhe"SafetyAssessment" supporting thischange.Enclosure 8istheNoSignificant HazardsConsiderations evaluation performed inaccordance withthecriteriaof10CFR50.92andtheEnvironmental Assessment.
Enclosure Ctothislettercontainstheapplicable pageoftheSusquehanna SESUnit2Technical Specifications, markedtoshowtheproposedchange.Attachment Dcontains"cameraready"versionoftherevisedTechnical Specification page.TheproposedchangehasbeenapprovedbytheSusquehanna SESPlantOperations ReviewCommittee andreviewedbytheSusquehanna ReviewCommittee.
Toassistinyourreview,Attachment Ehasbeenprovided.
Attachment EprovidestheU2C11CoreComposition.  
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PLA-5169DocumentControlDeskPPLplanstoimplementtheproposedchangesinMay2001tosupportthestartupofU2C11operation.Therefore,werequestNRCcompleteitsreviewofthischangebyJanuary31,2001withthechangeseffectiveuponstartupfollowingtheUnit210'"RefuelingandInspectionOutage.AnyquestionsregardingthisrequestshouldbedirectedtoMr.M.H.Crowthersat(610)774-7766.Verytrulyyours,Attachmentscopy:NRCRegionIMr.R.G.Schaaf,NRCSr.ProjectManagerMr.S.Hansell,NRCSr.ResidentInspectorMr.W.P.Dornsife,PADEP BEFORETHEUNITEDSTATESNUCLEARREGULATORYCOMMISSIONIntheMatterofPPEcL,INC.DocketNo.50-388PROPOSEDAMENDMENTNO.194TOLICENSENPF-22:MCPRSAFETYLIMITSSUSQUEHANNASTEAMELECTRICSTATIONUNITNO.2Licensee,PPEcL,Inc.,herebyfilesarevisiontoproposedAmendmentNo.194toitsFacilityOperatingLicenseNo.NPF-22datedMarch23,1984.ThisamendmentcontainsarevisiontotheSusquehannaSESUnit2TechnicalSpecifications.PP&L,INC.BY:Sworntoandsubscribedbeforemethisgo~dayofge~,2000.NotaryPublicR.ByrmS.Vice-PrsidentandChiefNuclearOfficerNOTARIALSEALJANlCEM.REESE,NotaryPublicCityotAllentown,LehighCounty,PA")JulyCorninimionExpiresJune11,200$
PLA-5169DocumentControlDeskPPLplanstoimplement theproposedchangesinMay2001tosupportthestartupofU2C11operation.
rt~f4~~Jt\rt ENCLOSUREATOPLA-5169SAFETYASSESSMENTMCPRSAFETYLIMITSBACKGROUNDSusquehannaSteamElectricStationUnit2,Cycle11willcontainSPCATRIUMŽ-10fuel.TheATRIUMY"'-10fueldesignisa10x10latticedesignwhichcontains83fulllengthfuelrods,8partlengthfuelrods,andacentralwaterchannel.TheMCPRSafetyLimitsforU2C11supportCoreThermalPowersupto3493MWt,whichisa1.5%increaseoverU2C10(3441MWt).Theanalysiswasperformedatthe3493MWtpowerleveltosupportlicenseamendmentstobeproposedinMay2000foranincreaseintheRatedThermalPowerlevelforSSESUnit2.SiemensPowerCorporationhasdevelopedtheANFB-10criticalpowercorrelationwhichisapplicabletotheATRIUMŽ-10fuelassemblies(TechnicalSpecification5.6.5b.19).ANFB-10isbasedonalargeamountofcriticalpowertestdataontheATRIUMY"'-10deslgil.TheMCPRSafetyLimitanalysisisperformedonacyclespecificbasissincethecoredesignchanges&omcycletocycle.TheU2C11MCPRSafetyLimitwascalculatedbySiemensPowerCorporation(SPC)usingtheNRCapprovedmethodsdescribedinTechnicalSpecification5.6.5b.5.DescritionoftheProosedChaneTheproposedUnit2TechnicalSpecificationchangesconsistof:(1)ReviseSection2.1.1.2toreflecttheU2C11MCPRSafetylimits.TheMCPRSLvaluesare1.12fortwo-loopoperationand1.14forsingle-loopoperation.TheNRC-approvedtopicalreportscontainedinSection5.6.5oftheTechnicalSpecificationscontainthemethodologyusedtoensuresafeoperationofUnit2withATRIUMŽ-10fuel.  
Therefore, werequestNRCcompleteitsreviewofthischangebyJanuary31,2001withthechangeseffective uponstartupfollowing theUnit210'"Refueling andInspection Outage.Anyquestions regarding thisrequestshouldbedirectedtoMr.M.H.Crowthers at(610)774-7766.
Verytrulyyours,Attachments copy:NRCRegionIMr.R.G.Schaaf,NRCSr.ProjectManagerMr.S.Hansell,NRCSr.ResidentInspector Mr.W.P.Dornsife, PADEP BEFORETHEUNITEDSTATESNUCLEARREGULATORY COMMISSION IntheMatterofPPEcL,INC.DocketNo.50-388PROPOSEDAMENDMENT NO.194TOLICENSENPF-22:MCPRSAFETYLIMITSSUSQUEHANNA STEAMELECTRICSTATIONUNITNO.2Licensee, PPEcL,Inc.,herebyfilesarevisiontoproposedAmendment No.194toitsFacilityOperating LicenseNo.NPF-22datedMarch23,1984.Thisamendment containsarevisiontotheSusquehanna SESUnit2Technical Specifications.
PP&L,INC.BY:Sworntoandsubscribed beforemethisgo~dayofge~,2000.NotaryPublicR.ByrmS.Vice-PrsidentandChiefNuclearOfficerNOTARIALSEALJANlCEM.REESE,NotaryPublicCityotAllentown, LehighCounty,PA")JulyCorninimion ExpiresJune11,200$
rt~f4~~Jt\rt ENCLOSURE ATOPLA-5169SAFETYASSESSMENT MCPRSAFETYLIMITSBACKGROUND Susquehanna SteamElectricStationUnit2,Cycle11willcontainSPCATRIUMŽ-10 fuel.TheATRIUMY"'-10 fueldesignisa10x10latticedesignwhichcontains83fulllengthfuelrods,8partlengthfuelrods,andacentralwaterchannel.TheMCPRSafetyLimitsforU2C11supportCoreThermalPowersupto3493MWt,whichisa1.5%increaseoverU2C10(3441MWt).Theanalysiswasperformed atthe3493MWtpowerleveltosupportlicenseamendments tobeproposedinMay2000foranincreaseintheRatedThermalPowerlevelforSSESUnit2.SiemensPowerCorporation hasdeveloped theANFB-10criticalpowercorrelation whichisapplicable totheATRIUMŽ-10 fuelassemblies (Technical Specification 5.6.5b.19).
ANFB-10isbasedonalargeamountofcriticalpowertestdataontheATRIUMY"'-10 deslgil.TheMCPRSafetyLimitanalysisisperformed onacyclespecificbasissincethecoredesignchanges&omcycletocycle.TheU2C11MCPRSafetyLimitwascalculated bySiemensPowerCorporation (SPC)usingtheNRCapprovedmethodsdescribed inTechnical Specification 5.6.5b.5.
DescritionoftheProosedChaneTheproposedUnit2Technical Specification changesconsistof:(1)ReviseSection2.1.1.2toreflecttheU2C11MCPRSafetylimits.TheMCPRSLvaluesare1.12fortwo-loopoperation and1.14forsingle-loop operation.
TheNRC-approved topicalreportscontained inSection5.6.5oftheTechnical Specifications containthemethodology usedtoensuresafeoperation ofUnit2withATRIUMŽ-10 fuel.  


