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{{#Wiki_filter:TECHNICALEVALUATIONREPORTEGGSREPORTS(F-47)TMIACTIONPLANREQUIREMENTSFLORIDAPOMERANDLIGHTCONPANYSTLUCIEUNIT1NRCOOCKETNO.50-335NRCCONTRACTNO.NRC43%1-130FRCPROJECTC59$FRCASSIGNMENT7FRCTASK296PreperedbyFranklinResearchCenter20thandRaceStreetsPhiladelphia,PA19103PreperedforNuclearRegulatoryCommissionWashington,D.C.20555Z.W-VosburyAuthor'~J.OverbeckB.W.LudingtonFRCGroupLeader:G.J.OverbeckLeadNRCEngineer:E.ChowSeptember28,1982XACopyHasBeenSenffoPDRThisreportwaspreparedasanaccountofworksponsoredbyanagencyoftheUnitedStatesGovernment.NeithertheUnitedStatesGovernmentnoranyagencythereof.oranyoftheiremployees,makesanywarranty,expressedorImplied,orassumesanylegalliabilityorresponsibilityforanythirdparty'suse,ortheresultsofsuchuse,ofanyInformation,appa-ratus,productorprocessdisclosedInthis.report,orrepresentsthatItsusebysuchthirdpartywouldnotInfringeprivatelyownedrights.Reviewedby:Approvedby:PrincipalAutDate:GroupLeaderD.te:DepartmentDlrecrDate:OFranklinResearchcenterADivisionofTheFranklininstituteWeSenlarninFranMlnParkway,Phile.,Pa.19103(215)4481000 TERM5506-296SectionTitleParcae1INTRODUCTION1.1PurposeofReview.l.2GeneticBackground.1.3Plant-SpecificBackground.2REVLEWCRITERIA3TECHNICALEVALUATION11~2~33.1ReviewofCompletenessoftheLicensee'sReport3.2ComparisonofECCSystemOutageswithThoseofOtherPlants.3.3ReviewofProposedChangestoImprovetheAvailabilityofECCZguipment.CONCLUSIONS~~~~~~~~~458~9REPERENCES~e~~~e~~~10(illFranklinResenrehCenterADlvbkedTheFra@Onkaatute TER-C5506296ThisTechnicalEvaluationReportwaspreparedbyFranklinResearchCenterunderacontractwiththeU.S.NuclearRegulatoryCommission(OfficeofNuclearReactorRegulation,DivisionofOperatingReactors)fortechnicalassistanceinsupportofNRCoperatingreactorlicensingactions.ThetechnicalevaluationwasconductedinaccordancewithcriteriaestablishedbyItheNRC.-Mr-Q.JOverheck,-MrZ..NVosbury.,andMrBWLudingtoncontributedtothetechnicalpreparationofthisreportthroughasubcontractwithWESTECServices,Inc.IjtlFranklinResearchCenterAGMsiond%heFtanldtnInstitute TERW5506-296loINTRODUCTION1+1PURPOSEOPREVIEWThistechnicalevaluationreport(TER)documentsanindependentreviewoftheoutagesoftheemergencycorecooling(ECC)systemsatPloridaPowerandLightCompany's(PPL)St.LucieUnit1.ThepurposeofthisevaluationistodetermineiftheLicenseehassubmittedareportthatiscompleteandsatisfiestherequirementsofTNZActionItemZZ.K.3.17,"ReportonOutagesofEmergencyCore-CoolingSystemsLicenseeReportandProposedTechnicalSpecificationChanges."1o2GENERICBACKGROUNDFollowingtheThreeMileZslandUnit2accident,theBulletinsandOrdersTaskForcereviewednuclearsteamsupplysystem(NSSS)vendors'mallbreakloss-of-coolantaccident(LOCA)analysestoensurethatanadequatebasisexistedfordevelopingguidelinesforsmallbreakLOCAemergencyprocedures.Duringthesereviews,aconcerndevelopedabouttheassumptionoftheworstsinglefailure.Typically,thesmallbreakLOCAanalysisforboilingwaterreactors(BWRs)assumedalossofthehighpressurecoolantinjection(HPCZ)systemastheworstsinglefailure.However,thetechnicalspecificationspermittedplantoperationforsubstantialperiodswiththeHPCIsystemoutofservicewithnolimitontheaccumulatedoutagetime.ThereisconcernnotonlyabouttheHPCZsystem,butalsoaboutallECCsystemsforwhichsubstantialoutagesmightoccurwithinthelimitsofthepresenttechnicalspecification.Therefore,toensurethatthesmallbreakLOCAanalysesareconsistentwiththeactualplantresponse,theBulletinandOrdersTaskPorcerecommendedinNUREG-0626[1]>"GenericEvaluationofPeedwaterTransientsandSmallBreakLoss-of-CoolantAccidentsinGE-DesignedOperatingPlantsandNear-TermOperatingLicenseApplications,"thatlicenseesofGeneralElectric(GE)MesignedNSSSsdothefollowing:"SubmitareportdetailingoutagedatesandlengthsoftheoutagesforallECCsystems.Thereportshouldalsoincludethecauseoftheoutage(e.g.,controllerfailureorspuriousisolation).TheoutagedataforECCcomponentsshouldincludealloutagesforthelastfiveyearsoftill!IFranklinResearchCenterhO&swnolTheFranldinInsotu>c TERM5506-296operation.Theendresultshouldbethequantificationofhistoricalunreliabilityduetotestandmaintenanceoutages.Thiswillestablishifaneedexistsforcumulativeoutagerequirementsintechnicalspecifications.'atertherecommendationwasincorporatedintoNUREG-0660[2],"NRCActionPlanDevelopedasaResultoftheTMI-2Accident,"forallGE-designedNSSSsasTNIActionItemII.K.3.17.InNUREG-0737[3],"Clarificationof'INIActionPlanRequirements,"theNRCstaffexpandedtheactionitemtoincludealllightwaterreactorplantsandaddedarequirementthatlicenseesproposechangesthatwillimproveandcontrolavailabilityofECCsystemsandcomponents.Inaddition,thecontentsofthereportstobesubmittedbythelicenseeswerefurtherclarifiedasfollows:"Thereportshouldcontain(1)outagedatesanddurationofoutages;(2)causeoftheoutageg(3)ECCsystemsorcomponentsinvolvedintheoutagegand(4)correctiveactiontaken."13PLANT-SPECIPICEACKGRDUNDOnJanuary2,1981[4],PPLsubmittedareportinresponsetoNUREG-0737,ItemII.K.3.17,"ReportonOutagesofEmergencyCore-CoolingSystemsLicenseeReportandProposedTechnicalSpecificationChanges."ThereportsubmittedbyPPLcoveredtheperiodfromMarch1,1976toOctober31,1980fortheSt.LucieUnit1.PPLdidnotproposeanychangestoimproveorcontrolECCsystemavailability.(ll!FranklinResearchCenterADivelenB%heFrsnldlnInstaute TERW5506-2962oREVIEWCRITERIATheLicensee'sresponsetoNUREG-0737'temII.K.3~17,wasevaluatedagainstcriteriaprovidedbytheNRCinaletterdatedJuly21,1981[5],outliningTentativeWorkAssignmentP.Providedasreviewcriteriain.Reference5,theNRCstatedthattheLicensee'sresponseshouldcontainthefollowinginformation:l.Areportdetailingoutagedates,causesofoutages,andlengthsofoutagesforallECCsystemsforthelast5yearsofoperation.ThisreportwastoincludetheECCsystemsorcomponentsinvolvedandcorrectiveactionstaken.Testandmaintenanceoutagesweretobeincluded.2.AquantificationofthehistoricalunavailabilityoftheECCsystemsandcomponentsduetotestandmaintenanceoutages.3.ProposedchangestoimprovetheavailabilityofECCsystems,ifnecessary.ThetypeofinformationrequiredtosatisfythereviewcriteriawasclarifiedbytheNRConAugust12,1981[6].AuxiliarysystemssuchascomponentcoolingwaterandplantservicewatersystemswerenottobeconsideredindeterminingtheunavailabilityofECC'systems.OnlytheoutagesofthedieselgeneratorsweretobeincludedalongwiththeprimaryECCsystemoutages.Finally,the"lastfiveyearsofoperation"wastobelooselyinterpretedasacontinuous5-yearperiodofrecentoperation.OnJuly26,1982[7],theNRCfurtherclarifiedthatthepurposeofthereviewwastoidentifythoselicenseesthathaveexperiencedhigherECCsystemoutagesthanotherlicenseeswithsimilarNSSSs.TheneedforimprovedreliabilityofdieselgeneratorsisunderreviewbytheNRC.ADieselGeneratorInterimReliabilityProgramhasbeenproposedtoeffectimprovedperformanceatoperatingplantsAsaconsequence,acomparisonofdieselgeneratoroutageinformationwithinthisreviewisnotrequired.~AIJ(lFranMinResearchCenterADlvhionofTheFranklinInsome TER-C5506-2963TECHNICALE%iLUATION3~1REVZENOFCOMPLETENESSOPTHELICENSEE'SREPORTTheECCsystemsatPPL'sSt.LucieUnit1consistofthefollowingfourseparatesystems:o.safetyinjection(SI)tankohighpressuresafetyinjection(HPSZ)systemolowpressuresafetyinjection(LPSI)systemorefuelingwaterstoragetank(RWST).InReference4,FPLalsoincludedsystemsandcomponentsthatsupportthe..ZCC.systems.hn.carrying..out..their.design..functions.under.variousaccideatconditions.Thesupportsystemsare:ocontainmentsprayostandbydieselgeneratorsocomponentcoolingwateroauxiliaryfeedwatersystem.InestablishingthetypeofeventsthatconstituteanECCsystemoutage,FPLconsidexedanoutagetobeanyeventthatrenderedanECCsystemunabletorespondduringplantconditionsforwhichtechnicalspecificationsrequiredECCsystemoperability.ForeachECCsystemoutageevent,PPLprovidedtheoutagedates,theduration,andthecause,plussufficientdescriptiontodiscernthecorrectiveactiontaken.MaintenanceandsurveillancetestingactivitieswereincludedintheECCsystemoutagedata,unlesstheseactivitieswereperformedduringashutdownconditioninwhichtheaffectedECCsystemwasnotrequiredtobeopex'ational.TheresultsofFPL'sreviewwereprovidedfortheperiodfromMarch1,1976toOctober31,1980fortheSt.LucieUnitl.Basedontheprecedingdiscussion,ithasbeenestablishedthatFPLhassubmittedareportwhichfulfillstherequirementsofreviewcriterion1withoutexception.t)llFranklinResearchCenterAOiwionolTheFrau4nlnseatc