ML17229A181: Difference between revisions

From kanterella
Jump to navigation Jump to search
(Created page by program invented by StriderTol)
(Created page by program invented by StriderTol)
Line 17: Line 17:


=Text=
=Text=
{{#Wiki_filter:CATEGORY1REGULATINFORMATIONDISTRIBUTIONSTEM(RIDS)!'CCFSS.'fONNBR:9612270073DOC.DATE:96/12/20NOTARIZED:NOk'ACIL:50-335St.LuciePlant,Unit1,FloridaPower6LightCo.AUTH,NAMEAUTHORAFFILIATIONSTALL,J.A.FloridaPower&LightCo.RECIP.NAMERECIPIENTAFFILIATIONDocumentControlBranch(DocumentControlDesk)DOCKET05000335
{{#Wiki_filter:CATEGORY1REGULATINFORMATION DISTRIBUTION STEM(RIDS)!'CCFSS.'fON NBR:9612270073 DOC.DATE:
96/12/20NOTARIZED:
NOk'ACIL:50-335 St.LuciePlant,Unit1,FloridaPower6LightCo.AUTH,NAMEAUTHORAFFILIATION STALL,J.A.
FloridaPower&LightCo.RECIP.NAME RECIPIENT AFFILIATION DocumentControlBranch(Document ControlDesk)DOCKET05000335