ENCLOSUREATOPLA-5169SAI'KTYANALYSISExcessivethermaloverheatingofthefuelrodcladdingcanresultincladdingdamageandthereleaseoffissionproducts.Inordertoprotectthecladdingagainstthermaloverheatingduetoboilingtransition,theThermalPower,HighPressureandHighFlowSafetyLimit(Section2.1.1.2oftheSusquehannaSESUnit2TechnicalSpecification)wereestablished.ThechangestoSection2.1.1.2reflectthechange&omtheU2C10MCPRSafetyLimitstotheU2C11MCPRSafetyLimitsfortwo-loopoperationandsingle-loopoperation.NUREG-0800,StandardReviewPlanSection4.4,specifiesanacceptable,conservativeapproachtodefinethisSafetyLimit.Specifically,aMinimumCriticalPowerRatio(MCPR)valueisspecifiedsuchthatatleast99.9%ofthefuelrodsareexpectedtoavoidboilingtransitionduringnormaloperationorAnticipatedOperationalOccurrences(AOOs).Boilingtransitionispredictedusingacorrelationbasedontestdata(i.e.,aCriticalPowerCorrelation).TheSafetyLimitMCPRcalculationaccountsforvariousuncertaintiessuchasfeedwaterflow,feedwatertemperature,pressure,powerdistributionuncertainties,anduncertaintyintheCriticalPowerCorrelation.TheproposedSafetyLimitMCPRvalues(two-loopandsingle-loop)werecalculatedusingSPC'sNRCapprovedlicensingmethodswiththeANFB-10correlationforATRIUMŽ-10fuel.InputtotheU2C11MCPRSLanalysis,providedbyPPL,coveredplantoperationuptoaratedcorethermalpowerof3493MWt.Therefore,theanalysisboundsU2C11operationuptothisCoreThermalPower,whichisa1.5%increaseinpoweroverU2C10(3441MWt).HTheproposedSafetyLimitMCPRs(two-loopandsingle-loop)assurethatatleast99.9%ofthefuelrodsareexpectedtoavoidboilingtransitionduringnormaloperationoranticipatedoperationaloccurrences.TheMCPRSafetyLimitanalysisisthefirstinaseriesofanalysesthatassurethenewcoreloadingforU2C11isoperatedinasafemanner.PriortothestartupofU2C11,otherlicensinganalysesareperformedtodeterminechangesinthecriticalpowerratioasaresultofanticipatedoperationaloccurrences.TheseresultsarecombinedwiththeMCPRSafetylimitvaluesproposedheretogeneratetheMCPRoperatinglimitsintheU2C11COLR.OtheranalysesandevaluationsareperformedwhichareindependentofMCPR(e.g.,MechanicalDesignanalyses,LOCA,etc.)andalsoresultinlimitswhichgointotheU2C11COLR.AftercompletionoftheCOLR,areloadSafetyEvaluationiswrittenwhichprovidesthesafetybasis(i.e.,nounreviewedsafetyquestion)forthenewU2C11coreloading,theU2C11COLR,theU2C11FSARchanges,andanyotherevaluations/changesasaresultofthenewU2C11coreconfiguration.Therefore,theproposedactiondoesnotinvolveanincreaseintheprobabilityoranincreaseinconsequencesofanaccidentpreviouslyevaluatedintheSAR.
ENCLOSURE ATOPLA-5169SAI'KTYANALYSISExcessive thermaloverheating ofthefuelrodcladdingcanresultincladdingdamageandthereleaseoffissionproducts.
ENCLOSUREATOPLA-5169Asalludedtoabove,theMCPRSafetyLimitanalysisandtheU2C11coreloadingwhichitsupportsdoesnotdirectlyorindirectlyaffectanyplantsystem,equipment,orcomponent(otherthanthecoreitself)andthereforedoesnotaffectthefailuremodesofanyofthese.Thus,theproposedchangesdonotcreatethepossibilityofapreviouslyunevaluatedoperatorerrororanewsinglefailure.Therefore,theproposedchangesdonocreatethepossibilityofanewordifferentkindofaccidentfromanyaccidentpreviouslyevaluated.Asdiscussedabove,sincetheproposedchangesdonotaffectanyplantsystem,equipment,orcomponent(otherthanthecoreitself),theproposedchangewillnotjeopardizeordegradethefunctionoroperationofanyplantsystemorcomponentgovernedbyTechnicalSpecifications.TheproposedMCPRSafetyLimitsdonotinvolveasignificantreductioninthemargin,ofsafetyascurrentlydefinedintheBASESoftheapplicableTechnicalSpecificationsections,becausetheMCPRSafetyLimitscalculatedforU2C11preservetherequiredmarginofsafety.Operatorperformanceandproceduresareunaffectedbytheseproposedchangessincethechangesareessentiallytransparenttotheoperatorsandplantprocedures,anddonotchangethewayinwhichtheplantisoperated.FollowinguseofthemethodologytoanalyzetheUnit2Cycle11coredesignandfutureUnit2reloads,thereloadcyclespecificresultsareincorporatedintotheFSARviaanFSARchangenotice.Therearenootherimpactsonlicensingdocumentsand/orcommitments.CONCLUSIONSNRCapprovaloftheproposedchangedoesnotinvolveanyreductioninthemarginofsafety.  
