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| {{#Wiki_filter:CATEGORY1REGULATORYINFORMATIONDISTRIBUTIONSYSTEM(RIDS)ACCESSIONNBR:9811130285DOC.DATE:98/11/04NOTARIZED:NOFACZL:50-335St.LuciePlant,Unit1,FloridaPower6LightCo.AUTH.NAMEAUTHORAFFILIATIONFREK<FER,K.W.FloridaPower&LightCo.STALL,J.A.FloridaPower6LightCo.RECZP.NAME.RECIPIENTAFFILIATIONDOCKET05000335 | | {{#Wiki_filter:CATEGORY1REGULATORY INFORMATION DISTRIBUTION SYSTEM(RIDS)ACCESSION NBR:9811130285 DOC.DATE: |
| | 98/11/04NOTARIZED: |
| | NOFACZL:50-335 St.LuciePlant,Unit1,FloridaPower6LightCo.AUTH.NAMEAUTHORAFFILIATION FREK<FER,K.W. |
| | FloridaPower&LightCo.STALL,J.A. |
| | FloridaPower6LightCo.RECZP.NAME |
| | .RECIPIENT AFFILIATION DOCKET05000335 |
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| ==SUBJECT:== | | ==SUBJECT:== |
| LER98-008-'00:on981008,inadequatereactorprotectionsystripbypassTSwasnoted.CausedbypoorlywordedTS.SubmittedLARtoclarifypowerrequirementsforhighrateofpowertrips.With981104ltr.DISTRIBUTIONCODE:IE22TCOPIESRECEIVED:LTRENCLSIZE:TITLE:50.73/50.9LicenseeEventReport(LER),ncidentRpt,etc.NOTES:ERECIPIENTIDCODE/NAMEPD2-3PDINTERNAL:ACRSAEOD/SPD/RRABNRR/DE/ECGBNRR/DE/EMEBNRR/DRCH/HOHBNRR/DRPM/PECBRES/DET/EIBEXTERNAL:LSTLOBBYWARDNOACPOORE,W.NRCPDRCOPIESLTTRENCL1111111111111111111111RECIPIENTZDCODE/NAMEGLEAVES,WAEOD/SPD/RABCDEEELBNRR/DRCH/HZCBNRR/DRCH/HQMBNRR/DSSA/SPLBRGN2FILE01LZTCOBRYCE,JHNOACQUEENER,DSNUDOCSFULLTXTCOPIESLTTRENCL11221111111111111'1111RD0MI'NOTETOALE"RIDS"RECIPIENTS:PLEASEHELPUSTOREDUCEWASTE.TOHAVEYOURNAMEORORGANIZATIONREMOVEDFROMDISTRIBUTIONLISTSORREDUCETHENUMBEROFCOPIESRECEIVEDBYYOUORYOURORGANIZATION,CONTACTTHEDOCUMENTCONTROLDESK(DCD)ONEXTENSION415-2083FULLTEXTCONVERSIONREQUIREDTOTAL,NUMBEROFCOPIESREQUIRED:LTTR23ENCL23 FloridaPower&LightCompany,6351S.OceanDrive,JensenBeach.FL34957APLNovember4,1998L-98-28010CFRg50.73U.S.NuclearRegulatoryCommissionAttn:DocumentControlDeskWashington,D.C.20555Re:St.LucieUnits1and2DocketNos.50-335/389ReportableEvent:1998-008-00DateofEvent:October8,1998InadequateReactorProtectionemTriBTechni1ificationh.,';",f~.~".;":".+eattachedLicŽenseeEve.'.,;j~>v>.".p~l0,CFR$50,73toprovideanttotherequirementsofntReport1998-008isbeingsubmittedpursunotificationofthesubjectevent.ia,-P~Verytrulyyours,J.A.StallVicePresidentSt.LucieNuclearPlantJAS/EJW/KWFAttachmentcc:RegionalAdministrator,USNRCRegionIISeniorResidentInspector,USNRC,St.LucieNuclearPlant98ii13028598ii04PDRAMCK05000:335SPDRanFPLGroupcompany | | LER98-008-'00:on 981008,inadequate reactorprotection systripbypassTSwasnoted.CausedbypoorlywordedTS.Submitted LARtoclarifypowerrequirements forhighrateofpowertrips.With981104ltr.DISTRIBUTION CODE:IE22TCOPIESRECEIVED:LTR ENCLSIZE:TITLE:50.73/50.9 LicenseeEventReport(LER),ncidentRpt,etc.NOTES:ERECIPIENT IDCODE/NAME PD2-3PDINTERNAL: |
| | ACRSAEOD/SPD/RRABNRR/DE/ECGB NRR/DE/EMEB NRR/DRCH/HOHB NRR/DRPM/PECB RES/DET/EIB EXTERNAL: |
| | LSTLOBBYWARDNOACPOORE,W.NRCPDRCOPIESLTTRENCL1111111111111111111111RECIPIENT ZDCODE/NAME GLEAVES,W AEOD/SPD/RAB CDEEELBNRR/DRCH/HZCB NRR/DRCH/HQMB NRR/DSSA/SPLB RGN2FILE01LZTCOBRYCE,JHNOACQUEENER,DS NUDOCSFULLTXTCOPIESLTTRENCL11221111111111111'1111RD0MI'NOTETOALE"RIDS"RECIPIENTS: |
| | PLEASEHELPUSTOREDUCEWASTE.TOHAVEYOURNAMEORORGANIZATION REMOVEDFROMDISTRIBUTION LISTSORREDUCETHENUMBEROFCOPIESRECEIVEDBYYOUORYOURORGANIZATION, CONTACTTHEDOCUMENTCONTROLDESK(DCD)ONEXTENSION 415-2083FULLTEXTCONVERSION REQUIREDTOTAL,NUMBEROFCOPIESREQUIRED: |
| | LTTR23ENCL23 FloridaPower&LightCompany,6351 S.OceanDrive,JensenBeach.FL34957APLNovember4,1998L-98-28010CFRg50.73U.S.NuclearRegulatory Commission Attn:DocumentControlDeskWashington, D.C.20555Re:St.LucieUnits1and2DocketNos.50-335/389 Reportable Event:1998-008-00 DateofEvent:October8,1998Inadequate ReactorProtection emTriBTechni1ification h.,';",f~.~".;":".+e attachedLicŽensee Eve.'.,;j~>v> |
| | .".p~l0,CFR$ |
| | 50,73toprovideanttotherequirements ofntReport1998-008isbeingsubmitted pursunotification ofthesubjectevent.ia,-P~Verytrulyyours,J.A.StallVicePresident St.LucieNuclearPlantJAS/EJW/KWF Attachment cc:RegionalAdministrator, USNRCRegionIISeniorResidentInspector, USNRC,St.LucieNuclearPlant98ii130285 98ii04PDRAMCK05000:335 SPDRanFPLGroupcompany |
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| NRCFORM366IS-1999)U.S.NUCLEARREGULATORYCOMMISSIONLICENSEEEVENTREPORT(LER){Seereverseforrequirednumberofdigits/charactersforeachblock)APPROVEDBYOMBNO.3150.0104EXPIRES06I30l2001Estimatedburdenperresponsetocomplywiththismandalorybtfcrmagoncollecbonrequesl:50hrs.ReportedlessonslearnedareincorporatedintoIhelicensingprocessandfedbacktoIndusby.FonvardcommentsregardingburdenestimatelotheRecordsManagementBranch(TWF33),US.NudearRegulatoryCommission.Washington.DC205554001~andloIhePapenvrskRedudionProiect(31500104]OlrceofManagementandBudget,Washington.OC20503.IfaninformationcogecgondoesnoldisplayacurrentlyvalidOMBcontrolnumber,theNRCmaynotconductorsponsor,sndapersonisnolrequiredtorespondlo,thehformationcollection.FACIUTYNAME(1)St.LucieUnit1DOCKETNUMBER{2)05000335PAGE(3)Page1of4TITLE(4)InadequateReactorProtectionSystemTripBypassTechnicalSpecificationMONTHDAY10081998EVENTDATE(5LERNUMBER6REPORTDATE7)SEQUENTIALREVISIONMONTHNUMBERNUMBER1998-008-00OAY041998DOCKETNUMatn05000389DOCKETNUMSERFACIUTVNAMESt.LucieUnit2FACIUTVNAMEOTHERFACILITIESINVOLVED6OPERATINGMODE(9)POWERLEVEL{10)10020.2201(b)20.2203(a){I)20.2203(a)(2)(i)20.2203(e)(2)(ii)20.2203(a)(2)(iii)20.2203(a)(2)(iv)20.2203(e){2)(v)20.2203(a)(3)(i)20.2203(e)(3)(Ii)20.2203(a){4)50.36(c)(1)50.36(c)(2)50.73(a)(2)(i)50.73(a)(2)(ii)50.73(a)(2)(iii)50.73(a)(2)(iv)50.73(a)(2)(v)50.73{a)(2)(vii)50.73(a)(2)(viii)50.73(a)(2)(x)73.71OTHERSpecifyInAbstractbeloworInNRCForm3SSAUIREMENTSOF10CFR9:(Checkoneormoro){11)THISREPORTISSUBMITTEDPURSUANTTOTHEREQNAMEUCENSEECONTACTFORTHISLER12TELEPHONENUMBERSncludeAresCocci~K.W.Frehafer,LicensingEngineer(561)467-7748COMPLETEONELINEFOREACHCOMPONENTFAILUREDESCRIBEDINTHISREPORT13CAUSESYSTEMCOMPONENTMANUFACTURERREPORTABLETOEPIXCAUSESYSTEMCOMPONENTMANUFACTURERREPORTABLETOEPIXJCn/aN/ANO6PPTALRORTXPECTED(14)YES(IfYoe,completeEXPECTEDSUBMISSIONDATE).NOEXPECTEDSUBMISSIONDATE(15)ABSTRACT[Limitto1400spaces,ie.,approximately15singlespecedtypewrittenlines/{16)OnOctober8,1998,St.LucieUnits1and2wereinMODE1at100percentreactorpower.FPLdeterminedthattheTechnicalSpecificationgoverningthetripbypasssetpointsforthehighrateofchangeofpowerreactorprotectionsystemtripwasinerror.TheexplicittermTHERMALPOWERusedintheaffectedTechnicalSpecificationtablenotationrelativetothehighrateofchangeofpowertripbypassfunctioncannotbesatisfiedpriortoent'ryintoMODE2fromaMODE3conditionduetothenormallevelofheattransfertothereactorcoolantasaresultofreactorcoredecayheat.Thetermsofthespecificationcannotbeachievedsincedecayheatisnotadirectlymeasurableparameterandthe.operativeparameterforremovalofthebypassisexcoreneutronfluxthatismeasuredbythewiderangelogarithmicneutronfluxmonitors.Duringpastreactorstartups,literalcompliancewiththeTechnicalSpecificationsforthehighrateofchangeofpowertripwasnotmet.ThecauseofthiseventwasapoorlywordedTechnicalSpecificationthatdidnotexplicitlyexcludedecayheatfromthepowerlevelatwhichthehighrateofchangeofpowertripbypassisrequiredtoberemoved.Asacorrectiveaction,St.Luciehasdevelopedandsubmittedanamendmenttothelicensetoclarifythepowerrequirementsforthehighrateofchangeofpowertrip.Therevisionensuresthatthemeaningof'explicittermsusedintheaffectedTechnicalSpecificationsareconsistentwiththeintentofthestatedrequirementsbasedoneachSt.LuciePlantdesign.NACFORM3SSIS.1999) | | NRCFORM366IS-1999)U.S.NUCLEARREGULATORY COMMISSION LICENSEEEVENTREPORT(LER){Seereverseforrequirednumberofdigits/characters foreachblock)APPROVEDBYOMBNO.3150.0104 EXPIRES06I30l2001 Estimated burdenperresponsetocomplywiththismandalory btfcrmagon collecbon requesl:50hrs.Reportedlessonslearnedareincorporated intoIhelicensing processandfedbacktoIndusby.Fonvardcommentsregarding burdenestimatelotheRecordsManagement Branch(TWF33),US.NudearRegulatory Commission. |