==SUBJECT:==
==SUBJECT:==
ApplicationforamendtolicenseDP$-67,requestingdeletionoffootnotereTS2.1.1,"ReactorCoreSafetyLimits."CDISTRIBUTIONCODE:A001DCOPIESRECEIVED:LTRENCLSIZE:TITLE:ORSubmittal:GeneralDistributionNOTES:RECIPIENTIDCODE/NAMEPD2-3LAWIENS,L.INTERNAL:ACRSNRR/DE/ECGB/ANRR/DRCH/HICBNRR/DSSA/SRXBOGC/HDS3COPIESRECIPIENT.LTTRENCLIDCODE/NAME11PD2-3PD1111F1LECENTER~0111NRR/DE/EMCB11NRR/DSSA/SPLB11NUDOCS-ABSTRACT10COPIESLTTRENCL1111111111EXTERNAL:NOAC11NRCPDR11DNOTETOALL"RIDS"RECIPIENTS:PLEASEHELPUSTOREDUCEWASTE!CONTACTTHEDOCUMENTCONTROLDESK/ROOMOWFNSD-5(EXT.415-2083)TOELIMINATEYOURNAMEFROMDISTRIBUTIONLISTSFORDOCUMENTSYOUDON'TNEED!TOTALNUMBEROFCOPIESREQUIRED:LTTR14ENCL,'.13 Cew'tIr,>lC*('I December20,1996FloridaPower8tLightCompany,P.O.Box128,FortPierce,FL34954-0128L-96-33310CFR50.90U.S.NuclearRegulatoryCommissionAttn:DocumentControlDeskWashington,D.C.20555Re:St.LucieUnit1DocketNo.50-335ProposedLicenseAmendment.ReactorCoreSafetLimitPursuantto10CFR50.90,FloridaPower&LightCompany(FPL)requeststoamendFacilityOperatingLicenseDPR-67forSt.LucieUnit1byincorporatingtheattachedTechnicalSpecifications(TS)revision.TheamendmentwilldeleteafootnoteassociatedwithTS2.1.1,"ReactorCoreSafetyLimits,"whichrequiresreactorthermalpowertobelimitedto90%of2700MegawattsthermalforCycle14operationbeyond7000EffectiveFullPowerHours.Itisrequestedthattheproposedamendment,ifapproved,beissuedpriortoMay15,1997topermitcontinuedoperationofSt.LucieUnit1atfullpower.Attachment1isanevaluationoftheproposedTSchange.Attachment2isthe"DeterminationofNoSignificantHazardsConsideration."Attachment3containsacopyoftheaffectedTSpagemarked-uptoshowtheproposedchanges.EnclosedwiththissubmittalisacopyofreportEMF-96-176,"St.LucieUnit1SmallBreakLOCAAnalysiswith30%SteamGeneratorTube.Plugging,"SiemensPowerCorporation,Revision1,December1996.TheproposedamendmenthasbeenreviewedbytheSt.LucieFacilityReviewGroupandtheFloridaPower8.LightCompanyNuclearReviewBoard.Inaccordancewith10CFR50.91(b)(1),acopyoftheproposedamendmentisbeingforwardedtotheStateDesigneefortheStateofFlorida.Pleasecontactusifthereareanyquestionsaboutthissubmittal.Verytrulyyours,J.A.StallVicePresidentSt.LuciePlantJAS/RLDAttachments9hi22700739hi220PDR,ADQCK05000335PPDRPOD((StewartD.Ebnctcr,RegionalAdministrator,RegionII,USNRC.SeniorResidentInspector,USNRC,St.LucicPlant.Mr.W.A.Passctti,FloridaDcpartmcntofHealthandRchabilitativcScrviccs.anFPLGroupcompany 0r<t4 St.LucieUnit1DocketNo.50-335ProposedLicenseAmendmentReactorCoreSafetLimitSTATEOFFLORIDA))ss.COUNTYOFST.LUCIE)J.A.Stallbeingfirstdulysworn,deposesandsays:ThatheisVicePresident,St.LuciePlant,fortheNuclearDivisionofFloridaPowerEcLightCompany,theLicenseeherein;Thathehasexecutedtheforegoingdocument;thatthestatementsmadeinthisdocumentaretrueandcorrecttothebestofhisknowledge,informationandbelief,andthatheisauthorizedtoexecutethedocumentonbehalfofsaidLicensee.J.A.StallSTATEOFFLORIDACOUNTYOFST.~uc<<Sworntoandsubscribedbeforemethis~~dayofDKCFwR8R19+kbyJ.A.Stall,whoispersonallyknowntome.(''DScASignatureofNotaryPublic-StateofFloridao~pSs~sg~~ii~01%C,hnrtcs'D.>dfNameofNotaryPublic(Print,Type,orStamgiig(7''sjj8~,ii"'>llillla'l>>
Application foramendtolicenseDP$-67,requesting deletionoffootnotereTS2.1.1,"ReactorCoreSafetyLimits."CDISTRIBUTION CODE:A001DCOPIESRECEIVED:LTR ENCLSIZE:TITLE:ORSubmittal:
tlI4II1~~'>fe>~'k4 St.LucieUnit1DocketNo.50-335ProposedLicenseAmendmentReactorCoreSafetLimitATTACHMENT1EVALUATIONOFPROPOSEDCHANGES lI(IjhV4 L-96-333Attachment1P~aeIEVALUATIONOFPROPOSEDTSCHANGESIntroductionTheproposedamendmenttoFacilityOperatingLicenseDPR-67forSt.LucieUnit1willdeleteafootnoteassociatedwithTechnicalSpecification(TS)2.1.1,"ReactorCoreSafetyLimits,"whichrequiresthermalpowertobelimitedtolessthanorequalto90%of2700Megawattsthermal(MWth)forCycle14operationbeyond7000EffectiveFullPowerHours(EFPH).ThethermalpowerconstraintwasimposedinlieuofperformingaSmallBreakLossofCoolantAccident(SBLOCA)re-analysisforfullpoweroperationthatdemonstratesacceptableresultsusinginputassumptionscorrespondingto30%(average)ofallsteamgeneratortubesplugged(SGTP).Thatanalysishasbeencompleted,andareportofanalysisresultsisenclosedwiththissubmittal.DescritionofProosedChaneTS211Pae2-1:Deletetheasteriskfollowing"THERMALPOWER,"anddeletefootnote"*"shownatthebottomofpage2-1.AcopyofTSPage2-1,marked-uptoshowtheproposedchanges,iscontainedinAttachment3.BackroundAmendmentNo.145toFacilityOperatingLicenseNo.DPR-67(L.A.Wiens(NRC)toT.F.Plunkett(FPL):ST.LUCIEUNIT1-ISSUANCEOFAMENDMENTRE:THERIVfALMARGINANDREACTORCOOLANTSYSTEMFLOWLIMITS(TACNO.M95472),July9,1996)wasissuedtopermitplantoperationwithupto30%(average)SGTPand345,000gpmminimumReactorCoolantSystem(RCS)flow.Insupportofthisamendment,FPLhaddeterminedthatconservatismintheexistingSBLOCAanalysis,whichhadpreviouslybeenperformedforconditionscorrespondingto25%SGTPand355,000gpmRCSflow,wouldoffsetanyadverseeffectsduetotheincreasedSGTPanddecreasedreactorcoolantsystemflowforfullpoweroperationupto7000EFPH.Tooffsetanyadverseeffectsforoperationbeyond7000EFPH,itwasdeterminedthatlimitingcorethermalpowerto90%ofratedthermalpowerwouldprovidesufficientmargintoensure10CFR50.46conformityfortheremainderofoperatingCycle14.SubsequenttoissuanceofAmendmentNo.145,are-analysisoftheSBLOCAhasbeencompletedusinginputassumptionscorrespondingto30%(average)SGTPand345,000gpmRCSflow.Theresultsofthatanalysisarebrieflydiscussedinthisevaluation,anddataisprovidedingreaterdetailintheenclosedSiemensPowerCorporation-NuclearDivisionReportEMF-96-176,"St.LucieUnit1SmallBreakLOCAAnalysiswith30%SteamGeneratorTubePlugging,"Revision1,December1996.
GeneralDistribution NOTES:RECIPIENT IDCODE/NAME PD2-3LAWIENS,L.INTERNAL:
L-96-333Attachment1P~ee2BasesforTSChaneByAmendmentNo.145,theNRCapprovedalicenseamendmenttoreducetheRCSflowfrom355,000gpmto345,000gpmandthelowflowtripsetpointfrom95%to93%ofdesignRCSflow.ThisamendmentsupportedaSGTPlevelof30%+7%,witharequirementtoderateto90%of2700MWthpriortoexceeding7000EFPHofCycle14operation.TherequirementtoderatewasbasedontheSBLOCAanalysis,whichsupportedafullpoweroperationupto7000EFPHand90%powerlevelbeyond7000EFPH.ExceptfortheSBLOCA,acceptableresultswereshownwithintheapplicablesafetylimitsforallthesafetyandsetpointanalysesat100%poweroperationattheamendedconditionsandaSGTPlevelof30%+7%.TheSBLOCAwasevaluatedat100%ofratedpowerupto7000EFPHandat90%powerlevelbeyond7000EFPH.TosupportCycle14operationat2700MWthtoend-of-cyclerequiredareanalysisofSBLOCAwiththelimitingend-of-cycleconditions.TheSBLOCAhasbeenreanalyzedtosupportCycle14operationat100%powerfortheentireoperatingcycle.Theanalysis,includedastheenclosuretothisproposedlicenseamendment,demonstratesacceptableresultsincompliancewith10CFR50.46criteria.Thepeakcladdingtemperature(PCT)wascalculatedtobe1804'F,wellbelowtheacceptancecriteriaof2200'F.ThisanalysiswasperformedbySiemensPowerCorporation(SPC),usinganNRC-approvedSBLOCAevaluationmodel.Thereanalysiswasdonewithchangestoinputassumptionswithrespecttotheloopsealclearingandthelocationofcoldleginjectionpoint.Theloopsealsinthebrokenloopandoneoftheintactloopswerebiasedtoremainplugged.Inthecurrentanalysisofrecord,theloopsealinthebrokenloopdidnotstayplugged.Alsothesafetyinjectionpointwasmovedanodeawayfromthereactorcoolantpumptorepresentamorerealisticconfiguration.Overallthesechangesremovesomeoftheconservatismascomparedtotheanalysisofrecordfor25%tubeplugginglevel(EMF-92-148,"St.LucieUnit1SmallBreakLOCAAnalysis,"SiemensPowerCorporation,May1994).ConclusionTheSBLOCAreanalysis,alongwiththeanalysesaddressedinAmendmentNo.145,supportoperationofSt.LucieUnit1at100%ofRATEDTHERMALPOWERfortheentireCycle14.TheproposedchangesupportsthereducedRCSflowof345,000gpmcorrespondingtoaSGTPlevelof30%+7%approvedinAmendmentNo.145.
ACRSNRR/DE/ECGB/A NRR/DRCH/HICB NRR/DSSA/SRXB OGC/HDS3COPIESRECIPIENT
ATTACHMENT2DETERMINATIONOFNOSIGNIFICANTHAZARDSCONSIDERATION L-96-333Attachment2P~aeIDETERMINATIONOFNOSIGNIFICANTHAZARDSCONSIDERATIONDescriptionofamendmentrequest:TheproposedamendmentwilldeleteafootnoteassociatedwithTechnicalSpecification2.1.1,"ReactorCoreSafetyLimits,"whichrequiresthermalpowertobelimitedto90%of2700Megawattsthermal(MWth)forCycle14operationbeyond7000EffectiveFullPowerHours.Pursuantto10CFR50.92,adeterminationmaybemadethataproposedlicenseamendmentinvolvesnosignificanthazardsconsiderationifoperationofthefacilityinaccordancewiththeproposedamendmentwouldnot:(1)involveasignificantincreaseintheprobabilityorconsequencesofanaccidentpreviouslyevaluated;or(2)createthepossibilityofanewordifferentkindofaccidentfromanyaccidentpreviouslyevaluated;or(3)involveasignificantreductioninamarginofsafety.Eachstandardisdiscussedasfollows:(1)OperationofthefacilityinaccordancewiththeproposedamendmentwouldnotinvolveasigniTicantincreaseintheprobabilityorconsequencesofanaccidentpreviouslyevaluated.TheproposedchangewillallowfullCycle14operationat100%ofratedpower(2700MWth),bydeletingtherequirementtoderateto90%ofratedpowerpriortoexceeding7000EFPH.ThisrestrictionwasimposedintheNRCtransmittalletterforLicenseAmendment145forSBLOCAconsiderationswhenconsideringtheincreasedSGTPlevelof30%+7%.AllFinalSafetyAnalysisReport(FSAR)events,otherthanSBLOCAwereevaluatedat100%ofratedthermalpowerandshowednosignificantincreasesintheprobabilityorconsequencesofaccidentspreviouslyevaluated.TheSBLOCAwasreanalyzedtodemonstratecontinuedcompliancewith10CFR50.46criteria.ThereisnoimpactoftheproposedchangeonanyFSARaccidentinitiator.Theplantconfigurationandsystemsremainunchanged.Therefore,operationofthefacilityinaccordancewiththeproposedamendmentwouldnotinvolveasignificantincreaseintheprobabilityorconsequencesofanaccidentpreviouslyevaluated.(2)Operationofthefacilityinaccordancewiththeproposedamendmentwouldnotcreatethepossibilityofanewordifferentkindofaccidentfromanyaccidentpreviouslyevaluated.ThisproposedamendmentremovestherequirementintheTechnicalSpecificationstoderateto90%of2700MWthforCycle14operationbeyond7000EFPH.Therewillbe L-96-333Attachment2P~ae2nochangetothemodesofoperationoftheplant.Theplantconfigurationandthedesignfunctionsofallthesafetysystemsremainunchanged.Theproposedamendmentwillnotchangethephysicalplantorthemodesofoperationdefinedinthefacilitylicense.Thechangesdonotinvolvetheadditionofnewequipmentorthemodificationofexistingequipment,nordotheyalterthedesignofSt.Lucieplantsystems.Therefore,operationofthefacilityinaccordancewiththeproposedamendmentwouldnotcreatethepossibilityofanewordifFerentkindofaccidentfromanyaccidentpreviouslyevaluated.(3)Operationofthefacilityinaccordancewiththeproposedamendmentwouldnotinvolveasignificantreductioninamarginofsafety.Theimpactoftheproposedchangeon'availablemargintotheacceptancecriteriaforSpecifiedAcceptableFuelDesignLimits(SAFDL),primaryandsecondaryover-pressurization,peakcontainmentpressure,potentialradioactivereleases,10CFR50.46requirementsforthelargebreakLOCA,andexistinglimitingconditionsforoperationhasbeenevaluatedandaddressedinthereducedRCSflowoperatinglicenseAmendmentNo.145.Arequirementtoderateto90%of2700MWthwasimposedbasedontheSBLOCAanalysis.ThesmallbreakLOCAanalysiswith30%+7%SGTPsupportedoperationupto7000EFPHat100%of-ratedthermalpower.AreanalysisofSBLOCAwiththelimitingend-of-cycleconditionsat100%ofratedpower,demonstratescontinuedcompliancewith10CFR50.46criteria.Therefore,operationofthefacilityinaccordancewiththeproposedamendmentwouldnotinvolveasignificantreductioninamarginofsafety.BasedonthediscussionpresentedaboveandonthesupportingEvaluationofProposedTS~Changes,FPLhasconcludedthatthisproposedlicenseamendmentinvolvesnosignificanthazardsconsideration.}}