Inordertoprotectthecladdingagainstthermaloverheating duetoboilingtransition, theThermalPower,HighPressureandHighFlowSafetyLimit(Section2.1.1.2oftheSusquehanna SESUnit2Technical Specification) wereestablished.
ThechangestoSection2.1.1.2reflectthechange&omtheU2C10MCPRSafetyLimitstotheU2C11MCPRSafetyLimitsfortwo-loopoperation andsingle-loop operation.
NUREG-0800, StandardReviewPlanSection4.4,specifies anacceptable, conservative approachtodefinethisSafetyLimit.Specifically, aMinimumCriticalPowerRatio(MCPR)valueisspecified suchthatatleast99.9%ofthefuelrodsareexpectedtoavoidboilingtransition duringnormaloperation orAnticipated Operational Occurrences (AOOs).Boilingtransition ispredicted usingacorrelation basedontestdata(i.e.,aCriticalPowerCorrelation).
TheSafetyLimitMCPRcalculation accountsforvariousuncertainties suchasfeedwater flow,feedwater temperature,
: pressure, powerdistribution uncertainties, anduncertainty intheCriticalPowerCorrelation.
TheproposedSafetyLimitMCPRvalues(two-loop andsingle-loop) werecalculated usingSPC'sNRCapprovedlicensing methodswiththeANFB-10correlation forATRIUMŽ-10 fuel.InputtotheU2C11MCPRSLanalysis, providedbyPPL,coveredplantoperation uptoaratedcorethermalpowerof3493MWt.Therefore, theanalysisboundsU2C11operation uptothisCoreThermalPower,whichisa1.5%increaseinpoweroverU2C10(3441MWt).HTheproposedSafetyLimitMCPRs(two-loop andsingle-loop) assurethatatleast99.9%ofthefuelrodsareexpectedtoavoidboilingtransition duringnormaloperation oranticipated operational occurrences.
TheMCPRSafetyLimitanalysisisthefirstinaseriesofanalysesthatassurethenewcoreloadingforU2C11isoperatedinasafemanner.PriortothestartupofU2C11,otherlicensing analysesareperformed todetermine changesinthecriticalpowerratioasaresultofanticipated operational occurrences.
TheseresultsarecombinedwiththeMCPRSafetylimitvaluesproposedheretogeneratetheMCPRoperating limitsintheU2C11COLR.Otheranalysesandevaluations areperformed whichareindependent ofMCPR(e.g.,Mechanical Designanalyses, LOCA,etc.)andalsoresultinlimitswhichgointotheU2C11COLR.Aftercompletion oftheCOLR,areloadSafetyEvaluation iswrittenwhichprovidesthesafetybasis(i.e.,nounreviewed safetyquestion) forthenewU2C11coreloading,theU2C11COLR,theU2C11FSARchanges,andanyotherevaluations/changes asaresultofthenewU2C11coreconfiguration.
Therefore, theproposedactiondoesnotinvolveanincreaseintheprobability oranincreaseinconsequences ofanaccidentpreviously evaluated intheSAR.
ENCLOSURE ATOPLA-5169Asalludedtoabove,theMCPRSafetyLimitanalysisandtheU2C11coreloadingwhichitsupportsdoesnotdirectlyorindirectly affectanyplantsystem,equipment, orcomponent (otherthanthecoreitself)andtherefore doesnotaffectthefailuremodesofanyofthese.Thus,theproposedchangesdonotcreatethepossibility ofapreviously unevaluated operatorerrororanewsinglefailure.Therefore, theproposedchangesdonocreatethepossibility ofanewordifferent kindofaccidentfromanyaccidentpreviously evaluated.
Asdiscussed above,sincetheproposedchangesdonotaffectanyplantsystem,equipment, orcomponent (otherthanthecoreitself),theproposedchangewillnotjeopardize ordegradethefunctionoroperation ofanyplantsystemorcomponent governedbyTechnical Specifications.
TheproposedMCPRSafetyLimitsdonotinvolveasignificant reduction inthemargin,ofsafetyascurrently definedintheBASESoftheapplicable Technical Specification
: sections, becausetheMCPRSafetyLimitscalculated forU2C11preservetherequiredmarginofsafety.Operatorperformance andprocedures areunaffected bytheseproposedchangessincethechangesareessentially transparent totheoperators andplantprocedures, anddonotchangethewayinwhichtheplantisoperated.
Following useofthemethodology toanalyzetheUnit2Cycle11coredesignandfutureUnit2reloads,thereloadcyclespecificresultsareincorporated intotheFSARviaanFSARchangenotice.Therearenootherimpactsonlicensing documents and/orcommitments.
CONCLUSIONS NRCapprovaloftheproposedchangedoesnotinvolveanyreduction inthemarginofsafety.  