TERM5506-29632COMPARISONOFECCSYSTEMOUTAGESWITHTHOSEOFOTHERPLANTSTheoutagesofECCsystemscanbecategorizedas(1)unplannedoutagesduetoequipmentfailureor(2)plannedoutagesduetosurveillancetestingorpreventivemaintenance.UnplannedoutagesarereportableasLicenseeEventReports(LERs)underthetechnicalspecifications.PlannedoutagesforperiodicmaintenanceandtestingarenotreportableasLERs.ThetechnicalspecificationsidentifythetypeandquantityofECCequipmentrequiredaswellasthemaximumallowableoutagetimes.Ifanoutageexceedsthemaximumallowabletime,thentheplantoperatingmodeisalteredtoalowerstatusconsistentwiththeavailableECCsystemcomponentsstilloperational.ThepurposeofthetechnicalspecificationmaximumallowableoutagetimesistopreventextendedplantoperationwithoutsufficientECCsystemprotection.ThemximumallowableoutageCime,specified~event,tendstolimittheunavailabilityofanECCsystem.However,thereisnocumulative.outagetimelimitationtopreventrepeatedplannedandunplannedoutagesfromaccumulatingextensiveECCsystemdowntime.Unavailability,asdefinedingeneraltermsinWASH>>1400(8],istheprobabilityofasystembeinginafailedstatewhenrequired.However,forthisreview,adetailedunavailabilityanalysiswasnotrequired.Instead,apreliminaryestimateoftheunavailabilityofanECCsystemwasmadebycalculatingtheratiooftheECCsystemdowntimetothenumberofdaysthattheplantwasinoperationduiingthelast5years.Tosimplifythetabulationofoperatingtime,onlytheperiodwhentheplantwasinoperationalMode1wasconsidered.Thissimplifyingassumptionisreasonablegiventhattheperiodoftimethataplantisstartingup,shuttingdown,andcoolingdownissmallcomparedtothetimeitisoperatingatpower.Inaddition,anECCsystemwasconsidereddownwheneveranECCsystemcomponentwasunavailableduetoanycause.ItshouldbenotedthattheratiocalculatedinthismannerisnotatruemeasureoftheECCsystemunavailability,sinceoutageeventsareincludedthatappeartocompromisesystemperformancewhen,infact,partialorfullfunctionofthesystemwouldbeexpected.FullfunctionofanECCsystemtillFranklinResearchCenterA&visionoi~FranklinInsatute TERM5506-296wouldbeexpectedifthedesign'capabilityofthesystemexceededthecapacityrequiredforthesystemtofulfillitssafetyfunction.Forexample,ifanECCsystemconsistingoftwoloopswithmultiplepumpsineachloopisdesignedsothatonlyonepumpineachloopisrequiredtosatisfycorecoolingrequirements,thenanoutageofasinglepumpwouldnotpreventthe"systemfromperformingitssafetyfunction.Inaddition,theactualECCsystemunavailabilityisafunctionofplannedandunplannedoutagesofessentialsupportsystemsaswellasofplannedandunplannedoutagesofprimaryECCsystemcomponents.Znaccordancewiththeclarificat:iondiscussedinSection2,onlytheeffectsofoutagesassociatedwithprimaryECCsystemcomponentsandemergencydieselgeneratorsareconsideredinthisreview.TheinclusionofalloutageeventsassumedtobetrueECCsystemoutagestendstooverestimatetheunavailability,whiletheexclusionofsupportsystemoutagest:endstounderestimatetheunavailability,ofECCsystemsandcomponents.OnlyadetailedanalysisofeachECCsystemforeachplantcouldimprovetheconfidenceinthecalculatedresult.Suchananalysisisbeyondtheintendedscopeofthisreport.Theplannedandunplanned(forced)outagetimesforthefourECCsystems(SItank,HPSI,LPSZ,andRHST)andthestandbydieselgeneratorswereidentifiedfromtheoutageinformationinReference4andareshowninnumberofdaysandaspercentageofplantoperatingtimeperyearinTable1fortheSt.LucieUnitl.Outagesthatoccurredduringnonoperationalperiodswereeliminatedaswellasthosecaused.byfailuresortestan/maintenanceofsupportsystems.Dataonplantoperatingconditionswereobtainedfromtheannualreports,"NuclearPowerPlantOperatingExperience"[9-12],andfrommonthlyreports,"LicensedOperatingReactorsStatusSummaryReports"[13].TheremainingoutagesweresegregatedintoplannedandunplannedoutagesbasedonPPL'sdescriptionofthecausesTheoutageperiodsforeachcategorywerecalculatedbysummingtheindividualoutagedurations.ObservedoutagetimesofvariousECCsystemsatSt.LucieUnit1werecomparedwiththoseofotherPHRs.Basedonthiscomparison,itwasconcludedthatthehistoricalunavailabilityoftheSZtank,RWST,HPSZ,andLPSIsystemshasbeenconsistentwiththeperformanceofthosesystemsthroughout00FranklinResearchCenterARisenorTheFrsnl4nInsatwe Table1.PlannedandUnplanned(Porced)OutageTimesforSt.LucieUnit1SITankHPSIOutaeinDasForcedPlannedRWSTOutaeinDasLPSIOutaeinDasPorcedPlannedPorcedPlannedDieselGeneratorForcedPlanned1976CommercialOper.12/21/761977309.20.00.00.041.46(0.01%)(0'7%)0.0lo710.0(0'5%)0.0~6.021.83(1.95%)(0.59%)1978278.50.00.00.01421.58lo500.00.0(0~51%)(0.571)(0~54%)0'51.71(0.05%)(0'1%)1979269.60.10.0(0.04%)0.01.420.02o08000.0(0.53%)(0+77%)0.08(0'3'0)l.5''(0~56%)1980288.20.00.00.01.421.92i+500.00.0(0'9%)(0.67l)(0'24)0.02,25~(0,78%)Total1145.50.10.0(0.01%)0.045.72F506'90.00.0(<0.01%)(0.50%)(0.3ll)=(0'9%)-~.6,25F29(0.55')(0.64%)*Humbersinparenthesesindicatesystemoutagetimeasapercentageoftotalplantoperatingtime.
{{#Wiki_filter:TECHNICAL EVALUATION REPORTEGGSREPORTS(F-47)TMIACTIONPLANREQUIREMENTS FLORIDAPOMERANDLIGHTCONPANYSTLUCIEUNIT1NRCOOCKETNO.50-335NRCCONTRACTNO.NRC43%1-130 FRCPROJECTC59$FRCASSIGNMENT7 FRCTASK296PreperedbyFranklinResearchCenter20thandRaceStreetsPhiladelphia, PA19103PreperedforNuclearRegulatory Commission Washington, D.C.20555Z.W-VosburyAuthor'~J.OverbeckB.W.Ludington FRCGroupLeader:G.J.OverbeckLeadNRCEngineer:
TERW5506-296theindustry.Theobservedunavailabilitywaslessthantheindustrial,meanforSZtank,RWST,andHPSIsystemsandlessthanaboutonestandarddeviationabovetheindustrialmeanfortheLPSIsystem,assumingthattheunderlyingunavailabilityisdistributedlognormally.Theoutagetimeswerealsoconsistentwithexistingtechnicalspecif'ications.3.3REVIEWOPPROPOSEDCHANGESTOIMPROVE'ITHEAVAILABILITYOPECCEQUIPMENT'IInReference4,PPLdidnotproposeanychangestoimprovetheavailabilityofECCsystemsandcomponents.9I!FranklfnResearchCenterA5vtsendIhtfrsnldnhsacute TERM5506-2964CONCLUSIONSPloridaPowerandLightCompany(PPL)hassubmittedareportforSt.LucieUnit1thatcontains(1)outagedatesanddurationofoutages,(2)causesoftheoutages,(3)ECCsystemsorcomponentsinvolvedintheoutages,and(4)correctiveactionstaken.ItisconcludedthatPPLhasfulfilledtherequirementsofNUREG-0737,ItemIZ.K.3.17.Inaddition,thehistoricalunavailabilityoftheSItank,RWST,HPSI,andLPSIsystemshasbeenconsistentwiththeperformanceofthosesystemsthroughouttheindustry.TheobservedunavailabilitywaslessthantheindustrialmeanfortheSZtank,RWST,andHPSI'systemsandlessthanaboutonestandarddeviationabovetheindustrialmeanfortheLPSZsystem.Theoutagetimeswerealsoconsistentwithexistingtechnicalspecifications.tllIFranklinResearchCenter TERW5506-2965REPERENCESNUREG-0626"GenericEvaluationofPeedwaterTransientsandSmallBreakLoss~f-CoolantAccidentsinGE-DesignedOperatingPlantsandNear-TermOperatingLicenseApplications"NRC,January198024NUREG-0660"NRCActionPlanDevelopedasaResultoftheTMI-2Accident"NRC,March198030NUREG-0737"ClarificationofTMIActionPlanRequirements"NRC,October19804R.E.Uhrig(PPL).Letter',~D.QEisenhut.(Director,DivisionofLicensingNRC)SubjectiSubmittalofInformationRequiredbyNUREG-0737January2,19815.J.N.Donohew,Jr.(NRC)LettertoDr.S.P.Carfagno(PRC).
E.ChowSeptember 28,1982XACopyHasBeenSenffoPDRThisreportwaspreparedasanaccountofworksponsored byanagencyoftheUnitedStatesGovernment.
NeithertheUnitedStatesGovernment noranyagencythereof.oranyoftheiremployees, makesanywarranty, expressed orImplied,orassumesanylegalliability orresponsibility foranythirdparty'suse,ortheresultsofsuchuse,ofanyInformation, appa-ratus,productorprocessdisclosed Inthis.report,orrepresents thatItsusebysuchthirdpartywouldnotInfringeprivately ownedrights.Reviewedby:Approvedby:Principal AutDate:GroupLeaderD.te:Department DlrecrDate:OFranklinResearchcenterADivisionofTheFranklininstitute WeSenlarnin FranMlnParkway,Phile.,Pa.19103(215)4481000 TERM5506-296SectionTitleParcae1INTRODUCTION 1.1PurposeofReview.l.2GeneticBackground.
1.3Plant-Specific
 
