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| {{#Wiki_filter:FioridaPower6LightCompany,6351S.OceanDrive,JensenBeach,FL34957December29,1997~L-97-28010CFR50.90U.S.NuclearRegulatoryCommissionAttn:DocumentControlDeskWashington,D.C.20555Re:St.LucieUnit2DocketNo.50-389ProposedLicenseAmendmentCore0eratinLimitsReortCOLRRef:(1)LetterfromR.P.Croteau(NRC)toJ.H.Goldberg(FPL),TurkeyPointUnits3and4-IssuanceofAmendmentsRe:ImplementationofFPLNuclearPhysicsMethodology(TACNos.M91393andM91394;June9,1995.Pursuantto10CFR50.90,FloridaPower&LightCompany(FPL)requeststoamendFacilityOperatingLicenseNPF-16forSt.LucieUnit2byincorporatingtheattachedTechnicalSpecificationsrevisions.Theamendmentwillmodifyspecificationsforselectedcycle-specificreactorphysicsparameterssothattheyrefertotheSt.LucieUnit2CoreOperatingLimitsReport(COLR)forlimitingvalues.Minoradministrativechangesarealsoincluded.TheproposedTSchangesconformtotheguidance.providedinGenericLetter88-16andareconsistentwiththeStandardTechnicalSpecificationsforCombustionEngineeringPlants(NUREG-1432,Revision1).Itisrequestedthattheproposedamendment,ifapproved,beissuedbyJuly31,1998.Attachment1isanevaluationoftheproposedTSchanges.Attachment2isthe"DeterminationofNoSignificantHazardsConsideration."Attachment3containsacopyoftheaffectedTSpagesmarked-uptoshowtheproposedchanges.Enclosure(1)istheSt.LucieUnit2,Cycle10,CoreOperatingLimitsReport.Enclosure(2)isSupplement1toFPL'sTopicalReportNF-TR-95-01,NuclearPhysicsMethodologyforReloadDesignofTurkeyPointandSt.LucieNuclearPlants,whichprovidescomparisonsbetweencorephysicspredictionsandactualoperatingdataforSt.LucieUnit2.TheoriginalreportreviewedbytheNRCstaff(Reference1)didnotcontainSt.LucieUnit2specificdata.ThesupplementisvoluntarilysubmittedtofurtherdemonstrateFPL'sabilitytoperformreloadcoredesignforthatunit.TheproposedamendmenthasbeenreviewedbytheSt.LucieFacilityReviewGroupandtheFloridaPower&LightCompanyNuclearReviewBoard.Inaccordancewith10CFR50.91(b)(1),acopyoftheproposedamendmentisbeingforwardedtotheStateDesigneefortheStateofFlorida.Pleasecontactusifthereareanyquestionsaboutthissubmittal.Verytrulyyours,p.o~"J.A.Stall,VicePresidentSt.LuciePlant980i060i8597i229PDRADQCK05000250PPDRanFPLGroupcompanylllllllllllllllllillllllllllllllllll St.LucieUnit2DocketNo.50-389ProposedLicenseAmendmentCore0eratinLimitsReortCOLRL-97-280Page2JASIRLDAttachments | | {{#Wiki_filter:FioridaPower6LightCompany,6351 S.OceanDrive,JensenBeach,FL34957December29,1997~L-97-28010CFR50.90U.S.NuclearRegulatory Commission Attn:DocumentControlDeskWashington, D.C.20555Re:St.LucieUnit2DocketNo.50-389ProposedLicenseAmendment Core0eratinLimitsReortCOLRRef:(1)LetterfromR.P.Croteau(NRC)toJ.H.Goldberg(FPL),TurkeyPointUnits3and4-IssuanceofAmendments Re:Implementation ofFPLNuclearPhysicsMethodology (TACNos.M91393andM91394;June9,1995.Pursuantto10CFR50.90,FloridaPower&LightCompany(FPL)requeststoamendFacilityOperating LicenseNPF-16forSt.LucieUnit2byincorporating theattachedTechnical Specifications revisions. |
| | Theamendment willmodifyspecifications forselectedcycle-specific reactorphysicsparameters sothattheyrefertotheSt.LucieUnit2CoreOperating LimitsReport(COLR)forlimitingvalues.Minoradministrative changesarealsoincluded. |
| | TheproposedTSchangesconformtotheguidance. |
| | providedinGenericLetter88-16andareconsistent withtheStandardTechnical Specifications forCombustion Engineering Plants(NUREG-1432, Revision1).Itisrequested thattheproposedamendment, ifapproved, beissuedbyJuly31,1998.Attachment 1isanevaluation oftheproposedTSchanges.Attachment 2isthe"Determination ofNoSignificant HazardsConsideration." |
| | Attachment 3containsacopyoftheaffectedTSpagesmarked-up toshowtheproposedchanges.Enclosure (1)istheSt.LucieUnit2,Cycle10,CoreOperating LimitsReport.Enclosure (2)isSupplement 1toFPL'sTopicalReportNF-TR-95-01, NuclearPhysicsMethodology forReloadDesignofTurkeyPointandSt.LucieNuclearPlants,whichprovidescomparisons betweencorephysicspredictions andactualoperating dataforSt.LucieUnit2.TheoriginalreportreviewedbytheNRCstaff(Reference 1)didnotcontainSt.LucieUnit2specificdata.Thesupplement isvoluntarily submitted tofurtherdemonstrate FPL'sabilitytoperformreloadcoredesignforthatunit.Theproposedamendment hasbeenreviewedbytheSt.LucieFacilityReviewGroupandtheFloridaPower&LightCompanyNuclearReviewBoard.Inaccordance with10CFR50.91(b)(1),acopyoftheproposedamendment isbeingforwarded totheStateDesigneefortheStateofFlorida.Pleasecontactusifthereareanyquestions aboutthissubmittal. |
| | Verytrulyyours,p.o~"J.A.Stall,VicePresident St.LuciePlant980i060i85 97i229PDRADQCK05000250PPDRanFPLGroupcompanylllllllllllllllll illllllllllllllllll St.LucieUnit2DocketNo.50-389ProposedLicenseAmendment Core0eratinLimitsReortCOLRL-97-280Page2JASIRLDAttachments |
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| ==Enclosures:== | | ==Enclosures:== |
| (1)St.LucieUnit2,Cycle10,CoreOperatingLimitsReport,Revision0.(2)NuclearPhysicsMethodologyforReloadDesignofTurkeyPointandSt.LucieNuclearPlants,NF-TR-95-01,Supplement1;August,1997.cc:RegionalAdministrator,RegionII,USNRC.SeniorResidentInspector,USNRC,St.LuciePlant.Mr.W.A.Passetti,FloridaDepartmentofHealthandRehabilitativeServices.
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| St.LucieUnit2DocketNo.50-389ProposedLicenseAmendmentCore0eratinLimitsReortCOLRL-97-280Page3STATEOFFLORIDA))ss.COUNTYOFST.LUCIEJ.A.Stallbeingfirstdulysworn,deposesandsays:ThatheisVicePresident,St.LuciePlant,fortheNuclearDivisionofFloridaPower8LightCompany,theLicenseeherein;Thathehasexecutedtheforegoingdocument;thatthestatementsmadeinthisdocumentaretrueandcorrecttothebestofhisknowledge,informationandbelief,andthatheisauthorizedtoexecutethedocumentonbehalfofsaidLicensee.J.A.StallSTATEOFFLORIDACOUNTYOFSworntoandsubscribedbeforemethis~dayofOd08Ã58(byJ.A.Stall,whoispersonallyknowntome.SignatureofNotaublic-StateofFloridaLeslieJ.WMtwem~ss~:>>iNCOMMiSSiONfCCQ61S3EXPIAEShby12,2001'~i,~",~4'0NOEDllRUTteyfhN$5URAHCE,INC.NameofNotaryPublic(Print,Type,orStamp)
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| St.LucieUnit2DocketNo.50-389ProposedLicenseAmendmentCore0eratinLimitsReortCOLRATTACHMENT1toL-97-280EVALUATIONOFPROPOSEDTSCHANGES
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St.LucieUnit2DocketNo.50-389ProposedLicenseAmendmentCore0eratinLimitsReortCOLRL-97>>280Attachment1Page1of4EVALUATIONOFPROPOSEDTSCHANGESIntroductionTheproposedamendmenttoFacilityOperatingLicenseNPF-16forSt.LucieUnit2(PSL2)willmodifyTechnicalSpecifications(TS)forselectedcycle-specificreactorphysicsparameterssothattheyrefertotheSt.LucieUnit2CoreOperatingLimitsReport(COLR)forlimitingvalues.Minoradministrativechangesarealsoincluded.TherevisionsconformtotheguidanceprovidedinGenericLetter(GL)88-16andareconsistentwiththeStandardTechnicalSpecificationsforCombustionEngineeringPlants(NUREG-1432,Revision1).TheproposedTSchangesortheCOLRdonotalterthevalueofanyoftheexistingparameterlimits,andtheamendmentinvolvesnosignificanthazardsconsideration.BackroundAnumberofTSincludecycle-specificoperatinglimitsforreactorphysicsparametersthataresubjecttochangeasafunctionofreloadcoredesign,andtheanalyticalmethodsusedtodeterminesuchlimitsaretypicallydocumentedinTopicalReportsorinplant-specificsubmittalspreviouslyreviewedandapprovedbytheNRCstaff.Asaconsequence,thestaffsreviewofproposedchangestotheselimitsprimarilyinvolvesconfirmationthattheupdatedlimitsarecalculatedusinganNRCapprovedmethodologyandareconsistentwithallapplicablelimitsofthesafetyanalyses.Inordertoeliminatetheburdenthatisassociatedwiththeprocessforrequesting,reviewing,andapprovingalicenseamendmentsolelyforthepurposeofupdatingthecalculatedvaluesofcycle-specificparameterlimits,GL88-16encouragedlicenseestoproposechangestotheirtechnicalspecificationsthatareconsistentwiththeguidanceprovidedinthatletter.Threeseparateactionstomodifytheplant'sTSarediscussedinGL88-16:(1)addingadefinitionofanamedformalreport,e.g.,COLR,thatincludesthevaluesofcycle-specificparameterlimitsthathavebeenestablishedusinganNRCapprovedmethodologyandareconsistentwithallapplicablelimitsofthesafetyanalyses,(2)theadditionofanadministrativereportingrequirementtosubmittheformalreporttotheCommissionforinformation,and(3)themodificationofindividualTStonotethatcycle-specificparametersshallbemaintainedwithinthelimitsprovidedinthedefinedformalreport.TheNRCstaffnotedthat"itisessentialtosafetythattheplantisoperatedwithintheboundsofcycle-specificparameterlimitsandthatarequirementtomaintaintheplantwithintheappropriateboundsmustberetainedintheTS.However,thespecificvaluesoftheselimitsmaybemodifiedbylicensees,withoutaffectingnuclearsafety,providedthatthesechangesaredeterminedusinganNRC-approvedmethodologyand[are]consistentwithallapplicablelimitsoftheplantsafetyanalysisthatareaddressedintheFinalSafetyAnalysisReport(FSAR)."TheconceptofaCOLRandtheprovisionsofGL88-16wereincorporatedintotheimprovedStandardTechnicalSpecificationsforCombustionEngineeringPlants(NUREG-1432).DescritionofChanesModificationstoindividualspecificationsincludereplacingtheapplicableoperatinglimitswithreferencestotheCOLR,deletingapplicablefigures,addingtherequireddefinitionandadministrativecontrols,andmakingeditorialchangesasnecessaryforthepurposeofclarificationand/or