| | Washington. |
| | DC205554001 |
| | ~andloIhePapenvrsk RedudionProiect(31500104 |
| | ]OlrceofManagement andBudget,Washington. |
| | OC20503.Ifaninformation cogecgondoesnoldisplayacurrently validOMBcontrolnumber,theNRCmaynotconductorsponsor,sndapersonisnolrequiredtorespondlo,thehformation collection. |
| | FACIUTYNAME(1)St.LucieUnit1DOCKETNUMBER{2)05000335PAGE(3)Page1of4TITLE(4)Inadequate ReactorProtection SystemTripBypassTechnical Specification MONTHDAY10081998EVENTDATE(5LERNUMBER6REPORTDATE7)SEQUENTIAL REVISIONMONTHNUMBERNUMBER1998-008-00OAY041998DOCKETNUMatn05000389DOCKETNUMSERFACIUTVNAMESt.LucieUnit2FACIUTVNAMEOTHERFACILITIES INVOLVED6OPERATING MODE(9)POWERLEVEL{10)10020.2201(b)20.2203(a) |
| | {I)20.2203(a)(2) |
| | (i)20.2203(e)(2)(ii)20.2203(a)(2) |
| | (iii)20.2203(a)(2) |
| | (iv)20.2203(e) |
| | {2)(v)20.2203(a)(3)(i)20.2203(e)(3) |
| | (Ii)20.2203(a) |
| | {4)50.36(c)(1) 50.36(c)(2) 50.73(a)(2)(i)50.73(a)(2)(ii)50.73(a)(2)(iii) 50.73(a)(2)(iv)50.73(a)(2)(v)50.73{a)(2)(vii)50.73(a)(2)(viii)50.73(a)(2)(x)73.71OTHERSpecifyInAbstractbeloworInNRCForm3SSAUIREMENTS OF10CFR9:(Checkoneormoro){11)THISREPORTISSUBMITTEDPURSUANTTOTHEREQNAMEUCENSEECONTACTFORTHISLER12TELEPHONE NUMBERSncludeAresCocci~K.W.Frehafer, Licensing Engineer(561)467-7748COMPLETEONELINEFOREACHCOMPONENT FAILUREDESCRIBED INTHISREPORT13CAUSESYSTEMCOMPONENT MANUFACTURER REPORTABLE TOEPIXCAUSESYSTEMCOMPONENT MANUFACTURER REPORTABLE TOEPIXJCn/aN/ANO6PPTALRORTXPECTED(14)YES(IfYoe,completeEXPECTEDSUBMISSION DATE).NOEXPECTEDSUBMISSION DATE(15)ABSTRACT[Limitto1400spaces,ie.,approximately 15singlespeced typewritten lines/{16)OnOctober8,1998,St.LucieUnits1and2wereinMODE1at100percentreactorpower.FPLdetermined thattheTechnical Specification governing thetripbypasssetpoints forthehighrateofchangeofpowerreactorprotection systemtripwasinerror.TheexplicittermTHERMALPOWERusedintheaffectedTechnical Specification tablenotationrelativetothehighrateofchangeofpowertripbypassfunctioncannotbesatisfied priortoent'ryintoMODE2fromaMODE3condition duetothenormallevelofheattransfertothereactorcoolantasaresultofreactorcoredecayheat.Thetermsofthespecification cannotbeachievedsincedecayheatisnotadirectlymeasurable parameter andthe.operative parameter forremovalofthebypassisexcoreneutronfluxthatismeasuredbythewiderangelogarithmic neutronfluxmonitors. |
| | Duringpastreactorstartups, literalcompliance withtheTechnical Specifications forthehighrateofchangeofpowertripwasnotmet.ThecauseofthiseventwasapoorlywordedTechnical Specification thatdidnotexplicitly excludedecayheatfromthepowerlevelatwhichthehighrateofchangeofpowertripbypassisrequiredtoberemoved.Asacorrective action,St.Luciehasdeveloped andsubmitted anamendment tothelicensetoclarifythepowerrequirements forthehighrateofchangeofpowertrip.Therevisionensuresthatthemeaningof'explicit termsusedintheaffectedTechnical Specifications areconsistent withtheintentofthestatedrequirements basedoneachSt.LuciePlantdesign.NACFORM3SSIS.1999) |
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| INRCFORM366AI8-I888)LICENSEEEVENTREPORT(LER)TEXTCONTINUATIONU.S.NUCLEARREGULATORYCOMMISSIONFAGIUTYNAMEI1)St.LucieUnit1DocKETNUMBER205000335LERNUMBER(6)SEQUENTIALREVISIONNUMBERNUMBER1998-008-00PAGEI3)Page2of4TEXT(ffmorespeceisrequired,useedditionelcopiesofNRCForm366A/I17)DescriptionofEventOnOctober8,1998,St.LucieUnits1and2wereinMODE1at100percentreactorpower.FPLdeterminedthattheTechnicalSpecificationgoverningthetripandbypasssetpointsforthehighrateofchangeofpower(HRCP)reactorprotectionsystem(RPS)[BZISIJC]tripbypasswasinerror.Specifically,theTechnicalSpecificationincorrectlydefinestheHRCPtripbypassasafunctionofTHERMALPOWER,insteadofindicatedwiderangelogrithmicpower.Therateofchangeofreactorpowerismeasuredbyfourwiderangelogarithmicchannels.Eachchannelindependentlymonitorstheneutronfluxbyprocessingsignalsfromfissionchamberslocatedexternaltothereactorcoreandcoversatendecaderangefromapproximately10percenttoover100percentoffullpower.Theexcoreneutronfluxinthevicinityofthefissionchambersisproportionaltotheincorenuclearfissionrateandisnotsignificantlyinfluencedbyheattransferfromthecoretothecoolantfromthelong-termdecayofradioactivefissionproducts.Thelogarithmicpowerlevelsignalisdifferentiatedtoproviderateofchangeofpowerinformation.fromapproximately-1to+7decadesperminute(DPM)~TheratesignalisprocessedandinputtoabistablethatactuatestheHRCPtripwhentherateofchangeofreactorpowerexceeds2.49decadesperminute.Areactortripisinitiatedwhenreactorpowerexceedsthesetpointasmeasuredbyanytwowiderangechannels.Eachwiderangelogarithmicneutronfluxmonitoralsooperatesabistabletodisablethistripbelow10percentpowerand,conversely,ensurethatthisbypassisautomaticallyremovedatgreaterthanorequalto10percentpower.Thetripfeaturemayalsobebypassedabove15percentpower,butsettingandremovingthisbypassisaccomplishedbythepowerrangechannels(linear,narrowrangeneutronfluxmonitors)whichalsomonitortheexcoreneutronflux.TheTechnicalSpecificationsdefineTHERMALPOWERasthetotalreactorcoreheattransferratetothereactorcoolant.Inadditiontotheheatgeneratedbytheincorefissionrate,thisdefinitionofTHERMALPOWBRincludesdecayheatwhichisproducedfromtheradioactivedecayofcorefissionproducts.Forapreviouslyoperatedreactor,decayheatcontinuestoexistduringreactorshutdownandwouldtakeseveralyearstodecaytoalevelwherethecoreheattransferratecorrespondsto10percent,orless,ofRATEDTHERMALPOWER.Decay'heatisnotadirectlymeasureableparameter,doesnotreflectthereactivityconditionofthereactor,andisnotavariablenormallyassociatedwiththerateofchangeofreactorpower.Therefore,decayheatisnotsuitableforuseasanoperativeparameterforautomaticprotectiveactionsandthereisnoevidencetoindicatethatdecayheatwasconsideredinthedesignoftheHRCPtripfunction.CauseoftheEventThecauseofthiseventwasapoorlywordedTechnicalSpecificationthatdidnotexplicitlyexcludedecayheatfromthepowerlevelatwhichtheHRCPtripbypassisrequiredtoberemoved.AnalysisoftheEvent,Thiseventisreportableunder10CFR50.73(a)(2)(i)(B)as"anyoperationorconditionprohibitedbytheplant'sTechnicalSpecifications."ThefollowingNRCFORM388A(8.1888) | | INRCFORM366AI8-I888)LICENSEEEVENTREPORT(LER)TEXTCONTINUATION U.S.NUCLEARREGULATORY COMMISSION FAGIUTYNAMEI1)St.LucieUnit1DocKETNUMBER205000335LERNUMBER(6)SEQUENTIAL REVISIONNUMBERNUMBER1998-008-00PAGEI3)Page2of4TEXT(ffmorespeceisrequired, useedditionelcopiesofNRCForm366A/I17)Description ofEventOnOctober8,1998,St.LucieUnits1and2wereinMODE1at100percentreactorpower.FPLdetermined thattheTechnical Specification governing thetripandbypasssetpoints forthehighrateofchangeofpower(HRCP)reactorprotection system(RPS)[BZISIJC] |