===Background===
.2REVLEWCRITERIA3TECHNICAL EVALUATION 11~2~33.1ReviewofCompleteness oftheLicensee's Report3.2Comparison ofECCSystemOutageswithThoseofOtherPlants.3.3ReviewofProposedChangestoImprovetheAvailability ofECCZguipment
.CONCLUSIONS~~~~~~~~~458~9REPERENCES
~e~~~e~~~10(illFranklinResenrehCenterADlvbkedTheFra@Onkaatute TER-C5506 296ThisTechnical Evaluation ReportwaspreparedbyFranklinResearchCenterunderacontractwiththeU.S.NuclearRegulatory Commission (OfficeofNuclearReactorRegulation, DivisionofOperating Reactors) fortechnical assistance insupportofNRCoperating reactorlicensing actions.Thetechnical evaluation wasconducted inaccordance withcriteriaestablished byItheNRC.-Mr-Q.JOverheck,
-MrZ..NVosbury.,
andMrBWLudington contributed tothetechnical preparation ofthisreportthroughasubcontract withWESTECServices, Inc.IjtlFranklinResearchCenterAGMsiond%heFtanldtnInstitute TERW5506-296 loINTRODUCTION 1+1PURPOSEOPREVIEWThistechnical evaluation report(TER)documents anindependent reviewoftheoutagesoftheemergency corecooling(ECC)systemsatPloridaPowerandLightCompany's (PPL)St.LucieUnit1.Thepurposeofthisevaluation istodetermine iftheLicenseehassubmitted areportthatiscompleteandsatisfies therequirements ofTNZActionItemZZ.K.3.17, "ReportonOutagesofEmergency Core-Cooling SystemsLicenseeReportandProposedTechnical Specification Changes."
1o2GENERICBACKGROUND Following theThreeMileZslandUnit2accident, theBulletins andOrdersTaskForcereviewednuclearsteamsupplysystem(NSSS)vendors'mall breakloss-of-coolant accident(LOCA)analysestoensurethatanadequatebasisexistedfordeveloping guidelines forsmallbreakLOCAemergency procedures.
Duringthesereviews,aconcerndeveloped abouttheassumption oftheworstsinglefailure.Typically, thesmallbreakLOCAanalysisforboilingwaterreactors(BWRs)assumedalossofthehighpressurecoolantinjection (HPCZ)systemastheworstsinglefailure.However,thetechnical specifications permitted plantoperation forsubstantial periodswiththeHPCIsystemoutofservicewithnolimitontheaccumulated outagetime.ThereisconcernnotonlyabouttheHPCZsystem,butalsoaboutallECCsystemsforwhichsubstantial outagesmightoccurwithinthelimitsofthepresenttechnical specification.
Therefore, toensurethatthesmallbreakLOCAanalysesareconsistent withtheactualplantresponse, theBulletinandOrdersTaskPorcerecommended inNUREG-0626
[1]>"GenericEvaluation ofPeedwater Transients andSmallBreakLoss-of-Coolant Accidents inGE-Designed Operating PlantsandNear-Term Operating LicenseApplications,"
thatlicensees ofGeneralElectric(GE)MesignedNSSSsdothefollowing:
"Submitareportdetailing outagedatesandlengthsoftheoutagesforallECCsystems.Thereportshouldalsoincludethecauseoftheoutage(e.g.,controller failureorspuriousisolation)
.TheoutagedataforECCcomponents shouldincludealloutagesforthelastfiveyearsoftill!IFranklinResearchCenterhO&swnolTheFranldinInsotu>c TERM5506-296 operation.
Theendresultshouldbethequantification ofhistorical unreliability duetotestandmaintenance outages.Thiswillestablish ifaneedexistsforcumulative outagerequirements intechnical specifications.'ater therecommendation wasincorporated intoNUREG-0660
[2],"NRCActionPlanDeveloped asaResultoftheTMI-2Accident,"
forallGE-designed NSSSsasTNIActionItemII.K.3.17.
InNUREG-0737
[3],"Clarification of'INIActionPlanRequirements,"
theNRCstaffexpandedtheactionitemtoincludealllightwaterreactorplantsandaddedarequirement thatlicensees proposechangesthatwillimproveandcontrolavailability ofECCsystemsandcomponents.
Inaddition, thecontentsofthereportstobesubmitted bythelicensees werefurtherclarified asfollows:"Thereportshouldcontain(1)outagedatesanddurationofoutages;(2)causeoftheoutageg(3)ECCsystemsorcomponents involvedintheoutagegand(4)corrective actiontaken."13PLANT-SPECIPIC EACKGRDUND OnJanuary2,1981[4],PPLsubmitted areportinresponsetoNUREG-0737, ItemII.K.3.17, "ReportonOutagesofEmergency Core-Cooling SystemsLicenseeReportandProposedTechnical Specification Changes."
Thereportsubmitted byPPLcoveredtheperiodfromMarch1,1976toOctober31,1980fortheSt.LucieUnit1.PPLdidnotproposeanychangestoimproveorcontrolECCsystemavailability.
(ll!FranklinResearchCenterADivelenB%heFrsnldlnInstaute TERW5506-2962oREVIEWCRITERIATheLicensee's responsetoNUREG-0737'tem II.K.3~17,wasevaluated againstcriteriaprovidedbytheNRCinaletterdatedJuly21,1981[5],outlining Tentative WorkAssignment P.Providedasreviewcriteriain.Reference 5,theNRCstatedthattheLicensee's responseshouldcontainthefollowing information:
l.Areportdetailing outagedates,causesofoutages,andlengthsofoutagesforallECCsystemsforthelast5yearsofoperation.
ThisreportwastoincludetheECCsystemsorcomponents involvedandcorrective actionstaken.Testandmaintenance outagesweretobeincluded.
2.Aquantification ofthehistorical unavailability oftheECCsystemsandcomponents duetotestandmaintenance outages.3.Proposedchangestoimprovetheavailability ofECCsystems,ifnecessary.
Thetypeofinformation requiredtosatisfythereviewcriteriawasclarified bytheNRConAugust12,1981[6].Auxiliary systemssuchascomponent coolingwaterandplantservicewatersystemswerenottobeconsidered indetermining theunavailability ofECC'systems.
Onlytheoutagesofthedieselgenerators weretobeincludedalongwiththeprimaryECCsystemoutages.Finally,the"lastfiveyearsofoperation" wastobelooselyinterpreted asacontinuous 5-yearperiodofrecentoperation.
OnJuly26,1982[7],theNRCfurtherclarified thatthepurposeofthereviewwastoidentifythoselicensees thathaveexperienced higherECCsystemoutagesthanotherlicensees withsimilarNSSSs.Theneedforimprovedreliability ofdieselgenerators isunderreviewbytheNRC.ADieselGenerator InterimReliability Programhasbeenproposedtoeffectimprovedperformance atoperating plantsAsaconsequence, acomparison ofdieselgenerator outageinformation withinthisreviewisnotrequired.
~AIJ(lFranMinResearchCenterADlvhionofTheFranklinInsome TER-C5506-2963TECHNICAL E%iLUATION 3~1REVZENOFCOMPLETENESS OPTHELICENSEE'S REPORTTheECCsystemsatPPL'sSt.LucieUnit1consistofthefollowing fourseparatesystems:o.safetyinjection (SI)tankohighpressuresafetyinjection (HPSZ)systemolowpressuresafetyinjection (LPSI)systemorefueling waterstoragetank(RWST).InReference 4,FPLalsoincludedsystemsandcomponents thatsupportthe..ZCC.systems.hn.
carrying..out..their.
design..functions.under
.variousaccideatconditions.
Thesupportsystemsare:ocontainment sprayostandbydieselgenerators ocomponent coolingwateroauxiliary feedwater system.Inestablishing thetypeofeventsthatconstitute anECCsystemoutage,FPLconsidexed anoutagetobeanyeventthatrenderedanECCsystemunabletorespondduringplantconditions forwhichtechnical specifications requiredECCsystemoperability.
ForeachECCsystemoutageevent,PPLprovidedtheoutagedates,theduration, andthecause,plussufficient description todiscernthecorrective actiontaken.Maintenance andsurveillance testingactivities wereincludedintheECCsystemoutagedata,unlesstheseactivities wereperformed duringashutdowncondition inwhichtheaffectedECCsystemwasnotrequiredtobeopex'ational.