ELOSUREBTOPLA-5169NOSIGNIFICANTHAZARDSCONSIDERATIONSANDENVIRONMENTAI.ASSESSMENTMCPRSAFETYLIMITSPPLhasevaluatedtheproposedTechnicalSpecificationchangeinaccordancewiththecriteriaspecifiedby10CFR50.92andhasdeterminedthattheproposedchangedoesnotinvolveasignificanthazardsconsideration.Thecriteriaandconclusionsofourevaluationarepresentedbelow.1.Theproposedchangedoesnotinvolveasignificantincreaseintheprobabilityorconsequencesofanaccidentpreviouslyevaluated.TheproposedchangesinMCPRSafetyLimitsdonotaffectanyplantsystemorcomponent(exceptthereactorcore)andthereforedoesnotincreasetheprobabilityofanaccidentpreviouslyevaluated.AUnit2Cycle11MCPRSafetyLimitanalysiswasperformedforPPLbySPC.ThisanalysisusedNRCapprovedmethodsasrequiredbySSESTechnicalSpecifications.ForUnit2Cycle11,thecriticalpowerperformanceoftheATRIUM'r"'-10fuelwasdeterminedusingtheNRCapprovedANFB-10correlation.Also,theanalysisforU2C11supportsaCoreThermalPowerof3493MWtwhichisa1.5%increaseoverU2C10(3441MWt).TheSafetyLimitMCPRcalculationsstatisticallycombineuncertaintiesonfeedwaterflow,feedwatertemperature,coreflow,corepressure,corepowerdistribution,anduncertaintiesintheCriticalPowerCorrelation.TheSPCanalysisusedcyclespecificpowerdistributionsandcalculatedMCPRvaluessuchthatatleast99.9%ofthefuelrodsareexpectedtoavoidboilingtransitionduringnormaloperationoranticipatedoperationaloccurrences.Theresultingtwo-loopandsingle-loopMCPRSafetyLimitsareincludedintheproposedTechnicalSpecificationchange.Thus,thecladdingintegrityanditsabilitytocontainfissionproductsarenotadverselyaffected.Itisthereforeconcludedthattheproposedchangedoesnotincreasetheconsequencesofanaccidentpreviouslyevaluated.
ELOSUREBTOPLA-5169NOSIGNIFICANT HAZARDSCONSIDERATIONS ANDENVIRONMENTAI.
ELOSUREBTOPLA-51692.Theproposedchangedoesnotcreatethepossibilityofanewordifferentkindofaccidentfromanyaccidentpreviouslyevaluated.Asdiscussedabove,theproposedchangestotheUnit2TechnicalSpecifications(MCPRSafetyLimits)donotaffectanyplantsystemorcomponentanddonotaffectplantoperation.TheconsequencesoftransientsandaccidentswillremainwithinthecriteriaapprovedbytheNRC.Therefore,theproposedchangedoesnotcreatethepossibilityofanewordifferentkindofaccident&omanyaccidentpreviouslyevaluated.3.Theproposedchangedoesnotinvolveasignificantreductioninamarginofsafety.Sincetheproposedchangesdonotaffectanyplantsystemorcomponent,anddonothaveanyimpactonplantoperation,theproposedchangeswillnotaffectthefunctionoroperationofanyplantsystemorcomponent.TheconsequencesoftransientsandaccidentswillremainwithinthecriteriaapprovedbytheNRC.TheproposedMCPRSafetyLimitsdonotinvolveasignificantreductioninthemarginofsafetyascurrentlydefinedinthebasesoftheapplicableTechnicalSpecificationsections.Therefore,theproposedchangedoesnotinvolveasignificantreductioninthemarginofsafety.ENVIRONMENTALCONSKUKNCESAnenvironmentalassessmentisnotrequiredfortheproposedchangebecausetherequestedchangeconformstothecriteriaforactionseligibleforcategoricalexclusionasspecifiedin10CFR51.22(c)(9).Therequestedchangewillhavenoimpactontheenvironment.Theproposedchangedoesnotinvolveasignificanthazardsconsiderationasdiscussedabove.Theproposedchangedoesnotinvolveasignificantchangeinthetypesorsignificantincreaseintheamountsofanyeffluentsthatmaybereleasedoffsite.Inaddition,theproposedchangedoesnotinvolveasignificantincreaseintheindividualorcumulativeoccupationalradiationexposure.
ASSESSMENT MCPRSAFETYLIMITSPPLhasevaluated theproposedTechnical Specification changeinaccordance withthecriteriaspecified by10CFR50.92andhasdetermined thattheproposedchangedoesnotinvolveasignificant hazardsconsideration.
ELOSURECTOPLA-5169ENCLOSURECTOPLA-5169TECHNICALSPECIFICATIONMARK-UPs SLs2.02.0SAFETYLIMITS(SLs)2.1SLs2.1.1ReactorCoreSLs2.1.1.1.Withthereactorsteamdomepressure<785psigorcoreflow<10millionibm/hr:THERMALPOWERshallbe~25KRTP.2.1.1.2Withthereactorsteamdomepressurea785psigandcoreflowa10millionibm/hr::MCPRsh11be'llfortworecirculationloopoperation'ra.1forsingerecirculationloopoperation.1~+2.1.1.3'eactorvesselwaterlevelshallbegreaterthanthetopofactiveirradiatedfuel.2.1.2ReactorCoolantSstemPressureSLReactorsteamdomepressureshallbe~1325psig.2'SLViolationsWithanySLviolation,thefollowingactionsshallbecompletedwithin2hours:2.2.1RestorecompliancewithallSLs;and'.2.2Insertallinsertablecontrolrods.SUSQUEHANNA-UNIT2TS/2.0-1Amendment154 ENLOSUREDTOPLA-5169ATTACHMENTDTOPIA-5169"CAMERA-READY"TKCHNICAI,SPECIFICATIONPAGES 2.0SAFETYLIMITS(SLs)2.1SLs2.1.1ReactorCoreSLs2.1.1.1Withthereactorsteamdomepressure<785psigorcoreflow<10millionibm/hr:THERMALPOWERshallbe~25KRTP.2.1.1.2Withthereactorsteamdomepressure>785psigandcoreflow>10millionibm/hr:MCPRshallbe>1.12fortworecirculationloopoperationor~1.14forsinglerecirculationloopoperation.2.1.1.3Reactorvesselwaterlevelshallbegreaterthanthetopofactiveirradiatedfuel.2.1.2ReactorCoolantSstemPressureSLReactorsteamdomepressureshallbe<1325psig.2.2SLViolationsWithanySLviolation,thefollowingactionsshallbecompletedwithin2hours:2.2.1RestorecompliancewithallSLs:and2.2.2Insertallinsertablecontrolrods.SUSQUEHANNA-UNIT2TS/2.0-1Amendment ELOSUREETOPLA-5169ENCLOSUREKTOPLA-5169UNIT2CYCLE11CORKCOMPOSITIONikmih<YNNSPCATRIUM&#x17d;10SPCATRIUM&#x17d;-10SPCATRIUM&#x17d;10FreshOnce-burnedTwice-burned300280184 0~~}}