| NRCFDRM366A(6-1998)LlCENSEEEVENTREPORT(LER)TEXTCONTINUATIONU.S.NUCLEARREGULATORYCOMMISSIONFACILITYNAME(1)St.LucieUnit1DOCKETNUMBER(2)05000335LERNUMBER(8)SEQUENTIALREVISION'UMBERNUMBER1998-008-00PAGE(3)Page3of4TEXT(ifmorespeceisrequired,useedditionelcopiesofiIfRCForm366AI(17)FTechnicalSpecificationtablenotationsapplytothewiderangelogarithmicneutronfluxmonitorfunctionalunit:ForbothUnits:TS1.25:RATEDTHERMALPOWERshallbeatotalreactorcoreheattransferratetothereactorcoolantof2700MWt.TS1.33:THERMALPOWERshallbethetotalreactorcoreheattransferratetothereactorcoolant.TS1.20,OPERATZOMALMODE:AnOPBRATZOHALMODE(i.e.,MODE)shallcorrespondtoanyoneinclusivecombinationofcorereactivitycondition,powerlevel,andaveragereactorcoolanttemperaturespecifiedinTSTable1'.ZnTABLE1.2,theterm0RATEDTHERMALPOWERismodifiedwithafootnotethatstates,*Excludingdecayheat.Unit1:TABLE2.2-1,NOTE(4):Tripmaybebypassedbelow10%andabove15%ofRATEDTHERMALPOWERTABLE3.3-1,Note(d):Tripmaybebypassedbelow100andabove15%ofRATEDTHERMALPOWER)bypassshallbeautomaticallyremovedwhenTHERMALpowerisabove100orbelow15%ofRATEDTHBRKQPOWBR.Unit2:TABLE2.2-2,NOTE(4)andTABLE3.3-7,NOTE(e):Tripmaybebypassedbelow10andabove15%.ofRATEDTHERMALPOWBR;bypassshallbeautomaticallyremovedwhenTHERMALpowerisabove10%orbelow15%ofRATBDTHERMALPOWER.TheHRCPtripwasprovidedwiththeSt.LucieUnit1andUnit2analogRPSas"backupprotectionagainstpowerexcursioneventsinitiatedfromsubcriticalconditions.Thetripisrequiredtobeoperablei.nModes1and2,butmaybebypassedbelow10percentandabove15percentofreactorpower.Assuch,thetripisbasedonboththeOPBRATZONALMODBofthereactorandonhowfastthemeasuredparameterrepresentingreactorpowerchangesinagiventimeperiod.Thesetpointisspecifiedinunitsofreactorstartuprate,i.e.,indecadesperminute(DPM).Thestartuprateisobtainedfromthewiderangelogarithmicneutronfluxmonitorswhichmonitortheexcoreneutronflux.Theexcoreneutronfluxisproportionaltotheincorefissionrate,andtherefore,isproportionaltothereactorpowerproducedfromtheincorefissionrate.Duringstartupofacommercialnuclearreactorfromsubcriticalconditions,heattransfertothereactorcoolantasaresultofonlythefissionrateistypicallyinsufficienttosignificantlyaffectthereactorcoolanttemperaturewhenlessthanapproximately0.1percentoffullpowerandtherateofchangeofneutronfluxisessentiallytheonlymeasureableparameterthatprovidesrateofchangeofpowerinformation.Table1.2ofthefacilityTechnicalSpecificationsdefinestheOPBRATZOHALMODBSofplantoperationintermsofreactivity,thermalpower,andaveragecoolanttemperature.ThetermpercentRATEDTHERMALPOWERisclearlyannotatedandfootnotedwithanasterisktoclarifythatthenumericalvaluesusedinthetableexcludedecayheat.Thisexclusionappliestothepowerlevelthat,inpart,definesMODE2whereintheHRCPtripisrequiredtobeoperableduringreactorstartup.NAGFOAM386A(6-1998) | | tripbypasswasinerror.Specifically, theTechnical Specification incorrectly definestheHRCPtripbypassasafunctionofTHERMALPOWER,insteadofindicated widerangelogrithmic power.Therateofchangeofreactorpowerismeasuredbyfourwiderangelogarithmic channels. |
| NRCFORM366A18-1998)LICENSEEEVENTREPORT(LER)TEXTCONTINUATIONU.S.NUCUARREGULATORYCOMMlSSlONFACIUTYNAMEt1)0OCKETNUMBER2lt.ERNUMBER(6)PAGE(3)St.LucieUnit1SEQUENTIALREVISIONNUMBERNUMBER050003351998-008-00Page4of4TEXTllfmorespecsisreguired,useedditionelcopiesofNRCFerm36&i/I17)TheuseofexcoreneutronfluxasthemeasuredparametertoimplementtheHRCPtripfunctionisappropriate,andtheRPSnuclearinstrumentationchannelsdesignedtocoverthestartuprangesoftheSt.Luciereactorsarethewiderangelogarithmicneutronfluxmonitors.Similartodesignfeaturesofthetrip,thepowerlevelatwhichthetripfunctionbypassmustberemovedduringareactorstartupisassociatedwiththeOPERATIONALMODBofthereactorandmustbeinarangeofreactorpowerthatwillassuresuccessoftheprotectiveaction.TheonsetofoperabilityfortheHRCPtripinMODE2duringstartupisatanexcoreneutronfluxthatcorrespondstoapproximately10percentoftheincorefull-powerfissionrate.However,thethermalpowerproducedfromthisfissionrateistypicallybelowtheTHEMQPOWERdefinedbyTS1.33which,absentanexplicitmodifiertoindicateotherwise,includesdecayheat.IntheSt.LuciereactorsfollowingshutdownfromextendedpoweroperationstobelowMODE2,thethermalpowerproducedfromdecayheatistypicallyhigherthanthethermalpowerproducedonlybythefi.ssionrate.AlthoughtheexclusionofdecayheatfromtheHRCptripisimpliedbythedefinitionofOPERATIONALMODE,literalcompliancewiththeTechnicalSpecificationrequirementsfordefiningtheHRCPtripbypasssetpointasafunctionofTHERMALPOWERwasnotmet.AnalysisofSafetySignificanceTheTechnicalSpecificationinadequacydoesnotapplyduringshutdownreactoroperationsorMODB1reactoroperationabove15percentpower.Currently,bothSt.LucieunitsareoperatinginMIODE1above15percentpower,sonocurrentTechnicalSpecificationcomplianceissueexists.Duringpastreactorstartups,literalcompliancewiththeTechnicalSpecificationsfortheHRCPtripwasnotmet.However,thedesignoftheHRCPtripfunctionanditsautomaticbypassremovalfeatureareassociatedwiththereactorpowergeneratedonlybythefissionprocessandexcludesconsiderationofdecayheat.Decayheatisnotadirectlymeasureableparameter,doesnotreflectthereactivityconditionofthereactor,andisnotavariablenormallyassociatedwiththerateofchangeofreactorpower.Therefore,thehealthandsafetyofthepublicwerenotaffectedbythisevent.CorrectiveActions1.St.Luciehasdevelopedandsubmittedanamendmenttothelicensestoclarifythepowerrequirementsforthe'HRCPtrip.TheTechni.calSpecificationchangeswillneedtobeapprovedbytheNRCpriortoanysubsequentunitstartup.2.FPLreviewedtheTechnicalSpecificationsgoverningtheautomaticremovalof,andpermissivesfor,otherRPStripbypassesfortheincorrectuseofTHERMALPOWERanddecayheat.Thelicenseamendmentssubmittedinaction(1)abovealsoreplacesthetermTHERMALPOWERwiththepowermeasuredbytheappropriateneutronfluxmonitorforthetripbypassesassociatedwiththeRPSzeropowermodebypass,localpowerdensitytripbypass,andturbinetripbypass.AdditionalInformationNoneNRCFORM3BBA18-1998)}} | | Eachchannelindependently monitorstheneutronfluxbyprocessing signalsfromfissionchamberslocatedexternaltothereactorcoreandcoversatendecaderangefromapproximately 10percenttoover100percentoffullpower.Theexcoreneutronfluxinthevicinityofthefissionchambersisproportional totheincorenuclearfissionrateandisnotsignificantly influenced byheattransferfromthecoretothecoolantfromthelong-term decayofradioactive fissionproducts. |
| | Thelogarithmic powerlevelsignalisdifferentiated toproviderateofchangeofpowerinformation. |
| | fromapproximately |
| | -1to+7decadesperminute(DPM)~Theratesignalisprocessed andinputtoabistablethatactuatestheHRCPtripwhentherateofchangeofreactorpowerexceeds2.49decadesperminute.Areactortripisinitiated whenreactorpowerexceedsthesetpointasmeasuredbyanytwowiderangechannels. |
| | Eachwiderangelogarithmic neutronfluxmonitoralsooperatesabistabletodisablethistripbelow10percentpowerand,conversely, ensurethatthisbypassisautomatically removedatgreaterthanorequalto10percentpower.Thetripfeaturemayalsobebypassedabove15percentpower,butsettingandremovingthisbypassisaccomplished bythepowerrangechannels(linear,narrowrangeneutronfluxmonitors) whichalsomonitortheexcoreneutronflux.TheTechnical Specifications defineTHERMALPOWERasthetotalreactorcoreheattransferratetothereactorcoolant.Inadditiontotheheatgenerated bytheincorefissionrate,thisdefinition ofTHERMALPOWBRincludesdecayheatwhichisproducedfromtheradioactive decayofcorefissionproducts. |