TheresultsofFPL'sreviewwereprovidedfortheperiodfromMarch1,1976toOctober31,1980fortheSt.LucieUnitl.Basedonthepreceding discussion, ithasbeenestablished thatFPLhassubmitted areportwhichfulfillstherequirements ofreviewcriterion 1withoutexception.
t)llFranklinResearchCenterAOiwionolTheFrau4nlnseatc TERM5506-29632COMPARISON OFECCSYSTEMOUTAGESWITHTHOSEOFOTHERPLANTSTheoutagesofECCsystemscanbecategorized as(1)unplanned outagesduetoequipment failureor(2)plannedoutagesduetosurveillance testingorpreventive maintenance.
Unplanned outagesarereportable asLicenseeEventReports(LERs)underthetechnical specifications.
Plannedoutagesforperiodicmaintenance andtestingarenotreportable asLERs.Thetechnical specifications identifythetypeandquantityofECCequipment requiredaswellasthemaximumallowable outagetimes.Ifanoutageexceedsthemaximumallowable time,thentheplantoperating modeisalteredtoalowerstatusconsistent withtheavailable ECCsystemcomponents stilloperational.
Thepurposeofthetechnical specification maximumallowable outagetimesistopreventextendedplantoperation withoutsufficient ECCsystemprotection.
Themximum allowable outageCime,specified
~event,tendstolimittheunavailability ofanECCsystem.However,thereisnocumulative
.outagetimelimitation topreventrepeatedplannedandunplanned outagesfromaccumulating extensive ECCsystemdowntime.
Unavailability, asdefinedingeneraltermsinWASH>>1400 (8],istheprobability ofasystembeinginafailedstatewhenrequired.
However,forthisreview,adetailedunavailability analysiswasnotrequired.
Instead,apreliminary estimateoftheunavailability ofanECCsystemwasmadebycalculating theratiooftheECCsystemdowntimetothenumberofdaysthattheplantwasinoperation duiingthelast5years.Tosimplifythetabulation ofoperating time,onlytheperiodwhentheplantwasinoperational Mode1wasconsidered.
Thissimplifying assumption isreasonable giventhattheperiodoftimethataplantisstartingup,shuttingdown,andcoolingdownissmallcomparedtothetimeitisoperating atpower.Inaddition, anECCsystemwasconsidered downwheneveranECCsystemcomponent wasunavailable duetoanycause.Itshouldbenotedthattheratiocalculated inthismannerisnotatruemeasureoftheECCsystemunavailability, sinceoutageeventsareincludedthatappeartocompromise systemperformance when,infact,partialorfullfunctionofthesystemwouldbeexpected.
FullfunctionofanECCsystemtillFranklinResearchCenterA&visionoi~FranklinInsatute TERM5506-296 wouldbeexpectedifthedesign'capability ofthesystemexceededthecapacityrequiredforthesystemtofulfillitssafetyfunction.
Forexample,ifanECCsystemconsisting oftwoloopswithmultiplepumpsineachloopisdesignedsothatonlyonepumpineachloopisrequiredtosatisfycorecoolingrequirements, thenanoutageofasinglepumpwouldnotpreventthe"systemfromperforming itssafetyfunction.
Inaddition, theactualECCsystemunavailability isafunctionofplannedandunplanned outagesofessential supportsystemsaswellasofplannedandunplanned outagesofprimaryECCsystemcomponents.
Znaccordance withtheclarificat:ion discussed inSection2,onlytheeffectsofoutagesassociated withprimaryECCsystemcomponents andemergency dieselgenerators areconsidered inthisreview.Theinclusion ofalloutageeventsassumedtobetrueECCsystemoutagestendstooverestimate theunavailability, whiletheexclusion ofsupportsystemoutagest:endstounderestimate theunavailability, ofECCsystemsandcomponents.
OnlyadetailedanalysisofeachECCsystemforeachplantcouldimprovetheconfidence inthecalculated result.Suchananalysisisbeyondtheintendedscopeofthisreport.Theplannedandunplanned (forced)outagetimesforthefourECCsystems(SItank,HPSI,LPSZ,andRHST)andthestandbydieselgenerators wereidentified fromtheoutageinformation inReference 4andareshowninnumberofdaysandaspercentage ofplantoperating timeperyearinTable1fortheSt.LucieUnitl.Outagesthatoccurredduringnonoperational periodswereeliminated aswellasthosecaused.byfailuresortestan/maintenance ofsupportsystems.Dataonplantoperating conditions wereobtainedfromtheannualreports,"NuclearPowerPlantOperating Experience"
[9-12],andfrommonthlyreports,"Licensed Operating ReactorsStatusSummaryReports"[13].Theremaining outagesweresegregated intoplannedandunplanned outagesbasedonPPL'sdescription ofthecausesTheoutageperiodsforeachcategorywerecalculated bysummingtheindividual outagedurations.
ObservedoutagetimesofvariousECCsystemsatSt.LucieUnit1werecomparedwiththoseofotherPHRs.Basedonthiscomparison, itwasconcluded thatthehistorical unavailability oftheSZtank,RWST,HPSZ,andLPSIsystemshasbeenconsistent withtheperformance ofthosesystemsthroughout 00FranklinResearchCenterARisenorTheFrsnl4nInsatwe Table1.PlannedandUnplanned (Porced)OutageTimesforSt.LucieUnit1SITankHPSIOutaeinDasForcedPlannedRWSTOutaeinDasLPSIOutaeinDasPorcedPlannedPorcedPlannedDieselGenerator ForcedPlanned1976Commercial Oper.12/21/761977309.20.00.00.041.46(0.01%)(0'7%)0.0lo710.0(0'5%)0.0~6.021.83(1.95%)(0.59%)1978278.50.00.00.01421.58lo500.00.0(0~51%)(0.571)(0~54%)0'51.71(0.05%)(0'1%)1979269.60.10.0(0.04%)0.01.420.02o08000.0(0.53%)(0+77%)0.08(0'3'0)l.5''(0~56%)1980288.20.00.00.01.421.92i+500.00.0(0'9%)(0.67l)(0'24)0.02,25~(0,78%)Total1145.50.10.0(0.01%)0.045.72F506'90.00.0(<0.01%)(0.50%)
(0.3ll)=(0
'9%)-~.6,25F29(0.55')(0.64%)*Humbersinparentheses indicatesystemoutagetimeasapercentage oftotalplantoperating time.
TERW5506-296 theindustry.
Theobservedunavailability waslessthantheindustrial, meanforSZtank,RWST,andHPSIsystemsandlessthanaboutonestandarddeviation abovetheindustrial meanfortheLPSIsystem,assumingthattheunderlying unavailability isdistributed lognormally.
Theoutagetimeswerealsoconsistent withexistingtechnical specif'ications.
3.3REVIEWOPPROPOSEDCHANGESTOIMPROVE'ITHE AVAILABILITY OPECCEQUIPMENT
'IInReference 4,PPLdidnotproposeanychangestoimprovetheavailability ofECCsystemsandcomponents.
9I!FranklfnResearchCenterA5vtsendIhtfrsnldnhsacute TERM5506-2964CONCLUSIONS PloridaPowerandLightCompany(PPL)hassubmitted areportforSt.LucieUnit1thatcontains(1)outagedatesanddurationofoutages,(2)causesoftheoutages,(3)ECCsystemsorcomponents involvedintheoutages,and(4)corrective actionstaken.Itisconcluded thatPPLhasfulfilled therequirements ofNUREG-0737, ItemIZ.K.3.17.
Inaddition, thehistorical unavailability oftheSItank,RWST,HPSI,andLPSIsystemshasbeenconsistent withtheperformance ofthosesystemsthroughout theindustry.
Theobservedunavailability waslessthantheindustrial meanfortheSZtank,RWST,andHPSI'systems andlessthanaboutonestandarddeviation abovetheindustrial meanfortheLPSZsystem.Theoutagetimeswerealsoconsistent withexistingtechnical specifications.
tllIFranklinResearchCenter TERW5506-2965REPERENCES NUREG-0626 "GenericEvaluation ofPeedwater Transients andSmallBreakLoss~f-Coolant Accidents inGE-Designed Operating PlantsandNear-Term Operating LicenseApplications" NRC,January198024NUREG-0660 "NRCActionPlanDeveloped asaResultoftheTMI-2Accident" NRC,March198030NUREG-073 7"Clarification ofTMIActionPlanRequirements" NRC,October19804R.E.Uhrig(PPL).Letter',~
D.QEisenhut.
(Director, DivisionofLicensing NRC)SubjectiSubmittal ofInformation RequiredbyNUREG-0737 January2,19815.J.N.Donohew,Jr.(NRC)LettertoDr.S.P.Carfagno(PRC).