Thecriteriaandconclusions ofourevaluation arepresented below.1.Theproposedchangedoesnotinvolveasignificant increaseintheprobability orconsequences ofanaccidentpreviously evaluated.
TheproposedchangesinMCPRSafetyLimitsdonotaffectanyplantsystemorcomponent (exceptthereactorcore)andtherefore doesnotincreasetheprobability ofanaccidentpreviously evaluated.
AUnit2Cycle11MCPRSafetyLimitanalysiswasperformed forPPLbySPC.ThisanalysisusedNRCapprovedmethodsasrequiredbySSESTechnical Specifications.
ForUnit2Cycle11,thecriticalpowerperformance oftheATRIUM'r"'-10 fuelwasdetermined usingtheNRCapprovedANFB-10correlation.
Also,theanalysisforU2C11supportsaCoreThermalPowerof3493MWtwhichisa1.5%increaseoverU2C10(3441MWt).TheSafetyLimitMCPRcalculations statistically combineuncertainties onfeedwater flow,feedwater temperature, coreflow,corepressure, corepowerdistribution, anduncertainties intheCriticalPowerCorrelation.
TheSPCanalysisusedcyclespecificpowerdistributions andcalculated MCPRvaluessuchthatatleast99.9%ofthefuelrodsareexpectedtoavoidboilingtransition duringnormaloperation oranticipated operational occurrences.
Theresulting two-loopandsingle-loop MCPRSafetyLimitsareincludedintheproposedTechnical Specification change.Thus,thecladdingintegrity anditsabilitytocontainfissionproductsarenotadversely affected.
Itistherefore concluded thattheproposedchangedoesnotincreasetheconsequences ofanaccidentpreviously evaluated.
ELOSUREBTOPLA-51692.Theproposedchangedoesnotcreatethepossibility ofanewordifferent kindofaccidentfromanyaccidentpreviously evaluated.
Asdiscussed above,theproposedchangestotheUnit2Technical Specifications (MCPRSafetyLimits)donotaffectanyplantsystemorcomponent anddonotaffectplantoperation.
Theconsequences oftransients andaccidents willremainwithinthecriteriaapprovedbytheNRC.Therefore, theproposedchangedoesnotcreatethepossibility ofanewordifferent kindofaccident&omanyaccidentpreviously evaluated.
3.Theproposedchangedoesnotinvolveasignificant reduction inamarginofsafety.Sincetheproposedchangesdonotaffectanyplantsystemorcomponent, anddonothaveanyimpactonplantoperation, theproposedchangeswillnotaffectthefunctionoroperation ofanyplantsystemorcomponent.
Theconsequences oftransients andaccidents willremainwithinthecriteriaapprovedbytheNRC.TheproposedMCPRSafetyLimitsdonotinvolveasignificant reduction inthemarginofsafetyascurrently definedinthebasesoftheapplicable Technical Specification sections.
Therefore, theproposedchangedoesnotinvolveasignificant reduction inthemarginofsafety.ENVIRONMENTAL CONSKUKNCESAnenvironmental assessment isnotrequiredfortheproposedchangebecausetherequested changeconformstothecriteriaforactionseligibleforcategorical exclusion asspecified in10CFR51.22(c)(9).
Therequested changewillhavenoimpactontheenvironment.
Theproposedchangedoesnotinvolveasignificant hazardsconsideration asdiscussed above.Theproposedchangedoesnotinvolveasignificant changeinthetypesorsignificant increaseintheamountsofanyeffluents thatmaybereleasedoffsite.Inaddition, theproposedchangedoesnotinvolveasignificant increaseintheindividual orcumulative occupational radiation exposure.
ELOSURECTOPLA-5169ENCLOSURE CTOPLA-5169TECHNICAL SPECIFICATION MARK-UPs SLs2.02.0SAFETYLIMITS(SLs)2.1SLs2.1.1ReactorCoreSLs2.1.1.1.Withthereactorsteamdomepressure<785psigorcoreflow<10millionibm/hr:THERMALPOWERshallbe~25KRTP.2.1.1.2Withthereactorsteamdomepressurea785psigandcoreflowa10millionibm/hr::MCPRsh11be'llfortworecirculation loopoperation'r a.1forsingerecirculation loopoperation.
1~+2.1.1.3'eactorvesselwaterlevelshallbegreaterthanthetopofactiveirradiated fuel.2.1.2ReactorCoolantSstemPressureSLReactorsteamdomepressureshallbe~1325psig.2'SLViolations WithanySLviolation, thefollowing actionsshallbecompleted within2hours:2.2.1Restorecompliance withallSLs;and'.2.2Insertallinsertable controlrods.SUSQUEHANNA
-UNIT2TS/2.0-1Amendment 154 ENLOSUREDTOPLA-5169ATTACHMENT DTOPIA-5169"CAMERA-READY" TKCHNICAI, SPECIFICATION PAGES 2.0SAFETYLIMITS(SLs)2.1SLs2.1.1ReactorCoreSLs2.1.1.1Withthereactorsteamdomepressure<785psigorcoreflow<10millionibm/hr:THERMALPOWERshallbe~25KRTP.2.1.1.2Withthereactorsteamdomepressure>785psigandcoreflow>10millionibm/hr:MCPRshallbe>1.12fortworecirculation loopoperation or~1.14forsinglerecirculation loopoperation.
2.1.1.3Reactorvesselwaterlevelshallbegreaterthanthetopofactiveirradiated fuel.2.1.2ReactorCoolantSstemPressureSLReactorsteamdomepressureshallbe<1325psig.2.2SLViolations WithanySLviolation, thefollowing actionsshallbecompleted within2hours:2.2.1Restorecompliance withallSLs:and2.2.2Insertallinsertable controlrods.SUSQUEHANNA
-UNIT2TS/2.0-1Amendment ELOSUREETOPLA-5169ENCLOSURE KTOPLA-5169UNIT2CYCLE11CORKCOMPOSITION ikmih<YNN SPCATRIUM&#x17d;10 SPCATRIUM&#x17d;-10 SPCATRIUM&#x17d;10 FreshOnce-burned Twice-burned 300280184 0~~}}