| | Forapreviously operatedreactor,decayheatcontinues toexistduringreactorshutdownandwouldtakeseveralyearstodecaytoalevelwherethecoreheattransferratecorresponds to10percent,orless,ofRATEDTHERMALPOWER.Decay'heat isnotadirectlymeasureable parameter, doesnotreflectthereactivity condition ofthereactor,andisnotavariablenormallyassociated withtherateofchangeofreactorpower.Therefore, decayheatisnotsuitableforuseasanoperative parameter forautomatic protective actionsandthereisnoevidencetoindicatethatdecayheatwasconsidered inthedesignoftheHRCPtripfunction. |
| | CauseoftheEventThecauseofthiseventwasapoorlywordedTechnical Specification thatdidnotexplicitly excludedecayheatfromthepowerlevelatwhichtheHRCPtripbypassisrequiredtoberemoved.AnalysisoftheEvent,Thiseventisreportable under10CFR50.73(a)(2)(i)(B) as"anyoperation orcondition prohibited bytheplant'sTechnical Specifications." |
| | Thefollowing NRCFORM388A(8.1888) |
| | NRCFDRM366A(6-1998)LlCENSEEEVENTREPORT(LER)TEXTCONTINUATION U.S.NUCLEARREGULATORY COMMISSION FACILITYNAME(1)St.LucieUnit1DOCKETNUMBER(2)05000335LERNUMBER(8)SEQUENTIAL REVISION'UMBERNUMBER1998-008-00PAGE(3)Page3of4TEXT(ifmorespeceisrequired, useedditionel copiesofiIfRCForm366AI(17)FTechnical Specification tablenotations applytothewiderangelogarithmic neutronfluxmonitorfunctional unit:ForbothUnits:TS1.25:RATEDTHERMALPOWERshallbeatotalreactorcoreheattransferratetothereactorcoolantof2700MWt.TS1.33:THERMALPOWERshallbethetotalreactorcoreheattransferratetothereactorcoolant.TS1.20,OPERATZOMAL MODE:AnOPBRATZOHAL MODE(i.e.,MODE)shallcorrespond toanyoneinclusive combination ofcorereactivity condition, powerlevel,andaveragereactorcoolanttemperature specified inTSTable1'.ZnTABLE1.2,theterm0RATEDTHERMALPOWERismodifiedwithafootnotethatstates,*Excluding decayheat.Unit1:TABLE2.2-1,NOTE(4):Tripmaybebypassedbelow10%andabove15%ofRATEDTHERMALPOWERTABLE3.3-1,Note(d):Tripmaybebypassedbelow100andabove15%ofRATEDTHERMALPOWER)bypassshallbeautomatically removedwhenTHERMALpowerisabove100orbelow15%ofRATEDTHBRKQPOWBR.Unit2:TABLE2.2-2,NOTE(4)andTABLE3.3-7,NOTE(e):Tripmaybebypassedbelow10andabove15%.ofRATEDTHERMALPOWBR;bypassshallbeautomatically removedwhenTHERMALpowerisabove10%orbelow15%ofRATBDTHERMALPOWER.TheHRCPtripwasprovidedwiththeSt.LucieUnit1andUnit2analogRPSas"backupprotection againstpowerexcursion eventsinitiated fromsubcritical conditions. |
| | Thetripisrequiredtobeoperablei.nModes1and2,butmaybebypassedbelow10percentandabove15percentofreactorpower.Assuch,thetripisbasedonboththeOPBRATZONAL MODBofthereactorandonhowfastthemeasuredparameter representing reactorpowerchangesinagiventimeperiod.Thesetpointisspecified inunitsofreactorstartuprate,i.e.,indecadesperminute(DPM).Thestartuprateisobtainedfromthewiderangelogarithmic neutronfluxmonitorswhichmonitortheexcoreneutronflux.Theexcoreneutronfluxisproportional totheincorefissionrate,andtherefore, isproportional tothereactorpowerproducedfromtheincorefissionrate.Duringstartupofacommercial nuclearreactorfromsubcritical conditions, heattransfertothereactorcoolantasaresultofonlythefissionrateistypically insufficient tosignificantly affectthereactorcoolanttemperature whenlessthanapproximately 0.1percentoffullpowerandtherateofchangeofneutronfluxisessentially theonlymeasureable parameter thatprovidesrateofchangeofpowerinformation. |
| | Table1.2ofthefacilityTechnical Specifications definestheOPBRATZOHAL MODBSofplantoperation intermsofreactivity, thermalpower,andaveragecoolanttemperature. |
| | ThetermpercentRATEDTHERMALPOWERisclearlyannotated andfootnoted withanasterisktoclarifythatthenumerical valuesusedinthetableexcludedecayheat.Thisexclusion appliestothepowerlevelthat,inpart,definesMODE2whereintheHRCPtripisrequiredtobeoperableduringreactorstartup.NAGFOAM386A(6-1998) |
| | NRCFORM366A18-1998)LICENSEEEVENTREPORT(LER)TEXTCONTINUATION U.S.NUCUARREGULATORY COMMlSSlON FACIUTYNAMEt1)0OCKETNUMBER2lt.ERNUMBER(6)PAGE(3)St.LucieUnit1SEQUENTIAL REVISIONNUMBERNUMBER050003351998-008-00Page4of4TEXTllfmorespecsisreguired, useedditionel copiesofNRCFerm36&i/I17)Theuseofexcoreneutronfluxasthemeasuredparameter toimplement theHRCPtripfunctionisappropriate, andtheRPSnuclearinstrumentation channelsdesignedtocoverthestartuprangesoftheSt.Luciereactorsarethewiderangelogarithmic neutronfluxmonitors. |
| | Similartodesignfeaturesofthetrip,thepowerlevelatwhichthetripfunctionbypassmustberemovedduringareactorstartupisassociated withtheOPERATIONAL MODBofthereactorandmustbeinarangeofreactorpowerthatwillassuresuccessoftheprotective action.Theonsetofoperability fortheHRCPtripinMODE2duringstartupisatanexcoreneutronfluxthatcorresponds toapproximately 10percentoftheincorefull-power fissionrate.However,thethermalpowerproducedfromthisfissionrateistypically belowtheTHEMQPOWERdefinedbyTS1.33which,absentanexplicitmodifiertoindicateotherwise, includesdecayheat.IntheSt.Luciereactorsfollowing shutdownfromextendedpoweroperations tobelowMODE2,thethermalpowerproducedfromdecayheatistypically higherthanthethermalpowerproducedonlybythefi.ssionrate.Althoughtheexclusion ofdecayheatfromtheHRCptripisimpliedbythedefinition ofOPERATIONAL MODE,literalcompliance withtheTechnical Specification requirements fordefiningtheHRCPtripbypasssetpointasafunctionofTHERMALPOWERwasnotmet.AnalysisofSafetySignificance TheTechnical Specification inadequacy doesnotapplyduringshutdownreactoroperations orMODB1reactoroperation above15percentpower.Currently, bothSt.Lucieunitsareoperating inMIODE1above15percentpower,sonocurrentTechnical Specification compliance issueexists.Duringpastreactorstartups, literalcompliance withtheTechnical Specifications fortheHRCPtripwasnotmet.However,thedesignoftheHRCPtripfunctionanditsautomatic bypassremovalfeatureareassociated withthereactorpowergenerated onlybythefissionprocessandexcludesconsideration ofdecayheat.Decayheatisnotadirectlymeasureable parameter, doesnotreflectthereactivity condition ofthereactor,andisnotavariablenormallyassociated withtherateofchangeofreactorpower.Therefore, thehealthandsafetyofthepublicwerenotaffectedbythisevent.Corrective Actions1.St.Luciehasdeveloped andsubmitted anamendment tothelicensestoclarifythepowerrequirements forthe'HRCPtrip.TheTechni.cal Specification changeswillneedtobeapprovedbytheNRCpriortoanysubsequent unitstartup.2.FPLreviewedtheTechnical Specifications governing theautomatic removalof,andpermissives for,otherRPStripbypassesfortheincorrect useofTHERMALPOWERanddecayheat.Thelicenseamendments submitted inaction(1)abovealsoreplacesthetermTHERMALPOWERwiththepowermeasuredbytheappropriate neutronfluxmonitorforthetripbypassesassociated withtheRPSzeropowermodebypass,localpowerdensitytripbypass,andturbinetripbypass.Additional Information NoneNRCFORM3BBA18-1998)}} |
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Category:LICENSEE EVENT REPORT (SEE ALSO AO