.LTTRENCLIDCODE/NAME 11PD2-3PD1111F1LECENTER~01 11NRR/DE/EMCB 11NRR/DSSA/SPLB 11NUDOCS-ABSTRACT 10COPIESLTTRENCL1111111111EXTERNAL:
NOAC11NRCPDR11DNOTETOALL"RIDS"RECIPIENTS:
PLEASEHELPUSTOREDUCEWASTE!CONTACTTHEDOCUMENTCONTROLDESK/ROOMOWFNSD-5(EXT.
415-2083)
TOELIMINATE YOURNAMEFROMDISTRIBUTION LISTSFORDOCUMENTS YOUDON'TNEED!TOTALNUMBEROFCOPIESREQUIRED:
LTTR14ENCL,'.13 Cew'tIr,>lC*('I December20,1996FloridaPower8tLightCompany,P.O.Box128,FortPierce,FL34954-0128 L-96-33310CFR50.90U.S.NuclearRegulatory Commission Attn:DocumentControlDeskWashington, D.C.20555Re:St.LucieUnit1DocketNo.50-335ProposedLicenseAmendment.
ReactorCoreSafetLimitPursuantto10CFR50.90,FloridaPower&LightCompany(FPL)requeststoamendFacilityOperating LicenseDPR-67forSt.LucieUnit1byincorporating theattachedTechnical Specifications (TS)revision.
Theamendment willdeleteafootnoteassociated withTS2.1.1,"ReactorCoreSafetyLimits,"whichrequiresreactorthermalpowertobelimitedto90%of2700Megawatts thermalforCycle14operation beyond7000Effective FullPowerHours.Itisrequested thattheproposedamendment, ifapproved, beissuedpriortoMay15,1997topermitcontinued operation ofSt.LucieUnit1atfullpower.Attachment 1isanevaluation oftheproposedTSchange.Attachment 2isthe"Determination ofNoSignificant HazardsConsideration."
Attachment 3containsacopyoftheaffectedTSpagemarked-up toshowtheproposedchanges.Enclosedwiththissubmittal isacopyofreportEMF-96-176,"St.LucieUnit1SmallBreakLOCAAnalysiswith30%SteamGenerator Tube.Plugging,"
SiemensPowerCorporation, Revision1,December1996.Theproposedamendment hasbeenreviewedbytheSt.LucieFacilityReviewGroupandtheFloridaPower8.LightCompanyNuclearReviewBoard.Inaccordance with10CFR50.91(b)(1),acopyoftheproposedamendment isbeingforwarded totheStateDesigneefortheStateofFlorida.Pleasecontactusifthereareanyquestions aboutthissubmittal.
Verytrulyyours,J.A.StallVicePresident St.LuciePlantJAS/RLDAttachments 9hi2270073 9hi220PDR,ADQCK05000335PPDRPOD((StewartD.Ebnctcr,RegionalAdministrator, RegionII,USNRC.SeniorResidentInspector, USNRC,St.LucicPlant.Mr.W.A.Passctti, FloridaDcpartmcnt ofHealthandRchabilitativc Scrviccs.
anFPLGroupcompany 0r<t4 St.LucieUnit1DocketNo.50-335ProposedLicenseAmendment ReactorCoreSafetLimitSTATEOFFLORIDA))ss.COUNTYOFST.LUCIE)J.A.Stallbeingfirstdulysworn,deposesandsays:ThatheisVicePresident, St.LuciePlant,fortheNuclearDivisionofFloridaPowerEcLightCompany,theLicenseeherein;Thathehasexecutedtheforegoing document; thatthestatements madeinthisdocumentaretrueandcorrecttothebestofhisknowledge, information andbelief,andthatheisauthorized toexecutethedocumentonbehalfofsaidLicensee.
J.A.StallSTATEOFFLORIDACOUNTYOFST.~uc<<Sworntoandsubscribed beforemethis~~dayofDKCFwR8R19+kbyJ.A.Stall,whoispersonally knowntome.(''DScASignature ofNotaryPublic-State ofFloridao~pSs~sg~~ii~01%C,hnrtcs'D.>dfNameofNotaryPublic(Print,Type,orStamgiig(7''sjj8~,ii"'>llillla'l>>
tlI4II1~~'>fe>~'k4 St.LucieUnit1DocketNo.50-335ProposedLicenseAmendment ReactorCoreSafetLimitATTACHMENT 1EVALUATION OFPROPOSEDCHANGES lI(IjhV4 L-96-333Attachment 1P~aeIEVALUATION OFPROPOSEDTSCHANGESIntroduction Theproposedamendment toFacilityOperating LicenseDPR-67forSt.LucieUnit1willdeleteafootnoteassociated withTechnical Specification (TS)2.1.1,"Reactor CoreSafetyLimits,"whichrequiresthermalpowertobelimitedtolessthanorequalto90%of2700Megawatts thermal(MWth)forCycle14operation beyond7000Effective FullPowerHours(EFPH).Thethermalpowerconstraint wasimposedinlieuofperforming aSmallBreakLossofCoolantAccident(SBLOCA)re-analysis forfullpoweroperation thatdemonstrates acceptable resultsusinginputassumptions corresponding to30%(average) ofallsteamgenerator tubesplugged(SGTP).Thatanalysishasbeencompleted, andareportofanalysisresultsisenclosedwiththissubmittal.
DescritionofProosedChaneTS211Pae2-1:Deletetheasteriskfollowing "THERMALPOWER,"anddeletefootnote"*"shownatthebottomofpage2-1.AcopyofTSPage2-1,marked-up toshowtheproposedchanges,iscontained inAttachment 3.BackroundAmendment No.145toFacilityOperating LicenseNo.DPR-67(L.A.Wiens(NRC)toT.F.Plunkett(FPL):ST.LUCIEUNIT1-ISSUANCEOFAMENDMENT RE:THERIVfAL MARGINANDREACTORCOOLANTSYSTEMFLOWLIMITS(TACNO.M95472),July9,1996)wasissuedtopermitplantoperation withupto30%(average)
SGTPand345,000gpmminimumReactorCoolantSystem(RCS)flow.Insupportofthisamendment, FPLhaddetermined thatconservatism intheexistingSBLOCAanalysis, whichhadpreviously beenperformed forconditions corresponding to25%SGTPand355,000gpmRCSflow,wouldoffsetanyadverseeffectsduetotheincreased SGTPanddecreased reactorcoolantsystemflowforfullpoweroperation upto7000EFPH.Tooffsetanyadverseeffectsforoperation beyond7000EFPH,itwasdetermined thatlimitingcorethermalpowerto90%ofratedthermalpowerwouldprovidesufficient margintoensure10CFR50.46conformity fortheremainder ofoperating Cycle14.Subsequent toissuanceofAmendment No.145,are-analysis oftheSBLOCAhasbeencompleted usinginputassumptions corresponding to30%(average)
SGTPand345,000gpmRCSflow.Theresultsofthatanalysisarebrieflydiscussed inthisevaluation, anddataisprovidedingreaterdetailintheenclosedSiemensPowerCorporation-Nuclear DivisionReportEMF-96-176, "St.LucieUnit1SmallBreakLOCAAnalysiswith30%SteamGenerator TubePlugging,"
Revision1,December1996.
L-96-333Attachment 1P~ee2BasesforTSChaneByAmendment No.145,theNRCapprovedalicenseamendment toreducetheRCSflowfrom355,000gpmto345,000gpmandthelowflowtripsetpointfrom95%to93%ofdesignRCSflow.Thisamendment supported aSGTPlevelof30%+7%,witharequirement toderateto90%of2700MWthpriortoexceeding 7000EFPHofCycle14operation.