St.LucieUnit2DocketNo.50-389ProposedLicenseAmendmentCore0eratinLimitsReortCOLRL-97-280Attachment1Page2of4consistency.CopiesoftheaffectedTSpages,marked-uptoshowtheproposedchanges,arecontainedinAttachment3tothissubmittal.Section1.0DEFINITIONSAddnewdefinition1.9a,COREOPERATINGLIMITSREPORTCOLR,showninInsert-AofAttachment3tothissubmittal.TS3.1.1.4MODERATORTEMPERATURECOEFFICIENTSpecification3.1.1.4.cisdeleted,andtheassociatedlimitofmaximumnegativemoderatortemperaturecoefficientatRATEDTHERMAL'OWERisrelocatedtotheCOLR.TS3/4.1.3MOVABLECONTROLASSEMBLIES-CEAPOSITIONFigure3.1-1a,AllowableTimetoRealignCEAvs.InitialFR~,specifyingthetimeconstraintforfullpoweroperationwithoneCEAmisalignedfromanyotherCEAinitsgroupbymorethan15inchesisdeletedfromTSandrelocatedtotheCOLR.TS3.1.3.6REGULATINGCEAINSERTIONLIMITSFigure3.1-2,%CEAInsertionvs.FractionofRatedThermalPower,showingtheregulatingCEAgroupswithdrawalsequenceandinsertionlimitsisdeletedfromTSandrelocatedtotheCOLR.TS3/4.2.1LINEARHEATRATEFigure3.2-1,AllowablePeakLinearHeatRatevs.Bumup;Figure3.2-2,AxialShapeIndexvs.FractionofMaximumAllowablePowerLevelperSpecification4.2.1.3;andFigure3.2-3,AllowableCombinationsofThermalPowerandFR',Fx',aredeletedfromTSandrelocatedtotheCOLR.Additionally,inSpecifications4.2.1.3and4.2.1.4,thephrase"monitoringthecorepowerdistribution"ischangedto"monitoringthelinearheatrate".S'32.2OTALPLANARRADIALPEAKINGFACTOS-F~ThecalculatedvaluefortheF~limitisdeletedfromTSandrelocatedtotheCOLR.TS3.23OTLINGTEDRDIALPKINGCOR-F~ThecalculatedvaluefortheF,~limit,andFigure3.2P,AxialShapeIndexOperatingLimitswithFourReactorCoolantPumpsOperating,aredeletedfromTSandrelocatedtotheCOLR.TS3.2.5DNBPARAMETERS-AXIALSHAPEINDEXTABLE3.2-2isrevisedtorefertoCOLRFigure3.2AfortheAXIALSHAPEINDEXlimit. | | (1)St.LucieUnit2,Cycle10,CoreOperating LimitsReport,Revision0.(2)NuclearPhysicsMethodology forReloadDesignofTurkeyPointandSt.LucieNuclearPlants,NF-TR-95-01, Supplement 1;August,1997.cc:RegionalAdministrator, RegionII,USNRC.SeniorResidentInspector, USNRC,St.LuciePlant.Mr.W.A.Passetti, FloridaDepartment ofHealthandRehabilitative Services. |
| St.LucieUnit2DocketNo.50-389ProposedLicenseAmendmentCore0eratinLimitsReortCOLRL-97-280Attachment1Page3of4TS3/4.9.1REFUELINGOPERATIONS-BORONCONCENTRATIONTheboronconcentrationlimitsaredeletedfromtheTSandrelocatedtotheCOLR.BASES3/4.1.33/4.2.1and3/4.9.1ThebasesareupdatedtoreflectthechangestocorrespondingTSdescribedabove.Section6.0ADMINISTRATIVECONTROLS:Addnewadministrativecontrol,"6.9.1.11COREOPERATINGLIIMITSREPORT(COLR)"asshowninInsert-BofAttachment3tothissubmittal.Page3/41-19a,page3/41-28,pages3/424through3/42-6,andpage3/42-12willbedeletedfromtheTSsincethesepageswillbeblank.Anoteisaddedtopage3/42-3and3/42-11whichdocumentsdeletionoftheaffectedpagesandmaintainscontinuityofpagination.BasesfortheProosedTSChanesCycle-specificparameterlimitsestablishedintheCOLR(Enclosure1)havebeenrelocatedwithoutchangefromtheexistingTS.TheproposedamendmentwillallowFPLtomakechangestothelimitsestablishedintheCOLR,providedNRC-approvedmethodsareusedandthecalculatedparametervaluesareconsistentwithallapplicablelimitsoftheplantsafetyanalyses.Underthespecifiedconditions,suchchangescanbemadewithoutanadverseimpactonnuclearsafety.DEFINITION1.9aisaddedtotheSt.LucieUnit2TechnicalSpecificationstoformallydefinetheCoreOperatingLimitsReport(COLR).TheCOLRwillprovidecyclespecificreactorphysicsparameterlimitsforeachcurrentoperatingreloadcyclethatarenototherwiseretainedinindividualtechnicalspecifications.Accordingly,LimitingConditionsforOperation(LCO)3.1.1.4,ModeratorTemperatureCoefficient;3/4.1.3,MovableControlAssemblies-CEAPosition;3.1.3.6,RegulatingCEAInsertionLimits;3/4.2.1,LinearHeatRate;3.2.2,TotalPlanarRadialPeakingFactors;3.2.3,TotalIntegratedRadialPeakingFactor,3.2.5,DNBParameters;and3/4.9.1,RefuelingOperations-BoronConcentrationaremodifiedtoreplacethespecificvaluesofcycle-specificparameterlimitswiththeappropriatereferencetotheformallydefinedCOLR.Theaffectedspecificationsarealsomodified,asappropriate,torequirethattheplantbeoperatedwithintheboundsofthelimitsprovidedintheCOLR.TheproposedTSchangesconformtotheguidanceinGL88-16and,areconsistentwithNUREG-1432.Specification6.9.1.11isaddedtotheadministrativecontrolssectionand(a)requiresthecycle-specificlimitsfortheabovelistedLCOstobedocumentedintheCOLRpriortoeachreloadcycleorpriortoanyremainingportionofareloadcycle;(b)liststheapprovedanalyticalmethodsusedtodeterminethecoreoperatinglimits;(c)requiresthecoreoperatinglimitstobeconsistentwithapplicablelimitsofthesafetyanalyses;and(d)requirestheCOLR,includinganyrevisionsorsupplementsthereto,tobeprovideduponissuanceforeachreloadcycletotheNRC.TheproposedspecificationisconsistentwithGL88-16andNUREG-1432. | | St.LucieUnit2DocketNo.50-389ProposedLicenseAmendment Core0eratinLimitsReortCOLRL-97-280Page3STATEOFFLORIDA))ss.COUNTYOFST.LUCIEJ.A.Stallbeingfirstdulysworn,deposesandsays:ThatheisVicePresident, St.LuciePlant,fortheNuclearDivisionofFloridaPower8LightCompany,theLicenseeherein;Thathehasexecutedtheforegoing document; thatthestatements madeinthisdocumentaretrueandcorrecttothebestofhisknowledge, information andbelief,andthatheisauthorized toexecutethedocumentonbehalfofsaidLicensee. |
| | J.A.StallSTATEOFFLORIDACOUNTYOFSworntoandsubscribed beforemethis~dayofOd08Ã58(byJ.A.Stall,whoispersonally knowntome.Signature ofNotaublic-State ofFloridaLeslieJ.WMtwem~ss~:>>iNCOMMiSSiON fCCQ61S3EXPIAEShby12,2001'~i,~",~4'0NOED llRUTteyfhN$5URAHCE,INC.NameofNotaryPublic(Print,Type,orStamp) |
| | St.LucieUnit2DocketNo.50-389ProposedLicenseAmendment Core0eratinLimitsReortCOLRATTACHMENT 1toL-97-280EVALUATION OFPROPOSEDTSCHANGES |
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| St.LucieUnit2DocketNo.50-389ProposedLicenseAmendmentCore0eratinLimitsReortCOLRL-97-280Attachment1-Page4of4IncludedinthelistofdocumentsdescribingtheanalyticalmethodsisFPL'sTopicalReportNF-TR-95-01,"NuclearPhysicsMethodologyforReloadDesignofTurkeyPoint&St.LucieNuclearPlants,"January,1995.ThetopicalreportwasapprovedasanacceptablereferenceintheCOLRandassociatedTSforFPL'sTurkeyPointPlants(Reference1),andforSt.LucieUnit1inAmendmentNo.150(4/1/97)toFacilityOperatingLicenseDPR-67.ThetopicalreportdescribestheWestinghouseElectricCorporation(W}nucleardesignmethodsandcomputerprogramsavailableatFPLforwhichFPLhasreceivedextensivetraining.ForPSL2,thesafetyanalysismethodsofAseaBrownBoveri-CombustionEngineering(ABB-CE)andthenucleardesignmethodsofWareused,whereappropriate,indefiningthespecifiedCOLRparameterlimits.ThesafetyanalysisisperformedbyABB-CEwiththeNRCapprovedcomputercodes.ThegenerationofphysicsinputtothesafetyanalysisisaccomplishedbyeitherABB-CEusingtheircodesorbyFPLusingtheNRCapprovedWcomputercodes.SinceNF-TR-95-01didnotincludeanybenchmarkdataforPSL2,Supplement1(August1997)totheTopicalReportisprovidedasEnclosure2tothissubmittaltofurtherdemonstrateFPL'sabilitytoperformreloadcoredesignforSt.LucieUnit2.ThepredictionsofphysicsparametersusingtheWmethodsshowgoodagreementwhencomparedtotheSt.LucieUnit2measureddata.InTS4.2.1.3and4.2.1.4,thephrase"corepowerdistribution"isreplacedwith"linearheatrate"tomoreaccuratelyreflectthemonitoredparameteraddressedbythesurveillancerequirements.Thisisanadministrativechangeanddoesnotalterthespecifiedrequirements.ConclusionTheproposedchangestotheTechnicalSpecificationsthathavecycle-specificparameterlimitsconformtotheguidelinesofGL88-16.ThevaluesoftheseparameterlimitsaredefinedintheCOLR.Inadditionto10CFR50.59,changestotheCOLRwillbecontrolledinaccordancewiththeproposedadministrativecontrolsinthissubmittalwhichrequiretheuseofNRC-approvedanalyticalmethodsandrequirethatallapplicablelimitsofthesafetyanalysesaremet.TheCOLR,includinganymid-cyclerevisionsorsupplementsthereto,shallbeprovidedtotheNRCuponissuance,foreachreloadcycle.Accountingforplantspecificdifferencesinformat,theproposedTSchangesareconsistentwiththeStandardTechnicalSpecificationsforCombustionEngineeringPlants.AsdiscussedinAttachment2tothissubmittal,theproposedlicenseamendmentdoesnotinvolveasignificanthazardsconsideration | | St.LucieUnit2DocketNo.50-389ProposedLicenseAmendment Core0eratinLimitsReortCOLRL-97>>280Attachment 1Page1of4EVALUATION OFPROPOSEDTSCHANGESIntroduction Theproposedamendment toFacilityOperating LicenseNPF-16forSt.LucieUnit2(PSL2)willmodifyTechnical Specifications (TS)forselectedcycle-specific reactorphysicsparameters sothattheyrefertotheSt.LucieUnit2CoreOperating LimitsReport(COLR)forlimitingvalues.Minoradministrative changesarealsoincluded. |
| | Therevisions conformtotheguidanceprovidedinGenericLetter(GL)88-16andareconsistent withtheStandardTechnical Specifications forCombustion Engineering Plants(NUREG-1432, Revision1).TheproposedTSchangesortheCOLRdonotalterthevalueofanyoftheexistingparameter limits,andtheamendment involvesnosignificant hazardsconsideration. |
| | BackroundAnumberofTSincludecycle-specific operating limitsforreactorphysicsparameters thataresubjecttochangeasafunctionofreloadcoredesign,andtheanalytical methodsusedtodetermine suchlimitsaretypically documented inTopicalReportsorinplant-specific submittals previously reviewedandapprovedbytheNRCstaff.Asaconsequence, thestaffsreviewofproposedchangestotheselimitsprimarily involvesconfirmation thattheupdatedlimitsarecalculated usinganNRCapprovedmethodology andareconsistent withallapplicable limitsofthesafetyanalyses. |