==Subject:==
==Subject:==
ContractNo.NRC-03-81-130,TentativeAssignmentPNRC,July21,19816oNRCMeetingbetweenNRCandPRC.
ContractNo.NRC-03-81-130, Tentative Assignment PNRC,July21,19816oNRCMeetingbetweenNRCandPRC.


==Subject:==
==Subject:==
C5506TentativeWorkAssignmentP,OperatingReactorPORVandECCSOutageReports'ugust12,198170NRCMeetingbetweenNRCandPRC.
C5506Tentative WorkAssignment P,Operating ReactorPORVandECCSOutageReports'ugust12,198170NRCMeetingbetweenNRCandPRC.


==Subject:==
==Subject:==
ResolutionofReviewCriteriaandScopeofWork'uly26,1982WASH-1400"ReactorSafetyStudy"NRC,October19759.NUREG-0366"NuclearPowerPlantOperating'Experience1976"NRC,December197710.NUREG-0483NuclearPowerPlantOperatingExperience1977"NRC,Pebruary1979II'ranklinResearchCenterASusenotTheFnusSnIns~
Resolution ofReviewCriteriaandScopeofWork'uly26,1982WASH-1400 "ReactorSafetyStudy"NRC,October19759.NUREG-0366 "NuclearPowerPlantOperating
TER-C5506-29611NUREG-0618"NuclearPowerPlantOperatingExperience1978"NRC,December197912NUREG/CR-1496"NuclearPowerPlantOperatingExperience1979"NRC,May198113NUREG-0020"LicensedOperatingReactorsStatusSummaryReport"Volume4,Nos.1through12,andVolume5,No.1NRC,December1980throughJanuary198199FranklinResearchCenterA&veenelTheFrankfinInsotuct}}
'Experience 1976"NRC,December197710.NUREG-048 3NuclearPowerPlantOperating Experience 1977"NRC,Pebruary1979II'ranklin ResearchCenterASusenotTheFnusSnIns~
TER-C5506-29 611NUREG-0618"NuclearPowerPlantOperating Experience 1978"NRC,December197912NUREG/CR-14 96"NuclearPowerPlantOperating Experience 1979"NRC,May198113NUREG-0020 "Licensed Operating ReactorsStatusSummaryReport"Volume4,Nos.1through12,andVolume5,No.1NRC,December1980throughJanuary198199FranklinResearchCenterA&veenelTheFrankfinInsotuct}}