Therequirement toderatewasbasedontheSBLOCAanalysis, whichsupported afullpoweroperation upto7000EFPHand90%powerlevelbeyond7000EFPH.ExceptfortheSBLOCA,acceptable resultswereshownwithintheapplicable safetylimitsforallthesafetyandsetpointanalysesat100%poweroperation attheamendedconditions andaSGTPlevelof30%+7%.TheSBLOCAwasevaluated at100%ofratedpowerupto7000EFPHandat90%powerlevelbeyond7000EFPH.TosupportCycle14operation at2700MWthtoend-of-cyclerequiredareanalysis ofSBLOCAwiththelimitingend-of-cycle conditions.
TheSBLOCAhasbeenreanalyzed tosupportCycle14operation at100%powerfortheentireoperating cycle.Theanalysis, includedastheenclosure tothisproposedlicenseamendment, demonstrates acceptable resultsincompliance with10CFR50.46criteria.
Thepeakcladdingtemperature (PCT)wascalculated tobe1804'F,wellbelowtheacceptance criteriaof2200'F.Thisanalysiswasperformed bySiemensPowerCorporation (SPC),usinganNRC-approved SBLOCAevaluation model.Thereanalysis wasdonewithchangestoinputassumptions withrespecttotheloopsealclearingandthelocationofcoldleginjection point.Theloopsealsinthebrokenloopandoneoftheintactloopswerebiasedtoremainplugged.Inthecurrentanalysisofrecord,theloopsealinthebrokenloopdidnotstayplugged.Alsothesafetyinjection pointwasmovedanodeawayfromthereactorcoolantpumptorepresent amorerealistic configuration.
Overallthesechangesremovesomeoftheconservatism ascomparedtotheanalysisofrecordfor25%tubeplugginglevel(EMF-92-148, "St.LucieUnit1SmallBreakLOCAAnalysis,"
SiemensPowerCorporation, May1994).Conclusion TheSBLOCAreanalysis, alongwiththeanalysesaddressed inAmendment No.145,supportoperation ofSt.LucieUnit1at100%ofRATEDTHERMALPOWERfortheentireCycle14.TheproposedchangesupportsthereducedRCSflowof345,000gpmcorresponding toaSGTPlevelof30%+7%approvedinAmendment No.145.
ATTACHMENT 2DETERMINATION OFNOSIGNIFICANT HAZARDSCONSIDERATION L-96-333Attachment 2P~aeIDETERMINATION OFNOSIGNIFICANT HAZARDSCONSIDERATION Description ofamendment request:Theproposedamendment willdeleteafootnoteassociated withTechnical Specification 2.1.1,"Reactor CoreSafetyLimits,"whichrequiresthermalpowertobelimitedto90%of2700Megawatts thermal(MWth)forCycle14operation beyond7000Effective FullPowerHours.Pursuantto10CFR50.92,adetermination maybemadethataproposedlicenseamendment involvesnosignificant hazardsconsideration ifoperation ofthefacilityinaccordance withtheproposedamendment wouldnot:(1)involveasignificant increaseintheprobability orconsequences ofanaccidentpreviously evaluated; or(2)createthepossibility ofanewordifferent kindofaccidentfromanyaccidentpreviously evaluated; or(3)involveasignificant reduction inamarginofsafety.Eachstandardisdiscussed asfollows:(1)Operation ofthefacilityinaccordance withtheproposedamendment wouldnotinvolveasigniTicant increaseintheprobability orconsequences ofanaccidentpreviously evaluated.
TheproposedchangewillallowfullCycle14operation at100%ofratedpower(2700MWth),bydeletingtherequirement toderateto90%ofratedpowerpriortoexceeding 7000EFPH.Thisrestriction wasimposedintheNRCtransmittal letterforLicenseAmendment 145forSBLOCAconsiderations whenconsidering theincreased SGTPlevelof30%+7%.AllFinalSafetyAnalysisReport(FSAR)events,otherthanSBLOCAwereevaluated at100%ofratedthermalpowerandshowednosignificant increases intheprobability orconsequences ofaccidents previously evaluated.
TheSBLOCAwasreanalyzed todemonstrate continued compliance with10CFR50.46criteria.
ThereisnoimpactoftheproposedchangeonanyFSARaccidentinitiator.
Theplantconfiguration andsystemsremainunchanged.
Therefore, operation ofthefacilityinaccordance withtheproposedamendment wouldnotinvolveasignificant increaseintheprobability orconsequences ofanaccidentpreviously evaluated.
(2)Operation ofthefacilityinaccordance withtheproposedamendment wouldnotcreatethepossibility ofanewordifferent kindofaccidentfromanyaccidentpreviously evaluated.
Thisproposedamendment removestherequirement intheTechnical Specifications toderateto90%of2700MWthforCycle14operation beyond7000EFPH.Therewillbe L-96-333Attachment 2P~ae2nochangetothemodesofoperation oftheplant.Theplantconfiguration andthedesignfunctions ofallthesafetysystemsremainunchanged.
Theproposedamendment willnotchangethephysicalplantorthemodesofoperation definedinthefacilitylicense.Thechangesdonotinvolvetheadditionofnewequipment orthemodification ofexistingequipment, nordotheyalterthedesignofSt.Lucieplantsystems.Therefore, operation ofthefacilityinaccordance withtheproposedamendment wouldnotcreatethepossibility ofanewordifFerent kindofaccidentfromanyaccidentpreviously evaluated.
(3)Operation ofthefacilityinaccordance withtheproposedamendment wouldnotinvolveasignificant reduction inamarginofsafety.Theimpactoftheproposedchangeon'available margintotheacceptance criteriaforSpecified Acceptable FuelDesignLimits(SAFDL),primaryandsecondary over-pressurization, peakcontainment
: pressure, potential radioactive
: releases, 10CFR50.46requirements forthelargebreakLOCA,andexistinglimitingconditions foroperation hasbeenevaluated andaddressed inthereducedRCSflowoperating licenseAmendment No.145.Arequirement toderateto90%of2700MWthwasimposedbasedontheSBLOCAanalysis.
ThesmallbreakLOCAanalysiswith30%+7%SGTPsupported operation upto7000EFPHat100%of-ratedthermalpower.Areanalysis ofSBLOCAwiththelimitingend-of-cycle conditions at100%ofratedpower,demonstrates continued compliance with10CFR50.46criteria.
Therefore, operation ofthefacilityinaccordance withtheproposedamendment wouldnotinvolveasignificant reduction inamarginofsafety.Basedonthediscussion presented aboveandonthesupporting Evaluation ofProposedTS~Changes,FPLhasconcluded thatthisproposedlicenseamendment involvesnosignificant hazardsconsideration.}}