MONTHYEARML17241A4891999-10-0707 October 1999 LER 99-004-00:on 990912,noted That MSSV Surveillance Was Outside of TS Requirements.Caused by Setpoint Drift.Subject MSSVs Are Being Refurbished & Retested Prior to Unit Startup from SL1-16 Refueling Outage.With 991007 Ltr ML17241A4111999-07-16016 July 1999 LER 99-007-00:on 990610,unplanned Cooldown Transient Occurred Due to Personnel Error.Trained & Briefed Personnel & Revised Procedures.With 990716 Ltr ML17241A4031999-07-0606 July 1999 LER 99-006-00:on 990605,sub-critical Reactor Trip Occurred Due to Inadvertent MSIV Opening.Caused by Personnel Error. Provided Operation Supervision Instruction to Operating Crews,Stand Down Meetings & Operator Aids.With 990706 Ltr ML17241A4041999-07-0606 July 1999 LER 99-005-00:on 990604,CEA Drop Resulted in Manual Reactor Trip.Caused by Procedural Inadequacies.Procedure Changes Are Planned to Correct Lack of Procedural Guidance for CEA Subgroup Power Switch Replacement.With 990706 Ltr ML17241A3941999-06-30030 June 1999 LER 99-004-01:on 990415,as Found Cycle 10 Psv Setpoints Were Outside TS Limits.Caused by Manufacturing Process Defect. All Three Psvs Were Replaced with pre-tested Valves During Cycle 11 Refueling Outage.With 990630 Ltr ML17241A3551999-06-0404 June 1999 LER 99-002-00:on 990505,both Trains of Safety Injection Actuation Were Blocked During Surveillance.Caused by Procedure Error.Procedure Revised.With 990604 Ltr ML17241A3321999-05-17017 May 1999 LER 99-004-00:on 990415,determined That as Found Cycle 10 Psv Setpoints Outside TS Limits.Root Cause Under Investigation.Psvs Replaced with pe-tested Valves During Cycle 11 ML17241A3271999-05-0606 May 1999 LER 99-003-00:on 990406,ECCS Suction Header Leak Resulted in Both ECCS Trains Being Inoperable & Entry Into TS 3.0.3. Caused by Chloride Induced OD Stress Corrosion Cracking of Piping.Made Code Repairs & Coated Piping.With 990506 Ltr ML17229B0791999-04-0707 April 1999 LER 99-001-00:on 990309,discovered Inadequate Design & IST SRs for Iodine Removal Sys (Irs).Caused by Original Design Inadequacies & Personnel Error.Naoh Tank Vent Valve V07233 Was Tagged Open.With 990407 Ltr ML17229B0801999-04-0707 April 1999 LER 99-002-00:on 990311,SG ECT Error Caused Operation with Condition Prohibited by Ts.Caused by Deficiencies in Data Analysis Guideline Instructions.Licensee Will Change Data Analysis Guidelines for Lead Analysts.With 990407 Ltr ML17229B0541999-03-10010 March 1999 LER 99-001-00:on 990211,inadequate TS SRs for SIT & SDC Isolation Valves Were Noted.Caused by Failure to Correctly Implement TS Srs.Submitted LAR to Align Required TS SR with Design Bases Requirements Being Verified.With 990310 Ltr ML17229A9901999-01-20020 January 1999 LER 98-009-00:on 981223,noted That Facility Operated Outside of Design Basis.Caused by non-conservative MSLB Analysis Inputs.Will Review SR Component Differences Between Units & Will re-baseline LTOP Analysis.With 990120 Ltr ML17229A9821999-01-0404 January 1999 LER 98-010-00:on 981207,RCS Boron Sample Frequency Required by Ts,Was Exceeded by Twelve Minutes.Caused by Personnel Error.Equipment Clearance Order Was Lifted to Draw Required Sample & Operations Procedure Was Changed.With 990104 Ltr ML17229A9611998-12-22022 December 1998 LER 97-002-01:on 981204,containment Sump Debris Screen Was Not IAW Design.Caused by Inadequate C/As for Sump Screen Anamolies.All Identified Sump Screen Deficiencies Were Dispositioned &/Or Repaired.With 981222 Ltr ML17229A9561998-12-15015 December 1998 LER 98-008-00:on 981118,missed TS SG U Tube Insp.Caused by Encoding Errors While Using Remote Positioning Fixtures.All SG Tube Surveyed.With 981215 Ltr ML17229A9301998-11-25025 November 1998 LER 98-005-01:on 980807,discovered That New MOV Methodology Caused Past PORV Block Valve Operability Problem.Caused by Inadequacies in Original Vendor MOV Methodology.Planned Valve Mods Will Be Implemented During Cycle 11 1998 Outage ML17229A9021998-11-0404 November 1998 LER 98-008-00:on 981008,inadequate Reactor Protection Sys Trip Bypass TS Was Noted.Caused by Poorly Worded Ts. Submitted LAR to Clarify Power Requirements for High Rate of Power Trips.With 981104 Ltr ML17229A8771998-10-14014 October 1998 LER 98-006-00:on 980918,inadvertent Afas Actuation Was Noted.Caused by Degradation of Multiple Afas Power Supplies. Replaced Afas Power Supplies & Revised Procedures.With 981014 Ltr ML17229A8761998-10-14014 October 1998 LER 98-007-00:on 980918,identified Discrepancies Between Fire Protection Design Requirements & Field Conditions. Caused by Inadequate Translation & Implementation of Fire Protection Requirements.Procedures Revised.With 981014 Ltr ML17229A8511998-09-0202 September 1998 LER 98-005-00:on 980807,discovered That PORV Margins Were Insufficient to Accommodate Addl Conservatism.Caused by Inadequacies in Original Vendor MOV Methodology.Will Implement Planned Valve Actuator mods.W/980902 Ltr ML17229A8201998-07-29029 July 1998 LER 98-007-00:on 980630,inadequate Procedure May Have Resulted in SBO Recovery Complications.Caused by Inadequate Procedures.Attached Caution Tags to Appropriate Control switches.W/980729 Ltr ML17229A7411998-05-28028 May 1998 LER 98-004-00:on 980430,discovered Waste Gas Decay Tank Operation W/O Available Oxygen Analyzers,Which Is Prohibited by Ts.Caused by Inadequate Licensee Review of License Amend. Oxygen Analyzer recalibrated.W/980528 Ltr ML17229A7381998-05-21021 May 1998 LER 98-006-00:on 980421,missed EDG Fuel Oil Sample Surveillance Was Noted.Caused by Personnel Error.Revised Fuel Oil Sampling Service Purchase Order & Revised Site procedure.W/980521 Ltr ML17229A7011998-04-27027 April 1998 LER 98-003-00:on 980326,discovered Containment Pressure Instrumentation Design Single Failure Vulnerability.Caused by Inadequate Design by Personnel Error.Removed RPS & ESFAS Containment Pressure Bypass Keys immediately.W/980427 Ltr ML17229A6761998-04-0202 April 1998 LER 98-005-00:on 980305,identified Two Conditions That Were Outside App R Design Bases.Caused by Design Oversight During Development of Original App R Safe SD Design.Established 30 Minute Roving Fire Watches & Provided training.W/980402 Ltr ML17229A6731998-03-26026 March 1998 LER 98-002-00:on 980224,radiation Monitor Surveillance Inadequacies Led to Operating of Facility Prohibited by Tss. Caused by Congnitive Personnel Error.Permanent Procedure Changes Were implemented.W/980326 Ltr ML17229A6551998-03-0505 March 1998 LER 98-001-00:on 980206,high/low Pressure Shutdown Cooling Interface Was Noted Outside App R Design Bases.Caused by Personnel Error.Addl Guidance Was Provided to Engineering Dept personnel.W/980305 Ltr ML17229A6281998-02-19019 February 1998 LER 98-004-00:on 980121,emergency Lighting Outside App R Design Bases Occurred.Caused by Congnitive Personnel Error During Translation of App R Section Iii.Procedures Onop 1 & 2 ONP-100.01 Were Issued for Use on 980206.W/980219 Ltr ML17229A6211998-02-0909 February 1998 LER 98-003-00:on 980110,manual Rt Due to DEH Leak at Turbine Test Block Was Noted.Caused by o-ring Extrusion.Shortened Bolts by About 0.125 & Reinstalled at Correct Torque values.W/980209 Ltr ML17229A6191998-02-0404 February 1998 LER 98-002-00:on 980105,CIS Bistable in Bypass Resulted in Condition Prohibited by Tss.Caused by Personnel Error. Radiation Monitor Was Restored to service.W/980204 Ltr ML17229A6161998-02-0303 February 1998 LER 98-001-00:on 980104,inadvertent RPS Actuation Occurred Due to Personnel Error.Caused by Procedural Inadequacies & Inadequate self-checking by Licensed Utility Personnel. Placards Have Been Placed in CRs.W/980203 Ltr ML17229A6051998-01-27027 January 1998 LER 97-010-01:on 971027,inadvertent Core Alteration Prohibited by TSs Were Noted Due to Stuck Cea.Caused by Personnel Error.Cea #24 Was Dislodged & Transferred to Spent Pool for insp.W/980127 Ltr ML17229A5501997-12-0505 December 1997 LER 97-008-00:on 971107,inadequate CR Ventilation Surveillance Resulted in Condition Prohibited by Ts.Caused by non-cognitive