Revision as of 02:12, 29 June 2018

Proposed Tech Specs Re ANFB-10 Critical Power Correlation & MCPR Safety Limits
ML18040B288
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Reporting Requirements D.O5.6Reporting Requirements5.6.5COLR(continued)

XN-NF-81-58(P)(A)

Supplements 1and2Revision2"RODEX2FuelRodThermal-Mechanical ResponseluationModel,"May1986.24.XN-NF-4(P)(A)."RODEX2A(BWR)FRodThermal-Mechanica sponseEvaluation Mo,"August1986.'V0LllQIOlC+d00aa0-~P00CLIVloChC25.26.27.2.30~17.el'N-NF-82-06(P)(A) aements2~4and5Revision1,"QualifiofExxonNuclearFuel'for.

ExtendedBurnup,"ober8.XN-NF-85-92 A)."ExxonNuclearaniumDioxide/oliniaIrradiation ExamiionandThermalConduvity."November1986.-90-082(P)(A)

Revision1andRevision1Supplement 1,"Application ofANFDesignMethodoforFuelAssembl'y Reconstitution,"

May1995.ANF-91-048(P)(A).

"Advanced NuclearFuelsCorporation Methodology forBoilingWaterReactorsEXEMBWREvaluation Model."January1993.-CC-33(P)(A)

Supplement 2,"HUXY:AGenerMulitupCodewith10CRF50A'eatupOption,"Janl.XN-CC-33(P) sion1.".eneralized Mult'tupCodewith10CFR50Appe'eatupionUsersManual,"November1975:XN-NF-80-19(P)(A).

Volumes2.2A.2B;and2C"Exxon'uclearMethodology forBoilingWaterReactors:

EXEMBWRECCSEvaluation Model."September 1982.XN-NF-80-19(P)(A).

Volumes3Revision2"ExxonNuclearMethodology forBoilingWaterReactorsThermex:ThermalLimitsMethodology SummaryDescription,"

January1987.XN-NF-79-71(P)(A)

Revision2,Supplements 1,.2.and3."ExxonNuclearPlantTransient Methodology forBoilingt"r61OmcontinuSUSQUEHANNA

-UNIT25.0-24Amendment 151990i2i0326 990ii2PDRADQCK-05000388 P'.PDR 0\PlnftP'tIC a'Distribution SheetDistri58.txt

~/~PonePriority:

NormalFrom:Esperanza LomosbogActionRecipients:

RidsNrrPMRSchaaf RidsNrrLAMObrien RidsNrrDlpmLpdi1 Copies:000OKOKOKInternalRecipients:

RidsRgn1MailCenter RidsOgcRp RidsNrrWpcMail RidsNrrDssaSrxb RidsManagerRidsAcrsAcnwMai+Center

+FILECENTER-01~

ACRS000OKOKOKOKOK0OKPaperCopyPaperCopyExternalRecipients:

NOACPaperCopyTotalCopies:Item:ADAMSDocumentLibrary:MLADAMS"HQNTAD01ID:003700504:1

Subject:

SSES,ProposedAmendment 194,Inclusion ofMCPRSafetyLimitsinTechnical SpecificationsSection2.1.1.2Body:ADAMSDISTRIBUTION NOTIFICATION.

Electronic Recipients canRIGHTCLICKandOPENthefirstAttachment toViewtheDocumentinADAMS.TheDocumentmayalsobeviewedbysearching forAccession NumberML003700504.

Page1 Distri58.txt A001-ORSubmittal:

GeneralDistribution Docket:05000388Page2 RobertG.ByramSeniorVicePresident andChiefNuclearOfficerTel.610.774.7502 Fax610.774.5019 E-mail:rgbyram@papl.corn PP&L,Inc.TwoNorthNinthStreetAllentovm, PA16101-1179 Tel.610.774.51 51IgIppMAR20,2000U.S.NuclearRegulatory Commission Attn:DocumentControlDeskMailStationOP1-17Washington, D.C.20555\SUSQUEHANNA STEAMELECTRICSTATIONPROPOSEDAMENDMENT NO.194TOLICENSENPF-22:MCPRSAFETYLIMITSPLA-5169DocketNo.50-388ThepurposeofthisletteristoproposechangestotheSusquehanna SteamElectricStationUnit2Technical Specifications.

Thisproposedchangeentailstheinclusion ofUnit2Cycle11(U2C11)MCPRSafetyLimitsinSection2.1.1.2.Consistent withthepreviousUnit2reloadanalysis, theanalysismethodsdescribed inTechnical Specification 5.6.5b.,asapprovedbytheNRC,areusedtogeneratetheSafetyLimitsandCoreOperating LimitsfortheU2C11reload.Enclosure Atothisletteristhe"SafetyAssessment" supporting thischange.Enclosure 8istheNoSignificant HazardsConsiderations evaluation performed inaccordance withthecriteriaof10CFR50.92andtheEnvironmental Assessment.

Enclosure Ctothislettercontainstheapplicable pageoftheSusquehanna SESUnit2Technical Specifications, markedtoshowtheproposedchange.Attachment Dcontains"cameraready"versionoftherevisedTechnical Specification page.TheproposedchangehasbeenapprovedbytheSusquehanna SESPlantOperations ReviewCommittee andreviewedbytheSusquehanna ReviewCommittee.

Toassistinyourreview,Attachment Ehasbeenprovided.

Attachment EprovidestheU2C11CoreComposition.

.~,~

PLA-5169DocumentControlDeskPPLplanstoimplement theproposedchangesinMay2001tosupportthestartupofU2C11operation.

Therefore, werequestNRCcompleteitsreviewofthischangebyJanuary31,2001withthechangeseffective uponstartupfollowing theUnit210'"Refueling andInspection Outage.Anyquestions regarding thisrequestshouldbedirectedtoMr.M.H.Crowthers at(610)774-7766.

Verytrulyyours,Attachments copy:NRCRegionIMr.R.G.Schaaf,NRCSr.ProjectManagerMr.S.Hansell,NRCSr.ResidentInspector Mr.W.P.Dornsife, PADEP BEFORETHEUNITEDSTATESNUCLEARREGULATORY COMMISSION IntheMatterofPPEcL,INC.DocketNo.50-388PROPOSEDAMENDMENT NO.194TOLICENSENPF-22:MCPRSAFETYLIMITSSUSQUEHANNA STEAMELECTRICSTATIONUNITNO.2Licensee, PPEcL,Inc.,herebyfilesarevisiontoproposedAmendment No.194toitsFacilityOperating LicenseNo.NPF-22datedMarch23,1984.Thisamendment containsarevisiontotheSusquehanna SESUnit2Technical Specifications.

PP&L,INC.BY:Sworntoandsubscribed beforemethisgo~dayofge~,2000.NotaryPublicR.ByrmS.Vice-PrsidentandChiefNuclearOfficerNOTARIALSEALJANlCEM.REESE,NotaryPublicCityotAllentown, LehighCounty,PA")JulyCorninimion ExpiresJune11,200$

rt~f4~~Jt\rt ENCLOSURE ATOPLA-5169SAFETYASSESSMENT MCPRSAFETYLIMITSBACKGROUND Susquehanna SteamElectricStationUnit2,Cycle11willcontainSPCATRIUMŽ-10 fuel.TheATRIUMY"'-10 fueldesignisa10x10latticedesignwhichcontains83fulllengthfuelrods,8partlengthfuelrods,andacentralwaterchannel.TheMCPRSafetyLimitsforU2C11supportCoreThermalPowersupto3493MWt,whichisa1.5%increaseoverU2C10(3441MWt).Theanalysiswasperformed atthe3493MWtpowerleveltosupportlicenseamendments tobeproposedinMay2000foranincreaseintheRatedThermalPowerlevelforSSESUnit2.SiemensPowerCorporation hasdeveloped theANFB-10criticalpowercorrelation whichisapplicable totheATRIUMŽ-10 fuelassemblies (Technical Specification 5.6.5b.19).