Revision as of 15:47, 29 June 2018

Application for Amend to License DPR-67,requesting Deletion of Footnote Re TS 2.1.1, Reactor Core Safety Limits.
ML17229A181
Person / Time
Site: Saint Lucie NextEra Energy icon.png
Issue date: 12/20/1996
From: STALL J A
FLORIDA POWER & LIGHT CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML17229A182 List:
References
L-96-333, NUDOCS 9612270073
Download: ML17229A181 (13)
v • d • e


Text

CATEGORY1REGULATINFORMATION DISTRIBUTION STEM(RIDS)!'CCFSS.'fON NBR:9612270073 DOC.DATE:

96/12/20NOTARIZED:

NOk'ACIL:50-335 St.LuciePlant,Unit1,FloridaPower6LightCo.AUTH,NAMEAUTHORAFFILIATION STALL,J.A.

FloridaPower&LightCo.RECIP.NAME RECIPIENT AFFILIATION DocumentControlBranch(Document ControlDesk)DOCKET05000335

SUBJECT:

Application foramendtolicenseDP$-67,requesting deletionoffootnotereTS2.1.1,"ReactorCoreSafetyLimits."CDISTRIBUTION CODE:A001DCOPIESRECEIVED:LTR ENCLSIZE:TITLE:ORSubmittal:

GeneralDistribution NOTES:RECIPIENT IDCODE/NAME PD2-3LAWIENS,L.INTERNAL:

ACRSNRR/DE/ECGB/A NRR/DRCH/HICB NRR/DSSA/SRXB OGC/HDS3COPIESRECIPIENT

.LTTRENCLIDCODE/NAME 11PD2-3PD1111F1LECENTER~01 11NRR/DE/EMCB 11NRR/DSSA/SPLB 11NUDOCS-ABSTRACT 10COPIESLTTRENCL1111111111EXTERNAL:

NOAC11NRCPDR11DNOTETOALL"RIDS"RECIPIENTS:

PLEASEHELPUSTOREDUCEWASTE!CONTACTTHEDOCUMENTCONTROLDESK/ROOMOWFNSD-5(EXT.

415-2083)

TOELIMINATE YOURNAMEFROMDISTRIBUTION LISTSFORDOCUMENTS YOUDON'TNEED!TOTALNUMBEROFCOPIESREQUIRED:

LTTR14ENCL,'.13 Cew'tIr,>lC*('I December20,1996FloridaPower8tLightCompany,P.O.Box128,FortPierce,FL34954-0128 L-96-33310CFR50.90U.S.NuclearRegulatory Commission Attn:DocumentControlDeskWashington, D.C.20555Re:St.LucieUnit1DocketNo.50-335ProposedLicenseAmendment.

ReactorCoreSafetLimitPursuantto10CFR50.90,FloridaPower&LightCompany(FPL)requeststoamendFacilityOperating LicenseDPR-67forSt.LucieUnit1byincorporating theattachedTechnical Specifications (TS)revision.

Theamendment willdeleteafootnoteassociated withTS2.1.1,"ReactorCoreSafetyLimits,"whichrequiresreactorthermalpowertobelimitedto90%of2700Megawatts thermalforCycle14operation beyond7000Effective FullPowerHours.Itisrequested thattheproposedamendment, ifapproved, beissuedpriortoMay15,1997topermitcontinued operation ofSt.LucieUnit1atfullpower.Attachment 1isanevaluation oftheproposedTSchange.Attachment 2isthe"Determination ofNoSignificant HazardsConsideration."

Attachment 3containsacopyoftheaffectedTSpagemarked-up toshowtheproposedchanges.Enclosedwiththissubmittal isacopyofreportEMF-96-176,"St.LucieUnit1SmallBreakLOCAAnalysiswith30%SteamGenerator Tube.Plugging,"

SiemensPowerCorporation, Revision1,December1996.Theproposedamendment hasbeenreviewedbytheSt.LucieFacilityReviewGroupandtheFloridaPower8.LightCompanyNuclearReviewBoard.Inaccordance with10CFR50.91(b)(1),acopyoftheproposedamendment isbeingforwarded totheStateDesigneefortheStateofFlorida.Pleasecontactusifthereareanyquestions aboutthissubmittal.