Personnel Error.Operating Procedure 2-1900050 Was revised.W/971205 Ltr ML17309A9091997-12-0202 December 1997 LER 97-011-00:on 971102,non-conservative RAS Set Point Resulted in Operation Prohibited by Ts.Caused by Inadequate Set Point & Instrument Loop Scaling Process.Revised ESFAS Functional Tp W/Proper Set point.W/971202 Ltr ML17229A5391997-11-26026 November 1997 LER 97-010-00:on 971027,inadvertant Core Alteration Prohibited by TS Occurred.Caused by CEA Failure to Detach from Ugs.Safety Evaluation Was Performed & Procedural Rev Made to Continue Upper Guide Structure move.W/971126 Ltr ML17229A5151997-11-0707 November 1997 LER 97-007-00:on 971008,inoperable Containment Cooling Fan Resulted in Operation of Facility Outside Design Basis. Caused by non-cognitive Personnel Error.Ccs Operation Was Revised & Issued on 971013.W/971107 Ltr ML17229A4991997-10-17017 October 1997 LER 97-009-00:on 970917,inoperable PORV Block Valve Resulted in Operation Prohibited by Tech Specs Occurred.Caused by Plant GL 89-10 Program Plan to Review Plant Manager Action Item Sys.Porv Block Valve V-1403 restored.W/971017 Ltr ML17309A9011997-08-27027 August 1997 LER 97-008-00:on 970728,mechanical Fire Penetrations Were Inoperable & Outside App R Design Bases.Caused by Seal Mfg Not Providing Formal Documentation for Installed Seals. Modified Inoperable Fire penetrations.W/970827 Ltr ML17229A4311997-07-29029 July 1997 LER 97-006-00:on 970630,discovered Inadequate Testing of Engineered Safety Features Subgroup Relays.Caused by Inadequacy in Implementing TS Requirements in Surveillance Procedures.Revised Surveillance procedures.W/970729 Ltr ML17229A4241997-07-25025 July 1997 LER 97-005-00:on 970625,discovered That Hot Shutdown Control Panel Shutdown Cooling Flow indicator,FI-3306 Inoperable. Caused by Weakness in Work Order & Procedure Used to Repair FI-3306.Section Meeting W/I&C Planners held.W/970725 Ltr ML17229A3971997-07-11011 July 1997 LER 97-004-00:on 970611,discovered Incorrect Original Cable Tray Fire Stop Assembly Installation Was Outside App R Design Basis.Caused by Personnel Error.Hourly Fire Watch Patrols Will Be posted.W/970711 Ltr ML17229A3871997-06-19019 June 1997 LER 97-003-00:on 970521,determined Required Post Maint Open Stroke Test for Valve V3245,2B2 SIT Discharge Check Valve, Had Not Been Performed.Caused by Personnel Error.Procedure revised.W/970619 Ltr ML17229A3841997-06-17017 June 1997 LER 97-002-00:on 970518,containment Sump Debris Screen Was Not IAW Design Due to Gaps in Screen Encl.Performed SER to Document Containment Sump Design requirements.W/970617 Ltr ML17229A3751997-06-0202 June 1997 LER 97-006-00:on 970501,operation Was Prohibited by TS Due to Inadequately Tested Degraded Voltage Sys.Revised Unit 1 ESFAS Surveillance Test procedure.W/970602 Ltr ML17229A3611997-05-29029 May 1997 LER 97-007-00:on 970502,reactor Coolant Pump Oil Collection Sys Was Outside App R Design Bases.Identified Leak Sites Were Repaired & Mods to RCP Oil Collection Sys to Capture Any Future Leakage from areas.W/970529 Ltr ML17229A3491997-05-21021 May 1997 LER 97-001-00:on 970423,containment Isolation Actuation Occurred.Caused by Increased Radiation Levels During Removal of Upper Guide Structure.Proper Actuation of Containment Isolation Components Was verified.W/970521 Ltr ML17229A3441997-05-13013 May 1997 LER 97-005-00:on 970419,reactor Was Shutdown Due to Reactor Coolant Pressure Boundary Leakage.Hot Cracking Was Caused by Weld Contamination.Repairs to RCPB Were Completed & 1A SDC Train Was Restored to Svc ML17229A3141997-04-30030 April 1997 LER 97-004-00:on 970402,refueling Machine Was Operating in Manner Prohibited by TS Due to Original Design of Refueling Machine Bypass Feature Conflicting W/Ts Requirements. Eliminated Overload Cut Off Limit bypass.W/970430 Ltr ML17229A2951997-03-31031 March 1997 LER 97-003-00:on 970304,automatic Rt Resulted from Loss of Electrical Power to 1A2 Rc Pump.Rcp Breaker Was Replaced & Pump Was Returned to svc.W/970331 Ltr ML17229A2721997-03-21021 March 1997 LER 97-002-00:on 970221,operation in Excess of Max Rated Thermal Power Occurred Due to Digital Data Processing Sys (Ddps) Calorimetric Error.Verified Acceptable Performance of Ddps Functions & Reviewed Software mods.W/970321 Ltr 1999-07-06
[Table view] Category:RO)
MONTHYEARML17241A4891999-10-0707 October 1999 LER 99-004-00:on 990912,noted That MSSV Surveillance Was Outside of TS Requirements.Caused by Setpoint Drift.Subject MSSVs Are Being Refurbished & Retested Prior to Unit Startup from SL1-16 Refueling Outage.With 991007 Ltr ML17241A4111999-07-16016 July 1999 LER 99-007-00:on 990610,unplanned Cooldown Transient Occurred Due to Personnel Error.Trained & Briefed Personnel & Revised Procedures.With 990716 Ltr ML17241A4031999-07-0606 July 1999 LER 99-006-00:on 990605,sub-critical Reactor Trip Occurred Due to Inadvertent MSIV Opening.Caused by Personnel Error. Provided Operation Supervision Instruction to Operating Crews,Stand Down Meetings & Operator Aids.With 990706 Ltr ML17241A4041999-07-0606 July 1999 LER 99-005-00:on 990604,CEA Drop Resulted in Manual Reactor Trip.Caused by Procedural Inadequacies.Procedure Changes Are Planned to Correct Lack of Procedural Guidance for CEA Subgroup Power Switch Replacement.With 990706 Ltr ML17241A3941999-06-30030 June 1999 LER 99-004-01:on 990415,as Found Cycle 10 Psv Setpoints Were Outside TS Limits.Caused by Manufacturing Process Defect. All Three Psvs Were Replaced with pre-tested Valves During Cycle 11 Refueling Outage.With 990630 Ltr ML17241A3551999-06-0404 June 1999 LER 99-002-00:on 990505,both Trains of Safety Injection Actuation Were Blocked During Surveillance.Caused by Procedure Error.Procedure Revised.With 990604 Ltr ML17241A3321999-05-17017 May 1999 LER 99-004-00:on 990415,determined That as Found Cycle 10 Psv Setpoints Outside TS Limits.Root Cause Under Investigation.Psvs Replaced with pe-tested Valves During Cycle 11 ML17241A3271999-05-0606 May 1999 LER 99-003-00:on 990406,ECCS Suction Header Leak Resulted in Both ECCS Trains Being Inoperable & Entry Into TS 3.0.3. Caused by Chloride Induced OD Stress Corrosion Cracking of Piping.Made Code Repairs & Coated Piping.With 990506 Ltr ML17229B0791999-04-0707 April 1999 LER 99-001-00:on 990309,discovered Inadequate Design & IST SRs for Iodine Removal Sys (Irs).Caused by Original Design Inadequacies & Personnel Error.Naoh Tank Vent Valve V07233 Was Tagged Open.With 990407 Ltr ML17229B0801999-04-0707 April 1999 LER 99-002-00:on 990311,SG ECT Error Caused Operation with Condition Prohibited by Ts.Caused by Deficiencies in Data Analysis Guideline Instructions.Licensee Will Change Data Analysis Guidelines for Lead Analysts.With 990407 Ltr ML17229B0541999-03-10010 March 1999 LER 99-001-00:on 990211,inadequate TS SRs for SIT & SDC Isolation Valves Were Noted.Caused by Failure to Correctly Implement TS Srs.Submitted LAR to Align Required TS SR with Design Bases Requirements Being Verified.With 990310 Ltr ML17229A9901999-01-20020 January 1999 LER 98-009-00:on 981223,noted That Facility Operated Outside of Design Basis.Caused by non-conservative MSLB Analysis Inputs.Will Review SR Component Differences Between Units & Will re-baseline LTOP Analysis.With 990120 Ltr ML17229A9821999-01-0404 January 1999 LER 98-010-00:on 981207,RCS Boron Sample Frequency