| | Inordertoeliminate theburdenthatisassociated withtheprocessforrequesting, reviewing, andapproving alicenseamendment solelyforthepurposeofupdatingthecalculated valuesofcycle-specific parameter limits,GL88-16encouraged licensees toproposechangestotheirtechnical specifications thatareconsistent withtheguidanceprovidedinthatletter.Threeseparateactionstomodifytheplant'sTSarediscussed inGL88-16:(1)addingadefinition ofanamedformalreport,e.g.,COLR,thatincludesthevaluesofcycle-specific parameter limitsthathavebeenestablished usinganNRCapprovedmethodology andareconsistent withallapplicable limitsofthesafetyanalyses, (2)theadditionofanadministrative reporting requirement tosubmittheformalreporttotheCommission forinformation, and(3)themodification ofindividual TStonotethatcycle-specific parameters shallbemaintained withinthelimitsprovidedinthedefinedformalreport.TheNRCstaffnotedthat"itisessential tosafetythattheplantisoperatedwithintheboundsofcycle-specific parameter limitsandthatarequirement tomaintaintheplantwithintheappropriate boundsmustberetainedintheTS.However,thespecificvaluesoftheselimitsmaybemodifiedbylicensees, withoutaffecting nuclearsafety,providedthatthesechangesaredetermined usinganNRC-approved methodology and[are]consistent withallapplicable limitsoftheplantsafetyanalysisthatareaddressed intheFinalSafetyAnalysisReport(FSAR)."TheconceptofaCOLRandtheprovisions ofGL88-16wereincorporated intotheimprovedStandardTechnical Specifications forCombustion Engineering Plants(NUREG-1432). |
| | DescritionofChanesModifications toindividual specifications includereplacing theapplicable operating limitswithreferences totheCOLR,deletingapplicable figures,addingtherequireddefinition andadministrative |
| | : controls, andmakingeditorial changesasnecessary forthepurposeofclarification and/or St.LucieUnit2DocketNo.50-389ProposedLicenseAmendment Core0eratinLimitsReortCOLRL-97-280Attachment 1Page2of4consistency. |
| | CopiesoftheaffectedTSpages,marked-up toshowtheproposedchanges,arecontained inAttachment 3tothissubmittal. |
| | Section1.0DEFINITIONS Addnewdefinition 1.9a,COREOPERATING LIMITSREPORTCOLR,showninInsert-AofAttachment 3tothissubmittal. |
| | TS3.1.1.4MODERATOR TEMPERATURE COEFFICIENT Specification 3.1.1.4.c isdeleted,andtheassociated limitofmaximumnegativemoderator temperature coefficient atRATEDTHERMAL'OWER isrelocated totheCOLR.TS3/4.1.3MOVABLECONTROLASSEMBLIES |
| | -CEAPOSITIONFigure3.1-1a,Allowable TimetoRealignCEAvs.InitialFR~,specifying thetimeconstraint forfullpoweroperation withoneCEAmisaligned fromanyotherCEAinitsgroupbymorethan15inchesisdeletedfromTSandrelocated totheCOLR.TS3.1.3.6REGULATING CEAINSERTION LIMITSFigure3.1-2,%CEAInsertion vs.FractionofRatedThermalPower,showingtheregulating CEAgroupswithdrawal sequenceandinsertion limitsisdeletedfromTSandrelocated totheCOLR.TS3/4.2.1LINEARHEATRATEFigure3.2-1,Allowable PeakLinearHeatRatevs.Bumup;Figure3.2-2,AxialShapeIndexvs.FractionofMaximumAllowable PowerLevelperSpecification 4.2.1.3;andFigure3.2-3,Allowable Combinations ofThermalPowerandFR',Fx',aredeletedfromTSandrelocated totheCOLR.Additionally, inSpecifications 4.2.1.3and4.2.1.4,thephrase"monitoring thecorepowerdistribution" ischangedto"monitoring thelinearheatrate".S'32.2OTALPLANARRADIALPEAKINGFACTOS-F~Thecalculated valuefortheF~limitisdeletedfromTSandrelocated totheCOLR.TS3.23OTLINGTEDRDIALPKINGCOR-F~Thecalculated valuefortheF,~limit,andFigure3.2P,AxialShapeIndexOperating LimitswithFourReactorCoolantPumpsOperating, aredeletedfromTSandrelocated totheCOLR.TS3.2.5DNBPARAMETERS |
| | -AXIALSHAPEINDEXTABLE3.2-2isrevisedtorefertoCOLRFigure3.2AfortheAXIALSHAPEINDEXlimit. |
| | St.LucieUnit2DocketNo.50-389ProposedLicenseAmendment Core0eratinLimitsReortCOLRL-97-280Attachment 1Page3of4TS3/4.9.1REFUELING OPERATIONS |
| | -BORONCONCENTRATION Theboronconcentration limitsaredeletedfromtheTSandrelocated totheCOLR.BASES3/4.1.33/4.2.1and3/4.9.1Thebasesareupdatedtoreflectthechangestocorresponding TSdescribed above.Section6.0ADMINISTRATIVE CONTROLS: |
| | Addnewadministrative control,"6.9.1.11 COREOPERATING LIIMITSREPORT(COLR)"asshowninInsert-BofAttachment 3tothissubmittal. |
| | Page3/41-19a,page3/41-28,pages3/424through3/42-6,andpage3/42-12willbedeletedfromtheTSsincethesepageswillbeblank.Anoteisaddedtopage3/42-3and3/42-11whichdocuments deletionoftheaffectedpagesandmaintains continuity ofpagination. |
| | BasesfortheProosedTSChanesCycle-specific parameter limitsestablished intheCOLR(Enclosure 1)havebeenrelocated withoutchangefromtheexistingTS.Theproposedamendment willallowFPLtomakechangestothelimitsestablished intheCOLR,providedNRC-approved methodsareusedandthecalculated parameter valuesareconsistent withallapplicable limitsoftheplantsafetyanalyses. |
| | Underthespecified conditions, suchchangescanbemadewithoutanadverseimpactonnuclearsafety.DEFINITION 1.9aisaddedtotheSt.LucieUnit2Technical Specifications toformallydefinetheCoreOperating LimitsReport(COLR).TheCOLRwillprovidecyclespecificreactorphysicsparameter limitsforeachcurrentoperating reloadcyclethatarenototherwise retainedinindividual technical specifications. |
| | Accordingly, LimitingConditions forOperation (LCO)3.1.1.4,Moderator Temperature Coefficient; 3/4.1.3,MovableControlAssemblies |
| | -CEAPosition; 3.1.3.6,Regulating CEAInsertion Limits;3/4.2.1,LinearHeatRate;3.2.2,TotalPlanarRadialPeakingFactors;3.2.3,TotalIntegrated RadialPeakingFactor,3.2.5,DNBParameters; and3/4.9.1,Refueling Operations-BoronConcentration aremodifiedtoreplacethespecificvaluesofcycle-specific parameter limitswiththeappropriate reference totheformallydefinedCOLR.Theaffectedspecifications arealsomodified, asappropriate, torequirethattheplantbeoperatedwithintheboundsofthelimitsprovidedintheCOLR.TheproposedTSchangesconformtotheguidanceinGL88-16and,areconsistent withNUREG-1432. |
| | Specification 6.9.1.11isaddedtotheadministrative controlssectionand(a)requiresthecycle-specificlimitsfortheabovelistedLCOstobedocumented intheCOLRpriortoeachreloadcycleorpriortoanyremaining portionofareloadcycle;(b)liststheapprovedanalytical methodsusedtodetermine thecoreoperating limits;(c)requiresthecoreoperating limitstobeconsistent withapplicable limitsofthesafetyanalyses; and(d)requirestheCOLR,including anyrevisions orsupplements thereto,tobeprovideduponissuanceforeachreloadcycletotheNRC.Theproposedspecification isconsistent withGL88-16andNUREG-1432. |
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| St.LucieUnit2DocketNo.50-389ProposedLicenseAmendmentCore0eratinLimitsReortCOLRATTACHMENT2toL-97-280DETERMINATIONOFNOSIGNIFICANTHAZARDSCONSIDERATION St.LucieUnit2DocketNo.50-389ProposedLicenseAmendmentCore0eratinLimitsReortCOLRL-97-280Attachment2Page1of2DETERMINATIONOFNOSIGNIFICANTHAZARDSCONSIDERATIONDescrfpI/onofamendmentrequest:TheproposedamendmenttoFacilityOperatingLicenseNPF-16forSt.LucieUnit2(PSL2)willmodifyspecificationsforselectedcycle-specificreactorphysicsparameterstorefertotheSt.LucieUnit2CoreOperatingLimitsReport(COLR)forlimitingvalues.Editorialchangesarealsoincludedforpurposesofclarificationand/orconsistency.TheproposedTechnicalSpecification(TS)changesconformtotheguidanceprovidedinGenericLetter88-16andareconsistentwiththeStandardTechnicalSpecificationsforCombustionEngineeringPlants(NUREG-1432,Revision1).Pursuantto10CFR50.92,adeterminationmaybemadethataproposedlicenseamendmentinvolvesnosignificanthazardsconsiderationifoperationofthefacilityinaccordancewiththeproposedamendmentwouldnot:(1)involveasignificantincreaseintheprobabilityorconsequencesofanaccidentpreviouslyevaluated;or(2)createthepossibilityofanewordifferentkindofaccidentfromanyaccidentpreviouslyevaluated;or(3)involveasignificantreductioninamarginofsafety.Eachstandardisdiscussedasfollows:(1)Operationofthefacilityinaccordancewiththeproposedamendmentwouldnotinvolveasignificantincreaseintheprobabilityorconsequencesofanaccidentpreviouslyevaluated.Theproposedamendmentrelocatesthecalculatedvaluesofselectedcycle-speciTicreactorphysicsparameterlimitsfromtheTStotheCOLR,andincludesminoreditorialchangeswhichdonotaltertheintentofstatedrequirements.Theamendmentisadministrativeinnatureandhasnoimpactonanyplantconfigurationorsystemperformancereliedupontomitigatetheconsequencesofanaccident.ParameterlimitsspecifiedintheCOLRforthisamendmentarenotchangedfromthevaluespresentlyrequiredbyTechnicalSpecifications.FuturechangestothecalculatedvaluesofsuchlimitsmayonlybemadeusingNRCapprovedmethodologies,mustbeconsistentwithallapplicablesafetyanalysislimits,andarecontrolledbythe10CFR50.59process.Assumptionsusedforaccidentinitiatorsand/orsafetyanalysisacceptancecriteriaarenotchangedbythisamendment.Therefore,operationofthefacilityinaccordancewiththeproposedamendmentwillnotinvolveasignificantincreaseintheprobabilityorconsequencesofanaccidentpreviouslyevaluated.(2)Operationofthefacilityinaccordancewiththeproposedamendmentwouldnotcreatethepossibilityofanewordifferentkindofaccidentfromanyaccidentpreviouslyevaluated.TheproposedamendmentrelocatesthecalculatedvaluesofcyclespecificreactorphysicslimitingparameterstotheCOLRandwillnotchangethephysicalplantorthemodesofoperationdefinedinthefacilitylicense.Thechangesdonotinvolvetheadditionofnewequipmentorthemodificationofexistingequipment,nordotheyalterthedesignconfigurationofSt.Lucieplantsystems.Therefore,operationofthefacilityinaccordancewiththeproposedamendmentwouldnotcreatethepossibilityofanewordifferentkindofaccidentfromanyaccidentpreviouslyevaluated. | | St.LucieUnit2DocketNo.50-389ProposedLicenseAmendment Core0eratinLimitsReortCOLRL-97-280Attachment 1-Page4of4Includedinthelistofdocuments describing theanalytical methodsisFPL'sTopicalReportNF-TR-95-01,"NuclearPhysicsMethodology forReloadDesignofTurkeyPoint&St.LucieNuclearPlants,"January,1995.Thetopicalreportwasapprovedasanacceptable reference intheCOLRandassociated TSforFPL'sTurkeyPointPlants(Reference 1),andforSt.LucieUnit1inAmendment No.150(4/1/97)toFacilityOperating LicenseDPR-67.Thetopicalreportdescribes theWestinghouse ElectricCorporation (W}nucleardesignmethodsandcomputerprogramsavailable atFPLforwhichFPLhasreceivedextensive training. |