ANFB-10isbasedonalargeamountofcriticalpowertestdataontheATRIUMY"'-10 deslgil.TheMCPRSafetyLimitanalysisisperformed onacyclespecificbasissincethecoredesignchanges&omcycletocycle.TheU2C11MCPRSafetyLimitwascalculated bySiemensPowerCorporation (SPC)usingtheNRCapprovedmethodsdescribed inTechnical Specification 5.6.5b.5.

DescritionoftheProosedChaneTheproposedUnit2Technical Specification changesconsistof:(1)ReviseSection2.1.1.2toreflecttheU2C11MCPRSafetylimits.TheMCPRSLvaluesare1.12fortwo-loopoperation and1.14forsingle-loop operation.

TheNRC-approved topicalreportscontained inSection5.6.5oftheTechnical Specifications containthemethodology usedtoensuresafeoperation ofUnit2withATRIUMŽ-10 fuel.

ENCLOSURE ATOPLA-5169SAI'KTYANALYSISExcessive thermaloverheating ofthefuelrodcladdingcanresultincladdingdamageandthereleaseoffissionproducts.

Inordertoprotectthecladdingagainstthermaloverheating duetoboilingtransition, theThermalPower,HighPressureandHighFlowSafetyLimit(Section2.1.1.2oftheSusquehanna SESUnit2Technical Specification) wereestablished.

ThechangestoSection2.1.1.2reflectthechange&omtheU2C10MCPRSafetyLimitstotheU2C11MCPRSafetyLimitsfortwo-loopoperation andsingle-loop operation.

NUREG-0800, StandardReviewPlanSection4.4,specifies anacceptable, conservative approachtodefinethisSafetyLimit.Specifically, aMinimumCriticalPowerRatio(MCPR)valueisspecified suchthatatleast99.9%ofthefuelrodsareexpectedtoavoidboilingtransition duringnormaloperation orAnticipated Operational Occurrences (AOOs).Boilingtransition ispredicted usingacorrelation basedontestdata(i.e.,aCriticalPowerCorrelation).

TheSafetyLimitMCPRcalculation accountsforvariousuncertainties suchasfeedwater flow,feedwater temperature,

pressure, powerdistribution uncertainties, anduncertainty intheCriticalPowerCorrelation.

TheproposedSafetyLimitMCPRvalues(two-loop andsingle-loop) werecalculated usingSPC'sNRCapprovedlicensing methodswiththeANFB-10correlation forATRIUMŽ-10 fuel.InputtotheU2C11MCPRSLanalysis, providedbyPPL,coveredplantoperation uptoaratedcorethermalpowerof3493MWt.Therefore, theanalysisboundsU2C11operation uptothisCoreThermalPower,whichisa1.5%increaseinpoweroverU2C10(3441MWt).HTheproposedSafetyLimitMCPRs(two-loop andsingle-loop) assurethatatleast99.9%ofthefuelrodsareexpectedtoavoidboilingtransition duringnormaloperation oranticipated operational occurrences.

TheMCPRSafetyLimitanalysisisthefirstinaseriesofanalysesthatassurethenewcoreloadingforU2C11isoperatedinasafemanner.PriortothestartupofU2C11,otherlicensing analysesareperformed todetermine changesinthecriticalpowerratioasaresultofanticipated operational occurrences.

TheseresultsarecombinedwiththeMCPRSafetylimitvaluesproposedheretogeneratetheMCPRoperating limitsintheU2C11COLR.Otheranalysesandevaluations areperformed whichareindependent ofMCPR(e.g.,Mechanical Designanalyses, LOCA,etc.)andalsoresultinlimitswhichgointotheU2C11COLR.Aftercompletion oftheCOLR,areloadSafetyEvaluation iswrittenwhichprovidesthesafetybasis(i.e.,nounreviewed safetyquestion) forthenewU2C11coreloading,theU2C11COLR,theU2C11FSARchanges,andanyotherevaluations/changes asaresultofthenewU2C11coreconfiguration.

Therefore, theproposedactiondoesnotinvolveanincreaseintheprobability oranincreaseinconsequences ofanaccidentpreviously evaluated intheSAR.

ENCLOSURE ATOPLA-5169Asalludedtoabove,theMCPRSafetyLimitanalysisandtheU2C11coreloadingwhichitsupportsdoesnotdirectlyorindirectly affectanyplantsystem,equipment, orcomponent (otherthanthecoreitself)andtherefore doesnotaffectthefailuremodesofanyofthese.Thus,theproposedchangesdonotcreatethepossibility ofapreviously unevaluated operatorerrororanewsinglefailure.Therefore, theproposedchangesdonocreatethepossibility ofanewordifferent kindofaccidentfromanyaccidentpreviously evaluated.

Asdiscussed above,sincetheproposedchangesdonotaffectanyplantsystem,equipment, orcomponent (otherthanthecoreitself),theproposedchangewillnotjeopardize ordegradethefunctionoroperation ofanyplantsystemorcomponent governedbyTechnical Specifications.

TheproposedMCPRSafetyLimitsdonotinvolveasignificant reduction inthemargin,ofsafetyascurrently definedintheBASESoftheapplicable Technical Specification

sections, becausetheMCPRSafetyLimitscalculated forU2C11preservetherequiredmarginofsafety.Operatorperformance andprocedures areunaffected bytheseproposedchangessincethechangesareessentially transparent totheoperators andplantprocedures, anddonotchangethewayinwhichtheplantisoperated.

Following useofthemethodology toanalyzetheUnit2Cycle11coredesignandfutureUnit2reloads,thereloadcyclespecificresultsareincorporated intotheFSARviaanFSARchangenotice.Therearenootherimpactsonlicensing documents and/orcommitments.

CONCLUSIONS NRCapprovaloftheproposedchangedoesnotinvolveanyreduction inthemarginofsafety.

ELOSUREBTOPLA-5169NOSIGNIFICANT HAZARDSCONSIDERATIONS ANDENVIRONMENTAI.