Required by Ts,Was Exceeded by Twelve Minutes.Caused by Personnel Error.Equipment Clearance Order Was Lifted to Draw Required Sample & Operations Procedure Was Changed.With 990104 Ltr ML17229A9611998-12-22022 December 1998 LER 97-002-01:on 981204,containment Sump Debris Screen Was Not IAW Design.Caused by Inadequate C/As for Sump Screen Anamolies.All Identified Sump Screen Deficiencies Were Dispositioned &/Or Repaired.With 981222 Ltr ML17229A9561998-12-15015 December 1998 LER 98-008-00:on 981118,missed TS SG U Tube Insp.Caused by Encoding Errors While Using Remote Positioning Fixtures.All SG Tube Surveyed.With 981215 Ltr ML17229A9301998-11-25025 November 1998 LER 98-005-01:on 980807,discovered That New MOV Methodology Caused Past PORV Block Valve Operability Problem.Caused by Inadequacies in Original Vendor MOV Methodology.Planned Valve Mods Will Be Implemented During Cycle 11 1998 Outage ML17229A9021998-11-0404 November 1998 LER 98-008-00:on 981008,inadequate Reactor Protection Sys Trip Bypass TS Was Noted.Caused by Poorly Worded Ts. Submitted LAR to Clarify Power Requirements for High Rate of Power Trips.With 981104 Ltr ML17229A8771998-10-14014 October 1998 LER 98-006-00:on 980918,inadvertent Afas Actuation Was Noted.Caused by Degradation of Multiple Afas Power Supplies. Replaced Afas Power Supplies & Revised Procedures.With 981014 Ltr ML17229A8761998-10-14014 October 1998 LER 98-007-00:on 980918,identified Discrepancies Between Fire Protection Design Requirements & Field Conditions. Caused by Inadequate Translation & Implementation of Fire Protection Requirements.Procedures Revised.With 981014 Ltr ML17229A8511998-09-0202 September 1998 LER 98-005-00:on 980807,discovered That PORV Margins Were Insufficient to Accommodate Addl Conservatism.Caused by Inadequacies in Original Vendor MOV Methodology.Will Implement Planned Valve Actuator mods.W/980902 Ltr ML17229A8201998-07-29029 July 1998 LER 98-007-00:on 980630,inadequate Procedure May Have Resulted in SBO Recovery Complications.Caused by Inadequate Procedures.Attached Caution Tags to Appropriate Control switches.W/980729 Ltr ML17229A7411998-05-28028 May 1998 LER 98-004-00:on 980430,discovered Waste Gas Decay Tank Operation W/O Available Oxygen Analyzers,Which Is Prohibited by Ts.Caused by Inadequate Licensee Review of License Amend. Oxygen Analyzer recalibrated.W/980528 Ltr ML17229A7381998-05-21021 May 1998 LER 98-006-00:on 980421,missed EDG Fuel Oil Sample Surveillance Was Noted.Caused by Personnel Error.Revised Fuel Oil Sampling Service Purchase Order & Revised Site procedure.W/980521 Ltr ML17229A7011998-04-27027 April 1998 LER 98-003-00:on 980326,discovered Containment Pressure Instrumentation Design Single Failure Vulnerability.Caused by Inadequate Design by Personnel Error.Removed RPS & ESFAS Containment Pressure Bypass Keys immediately.W/980427 Ltr ML17229A6761998-04-0202 April 1998 LER 98-005-00:on 980305,identified Two Conditions That Were Outside App R Design Bases.Caused by Design Oversight During Development of Original App R Safe SD Design.Established 30 Minute Roving Fire Watches & Provided training.W/980402 Ltr ML17229A6731998-03-26026 March 1998 LER 98-002-00:on 980224,radiation Monitor Surveillance Inadequacies Led to Operating of Facility Prohibited by Tss. Caused by Congnitive Personnel Error.Permanent Procedure Changes Were implemented.W/980326 Ltr ML17229A6551998-03-0505 March 1998 LER 98-001-00:on 980206,high/low Pressure Shutdown Cooling Interface Was Noted Outside App R Design Bases.Caused by Personnel Error.Addl Guidance Was Provided to Engineering Dept personnel.W/980305 Ltr ML17229A6281998-02-19019 February 1998 LER 98-004-00:on 980121,emergency Lighting Outside App R Design Bases Occurred.Caused by Congnitive Personnel Error During Translation of App R Section Iii.Procedures Onop 1 & 2 ONP-100.01 Were Issued for Use on 980206.W/980219 Ltr ML17229A6211998-02-0909 February 1998 LER 98-003-00:on 980110,manual Rt Due to DEH Leak at Turbine Test Block Was Noted.Caused by o-ring Extrusion.Shortened Bolts by About 0.125 & Reinstalled at Correct Torque values.W/980209 Ltr ML17229A6191998-02-0404 February 1998 LER 98-002-00:on 980105,CIS Bistable in Bypass Resulted in Condition Prohibited by Tss.Caused by Personnel Error. Radiation Monitor Was Restored to service.W/980204 Ltr ML17229A6161998-02-0303 February 1998 LER 98-001-00:on 980104,inadvertent RPS Actuation Occurred Due to Personnel Error.Caused by Procedural Inadequacies & Inadequate self-checking by Licensed Utility Personnel. Placards Have Been Placed in CRs.W/980203 Ltr ML17229A6051998-01-27027 January 1998 LER 97-010-01:on 971027,inadvertent Core Alteration Prohibited by TSs Were Noted Due to Stuck Cea.Caused by Personnel Error.Cea #24 Was Dislodged & Transferred to Spent Pool for insp.W/980127 Ltr ML17229A5501997-12-0505 December 1997 LER 97-008-00:on 971107,inadequate CR Ventilation Surveillance Resulted in Condition Prohibited by Ts.Caused by non-cognitive Personnel Error.Operating Procedure 2-1900050 Was revised.W/971205 Ltr ML17309A9091997-12-0202 December 1997 LER 97-011-00:on 971102,non-conservative RAS Set Point Resulted in Operation Prohibited by Ts.Caused by Inadequate Set Point & Instrument Loop Scaling Process.Revised ESFAS Functional Tp W/Proper Set point.W/971202 Ltr ML17229A5391997-11-26026 November 1997 LER 97-010-00:on 971027,inadvertant Core Alteration Prohibited by TS Occurred.Caused by CEA Failure to Detach from Ugs.Safety Evaluation Was Performed & Procedural Rev Made to Continue Upper Guide Structure move.W/971126 Ltr ML17229A5151997-11-0707 November 1997 LER 97-007-00:on 971008,inoperable Containment Cooling Fan Resulted in Operation of Facility Outside Design Basis. Caused by non-cognitive Personnel Error.Ccs Operation Was Revised & Issued on 971013.W/971107 Ltr ML17229A4991997-10-17017 October 1997 LER 97-009-00:on 970917,inoperable PORV Block Valve Resulted in Operation Prohibited by Tech Specs Occurred.Caused by Plant GL 89-10 Program Plan to Review Plant Manager Action Item Sys.Porv Block Valve V-1403 restored.W/971017 Ltr ML17309A9011997-08-27027 August 1997 LER 97-008-00:on 970728,mechanical Fire Penetrations Were Inoperable & Outside App R Design Bases.Caused by Seal Mfg Not Providing Formal Documentation for Installed Seals. Modified Inoperable Fire penetrations.W/970827 Ltr ML17229A4311997-07-29029 July 1997 LER 97-006-00:on 970630,discovered Inadequate Testing of Engineered Safety Features Subgroup Relays.Caused by Inadequacy in Implementing TS Requirements in Surveillance Procedures.Revised Surveillance procedures.W/970729 Ltr ML17229A4241997-07-25025 July 1997 LER 97-005-00:on 970625,discovered That Hot Shutdown Control Panel Shutdown Cooling Flow indicator,FI-3306 Inoperable. Caused by Weakness in Work Order & Procedure Used to Repair FI-3306.Section Meeting W/I&C Planners held.W/970725 Ltr ML17229A3971997-07-11011 July 1997 LER 97-004-00:on 970611,discovered Incorrect Original Cable Tray Fire Stop Assembly Installation Was Outside App R Design Basis.Caused by Personnel Error.Hourly Fire Watch Patrols Will Be posted.W/970711 Ltr ML17229A3871997-06-19019 June 1997 LER 97-003-00:on 970521,determined Required Post Maint Open Stroke Test for Valve V3245,2B2 SIT Discharge Check Valve, Had Not Been Performed.Caused by Personnel Error.Procedure