| St.LucieUnit2DocketNo.50-389ProposedLicenseAmendmentCore0eratinLimitsReortCOLRL-97-280Attachment2Page2of2(3)Operationofthefacilityinaccordancewiththeproposedamendmentwouldnotinvolveasignificantreductioninamarginofsafety.ThecyclespecificparameterlimitsbeingrelocatedtotheCOLRbythisamendmenthavenotbeenchangedfromthevaluespresentlyrequiredbytheTS,andarequirementtooperatetheplantwithintheboundsofthelimitsspecifiedintheCOLRisretainedintheindividualspecifications.FuturechangestothecalculatedvaluesoftheselimitsbythelicenseemayonlybedevelopedusingNRC-approvedmethodologies,mustremainconsistentwithallapplicableplantsafetyanalysislimitsaddressedintheFinalSafetyAnalysisReport(FSAR),andarefurthercontrolledbythe10CFR50.59process.AsdiscussedinGenericLetter88-16,theadministrativecontrolsestablishedforthevaluesofcyclespecificparametersusingtheguidanceofthatletterassureconformancewith10CFR50.36.Safetyanalysisacceptancecriteriaarenotbeingalteredbythisamendment.Therefore,operationofthefacilityinaccordancewiththeproposedamendmentwouldnotinvolveasignificantreductioninamarginofsafety.BasedonthediscussionpresentedaboveandonthesupportingEvaluationofProposedTSChanges,FPLhasconcludedthatthisproposedlicenseamendmentinvolvesnosignificanthazardsconsideration.}} | | ForPSL2,thesafetyanalysismethodsofAseaBrownBoveri-Combustion Engineering (ABB-CE)andthenucleardesignmethodsofWareused,whereappropriate, indefiningthespecified COLRparameter limits.Thesafetyanalysisisperformed byABB-CEwiththeNRCapprovedcomputercodes.Thegeneration ofphysicsinputtothesafetyanalysisisaccomplished byeitherABB-CEusingtheircodesorbyFPLusingtheNRCapprovedWcomputercodes.SinceNF-TR-95-01 didnotincludeanybenchmark dataforPSL2,Supplement 1(August1997)totheTopicalReportisprovidedasEnclosure 2tothissubmittal tofurtherdemonstrate FPL'sabilitytoperformreloadcoredesignforSt.LucieUnit2.Thepredictions ofphysicsparameters usingtheWmethodsshowgoodagreement whencomparedtotheSt.LucieUnit2measureddata.InTS4.2.1.3and4.2.1.4,thephrase"corepowerdistribution" isreplacedwith"linearheatrate"tomoreaccurately reflectthemonitored parameter addressed bythesurveillance requirements. |
| | Thisisanadministrative changeanddoesnotalterthespecified requirements. |
| | Conclusion TheproposedchangestotheTechnical Specifications thathavecycle-specific parameter limitsconformtotheguidelines ofGL88-16.Thevaluesoftheseparameter limitsaredefinedintheCOLR.Inadditionto10CFR50.59,changestotheCOLRwillbecontrolled inaccordance withtheproposedadministrative controlsinthissubmittal whichrequiretheuseofNRC-approved analytical methodsandrequirethatallapplicable limitsofthesafetyanalysesaremet.TheCOLR,including anymid-cycle revisions orsupplements thereto,shallbeprovidedtotheNRCuponissuance, foreachreloadcycle.Accounting forplantspecificdifferences informat,theproposedTSchangesareconsistent withtheStandardTechnical Specifications forCombustion Engineering Plants.Asdiscussed inAttachment 2tothissubmittal, theproposedlicenseamendment doesnotinvolveasignificant hazardsconsideration |
| | |
| | St.LucieUnit2DocketNo.50-389ProposedLicenseAmendment Core0eratinLimitsReortCOLRATTACHMENT 2toL-97-280DETERMINATION OFNOSIGNIFICANT HAZARDSCONSIDERATION St.LucieUnit2DocketNo.50-389ProposedLicenseAmendment Core0eratinLimitsReortCOLRL-97-280Attachment 2Page1of2DETERMINATION OFNOSIGNIFICANT HAZARDSCONSIDERATION DescrfpI/on ofamendment request:Theproposedamendment toFacilityOperating LicenseNPF-16forSt.LucieUnit2(PSL2)willmodifyspecifications forselectedcycle-specific reactorphysicsparameters torefertotheSt.LucieUnit2CoreOperating LimitsReport(COLR)forlimitingvalues.Editorial changesarealsoincludedforpurposesofclarification and/orconsistency. |
| | TheproposedTechnical Specification (TS)changesconformtotheguidanceprovidedinGenericLetter88-16andareconsistent withtheStandardTechnical Specifications forCombustion Engineering Plants(NUREG-1432, Revision1).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 wouldnotinvolveasignificant increaseintheprobability orconsequences ofanaccidentpreviously evaluated. |
| | Theproposedamendment relocates thecalculated valuesofselectedcycle-speciTic reactorphysicsparameter limitsfromtheTStotheCOLR,andincludesminoreditorial changeswhichdonotaltertheintentofstatedrequirements. |
| | Theamendment isadministrative innatureandhasnoimpactonanyplantconfiguration orsystemperformance reliedupontomitigatetheconsequences ofanaccident. |
| | Parameter limitsspecified intheCOLRforthisamendment arenotchangedfromthevaluespresently requiredbyTechnical Specifications. |
| | Futurechangestothecalculated valuesofsuchlimitsmayonlybemadeusingNRCapprovedmethodologies, mustbeconsistent withallapplicable safetyanalysislimits,andarecontrolled bythe10CFR50.59process.Assumptions usedforaccidentinitiators and/orsafetyanalysisacceptance criteriaarenotchangedbythisamendment. |
| | Therefore, operation ofthefacilityinaccordance withtheproposedamendment willnotinvolveasignificant increaseintheprobability orconsequences ofanaccidentpreviously evaluated. |
| | (2)Operation ofthefacilityinaccordance withtheproposedamendment wouldnotcreatethepossibility ofanewordifferent kindofaccidentfromanyaccidentpreviously evaluated. |
| | Theproposedamendment relocates thecalculated valuesofcyclespecificreactorphysicslimitingparameters totheCOLRandwillnotchangethephysicalplantorthemodesofoperation definedinthefacilitylicense.Thechangesdonotinvolvetheadditionofnewequipment orthemodification ofexistingequipment, nordotheyalterthedesignconfiguration ofSt.Lucieplantsystems.Therefore, operation ofthefacilityinaccordance withtheproposedamendment wouldnotcreatethepossibility ofanewordifferent kindofaccidentfromanyaccidentpreviously evaluated. |
| | St.LucieUnit2DocketNo.50-389ProposedLicenseAmendment Core0eratinLimitsReortCOLRL-97-280Attachment 2Page2of2(3)Operation ofthefacilityinaccordance withtheproposedamendment wouldnotinvolveasignificant reduction inamarginofsafety.Thecyclespecificparameter limitsbeingrelocated totheCOLRbythisamendment havenotbeenchangedfromthevaluespresently requiredbytheTS,andarequirement tooperatetheplantwithintheboundsofthelimitsspecified intheCOLRisretainedintheindividual specifications. |
| | Futurechangestothecalculated valuesoftheselimitsbythelicenseemayonlybedeveloped usingNRC-approvedmethodologies, mustremainconsistent withallapplicable plantsafetyanalysislimitsaddressed intheFinalSafetyAnalysisReport(FSAR),andarefurthercontrolled bythe10CFR50.59process.Asdiscussed inGenericLetter88-16,theadministrative controlsestablished forthevaluesofcyclespecificparameters usingtheguidanceofthatletterassureconformance with10CFR50.36.Safetyanalysisacceptance criteriaarenotbeingalteredbythisamendment. |
| | Therefore, operation ofthefacilityinaccordance withtheproposedamendment wouldnotinvolveasignificant reduction inamarginofsafety.Basedonthediscussion presented aboveandonthesupporting Evaluation ofProposedTSChanges,FPLhasconcluded thatthisproposedlicenseamendment involvesnosignificant hazardsconsideration.}} |
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Category:OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING
MONTHYEARML17241A4441999-08-18018 August 1999
Application for Amend to License NPF-16,to Change Required Surveillance Frequency for Cycling Steam Valves in Turbine Overspeed Protection Sys from Once Per Month to Once Per Quarter (92 Days).Proprietary Encls Withheld
ML17355A3901999-07-27027 July 1999
Application for Amend to License DPR-31,modifying TSs 3.8.1.1,3.4.3 & 3.5.2 to Extend AOT for Inoperable EDG from 72 Hours to 7 Days on one-time Basis
ML17241A3521999-06-0101 June 1999
Application for Amends to Licenses DPR-67 & NPF-16,revising TS 3.5.2 to Allow Up to 7 Days to Restore Inoperable LPSI Train to Operable Status
ML17241A3431999-05-24024 May 1999
Application for Amend to License NPF-16,revising Unit 2 TS 3/4.5.1, Safety Injection Tanks, by Clarifying Nonconservative Wording of Surveillance 4.5.1.1.d.1 to Align Surveillance with Intent & Design Bases Requirements
ML17355A3021999-04-26026 April 1999
Application for Amends to Licenses DPR-31 & DPR-41,deleting Obsolete Part of License Condition 3.L & Incorporating Administrative Changes to TS Index,Ts 3/4.1.2.5 & TS 3/4.7.6
ML17355A2471999-03-0808 March 1999
Application for Amends to Licenses DPR-31 & DPR-41,deleting Certain Requirements from TS Section 6.0 That Are Adequately Controlled by Existing Regulations Other than 10CFR50.36 & TS
ML17355A2391999-02-24024 February 1999
Application for Amends to Licenses DPR-31 & DPR-41,removing Restrictions on Location at Which Temp of UHS May Be Monitored in TS 3/4.7.4
ML17229B0181999-02-23023 February 1999
Application for Amend to License NPF-16,removing Redundant Concentration Monitoring Requirements Specified for Modes 3 Through 6 by Deleting TS 3/4.1.2.9, Reactivity Control Sys- Boron Dilution.