ASSESSMENT MCPRSAFETYLIMITSPPLhasevaluated theproposedTechnical Specification changeinaccordance withthecriteriaspecified by10CFR50.92andhasdetermined thattheproposedchangedoesnotinvolveasignificant hazardsconsideration.

Thecriteriaandconclusions ofourevaluation arepresented below.1.Theproposedchangedoesnotinvolveasignificant increaseintheprobability orconsequences ofanaccidentpreviously evaluated.

TheproposedchangesinMCPRSafetyLimitsdonotaffectanyplantsystemorcomponent (exceptthereactorcore)andtherefore doesnotincreasetheprobability ofanaccidentpreviously evaluated.

AUnit2Cycle11MCPRSafetyLimitanalysiswasperformed forPPLbySPC.ThisanalysisusedNRCapprovedmethodsasrequiredbySSESTechnical Specifications.

ForUnit2Cycle11,thecriticalpowerperformance oftheATRIUM'r"'-10 fuelwasdetermined usingtheNRCapprovedANFB-10correlation.

Also,theanalysisforU2C11supportsaCoreThermalPowerof3493MWtwhichisa1.5%increaseoverU2C10(3441MWt).TheSafetyLimitMCPRcalculations statistically combineuncertainties onfeedwater flow,feedwater temperature, coreflow,corepressure, corepowerdistribution, anduncertainties intheCriticalPowerCorrelation.

TheSPCanalysisusedcyclespecificpowerdistributions andcalculated MCPRvaluessuchthatatleast99.9%ofthefuelrodsareexpectedtoavoidboilingtransition duringnormaloperation oranticipated operational occurrences.

Theresulting two-loopandsingle-loop MCPRSafetyLimitsareincludedintheproposedTechnical Specification change.Thus,thecladdingintegrity anditsabilitytocontainfissionproductsarenotadversely affected.

Itistherefore concluded thattheproposedchangedoesnotincreasetheconsequences ofanaccidentpreviously evaluated.

ELOSUREBTOPLA-51692.Theproposedchangedoesnotcreatethepossibility ofanewordifferent kindofaccidentfromanyaccidentpreviously evaluated.

Asdiscussed above,theproposedchangestotheUnit2Technical Specifications (MCPRSafetyLimits)donotaffectanyplantsystemorcomponent anddonotaffectplantoperation.

Theconsequences oftransients andaccidents willremainwithinthecriteriaapprovedbytheNRC.Therefore, theproposedchangedoesnotcreatethepossibility ofanewordifferent kindofaccident&omanyaccidentpreviously evaluated.

3.Theproposedchangedoesnotinvolveasignificant reduction inamarginofsafety.Sincetheproposedchangesdonotaffectanyplantsystemorcomponent, anddonothaveanyimpactonplantoperation, theproposedchangeswillnotaffectthefunctionoroperation ofanyplantsystemorcomponent.

Theconsequences oftransients andaccidents willremainwithinthecriteriaapprovedbytheNRC.TheproposedMCPRSafetyLimitsdonotinvolveasignificant reduction inthemarginofsafetyascurrently definedinthebasesoftheapplicable Technical Specification sections.

Therefore, theproposedchangedoesnotinvolveasignificant reduction inthemarginofsafety.ENVIRONMENTAL CONSKUKNCESAnenvironmental assessment isnotrequiredfortheproposedchangebecausetherequested changeconformstothecriteriaforactionseligibleforcategorical exclusion asspecified in10CFR51.22(c)(9).

Therequested changewillhavenoimpactontheenvironment.

Theproposedchangedoesnotinvolveasignificant hazardsconsideration asdiscussed above.Theproposedchangedoesnotinvolveasignificant changeinthetypesorsignificant increaseintheamountsofanyeffluents thatmaybereleasedoffsite.Inaddition, theproposedchangedoesnotinvolveasignificant increaseintheindividual orcumulative occupational radiation exposure.

ELOSURECTOPLA-5169ENCLOSURE CTOPLA-5169TECHNICAL SPECIFICATION MARK-UPs SLs2.02.0SAFETYLIMITS(SLs)2.1SLs2.1.1ReactorCoreSLs2.1.1.1.Withthereactorsteamdomepressure<785psigorcoreflow<10millionibm/hr:THERMALPOWERshallbe~25KRTP.2.1.1.2Withthereactorsteamdomepressurea785psigandcoreflowa10millionibm/hr::MCPRsh11be'llfortworecirculation loopoperation'r a.1forsingerecirculation loopoperation.

1~+2.1.1.3'eactorvesselwaterlevelshallbegreaterthanthetopofactiveirradiated fuel.2.1.2ReactorCoolantSstemPressureSLReactorsteamdomepressureshallbe~1325psig.2'SLViolations WithanySLviolation, thefollowing actionsshallbecompleted within2hours:2.2.1Restorecompliance withallSLs;and'.2.2Insertallinsertable controlrods.SUSQUEHANNA

-UNIT2TS/2.0-1Amendment 154 ENLOSUREDTOPLA-5169ATTACHMENT DTOPIA-5169"CAMERA-READY" TKCHNICAI, SPECIFICATION PAGES 2.0SAFETYLIMITS(SLs)2.1SLs2.1.1ReactorCoreSLs2.1.1.1Withthereactorsteamdomepressure<785psigorcoreflow<10millionibm/hr:THERMALPOWERshallbe~25KRTP.2.1.1.2Withthereactorsteamdomepressure>785psigandcoreflow>10millionibm/hr:MCPRshallbe>1.12fortworecirculation loopoperation or~1.14forsinglerecirculation loopoperation.

2.1.1.3Reactorvesselwaterlevelshallbegreaterthanthetopofactiveirradiated fuel.2.1.2ReactorCoolantSstemPressureSLReactorsteamdomepressureshallbe<1325psig.2.2SLViolations WithanySLviolation, thefollowing actionsshallbecompleted within2hours:2.2.1Restorecompliance withallSLs:and2.2.2Insertallinsertable controlrods.SUSQUEHANNA

-UNIT2TS/2.0-1Amendment ELOSUREETOPLA-5169ENCLOSURE KTOPLA-5169UNIT2CYCLE11CORKCOMPOSITION ikmih<YNN SPCATRIUMŽ10 SPCATRIUMŽ-10 SPCATRIUMŽ10 FreshOnce-burned Twice-burned 300280184 0~~

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