Verytrulyyours,J.A.StallVicePresident St.LuciePlantJAS/RLDAttachments 9hi2270073 9hi220PDR,ADQCK05000335PPDRPOD((StewartD.Ebnctcr,RegionalAdministrator, RegionII,USNRC.SeniorResidentInspector, USNRC,St.LucicPlant.Mr.W.A.Passctti, FloridaDcpartmcnt ofHealthandRchabilitativc Scrviccs.

anFPLGroupcompany 0r<t4 St.LucieUnit1DocketNo.50-335ProposedLicenseAmendment ReactorCoreSafetLimitSTATEOFFLORIDA))ss.COUNTYOFST.LUCIE)J.A.Stallbeingfirstdulysworn,deposesandsays:ThatheisVicePresident, St.LuciePlant,fortheNuclearDivisionofFloridaPowerEcLightCompany,theLicenseeherein;Thathehasexecutedtheforegoing document; thatthestatements madeinthisdocumentaretrueandcorrecttothebestofhisknowledge, information andbelief,andthatheisauthorized toexecutethedocumentonbehalfofsaidLicensee.

J.A.StallSTATEOFFLORIDACOUNTYOFST.~uc<<Sworntoandsubscribed beforemethis~~dayofDKCFwR8R19+kbyJ.A.Stall,whoispersonally knowntome.(DScASignature ofNotaryPublic-State ofFloridao~pSs~sg~~ii~01%C,hnrtcs'D.>dfNameofNotaryPublic(Print,Type,orStamgiig(7sjj8~,ii"'>llillla'l>>

tlI4II1~~'>fe>~'k4 St.LucieUnit1DocketNo.50-335ProposedLicenseAmendment ReactorCoreSafetLimitATTACHMENT 1EVALUATION OFPROPOSEDCHANGES lI(IjhV4 L-96-333Attachment 1P~aeIEVALUATION OFPROPOSEDTSCHANGESIntroduction Theproposedamendment toFacilityOperating LicenseDPR-67forSt.LucieUnit1willdeleteafootnoteassociated withTechnical Specification (TS)2.1.1,"Reactor CoreSafetyLimits,"whichrequiresthermalpowertobelimitedtolessthanorequalto90%of2700Megawatts thermal(MWth)forCycle14operation beyond7000Effective FullPowerHours(EFPH).Thethermalpowerconstraint wasimposedinlieuofperforming aSmallBreakLossofCoolantAccident(SBLOCA)re-analysis forfullpoweroperation thatdemonstrates acceptable resultsusinginputassumptions corresponding to30%(average) ofallsteamgenerator tubesplugged(SGTP).Thatanalysishasbeencompleted, andareportofanalysisresultsisenclosedwiththissubmittal.

DescritionofProosedChaneTS211Pae2-1:Deletetheasteriskfollowing "THERMALPOWER,"anddeletefootnote"*"shownatthebottomofpage2-1.AcopyofTSPage2-1,marked-up toshowtheproposedchanges,iscontained inAttachment 3.BackroundAmendment No.145toFacilityOperating LicenseNo.DPR-67(L.A.Wiens(NRC)toT.F.Plunkett(FPL):ST.LUCIEUNIT1-ISSUANCEOFAMENDMENT RE:THERIVfAL MARGINANDREACTORCOOLANTSYSTEMFLOWLIMITS(TACNO.M95472),July9,1996)wasissuedtopermitplantoperation withupto30%(average)

SGTPand345,000gpmminimumReactorCoolantSystem(RCS)flow.Insupportofthisamendment, FPLhaddetermined thatconservatism intheexistingSBLOCAanalysis, whichhadpreviously beenperformed forconditions corresponding to25%SGTPand355,000gpmRCSflow,wouldoffsetanyadverseeffectsduetotheincreased SGTPanddecreased reactorcoolantsystemflowforfullpoweroperation upto7000EFPH.Tooffsetanyadverseeffectsforoperation beyond7000EFPH,itwasdetermined thatlimitingcorethermalpowerto90%ofratedthermalpowerwouldprovidesufficient margintoensure10CFR50.46conformity fortheremainder ofoperating Cycle14.Subsequent toissuanceofAmendment No.145,are-analysis oftheSBLOCAhasbeencompleted usinginputassumptions corresponding to30%(average)

SGTPand345,000gpmRCSflow.Theresultsofthatanalysisarebrieflydiscussed inthisevaluation, anddataisprovidedingreaterdetailintheenclosedSiemensPowerCorporation-Nuclear DivisionReportEMF-96-176, "St.LucieUnit1SmallBreakLOCAAnalysiswith30%SteamGenerator TubePlugging,"

Revision1,December1996.

L-96-333Attachment 1P~ee2BasesforTSChaneByAmendment No.145,theNRCapprovedalicenseamendment toreducetheRCSflowfrom355,000gpmto345,000gpmandthelowflowtripsetpointfrom95%to93%ofdesignRCSflow.Thisamendment supported aSGTPlevelof30%+7%,witharequirement toderateto90%of2700MWthpriortoexceeding 7000EFPHofCycle14operation.

Therequirement toderatewasbasedontheSBLOCAanalysis, whichsupported afullpoweroperation upto7000EFPHand90%powerlevelbeyond7000EFPH.ExceptfortheSBLOCA,acceptable resultswereshownwithintheapplicable safetylimitsforallthesafetyandsetpointanalysesat100%poweroperation attheamendedconditions andaSGTPlevelof30%+7%.TheSBLOCAwasevaluated at100%ofratedpowerupto7000EFPHandat90%powerlevelbeyond7000EFPH.TosupportCycle14operation at2700MWthtoend-of-cyclerequiredareanalysis ofSBLOCAwiththelimitingend-of-cycle conditions.

TheSBLOCAhasbeenreanalyzed tosupportCycle14operation at100%powerfortheentireoperating cycle.Theanalysis, includedastheenclosure tothisproposedlicenseamendment, demonstrates acceptable resultsincompliance with10CFR50.46criteria.