ML17229A9541998-12-16016 December 1998
Application for Amends to Licenses DPR-67 & NPF-16,revising Administrative Controls TS 6.3, Unit Staff Qualifications & Incorporating Specific Staff Qualifications for Multi- Discipline Supervisor Position
ML17229A9221998-11-22022 November 1998
Application for Amend to License DPR-67,revising Thermal Margin SL Lines of TS Figure 2.1-1 to Reflect Increase in Value of Design Min RCS Flow from 345,000 Gpm to 365,000 Gpm & Change Flow Rates Stated in Tables 2.2-1 & 3.2-1
ML17229A9111998-11-19019 November 1998
Application for Amends to Licenses DPR-67 & NPF-16,revising Administrative Controls TS 6.3, Unit Staff Qualifications & Incorporate Specific Staff Qualifications for Multi-Discipline Supervisor (MDS) Position
ML17354B1621998-10-27027 October 1998
Application for Amends to Licenses DPR-31 & DPR-41,to Incorporate Specific Staff Qualifications for Multi- Discipline Supervisor Position Into TS
ML17229A8421998-08-24024 August 1998
Application for Amends to Licenses DPR-67 & NPF-16,removing Obsolete License Conditions & Incorporating Attached TS Revs
ML17229A7581998-06-0303 June 1998
Application for Amends to Licenses DPR-67 & NPF-16 to Incorporate Attached TS Revs.Proposed Amends Are Administrative in Nature & Will Modify Explosive Gas Mixture Surveillance Requirement 4.11.2.5.1
ML17229A7421998-05-27027 May 1998
Supplemental Application to 961031 Proposed Amend to Licenses DPR-67 & NPF-16,providing for More Efficient Use of on-site Mgt Personnel in Review & Approval Process for Plant Procedures
ML17229A7461998-05-27027 May 1998
Application for Amend to License NPF-16,removing Requirement for SITs to Be Operable in Mode 4,which Will Minimize Potential for Inadvertent SIT Discharge During RCS Cooldown/ Depressurization Evolutions
ML17229A7491998-05-27027 May 1998
Application for Amends to Licenses DPR-67 & NPF-16,revising TS 6.2.2.f to Allow Use of Longer Operating Shifts of Up to Twelve Hours Duration by Plant'S Operating Crews
ML17354A8321998-03-12012 March 1998
Application for Amends to Licenses DPR-31 & DPR-41,deleting License Conditions 3.I,3.K,3.H & 4 & Incorporating Recent Organization Change in TS 6.5.1.2 & 6.5.3.1.a
ML17229A6481998-03-0303 March 1998
Application for Amend to License NPF-16,revising Applicability of TS 3.4.7 Re RCS Chemistry,Consistent W/ Corresponding Specification for Unit 1
ML17354A7601998-01-0909 January 1998
Application for Amends to Licenses DPR-31 & DPR-41,modifying TS Sections 5.3.1 & 6.9.1.7 to Allow Implementation of Zirlo Fuel Rod Cladding
ML17309A9161997-12-31031 December 1997
Application for Amend to License NPF-16 by Incorporating Attached TS Rev.Amend Will Modify TS 5.6.1 & Associated Figure 5.6-1 & TS 5.6.3 to Accomodate Increase in Allowed SFP Storage Capacity
ML17309A9111997-12-29029 December 1997
Application for Amend to License NPF-16,modifying Specifications for Selected cycle-specific Reactor Physics Parameters to Provide Reference to St Lucie Unit 2 COLR for Limiting Values
ML17229A5471997-12-0101 December 1997
Application for Amends to Licenses DPR-67 & NPF-16,revising EPP Section 4, Environ Conditions & Section 5, Administrative Procedures, to Incorporate Proposed Terms & Conditions of Incidental Take Statement
ML17354A6141997-08-27027 August 1997
Application for Amends to Licenses DPR-31 & DPR-41,modifying Turkey Point Units 3 & 4 TS to Allow Use of 12 Hour Shifts for Nominal 40 (36 to 48) Hour Week
ML17229A4601997-08-22022 August 1997
Application for Amends to Licenses DPR-67 & NPF-16,revising Specification 4.0.5,Surveillance Requirements for ISI & Testing of ASME Code Class 1,2 & 3 Components,To Relocate IST Program Requirements to Administrative Controls Section
ML17229A4321997-08-0101 August 1997
Application for Amend to License NPF-16,extending semi- Annual Surveillance Interval Specified in Table 4.3-2 for Testing ESFAS Subgroup Relays to Interval Consistent W/Ceog Rept CEN-403,Rev 1-A for March 1996
ML17229A4211997-07-22022 July 1997
Application for Amend to License DPR-67,incorporating Recent Evaluation of Postulated Inadvertent Opening of MSSV Into Current Licensing Basis
ML17229A3581997-05-29029 May 1997
Application for Amends to Licenses DPR-67 & NPF-16, Incorporating Administrative Changes That Will Improve Consistency Throughout TSs & Related Bases
ML17354A4201997-02-24024 February 1997
Application for Amends to Licenses DPR-31 & DPR-41,modifying Tech Specs 6.9.1.7, COLR & Adding Best Estimate Large Break Loss of Coolant Accident Analysis to COLR
ML17229A1811996-12-20020 December 1996
Application for Amend to License DPR-67,requesting Deletion of Footnote Re TS 2.1.1, Reactor Core Safety Limits.
ML17354A3721996-12-17017 December 1996
Application for Amends to Licenses DPR-31 & DPR-41,modifying TS to Change SR for TS 4.4.10 Re Reactor Coolant Pump Flywheel Insp
ML17229A1591996-12-0909 December 1996
Application for Amend to License DPR-67,requesting Mod for Selected cycle-specific Reactor Physics Parameters to Refer to COLR for Limiting Values
ML17354A3501996-11-22022 November 1996
Application for Amends to Licenses DPR-31 & DPR-41, Requesting Rev to Allow Unit 3 Diesel Fuel Oil Storage Tank to Be Drained,Inspected & Cleaned While Maintaining at Least One Unit 3 Diesel Operable
ML17229A1171996-10-31031 October 1996
Application for Amends to Licenses DPR-67 & NPF-16, Requesting Revisions to 6.5.1 Re Facility Review Group & 6.8 Re Procedures & Programs
ML17339A0431996-10-30030 October 1996
Application for Amends to Licenses DPR-67 & NPF-16, Requesting to Revise TS 3/4.9.9 Re Refueling Requirements & TS 3/4.9.10 Re Refueling Operations,Water level-reactor Vessel
ML17229A1071996-10-28028 October 1996
Application for Amend to License NPF-16,modifying TS to Implement 10CFR50,App J,Option B,To Revise TS to Allow Type A,B & C Containment Leakage Tests to Be Conducted at Extended Intervals Determined by performance-based Criteria
ML17229A1041996-10-28028 October 1996
Application for Amend to License DPR-67,requesting to Allow Type A,B & C Containment Leakage Tests to Be Conducted at Extended Intervals Determined by performance-based Criteria
ML17354A2851996-10-0303 October 1996
Application for Amend to Licenses DPR-31 & DPR-41 to Modify Plants Units 3 & 4 to Revise TS Allowing Deferral for One Cycle of Reactor Coolant Pump Flywheel Ultrasonic Exams Required by Reg Guide 1.14
ML17353A7971996-07-17017 July 1996
Application for Amends to Licenses DPR-31 & DPR-41,revising TSs to Allow Type A,B & C Containment Leakage Tests to Be Conducted at Intervals Determined by performance-based Criteria
ML17228B5621996-07-15015 July 1996
Application for Amends to Licenses DPR-67 & NPF-16 Revising Core Alteration Definition
ML17228B5021996-06-0101 June 1996
Application for Exigent Amend to License DPR-67,revising TS Re Thermal Margin & RCS Flow Limits.Siemens Power Corp Rept EMF-96-135, St Lucie Unit 1 Chapter 15 Event Review & Analysis for 30% SG Tube Plugging Encl
ML17353A7091996-05-28028 May 1996
Application for Amends to Licenses DPR-31 & DPR-41,modifying TS Section 6.0, Administrative Controls, IAW 10CFR50.90 to Address Licensed Qualifications of Operations Manager
ML17353A6881996-05-10010 May 1996
Application for Amends to Licenses DPR-31 & DPR-41,revising TS to Achieve Consistency Throughout Document by Removing Outdated Matl & Incorporating Administrative Clarifications & Corrections
ML17353A6501996-04-23023 April 1996
Application for Amends to Licenses DPR-31 & DPR-41,modifying TS in Accordance w/Line-Item 7.4 from NRC GL 93-05, Line-Item Tech Specs Improvements to Reduce Surveillance Requirements for Testing During Power Operation.