Revision as of 11:38, 29 June 2018

ECCS Repts (F-47),TMI Action Plan Requirements,St Lucie Unit 1, Technical Evaluation Rept
ML17301A001
Person / Time
Site: Saint Lucie NextEra Energy icon.png
Issue date: 09/28/1982
From: LUDINGTON B W, OVERBECK G J, VOSBURY F W
FRANKLIN INSTITUTE
To: CHOW E
NRC
Shared Package
ML17214A397 List:
References
CON-NRC-03-81-130, CON-NRC-3-81-130, RTR-NUREG-0737, RTR-NUREG-737, TASK-2.K.3.17, TASK-TM TER-C5506-296, NUDOCS 8210010343
Download: ML17301A001 (14)
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TECHNICAL EVALUATION REPORTEGGSREPORTS(F-47)TMIACTIONPLANREQUIREMENTS FLORIDAPOMERANDLIGHTCONPANYSTLUCIEUNIT1NRCOOCKETNO.50-335NRCCONTRACTNO.NRC43%1-130 FRCPROJECTC59$FRCASSIGNMENT7 FRCTASK296PreperedbyFranklinResearchCenter20thandRaceStreetsPhiladelphia, PA19103PreperedforNuclearRegulatory Commission Washington, D.C.20555Z.W-VosburyAuthor'~J.OverbeckB.W.Ludington FRCGroupLeader:G.J.OverbeckLeadNRCEngineer:

E.ChowSeptember 28,1982XACopyHasBeenSenffoPDRThisreportwaspreparedasanaccountofworksponsored byanagencyoftheUnitedStatesGovernment.

NeithertheUnitedStatesGovernment noranyagencythereof.oranyoftheiremployees, makesanywarranty, expressed orImplied,orassumesanylegalliability orresponsibility foranythirdparty'suse,ortheresultsofsuchuse,ofanyInformation, appa-ratus,productorprocessdisclosed Inthis.report,orrepresents thatItsusebysuchthirdpartywouldnotInfringeprivately ownedrights.Reviewedby:Approvedby:Principal AutDate:GroupLeaderD.te:Department DlrecrDate:OFranklinResearchcenterADivisionofTheFranklininstitute WeSenlarnin FranMlnParkway,Phile.,Pa.19103(215)4481000 TERM5506-296SectionTitleParcae1INTRODUCTION 1.1PurposeofReview.l.2GeneticBackground.

1.3Plant-Specific

Background

.2REVLEWCRITERIA3TECHNICAL EVALUATION 11~2~33.1ReviewofCompleteness oftheLicensee's Report3.2Comparison ofECCSystemOutageswithThoseofOtherPlants.3.3ReviewofProposedChangestoImprovetheAvailability ofECCZguipment

.CONCLUSIONS~~~~~~~~~458~9REPERENCES

~e~~~e~~~10(illFranklinResenrehCenterADlvbkedTheFra@Onkaatute TER-C5506 296ThisTechnical Evaluation ReportwaspreparedbyFranklinResearchCenterunderacontractwiththeU.S.NuclearRegulatory Commission (OfficeofNuclearReactorRegulation, DivisionofOperating Reactors) fortechnical assistance insupportofNRCoperating reactorlicensing actions.Thetechnical evaluation wasconducted inaccordance withcriteriaestablished byItheNRC.-Mr-Q.JOverheck,

-MrZ..NVosbury.,

andMrBWLudington contributed tothetechnical preparation ofthisreportthroughasubcontract withWESTECServices, Inc.IjtlFranklinResearchCenterAGMsiond%heFtanldtnInstitute TERW5506-296 loINTRODUCTION 1+1PURPOSEOPREVIEWThistechnical evaluation report(TER)documents anindependent reviewoftheoutagesoftheemergency corecooling(ECC)systemsatPloridaPowerandLightCompany's (PPL)St.LucieUnit1.Thepurposeofthisevaluation istodetermine iftheLicenseehassubmitted areportthatiscompleteandsatisfies therequirements ofTNZActionItemZZ.K.3.17, "ReportonOutagesofEmergency Core-Cooling SystemsLicenseeReportandProposedTechnical Specification Changes."

1o2GENERICBACKGROUND Following theThreeMileZslandUnit2accident, theBulletins andOrdersTaskForcereviewednuclearsteamsupplysystem(NSSS)vendors'mall breakloss-of-coolant accident(LOCA)analysestoensurethatanadequatebasisexistedfordeveloping guidelines forsmallbreakLOCAemergency procedures.

Duringthesereviews,aconcerndeveloped abouttheassumption oftheworstsinglefailure.Typically, thesmallbreakLOCAanalysisforboilingwaterreactors(BWRs)assumedalossofthehighpressurecoolantinjection (HPCZ)systemastheworstsinglefailure.However,thetechnical specifications permitted plantoperation forsubstantial periodswiththeHPCIsystemoutofservicewithnolimitontheaccumulated outagetime.ThereisconcernnotonlyabouttheHPCZsystem,butalsoaboutallECCsystemsforwhichsubstantial outagesmightoccurwithinthelimitsofthepresenttechnical specification.