Thepeakcladdingtemperature (PCT)wascalculated tobe1804'F,wellbelowtheacceptance criteriaof2200'F.Thisanalysiswasperformed bySiemensPowerCorporation (SPC),usinganNRC-approved SBLOCAevaluation model.Thereanalysis wasdonewithchangestoinputassumptions withrespecttotheloopsealclearingandthelocationofcoldleginjection point.Theloopsealsinthebrokenloopandoneoftheintactloopswerebiasedtoremainplugged.Inthecurrentanalysisofrecord,theloopsealinthebrokenloopdidnotstayplugged.Alsothesafetyinjection pointwasmovedanodeawayfromthereactorcoolantpumptorepresent amorerealistic configuration.

Overallthesechangesremovesomeoftheconservatism ascomparedtotheanalysisofrecordfor25%tubeplugginglevel(EMF-92-148, "St.LucieUnit1SmallBreakLOCAAnalysis,"

SiemensPowerCorporation, May1994).Conclusion TheSBLOCAreanalysis, alongwiththeanalysesaddressed inAmendment No.145,supportoperation ofSt.LucieUnit1at100%ofRATEDTHERMALPOWERfortheentireCycle14.TheproposedchangesupportsthereducedRCSflowof345,000gpmcorresponding toaSGTPlevelof30%+7%approvedinAmendment No.145.

ATTACHMENT 2DETERMINATION OFNOSIGNIFICANT HAZARDSCONSIDERATION L-96-333Attachment 2P~aeIDETERMINATION OFNOSIGNIFICANT HAZARDSCONSIDERATION Description ofamendment request:Theproposedamendment willdeleteafootnoteassociated withTechnical Specification 2.1.1,"Reactor CoreSafetyLimits,"whichrequiresthermalpowertobelimitedto90%of2700Megawatts thermal(MWth)forCycle14operation beyond7000Effective FullPowerHours.Pursuantto10CFR50.92,adetermination maybemadethataproposedlicenseamendment involvesnosignificant hazardsconsideration ifoperation ofthefacilityinaccordance withtheproposedamendment wouldnot:(1)involveasignificant increaseintheprobability orconsequences ofanaccidentpreviously evaluated; or(2)createthepossibility ofanewordifferent kindofaccidentfromanyaccidentpreviously evaluated; or(3)involveasignificant reduction inamarginofsafety.Eachstandardisdiscussed asfollows:(1)Operation ofthefacilityinaccordance withtheproposedamendment wouldnotinvolveasigniTicant increaseintheprobability orconsequences ofanaccidentpreviously evaluated.

TheproposedchangewillallowfullCycle14operation at100%ofratedpower(2700MWth),bydeletingtherequirement toderateto90%ofratedpowerpriortoexceeding 7000EFPH.Thisrestriction wasimposedintheNRCtransmittal letterforLicenseAmendment 145forSBLOCAconsiderations whenconsidering theincreased SGTPlevelof30%+7%.AllFinalSafetyAnalysisReport(FSAR)events,otherthanSBLOCAwereevaluated at100%ofratedthermalpowerandshowednosignificant increases intheprobability orconsequences ofaccidents previously evaluated.

TheSBLOCAwasreanalyzed todemonstrate continued compliance with10CFR50.46criteria.

ThereisnoimpactoftheproposedchangeonanyFSARaccidentinitiator.

Theplantconfiguration andsystemsremainunchanged.

Therefore, operation ofthefacilityinaccordance withtheproposedamendment wouldnotinvolveasignificant increaseintheprobability orconsequences ofanaccidentpreviously evaluated.

(2)Operation ofthefacilityinaccordance withtheproposedamendment wouldnotcreatethepossibility ofanewordifferent kindofaccidentfromanyaccidentpreviously evaluated.

Thisproposedamendment removestherequirement intheTechnical Specifications toderateto90%of2700MWthforCycle14operation beyond7000EFPH.Therewillbe L-96-333Attachment 2P~ae2nochangetothemodesofoperation oftheplant.Theplantconfiguration andthedesignfunctions ofallthesafetysystemsremainunchanged.

Theproposedamendment willnotchangethephysicalplantorthemodesofoperation definedinthefacilitylicense.Thechangesdonotinvolvetheadditionofnewequipment orthemodification ofexistingequipment, nordotheyalterthedesignofSt.Lucieplantsystems.Therefore, operation ofthefacilityinaccordance withtheproposedamendment wouldnotcreatethepossibility ofanewordifFerent kindofaccidentfromanyaccidentpreviously evaluated.

(3)Operation ofthefacilityinaccordance withtheproposedamendment wouldnotinvolveasignificant reduction inamarginofsafety.Theimpactoftheproposedchangeon'available margintotheacceptance criteriaforSpecified Acceptable FuelDesignLimits(SAFDL),primaryandsecondary over-pressurization, peakcontainment

pressure, potential radioactive
releases, 10CFR50.46requirements forthelargebreakLOCA,andexistinglimitingconditions foroperation hasbeenevaluated andaddressed inthereducedRCSflowoperating licenseAmendment No.145.Arequirement toderateto90%of2700MWthwasimposedbasedontheSBLOCAanalysis.

ThesmallbreakLOCAanalysiswith30%+7%SGTPsupported operation upto7000EFPHat100%of-ratedthermalpower.Areanalysis ofSBLOCAwiththelimitingend-of-cycle conditions at100%ofratedpower,demonstrates continued compliance with10CFR50.46criteria.

Therefore, operation ofthefacilityinaccordance withtheproposedamendment wouldnotinvolveasignificant reduction inamarginofsafety.Basedonthediscussion presented aboveandonthesupporting Evaluation ofProposedTS~Changes,FPLhasconcluded thatthisproposedlicenseamendment involvesnosignificant hazardsconsideration.

Retrieved from "https://kanterella.com/w/index.php?title=ML17229A181&oldid=747194"