ML17353A6561996-04-19019 April 1996
Application for Amends to Licenses DPR-31 & DPR-41,revising TS to Achieve Consistency Throughout Document by Removing Outdated Matl & Incorporating Administrative Clarifications & Corrections
ML17353A6151996-03-21021 March 1996
Application for Amends to Licenses DPR-31 & DPR-41,revising TS Such That Requirements for Radiological Effluent Controls Relocated to Offsite Dose Calculation Manual or Process Control Program
ML17353A6061996-03-20020 March 1996
Application for Amends to Licenses DPR-31 & DPR-41,revising TS 3/4.5.1 to Remove SRs & Operability Requirements for ECCS SI Accumulators That Concern Water Level & Pressure Channels from Ts,Per Line-Item 7.4 from GL 93-05
ML17353A5981996-03-0505 March 1996
Application for Amends to Licenses DPR-31 & DPR-41,modifying TS Sections 4.4.3.3 & 4.5.2 to Reduce Frequency of Surveillances & Insps in Accordance W/Gl 93-05 Items,6.6 & 7.5
ML17228B3741996-01-0404 January 1996
Application for Amends to Licenses DPR-67 & NPF-16 Revising TS 3.5.3 to Rectify Discrepancy for Each St Lucie Unit & to Provide Assurance That Admin Controls for Hpsip Remain Effective in Lower Operational Modes
ML17353A5011995-12-18018 December 1995
Application for Amends to Licenses DPR-31 & DPR-41,revising Definition of RTP from 2,200 Mwt to 2,300 Mwt.Proprietary TR WCAP-13719,Rev 2 & Nonproprietary TRs WCAP-13718,Rev 2 & WCAP-14276,Rev 1 Encl.Proprietary TR WCAP-13719 Withheld
1999-08-18
[Table view]
Category:TEXT-LICENSE APPLICATIONS & PERMITS
MONTHYEARML17241A4441999-08-18018 August 1999
Application for Amend to License NPF-16,to Change Required Surveillance Frequency for Cycling Steam Valves in Turbine Overspeed Protection Sys from Once Per Month to Once Per Quarter (92 Days).Proprietary Encls Withheld
ML17355A3901999-07-27027 July 1999
Application for Amend to License DPR-31,modifying TSs 3.8.1.1,3.4.3 & 3.5.2 to Extend AOT for Inoperable EDG from 72 Hours to 7 Days on one-time Basis
ML17241A3521999-06-0101 June 1999
Application for Amends to Licenses DPR-67 & NPF-16,revising TS 3.5.2 to Allow Up to 7 Days to Restore Inoperable LPSI Train to Operable Status
ML17241A3431999-05-24024 May 1999
Application for Amend to License NPF-16,revising Unit 2 TS 3/4.5.1, Safety Injection Tanks, by Clarifying Nonconservative Wording of Surveillance 4.5.1.1.d.1 to Align Surveillance with Intent & Design Bases Requirements
ML17355A3021999-04-26026 April 1999
Application for Amends to Licenses DPR-31 & DPR-41,deleting Obsolete Part of License Condition 3.L & Incorporating Administrative Changes to TS Index,Ts 3/4.1.2.5 & TS 3/4.7.6
ML17355A2471999-03-0808 March 1999
Application for Amends to Licenses DPR-31 & DPR-41,deleting Certain Requirements from TS Section 6.0 That Are Adequately Controlled by Existing Regulations Other than 10CFR50.36 & TS
ML17355A2391999-02-24024 February 1999
Application for Amends to Licenses DPR-31 & DPR-41,removing Restrictions on Location at Which Temp of UHS May Be Monitored in TS 3/4.7.4
ML17229B0181999-02-23023 February 1999
Application for Amend to License NPF-16,removing Redundant Concentration Monitoring Requirements Specified for Modes 3 Through 6 by Deleting TS 3/4.1.2.9, Reactivity Control Sys- Boron Dilution.
ML17229A9541998-12-16016 December 1998
Application for Amends to Licenses DPR-67 & NPF-16,revising Administrative Controls TS 6.3, Unit Staff Qualifications & Incorporating Specific Staff Qualifications for Multi- Discipline Supervisor Position
ML17229A9221998-11-22022 November 1998
Application for Amend to License DPR-67,revising Thermal Margin SL Lines of TS Figure 2.1-1 to Reflect Increase in Value of Design Min RCS Flow from 345,000 Gpm to 365,000 Gpm & Change Flow Rates Stated in Tables 2.2-1 & 3.2-1
ML17229A9111998-11-19019 November 1998
Application for Amends to Licenses DPR-67 & NPF-16,revising Administrative Controls TS 6.3, Unit Staff Qualifications & Incorporate Specific Staff Qualifications for Multi-Discipline Supervisor (MDS) Position
ML17354B1621998-10-27027 October 1998
Application for Amends to Licenses DPR-31 & DPR-41,to Incorporate Specific Staff Qualifications for Multi- Discipline Supervisor Position Into TS
ML17229A8421998-08-24024 August 1998
Application for Amends to Licenses DPR-67 & NPF-16,removing Obsolete License Conditions & Incorporating Attached TS Revs
ML17229A7581998-06-0303 June 1998
Application for Amends to Licenses DPR-67 & NPF-16 to Incorporate Attached TS Revs.Proposed Amends Are Administrative in Nature & Will Modify Explosive Gas Mixture Surveillance Requirement 4.11.2.5.1
ML17229A7491998-05-27027 May 1998
Application for Amends to Licenses DPR-67 & NPF-16,revising TS 6.2.2.f to Allow Use of Longer Operating Shifts of Up to Twelve Hours Duration by Plant'S Operating Crews
ML17229A7461998-05-27027 May 1998
Application for Amend to License NPF-16,removing Requirement for SITs to Be Operable in Mode 4,which Will Minimize Potential for Inadvertent SIT Discharge During RCS Cooldown/ Depressurization Evolutions
ML17229A7421998-05-27027 May 1998
Supplemental Application to 961031 Proposed Amend to Licenses DPR-67 & NPF-16,providing for More Efficient Use of on-site Mgt Personnel in Review & Approval Process for Plant Procedures
ML17354A8321998-03-12012 March 1998
Application for Amends to Licenses DPR-31 & DPR-41,deleting License Conditions 3.I,3.K,3.H & 4 & Incorporating Recent Organization Change in TS 6.5.1.2 & 6.5.3.1.a
ML17229A6481998-03-0303 March 1998
Application for Amend to License NPF-16,revising Applicability of TS 3.4.7 Re RCS Chemistry,Consistent W/ Corresponding Specification for Unit 1
ML17354A7601998-01-0909 January 1998
Application for Amends to Licenses DPR-31 & DPR-41,modifying TS Sections 5.3.1 & 6.9.1.7 to Allow Implementation of Zirlo Fuel Rod Cladding
ML17309A9161997-12-31031 December 1997
Application for Amend to License NPF-16 by Incorporating Attached TS Rev.Amend Will Modify TS 5.6.1 & Associated Figure 5.6-1 & TS 5.6.3 to Accomodate Increase in Allowed SFP Storage Capacity
ML17309A9111997-12-29029 December 1997
Application for Amend to License NPF-16,modifying Specifications for Selected cycle-specific Reactor Physics Parameters to Provide Reference to St Lucie Unit 2 COLR for Limiting Values
ML17229A5471997-12-0101 December 1997
Application for Amends to Licenses DPR-67 & NPF-16,revising EPP Section 4, Environ Conditions & Section 5, Administrative Procedures, to Incorporate Proposed Terms & Conditions of Incidental Take Statement
ML17354A6141997-08-27027 August 1997
Application for Amends to Licenses DPR-31 & DPR-41,modifying Turkey Point Units 3 & 4 TS to Allow Use of 12 Hour Shifts for Nominal 40 (36 to 48) Hour Week
ML17229A4601997-08-22022 August 1997
Application for Amends to Licenses DPR-67 & NPF-16,revising Specification 4.0.5,Surveillance Requirements for ISI & Testing of ASME Code Class 1,2 & 3 Components,To Relocate IST Program Requirements to Administrative Controls Section
ML17229A4321997-08-0101 August 1997
Application for Amend to License NPF-16,extending semi- Annual Surveillance Interval Specified in Table 4.3-2 for Testing ESFAS Subgroup Relays to Interval Consistent W/Ceog Rept CEN-403,Rev 1-A for March 1996
ML17229A4211997-07-22022 July 1997
Application for Amend to License DPR-67,incorporating Recent Evaluation of Postulated Inadvertent Opening of MSSV Into Current Licensing Basis
ML17229A3581997-05-29029 May 1997
Application for Amends to Licenses DPR-67 & NPF-16, Incorporating Administrative Changes That Will Improve Consistency Throughout TSs & Related Bases
ML17354A4201997-02-24024 February 1997
Application for Amends to Licenses DPR-31 & DPR-41,modifying Tech Specs 6.9.1.7, COLR & Adding Best Estimate Large Break Loss of Coolant Accident Analysis to COLR
ML17229A1811996-12-20020 December 1996
Application for Amend to License DPR-67,requesting Deletion of Footnote Re TS 2.1.1, Reactor Core Safety Limits.
ML17354A3721996-12-17017 December 1996
Application for Amends to Licenses DPR-31 & DPR-41,modifying TS to Change SR for TS 4.4.10 Re Reactor Coolant Pump Flywheel Insp
ML17229A1591996-12-0909 December 1996
Application for Amend to License DPR-67,requesting Mod for Selected cycle-specific Reactor Physics Parameters to Refer to COLR for Limiting Values
ML17354A3501996-11-22022 November 1996
Application for Amends to Licenses DPR-31 & DPR-41, Requesting Rev to Allow Unit 3 Diesel Fuel Oil Storage Tank to Be Drained,Inspected & Cleaned While Maintaining at Least One Unit 3 Diesel Operable
ML17229A1171996-10-31031 October 1996
Application for Amends to Licenses DPR-67 & NPF-16, Requesting Revisions to 6.5.1 Re Facility Review Group & 6.8 Re Procedures & Programs
ML17339A0431996-10-30030 October 1996
Application for Amends to Licenses DPR-67 & NPF-16, Requesting to Revise TS 3/4.9.9 Re Refueling Requirements & TS 3/4.9.10 Re Refueling Operations,Water level-reactor Vessel
ML17229A1041996-10-28028 October 1996
Application for Amend to License DPR-67,requesting to Allow Type A,B & C Containment Leakage Tests to Be Conducted at Extended Intervals Determined by performance-based Criteria
ML17229A1071996-10-28028 October 1996
Application for Amend to License NPF-16,modifying TS to Implement 10CFR50,App J,Option B,To Revise TS to Allow Type A,B & C Containment Leakage Tests to Be Conducted at Extended Intervals Determined by performance-based Criteria
ML17354A2851996-10-0303 October 1996
Application for Amend to Licenses DPR-31 & DPR-41 to Modify Plants Units 3 & 4 to Revise TS Allowing Deferral for One Cycle of Reactor Coolant Pump Flywheel Ultrasonic Exams Required by Reg Guide 1.14
ML17353A7971996-07-17017 July 1996
Application for Amends to Licenses DPR-31 & DPR-41,revising TSs to Allow Type A,B & C Containment Leakage Tests to Be Conducted at Intervals Determined by performance-based Criteria
ML17228B5621996-07-15015 July 1996
Application for Amends to Licenses DPR-67 & NPF-16 Revising Core Alteration Definition
ML17228B5021996-06-0101 June 1996
Application for Exigent Amend to License DPR-67,revising TS Re Thermal Margin & RCS Flow Limits.Siemens Power Corp Rept EMF-96-135, St Lucie Unit 1 Chapter 15 Event Review & Analysis for 30% SG Tube Plugging Encl
ML17353A7091996-05-28028 May 1996
Application for Amends to Licenses DPR-31 & DPR-41,modifying TS Section 6.0, Administrative Controls, IAW 10CFR50.90 to Address Licensed Qualifications of Operations Manager
ML17353A6881996-05-10010 May 1996
Application for Amends to Licenses DPR-31 & DPR-41,revising TS to Achieve Consistency Throughout Document by Removing Outdated Matl & Incorporating Administrative Clarifications & Corrections
ML17353A6501996-04-23023 April 1996
Application for Amends to Licenses DPR-31 & DPR-41,modifying TS in Accordance w/Line-Item 7.4 from NRC GL 93-05, Line-Item Tech Specs Improvements to Reduce Surveillance Requirements for Testing During Power Operation.