Therefore, toensurethatthesmallbreakLOCAanalysesareconsistent withtheactualplantresponse, theBulletinandOrdersTaskPorcerecommended inNUREG-0626

[1]>"GenericEvaluation ofPeedwater Transients andSmallBreakLoss-of-Coolant Accidents inGE-Designed Operating PlantsandNear-Term Operating LicenseApplications,"

thatlicensees ofGeneralElectric(GE)MesignedNSSSsdothefollowing:

"Submitareportdetailing outagedatesandlengthsoftheoutagesforallECCsystems.Thereportshouldalsoincludethecauseoftheoutage(e.g.,controller failureorspuriousisolation)

.TheoutagedataforECCcomponents shouldincludealloutagesforthelastfiveyearsoftill!IFranklinResearchCenterhO&swnolTheFranldinInsotu>c TERM5506-296 operation.

Theendresultshouldbethequantification ofhistorical unreliability duetotestandmaintenance outages.Thiswillestablish ifaneedexistsforcumulative outagerequirements intechnical specifications.'ater therecommendation wasincorporated intoNUREG-0660

[2],"NRCActionPlanDeveloped asaResultoftheTMI-2Accident,"

forallGE-designed NSSSsasTNIActionItemII.K.3.17.

InNUREG-0737

[3],"Clarification of'INIActionPlanRequirements,"

theNRCstaffexpandedtheactionitemtoincludealllightwaterreactorplantsandaddedarequirement thatlicensees proposechangesthatwillimproveandcontrolavailability ofECCsystemsandcomponents.

Inaddition, thecontentsofthereportstobesubmitted bythelicensees werefurtherclarified asfollows:"Thereportshouldcontain(1)outagedatesanddurationofoutages;(2)causeoftheoutageg(3)ECCsystemsorcomponents involvedintheoutagegand(4)corrective actiontaken."13PLANT-SPECIPIC EACKGRDUND OnJanuary2,1981[4],PPLsubmitted areportinresponsetoNUREG-0737, ItemII.K.3.17, "ReportonOutagesofEmergency Core-Cooling SystemsLicenseeReportandProposedTechnical Specification Changes."

Thereportsubmitted byPPLcoveredtheperiodfromMarch1,1976toOctober31,1980fortheSt.LucieUnit1.PPLdidnotproposeanychangestoimproveorcontrolECCsystemavailability.

(ll!FranklinResearchCenterADivelenB%heFrsnldlnInstaute TERW5506-2962oREVIEWCRITERIATheLicensee's responsetoNUREG-0737'tem II.K.3~17,wasevaluated againstcriteriaprovidedbytheNRCinaletterdatedJuly21,1981[5],outlining Tentative WorkAssignment P.Providedasreviewcriteriain.Reference 5,theNRCstatedthattheLicensee's responseshouldcontainthefollowing information:

l.Areportdetailing outagedates,causesofoutages,andlengthsofoutagesforallECCsystemsforthelast5yearsofoperation.

ThisreportwastoincludetheECCsystemsorcomponents involvedandcorrective actionstaken.Testandmaintenance outagesweretobeincluded.

2.Aquantification ofthehistorical unavailability oftheECCsystemsandcomponents duetotestandmaintenance outages.3.Proposedchangestoimprovetheavailability ofECCsystems,ifnecessary.

Thetypeofinformation requiredtosatisfythereviewcriteriawasclarified bytheNRConAugust12,1981[6].Auxiliary systemssuchascomponent coolingwaterandplantservicewatersystemswerenottobeconsidered indetermining theunavailability ofECC'systems.

Onlytheoutagesofthedieselgenerators weretobeincludedalongwiththeprimaryECCsystemoutages.Finally,the"lastfiveyearsofoperation" wastobelooselyinterpreted asacontinuous 5-yearperiodofrecentoperation.

OnJuly26,1982[7],theNRCfurtherclarified thatthepurposeofthereviewwastoidentifythoselicensees thathaveexperienced higherECCsystemoutagesthanotherlicensees withsimilarNSSSs.Theneedforimprovedreliability ofdieselgenerators isunderreviewbytheNRC.ADieselGenerator InterimReliability Programhasbeenproposedtoeffectimprovedperformance atoperating plantsAsaconsequence, acomparison ofdieselgenerator outageinformation withinthisreviewisnotrequired.

~AIJ(lFranMinResearchCenterADlvhionofTheFranklinInsome TER-C5506-2963TECHNICAL E%iLUATION 3~1REVZENOFCOMPLETENESS OPTHELICENSEE'S REPORTTheECCsystemsatPPL'sSt.LucieUnit1consistofthefollowing fourseparatesystems:o.safetyinjection (SI)tankohighpressuresafetyinjection (HPSZ)systemolowpressuresafetyinjection (LPSI)systemorefueling waterstoragetank(RWST).InReference 4,FPLalsoincludedsystemsandcomponents thatsupportthe..ZCC.systems.hn.

carrying..out..their.

design..functions.under

.variousaccideatconditions.

Thesupportsystemsare:ocontainment sprayostandbydieselgenerators ocomponent coolingwateroauxiliary feedwater system.Inestablishing thetypeofeventsthatconstitute anECCsystemoutage,FPLconsidexed anoutagetobeanyeventthatrenderedanECCsystemunabletorespondduringplantconditions forwhichtechnical specifications requiredECCsystemoperability.

ForeachECCsystemoutageevent,PPLprovidedtheoutagedates,theduration, andthecause,plussufficient description todiscernthecorrective actiontaken.Maintenance andsurveillance testingactivities wereincludedintheECCsystemoutagedata,unlesstheseactivities wereperformed duringashutdowncondition inwhichtheaffectedECCsystemwasnotrequiredtobeopex'ational.

TheresultsofFPL'sreviewwereprovidedfortheperiodfromMarch1,1976toOctober31,1980fortheSt.LucieUnitl.Basedonthepreceding discussion, ithasbeenestablished thatFPLhassubmitted areportwhichfulfillstherequirements ofreviewcriterion 1withoutexception.

t)llFranklinResearchCenterAOiwionolTheFrau4nlnseatc TERM5506-29632COMPARISON OFECCSYSTEMOUTAGESWITHTHOSEOFOTHERPLANTSTheoutagesofECCsystemscanbecategorized as(1)unplanned outagesduetoequipment failureor(2)plannedoutagesduetosurveillance testingorpreventive maintenance.

Unplanned outagesarereportable asLicenseeEventReports(LERs)underthetechnical specifications.

Plannedoutagesforperiodicmaintenance andtestingarenotreportable asLERs.Thetechnical specifications identifythetypeandquantityofECCequipment requiredaswellasthemaximumallowable outagetimes.Ifanoutageexceedsthemaximumallowable time,thentheplantoperating modeisalteredtoalowerstatusconsistent withtheavailable ECCsystemcomponents stilloperational.

Thepurposeofthetechnical specification maximumallowable outagetimesistopreventextendedplantoperation withoutsufficient ECCsystemprotection.

Themximum allowable outageCime,specified

~event,tendstolimittheunavailability ofanECCsystem.However,thereisnocumulative

.outagetimelimitation topreventrepeatedplannedandunplanned outagesfromaccumulating extensive ECCsystemdowntime.

Unavailability, asdefinedingeneraltermsinWASH>>1400 (8],istheprobability ofasystembeinginafailedstatewhenrequired.

However,forthisreview,adetailedunavailability analysiswasnotrequired.

Instead,apreliminary estimateoftheunavailability ofanECCsystemwasmadebycalculating theratiooftheECCsystemdowntimetothenumberofdaysthattheplantwasinoperation duiingthelast5years.Tosimplifythetabulation ofoperating time,onlytheperiodwhentheplantwasinoperational Mode1wasconsidered.