ML17353A6561996-04-19019 April 1996
Application for Amends to Licenses DPR-31 & DPR-41,revising TS to Achieve Consistency Throughout Document by Removing Outdated Matl & Incorporating Administrative Clarifications & Corrections
ML17353A6151996-03-21021 March 1996
Application for Amends to Licenses DPR-31 & DPR-41,revising TS Such That Requirements for Radiological Effluent Controls Relocated to Offsite Dose Calculation Manual or Process Control Program
ML17353A6061996-03-20020 March 1996
Application for Amends to Licenses DPR-31 & DPR-41,revising TS 3/4.5.1 to Remove SRs & Operability Requirements for ECCS SI Accumulators That Concern Water Level & Pressure Channels from Ts,Per Line-Item 7.4 from GL 93-05
ML17353A5981996-03-0505 March 1996
Application for Amends to Licenses DPR-31 & DPR-41,modifying TS Sections 4.4.3.3 & 4.5.2 to Reduce Frequency of Surveillances & Insps in Accordance W/Gl 93-05 Items,6.6 & 7.5
ML17228B3741996-01-0404 January 1996
Application for Amends to Licenses DPR-67 & NPF-16 Revising TS 3.5.3 to Rectify Discrepancy for Each St Lucie Unit & to Provide Assurance That Admin Controls for Hpsip Remain Effective in Lower Operational Modes
ML17353A5011995-12-18018 December 1995
Application for Amends to Licenses DPR-31 & DPR-41,revising Definition of RTP from 2,200 Mwt to 2,300 Mwt.Proprietary TR WCAP-13719,Rev 2 & Nonproprietary TRs WCAP-13718,Rev 2 & WCAP-14276,Rev 1 Encl.Proprietary TR WCAP-13719 Withheld
1999-08-18
[Table view] |
Text
FioridaPower6LightCompany,6351 S.OceanDrive,JensenBeach,FL34957December29,1997~L-97-28010CFR50.90U.S.NuclearRegulatory Commission Attn:DocumentControlDeskWashington, D.C.20555Re:St.LucieUnit2DocketNo.50-389ProposedLicenseAmendment Core0eratinLimitsReortCOLRRef:(1)LetterfromR.P.Croteau(NRC)toJ.H.Goldberg(FPL),TurkeyPointUnits3and4-IssuanceofAmendments Re:Implementation ofFPLNuclearPhysicsMethodology (TACNos.M91393andM91394;June9,1995.Pursuantto10CFR50.90,FloridaPower&LightCompany(FPL)requeststoamendFacilityOperating LicenseNPF-16forSt.LucieUnit2byincorporating theattachedTechnical Specifications revisions.
Theamendment willmodifyspecifications forselectedcycle-specific reactorphysicsparameters sothattheyrefertotheSt.LucieUnit2CoreOperating LimitsReport(COLR)forlimitingvalues.Minoradministrative changesarealsoincluded.
TheproposedTSchangesconformtotheguidance.
providedinGenericLetter88-16andareconsistent withtheStandardTechnical Specifications forCombustion Engineering Plants(NUREG-1432, Revision1).Itisrequested thattheproposedamendment, ifapproved, beissuedbyJuly31,1998.Attachment 1isanevaluation oftheproposedTSchanges.Attachment 2isthe"Determination ofNoSignificant HazardsConsideration."
Attachment 3containsacopyoftheaffectedTSpagesmarked-up toshowtheproposedchanges.Enclosure (1)istheSt.LucieUnit2,Cycle10,CoreOperating LimitsReport.Enclosure (2)isSupplement 1toFPL'sTopicalReportNF-TR-95-01, NuclearPhysicsMethodology forReloadDesignofTurkeyPointandSt.LucieNuclearPlants,whichprovidescomparisons betweencorephysicspredictions andactualoperating dataforSt.LucieUnit2.TheoriginalreportreviewedbytheNRCstaff(Reference 1)didnotcontainSt.LucieUnit2specificdata.Thesupplement isvoluntarily submitted tofurtherdemonstrate FPL'sabilitytoperformreloadcoredesignforthatunit.Theproposedamendment hasbeenreviewedbytheSt.LucieFacilityReviewGroupandtheFloridaPower&LightCompanyNuclearReviewBoard.Inaccordance with10CFR50.91(b)(1),acopyoftheproposedamendment isbeingforwarded totheStateDesigneefortheStateofFlorida.Pleasecontactusifthereareanyquestions aboutthissubmittal.
Verytrulyyours,p.o~"J.A.Stall,VicePresident St.LuciePlant980i060i85 97i229PDRADQCK05000250PPDRanFPLGroupcompanylllllllllllllllll illllllllllllllllll St.LucieUnit2DocketNo.50-389ProposedLicenseAmendment Core0eratinLimitsReortCOLRL-97-280Page2JASIRLDAttachments
Enclosures:
(1)St.LucieUnit2,Cycle10,CoreOperating LimitsReport,Revision0.(2)NuclearPhysicsMethodology forReloadDesignofTurkeyPointandSt.LucieNuclearPlants,NF-TR-95-01, Supplement 1;August,1997.cc:RegionalAdministrator, RegionII,USNRC.SeniorResidentInspector, USNRC,St.LuciePlant.Mr.W.A.Passetti, FloridaDepartment ofHealthandRehabilitative Services.
St.LucieUnit2DocketNo.50-389ProposedLicenseAmendment Core0eratinLimitsReortCOLRL-97-280Page3STATEOFFLORIDA))ss.COUNTYOFST.LUCIEJ.A.Stallbeingfirstdulysworn,deposesandsays:ThatheisVicePresident, St.LuciePlant,fortheNuclearDivisionofFloridaPower8LightCompany,theLicenseeherein;Thathehasexecutedtheforegoing document; thatthestatements madeinthisdocumentaretrueandcorrecttothebestofhisknowledge, information andbelief,andthatheisauthorized toexecutethedocumentonbehalfofsaidLicensee.
J.A.StallSTATEOFFLORIDACOUNTYOFSworntoandsubscribed beforemethis~dayofOd08Ã58(byJ.A.Stall,whoispersonally knowntome.Signature ofNotaublic-State ofFloridaLeslieJ.WMtwem~ss~:>>iNCOMMiSSiON fCCQ61S3EXPIAEShby12,2001'~i,~",~4'0NOED llRUTteyfhN$5URAHCE,INC.NameofNotaryPublic(Print,Type,orStamp)
St.LucieUnit2DocketNo.50-389ProposedLicenseAmendment Core0eratinLimitsReortCOLRATTACHMENT 1toL-97-280EVALUATION OFPROPOSEDTSCHANGES
St.LucieUnit2DocketNo.50-389ProposedLicenseAmendment Core0eratinLimitsReortCOLRL-97>>280Attachment 1Page1of4EVALUATION OFPROPOSEDTSCHANGESIntroduction Theproposedamendment toFacilityOperating LicenseNPF-16forSt.LucieUnit2(PSL2)willmodifyTechnical Specifications (TS)forselectedcycle-specific reactorphysicsparameters sothattheyrefertotheSt.LucieUnit2CoreOperating LimitsReport(COLR)forlimitingvalues.Minoradministrative changesarealsoincluded.
Therevisions conformtotheguidanceprovidedinGenericLetter(GL)88-16andareconsistent withtheStandardTechnical Specifications forCombustion Engineering Plants(NUREG-1432, Revision1).TheproposedTSchangesortheCOLRdonotalterthevalueofanyoftheexistingparameter limits,andtheamendment involvesnosignificant hazardsconsideration.
BackroundAnumberofTSincludecycle-specific operating limitsforreactorphysicsparameters thataresubjecttochangeasafunctionofreloadcoredesign,andtheanalytical methodsusedtodetermine suchlimitsaretypically documented inTopicalReportsorinplant-specific submittals previously reviewedandapprovedbytheNRCstaff.Asaconsequence, thestaffsreviewofproposedchangestotheselimitsprimarily involvesconfirmation thattheupdatedlimitsarecalculated usinganNRCapprovedmethodology andareconsistent withallapplicable limitsofthesafetyanalyses.
Inordertoeliminate theburdenthatisassociated withtheprocessforrequesting, reviewing, andapproving alicenseamendment solelyforthepurposeofupdatingthecalculated valuesofcycle-specific parameter limits,GL88-16encouraged licensees toproposechangestotheirtechnical specifications thatareconsistent withtheguidanceprovidedinthatletter.Threeseparateactionstomodifytheplant'sTSarediscussed inGL88-16:(1)addingadefinition ofanamedformalreport,e.g.,COLR,thatincludesthevaluesofcycle-specific parameter limitsthathavebeenestablished usinganNRCapprovedmethodology andareconsistent withallapplicable limitsofthesafetyanalyses, (2)theadditionofanadministrative reporting requirement tosubmittheformalreporttotheCommission forinformation, and(3)themodification ofindividual TStonotethatcycle-specific parameters shallbemaintained withinthelimitsprovidedinthedefinedformalreport.TheNRCstaffnotedthat"itisessential tosafetythattheplantisoperatedwithintheboundsofcycle-specific parameter limitsandthatarequirement tomaintaintheplantwithintheappropriate boundsmustberetainedintheTS.However,thespecificvaluesoftheselimitsmaybemodifiedbylicensees, withoutaffecting nuclearsafety,providedthatthesechangesaredetermined usinganNRC-approved methodology and[are]consistent withallapplicable limitsoftheplantsafetyanalysisthatareaddressed intheFinalSafetyAnalysisReport(FSAR)."TheconceptofaCOLRandtheprovisions ofGL88-16wereincorporated intotheimprovedStandardTechnical Specifications forCombustion Engineering Plants(NUREG-1432).
DescritionofChanesModifications toindividual specifications includereplacing theapplicable operating limitswithreferences totheCOLR,deletingapplicable figures,addingtherequireddefinition andadministrative
- controls, andmakingeditorial changesasnecessary forthepurposeofclarification and/or St.LucieUnit2DocketNo.50-389ProposedLicenseAmendment Core0eratinLimitsReortCOLRL-97-280Attachment 1Page2of4consistency.
CopiesoftheaffectedTSpages,marked-up toshowtheproposedchanges,arecontained inAttachment 3tothissubmittal.
Section1.0DEFINITIONS Addnewdefinition 1.9a,COREOPERATING LIMITSREPORTCOLR,showninInsert-AofAttachment 3tothissubmittal.
TS3.1.1.4MODERATOR TEMPERATURE COEFFICIENT Specification 3.1.1.4.c isdeleted,andtheassociated limitofmaximumnegativemoderator temperature coefficient atRATEDTHERMAL'OWER isrelocated totheCOLR.TS3/4.1.3MOVABLECONTROLASSEMBLIES
-CEAPOSITIONFigure3.1-1a,Allowable TimetoRealignCEAvs.InitialFR~,specifying thetimeconstraint forfullpoweroperation withoneCEAmisaligned fromanyotherCEAinitsgroupbymorethan15inchesisdeletedfromTSandrelocated totheCOLR.TS3.1.3.6REGULATING CEAINSERTION LIMITSFigure3.1-2,%CEAInsertion vs.FractionofRatedThermalPower,showingtheregulating CEAgroupswithdrawal sequenceandinsertion limitsisdeletedfromTSandrelocated totheCOLR.TS3/4.2.1LINEARHEATRATEFigure3.2-1,Allowable PeakLinearHeatRatevs.Bumup;Figure3.2-2,AxialShapeIndexvs.FractionofMaximumAllowable PowerLevelperSpecification 4.2.1.3;andFigure3.2-3,Allowable Combinations ofThermalPowerandFR',Fx',aredeletedfromTSandrelocated totheCOLR.Additionally, inSpecifications 4.2.1.3and4.2.1.4,thephrase"monitoring thecorepowerdistribution" ischangedto"monitoring thelinearheatrate".S'32.2OTALPLANARRADIALPEAKINGFACTOS-F~Thecalculated valuefortheF~limitisdeletedfromTSandrelocated totheCOLR.TS3.23OTLINGTEDRDIALPKINGCOR-F~Thecalculated valuefortheF,~limit,andFigure3.2P,AxialShapeIndexOperating LimitswithFourReactorCoolantPumpsOperating, aredeletedfromTSandrelocated totheCOLR.TS3.2.5DNBPARAMETERS
-AXIALSHAPEINDEXTABLE3.2-2isrevisedtorefertoCOLRFigure3.2AfortheAXIALSHAPEINDEXlimit.