Thissimplifying assumption isreasonable giventhattheperiodoftimethataplantisstartingup,shuttingdown,andcoolingdownissmallcomparedtothetimeitisoperating atpower.Inaddition, anECCsystemwasconsidered downwheneveranECCsystemcomponent wasunavailable duetoanycause.Itshouldbenotedthattheratiocalculated inthismannerisnotatruemeasureoftheECCsystemunavailability, sinceoutageeventsareincludedthatappeartocompromise systemperformance when,infact,partialorfullfunctionofthesystemwouldbeexpected.

FullfunctionofanECCsystemtillFranklinResearchCenterA&visionoi~FranklinInsatute TERM5506-296 wouldbeexpectedifthedesign'capability ofthesystemexceededthecapacityrequiredforthesystemtofulfillitssafetyfunction.

Forexample,ifanECCsystemconsisting oftwoloopswithmultiplepumpsineachloopisdesignedsothatonlyonepumpineachloopisrequiredtosatisfycorecoolingrequirements, thenanoutageofasinglepumpwouldnotpreventthe"systemfromperforming itssafetyfunction.

Inaddition, theactualECCsystemunavailability isafunctionofplannedandunplanned outagesofessential supportsystemsaswellasofplannedandunplanned outagesofprimaryECCsystemcomponents.

Znaccordance withtheclarificat:ion discussed inSection2,onlytheeffectsofoutagesassociated withprimaryECCsystemcomponents andemergency dieselgenerators areconsidered inthisreview.Theinclusion ofalloutageeventsassumedtobetrueECCsystemoutagestendstooverestimate theunavailability, whiletheexclusion ofsupportsystemoutagest:endstounderestimate theunavailability, ofECCsystemsandcomponents.

OnlyadetailedanalysisofeachECCsystemforeachplantcouldimprovetheconfidence inthecalculated result.Suchananalysisisbeyondtheintendedscopeofthisreport.Theplannedandunplanned (forced)outagetimesforthefourECCsystems(SItank,HPSI,LPSZ,andRHST)andthestandbydieselgenerators wereidentified fromtheoutageinformation inReference 4andareshowninnumberofdaysandaspercentage ofplantoperating timeperyearinTable1fortheSt.LucieUnitl.Outagesthatoccurredduringnonoperational periodswereeliminated aswellasthosecaused.byfailuresortestan/maintenance ofsupportsystems.Dataonplantoperating conditions wereobtainedfromtheannualreports,"NuclearPowerPlantOperating Experience"

[9-12],andfrommonthlyreports,"Licensed Operating ReactorsStatusSummaryReports"[13].Theremaining outagesweresegregated intoplannedandunplanned outagesbasedonPPL'sdescription ofthecausesTheoutageperiodsforeachcategorywerecalculated bysummingtheindividual outagedurations.

ObservedoutagetimesofvariousECCsystemsatSt.LucieUnit1werecomparedwiththoseofotherPHRs.Basedonthiscomparison, itwasconcluded thatthehistorical unavailability oftheSZtank,RWST,HPSZ,andLPSIsystemshasbeenconsistent withtheperformance ofthosesystemsthroughout 00FranklinResearchCenterARisenorTheFrsnl4nInsatwe Table1.PlannedandUnplanned (Porced)OutageTimesforSt.LucieUnit1SITankHPSIOutaeinDasForcedPlannedRWSTOutaeinDasLPSIOutaeinDasPorcedPlannedPorcedPlannedDieselGenerator ForcedPlanned1976Commercial Oper.12/21/761977309.20.00.00.041.46(0.01%)(0'7%)0.0lo710.0(0'5%)0.0~6.021.83(1.95%)(0.59%)1978278.50.00.00.01421.58lo500.00.0(0~51%)(0.571)(0~54%)0'51.71(0.05%)(0'1%)1979269.60.10.0(0.04%)0.01.420.02o08000.0(0.53%)(0+77%)0.08(0'3'0)l.5(0~56%)1980288.20.00.00.01.421.92i+500.00.0(0'9%)(0.67l)(0'24)0.02,25~(0,78%)Total1145.50.10.0(0.01%)0.045.72F506'90.00.0(<0.01%)(0.50%)

(0.3ll)=(0

'9%)-~.6,25F29(0.55')(0.64%)*Humbersinparentheses indicatesystemoutagetimeasapercentage oftotalplantoperating time.

TERW5506-296 theindustry.

Theobservedunavailability waslessthantheindustrial, meanforSZtank,RWST,andHPSIsystemsandlessthanaboutonestandarddeviation abovetheindustrial meanfortheLPSIsystem,assumingthattheunderlying unavailability isdistributed lognormally.

Theoutagetimeswerealsoconsistent withexistingtechnical specif'ications.

3.3REVIEWOPPROPOSEDCHANGESTOIMPROVE'ITHE AVAILABILITY OPECCEQUIPMENT

'IInReference 4,PPLdidnotproposeanychangestoimprovetheavailability ofECCsystemsandcomponents.

9I!FranklfnResearchCenterA5vtsendIhtfrsnldnhsacute TERM5506-2964CONCLUSIONS PloridaPowerandLightCompany(PPL)hassubmitted areportforSt.LucieUnit1thatcontains(1)outagedatesanddurationofoutages,(2)causesoftheoutages,(3)ECCsystemsorcomponents involvedintheoutages,and(4)corrective actionstaken.Itisconcluded thatPPLhasfulfilled therequirements ofNUREG-0737, ItemIZ.K.3.17.

Inaddition, thehistorical unavailability oftheSItank,RWST,HPSI,andLPSIsystemshasbeenconsistent withtheperformance ofthosesystemsthroughout theindustry.

Theobservedunavailability waslessthantheindustrial meanfortheSZtank,RWST,andHPSI'systems andlessthanaboutonestandarddeviation abovetheindustrial meanfortheLPSZsystem.Theoutagetimeswerealsoconsistent withexistingtechnical specifications.

tllIFranklinResearchCenter TERW5506-2965REPERENCES NUREG-0626 "GenericEvaluation ofPeedwater Transients andSmallBreakLoss~f-Coolant Accidents inGE-Designed Operating PlantsandNear-Term Operating LicenseApplications" NRC,January198024NUREG-0660 "NRCActionPlanDeveloped asaResultoftheTMI-2Accident" NRC,March198030NUREG-073 7"Clarification ofTMIActionPlanRequirements" NRC,October19804R.E.Uhrig(PPL).Letter',~

D.QEisenhut.

(Director, DivisionofLicensing NRC)SubjectiSubmittal ofInformation RequiredbyNUREG-0737 January2,19815.J.N.Donohew,Jr.(NRC)LettertoDr.S.P.Carfagno(PRC).

Subject:

ContractNo.NRC-03-81-130, Tentative Assignment PNRC,July21,19816oNRCMeetingbetweenNRCandPRC.

Subject:

C5506Tentative WorkAssignment P,Operating ReactorPORVandECCSOutageReports'ugust12,198170NRCMeetingbetweenNRCandPRC.

Subject:

Resolution ofReviewCriteriaandScopeofWork'uly26,1982WASH-1400 "ReactorSafetyStudy"NRC,October19759.NUREG-0366 "NuclearPowerPlantOperating

'Experience 1976"NRC,December197710.NUREG-048 3NuclearPowerPlantOperating Experience 1977"NRC,Pebruary1979II'ranklin ResearchCenterASusenotTheFnusSnIns~

TER-C5506-29 611NUREG-0618"NuclearPowerPlantOperating Experience 1978"NRC,December197912NUREG/CR-14 96"NuclearPowerPlantOperating Experience 1979"NRC,May198113NUREG-0020 "Licensed Operating ReactorsStatusSummaryReport"Volume4,Nos.1through12,andVolume5,No.1NRC,December1980throughJanuary198199FranklinResearchCenterA&veenelTheFrankfinInsotuct

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