St.LucieUnit2DocketNo.50-389ProposedLicenseAmendment Core0eratinLimitsReortCOLRL-97-280Attachment 1Page3of4TS3/4.9.1REFUELING OPERATIONS
-BORONCONCENTRATION Theboronconcentration limitsaredeletedfromtheTSandrelocated totheCOLR.BASES3/4.1.33/4.2.1and3/4.9.1Thebasesareupdatedtoreflectthechangestocorresponding TSdescribed above.Section6.0ADMINISTRATIVE CONTROLS:
Addnewadministrative control,"6.9.1.11 COREOPERATING LIIMITSREPORT(COLR)"asshowninInsert-BofAttachment 3tothissubmittal.
Page3/41-19a,page3/41-28,pages3/424through3/42-6,andpage3/42-12willbedeletedfromtheTSsincethesepageswillbeblank.Anoteisaddedtopage3/42-3and3/42-11whichdocuments deletionoftheaffectedpagesandmaintains continuity ofpagination.
BasesfortheProosedTSChanesCycle-specific parameter limitsestablished intheCOLR(Enclosure 1)havebeenrelocated withoutchangefromtheexistingTS.Theproposedamendment willallowFPLtomakechangestothelimitsestablished intheCOLR,providedNRC-approved methodsareusedandthecalculated parameter valuesareconsistent withallapplicable limitsoftheplantsafetyanalyses.
Underthespecified conditions, suchchangescanbemadewithoutanadverseimpactonnuclearsafety.DEFINITION 1.9aisaddedtotheSt.LucieUnit2Technical Specifications toformallydefinetheCoreOperating LimitsReport(COLR).TheCOLRwillprovidecyclespecificreactorphysicsparameter limitsforeachcurrentoperating reloadcyclethatarenototherwise retainedinindividual technical specifications.
Accordingly, LimitingConditions forOperation (LCO)3.1.1.4,Moderator Temperature Coefficient; 3/4.1.3,MovableControlAssemblies
-CEAPosition; 3.1.3.6,Regulating CEAInsertion Limits;3/4.2.1,LinearHeatRate;3.2.2,TotalPlanarRadialPeakingFactors;3.2.3,TotalIntegrated RadialPeakingFactor,3.2.5,DNBParameters; and3/4.9.1,Refueling Operations-BoronConcentration aremodifiedtoreplacethespecificvaluesofcycle-specific parameter limitswiththeappropriate reference totheformallydefinedCOLR.Theaffectedspecifications arealsomodified, asappropriate, torequirethattheplantbeoperatedwithintheboundsofthelimitsprovidedintheCOLR.TheproposedTSchangesconformtotheguidanceinGL88-16and,areconsistent withNUREG-1432.
Specification 6.9.1.11isaddedtotheadministrative controlssectionand(a)requiresthecycle-specificlimitsfortheabovelistedLCOstobedocumented intheCOLRpriortoeachreloadcycleorpriortoanyremaining portionofareloadcycle;(b)liststheapprovedanalytical methodsusedtodetermine thecoreoperating limits;(c)requiresthecoreoperating limitstobeconsistent withapplicable limitsofthesafetyanalyses; and(d)requirestheCOLR,including anyrevisions orsupplements thereto,tobeprovideduponissuanceforeachreloadcycletotheNRC.Theproposedspecification isconsistent withGL88-16andNUREG-1432.
St.LucieUnit2DocketNo.50-389ProposedLicenseAmendment Core0eratinLimitsReortCOLRL-97-280Attachment 1-Page4of4Includedinthelistofdocuments describing theanalytical methodsisFPL'sTopicalReportNF-TR-95-01,"NuclearPhysicsMethodology forReloadDesignofTurkeyPoint&St.LucieNuclearPlants,"January,1995.Thetopicalreportwasapprovedasanacceptable reference intheCOLRandassociated TSforFPL'sTurkeyPointPlants(Reference 1),andforSt.LucieUnit1inAmendment No.150(4/1/97)toFacilityOperating LicenseDPR-67.Thetopicalreportdescribes theWestinghouse ElectricCorporation (W}nucleardesignmethodsandcomputerprogramsavailable atFPLforwhichFPLhasreceivedextensive training.
ForPSL2,thesafetyanalysismethodsofAseaBrownBoveri-Combustion Engineering (ABB-CE)andthenucleardesignmethodsofWareused,whereappropriate, indefiningthespecified COLRparameter limits.Thesafetyanalysisisperformed byABB-CEwiththeNRCapprovedcomputercodes.Thegeneration ofphysicsinputtothesafetyanalysisisaccomplished byeitherABB-CEusingtheircodesorbyFPLusingtheNRCapprovedWcomputercodes.SinceNF-TR-95-01 didnotincludeanybenchmark dataforPSL2,Supplement 1(August1997)totheTopicalReportisprovidedasEnclosure 2tothissubmittal tofurtherdemonstrate FPL'sabilitytoperformreloadcoredesignforSt.LucieUnit2.Thepredictions ofphysicsparameters usingtheWmethodsshowgoodagreement whencomparedtotheSt.LucieUnit2measureddata.InTS4.2.1.3and4.2.1.4,thephrase"corepowerdistribution" isreplacedwith"linearheatrate"tomoreaccurately reflectthemonitored parameter addressed bythesurveillance requirements.
Thisisanadministrative changeanddoesnotalterthespecified requirements.
Conclusion TheproposedchangestotheTechnical Specifications thathavecycle-specific parameter limitsconformtotheguidelines ofGL88-16.Thevaluesoftheseparameter limitsaredefinedintheCOLR.Inadditionto10CFR50.59,changestotheCOLRwillbecontrolled inaccordance withtheproposedadministrative controlsinthissubmittal whichrequiretheuseofNRC-approved analytical methodsandrequirethatallapplicable limitsofthesafetyanalysesaremet.TheCOLR,including anymid-cycle revisions orsupplements thereto,shallbeprovidedtotheNRCuponissuance, foreachreloadcycle.Accounting forplantspecificdifferences informat,theproposedTSchangesareconsistent withtheStandardTechnical Specifications forCombustion Engineering Plants.Asdiscussed inAttachment 2tothissubmittal, theproposedlicenseamendment doesnotinvolveasignificant hazardsconsideration
St.LucieUnit2DocketNo.50-389ProposedLicenseAmendment Core0eratinLimitsReortCOLRATTACHMENT 2toL-97-280DETERMINATION OFNOSIGNIFICANT HAZARDSCONSIDERATION St.LucieUnit2DocketNo.50-389ProposedLicenseAmendment Core0eratinLimitsReortCOLRL-97-280Attachment 2Page1of2DETERMINATION OFNOSIGNIFICANT HAZARDSCONSIDERATION DescrfpI/on ofamendment request:Theproposedamendment toFacilityOperating LicenseNPF-16forSt.LucieUnit2(PSL2)willmodifyspecifications forselectedcycle-specific reactorphysicsparameters torefertotheSt.LucieUnit2CoreOperating LimitsReport(COLR)forlimitingvalues.Editorial changesarealsoincludedforpurposesofclarification and/orconsistency.
TheproposedTechnical Specification (TS)changesconformtotheguidanceprovidedinGenericLetter88-16andareconsistent withtheStandardTechnical Specifications forCombustion Engineering Plants(NUREG-1432, Revision1).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 wouldnotinvolveasignificant increaseintheprobability orconsequences ofanaccidentpreviously evaluated.
Theproposedamendment relocates thecalculated valuesofselectedcycle-speciTic reactorphysicsparameter limitsfromtheTStotheCOLR,andincludesminoreditorial changeswhichdonotaltertheintentofstatedrequirements.
Theamendment isadministrative innatureandhasnoimpactonanyplantconfiguration orsystemperformance reliedupontomitigatetheconsequences ofanaccident.
Parameter limitsspecified intheCOLRforthisamendment arenotchangedfromthevaluespresently requiredbyTechnical Specifications.
Futurechangestothecalculated valuesofsuchlimitsmayonlybemadeusingNRCapprovedmethodologies, mustbeconsistent withallapplicable safetyanalysislimits,andarecontrolled bythe10CFR50.59process.Assumptions usedforaccidentinitiators and/orsafetyanalysisacceptance criteriaarenotchangedbythisamendment.
Therefore, operation ofthefacilityinaccordance withtheproposedamendment willnotinvolveasignificant increaseintheprobability orconsequences ofanaccidentpreviously evaluated.
(2)Operation ofthefacilityinaccordance withtheproposedamendment wouldnotcreatethepossibility ofanewordifferent kindofaccidentfromanyaccidentpreviously evaluated.
Theproposedamendment relocates thecalculated valuesofcyclespecificreactorphysicslimitingparameters totheCOLRandwillnotchangethephysicalplantorthemodesofoperation definedinthefacilitylicense.Thechangesdonotinvolvetheadditionofnewequipment orthemodification ofexistingequipment, nordotheyalterthedesignconfiguration ofSt.Lucieplantsystems.Therefore, operation ofthefacilityinaccordance withtheproposedamendment wouldnotcreatethepossibility ofanewordifferent kindofaccidentfromanyaccidentpreviously evaluated.
St.LucieUnit2DocketNo.50-389ProposedLicenseAmendment Core0eratinLimitsReortCOLRL-97-280Attachment 2Page2of2(3)Operation ofthefacilityinaccordance withtheproposedamendment wouldnotinvolveasignificant reduction inamarginofsafety.Thecyclespecificparameter limitsbeingrelocated totheCOLRbythisamendment havenotbeenchangedfromthevaluespresently requiredbytheTS,andarequirement tooperatetheplantwithintheboundsofthelimitsspecified intheCOLRisretainedintheindividual specifications.
Futurechangestothecalculated valuesoftheselimitsbythelicenseemayonlybedeveloped usingNRC-approvedmethodologies, mustremainconsistent withallapplicable plantsafetyanalysislimitsaddressed intheFinalSafetyAnalysisReport(FSAR),andarefurthercontrolled bythe10CFR50.59process.Asdiscussed inGenericLetter88-16,theadministrative controlsestablished forthevaluesofcyclespecificparameters usingtheguidanceofthatletterassureconformance with10CFR50.36.Safetyanalysisacceptance criteriaarenotbeingalteredbythisamendment.
Therefore, operation ofthefacilityinaccordance withtheproposedamendment wouldnotinvolveasignificant reduction inamarginofsafety.Basedonthediscussion presented aboveandonthesupporting Evaluation ofProposedTSChanges,FPLhasconcluded thatthisproposedlicenseamendment involvesnosignificant hazardsconsideration.