revised.W/970619 Ltr ML17229A3841997-06-17017 June 1997 LER 97-002-00:on 970518,containment Sump Debris Screen Was Not IAW Design Due to Gaps in Screen Encl.Performed SER to Document Containment Sump Design requirements.W/970617 Ltr ML17229A3751997-06-0202 June 1997 LER 97-006-00:on 970501,operation Was Prohibited by TS Due to Inadequately Tested Degraded Voltage Sys.Revised Unit 1 ESFAS Surveillance Test procedure.W/970602 Ltr ML17229A3611997-05-29029 May 1997 LER 97-007-00:on 970502,reactor Coolant Pump Oil Collection Sys Was Outside App R Design Bases.Identified Leak Sites Were Repaired & Mods to RCP Oil Collection Sys to Capture Any Future Leakage from areas.W/970529 Ltr ML17229A3491997-05-21021 May 1997 LER 97-001-00:on 970423,containment Isolation Actuation Occurred.Caused by Increased Radiation Levels During Removal of Upper Guide Structure.Proper Actuation of Containment Isolation Components Was verified.W/970521 Ltr ML17229A3441997-05-13013 May 1997 LER 97-005-00:on 970419,reactor Was Shutdown Due to Reactor Coolant Pressure Boundary Leakage.Hot Cracking Was Caused by Weld Contamination.Repairs to RCPB Were Completed & 1A SDC Train Was Restored to Svc ML17229A3141997-04-30030 April 1997 LER 97-004-00:on 970402,refueling Machine Was Operating in Manner Prohibited by TS Due to Original Design of Refueling Machine Bypass Feature Conflicting W/Ts Requirements. Eliminated Overload Cut Off Limit bypass.W/970430 Ltr ML17229A2951997-03-31031 March 1997 LER 97-003-00:on 970304,automatic Rt Resulted from Loss of Electrical Power to 1A2 Rc Pump.Rcp Breaker Was Replaced & Pump Was Returned to svc.W/970331 Ltr ML17229A2721997-03-21021 March 1997 LER 97-002-00:on 970221,operation in Excess of Max Rated Thermal Power Occurred Due to Digital Data Processing Sys (Ddps) Calorimetric Error.Verified Acceptable Performance of Ddps Functions & Reviewed Software mods.W/970321 Ltr 1999-07-06
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML17241A4891999-10-0707 October 1999 LER 99-004-00:on 990912,noted That MSSV Surveillance Was Outside of TS Requirements.Caused by Setpoint Drift.Subject MSSVs Are Being Refurbished & Retested Prior to Unit Startup from SL1-16 Refueling Outage.With 991007 Ltr ML17241A4951999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for St Lucie,Units 1 & 2.With 991014 Ltr ML17241A4741999-08-31031 August 1999 Rev 1 to PCM 99016, St Lucie Unit 1,Cycle 16 Colr. ML17241A4591999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for St Lucie,Units 1 & 2.With 990913 Ltr ML17241A4301999-07-31031 July 1999 Monthly Operating Repts for Jul 1999 for St Lucie Units 1 & 2.With 990805 Ltr ML17241A4111999-07-16016 July 1999 LER 99-007-00:on 990610,unplanned Cooldown Transient Occurred Due to Personnel Error.Trained & Briefed Personnel & Revised Procedures.With 990716 Ltr ML17241A4031999-07-0606 July 1999 LER 99-006-00:on 990605,sub-critical Reactor Trip Occurred Due to Inadvertent MSIV Opening.Caused by Personnel Error. Provided Operation Supervision Instruction to Operating Crews,Stand Down Meetings & Operator Aids.With 990706 Ltr ML17241A4041999-07-0606 July 1999 LER 99-005-00:on 990604,CEA Drop Resulted in Manual Reactor Trip.Caused by Procedural Inadequacies.Procedure Changes Are Planned to Correct Lack of Procedural Guidance for CEA Subgroup Power Switch Replacement.With 990706 Ltr ML17241A4091999-06-30030 June 1999 Monthly Operating Repts for June 1999 for St Lucie,Units 1 & 2.With 990712 Ltr ML17241A3941999-06-30030 June 1999 LER 99-004-01:on 990415,as Found Cycle 10 Psv Setpoints Were Outside TS Limits.Caused by Manufacturing Process Defect. All Three Psvs Were Replaced with pre-tested Valves During Cycle 11 Refueling Outage.With 990630 Ltr ML17355A3681999-06-30030 June 1999 Revised Update to Topical QA Rept, Dtd June 1999 ML17241A3551999-06-0404 June 1999 LER 99-002-00:on 990505,both Trains of Safety Injection Actuation Were Blocked During Surveillance.Caused by Procedure Error.Procedure Revised.With 990604 Ltr ML17241A3631999-05-31031 May 1999 Monthly Operating Repts for May 1999 for St Lucie Units 1 & 2.With 990610 Ltr ML17241A3321999-05-17017 May 1999 LER 99-004-00:on 990415,determined That as Found Cycle 10 Psv Setpoints Outside TS Limits.Root Cause Under Investigation.Psvs Replaced with pe-tested Valves During Cycle 11 ML17241A3271999-05-0606 May 1999 LER 99-003-00:on 990406,ECCS Suction Header Leak Resulted in Both ECCS Trains Being Inoperable & Entry Into TS 3.0.3. Caused by Chloride Induced OD Stress Corrosion Cracking of Piping.Made Code Repairs & Coated Piping.With 990506 Ltr ML17241A3331999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for St Lucie,Units 1 & 2.With 990517 Ltr ML17229B0801999-04-0707 April 1999 LER 99-002-00:on 990311,SG ECT Error Caused Operation with Condition Prohibited by Ts.Caused by Deficiencies in Data Analysis Guideline Instructions.Licensee Will Change Data Analysis Guidelines for Lead Analysts.With 990407 Ltr ML17229B0841999-04-0707 April 1999 Rev 2 to PSL-ENG-SEMS-98-102, Engineering Evaluation of ECCS Suction Lines. ML17229B0791999-04-0707 April 1999 LER 99-001-00:on 990309,discovered Inadequate Design & IST SRs for Iodine Removal Sys (Irs).Caused by Original Design Inadequacies & Personnel Error.Naoh Tank Vent Valve V07233 Was Tagged Open.With 990407 Ltr ML17229B0961999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for St Lucie,Units 1 & 2.With 990408 Ltr ML17229B0541999-03-10010 March 1999 LER 99-001-00:on 990211,inadequate TS SRs for SIT & SDC Isolation Valves Were Noted.Caused by Failure to Correctly Implement TS Srs.Submitted LAR to Align Required TS SR with Design Bases Requirements Being Verified.With 990310 Ltr ML17229B0461999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for St Lucie,Units 1 & 2.With 990310 Ltr ML17229B0051999-01-31031 January 1999 Monthly Operating Repts for Jan 1999 for St Lucie,Units 1 & 2.With 990211 Ltr ML17229A9901999-01-20020 January 1999 LER 98-009-00:on 981223,noted That Facility Operated Outside of Design Basis.Caused by non-conservative MSLB Analysis Inputs.Will Review SR Component Differences Between Units & Will re-baseline LTOP Analysis.With 990120 Ltr ML17229A9961999-01-14014 January 1999 SG Tube Inservice Insp Special Rept. ML17229A9821999-01-0404 January 1999 LER 98-010-00:on 981207,RCS Boron Sample Frequency Required by Ts,Was Exceeded by Twelve Minutes.Caused by Personnel Error.Equipment Clearance Order Was Lifted to Draw Required Sample & Operations Procedure Was Changed.With 990104 Ltr ML17229A9831998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for St Lucie,Units 1 & 2.With 990111 Ltr ML17229A9611998-12-22022 December 1998 LER 97-002-01:on 981204,containment Sump Debris Screen Was Not IAW Design.Caused by Inadequate C/As for Sump Screen Anamolies.All Identified Sump Screen Deficiencies Were Dispositioned &/Or Repaired.With 981222 Ltr ML17229A9561998-12-15015 December 1998 LER 98-008-00:on 981118,missed TS SG U Tube Insp.Caused by Encoding Errors While Using Remote Positioning Fixtures.All SG Tube Surveyed.With 981215 Ltr ML17241A3581998-12-0909 December 1998 Changes,Tests & Experiments Made as Allowed by 10CFR50.59 for Period of 970526-981209. ML17229A9421998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for St Lucie,Units 1 & 2.With 981215 Ltr ML17229A9301998-11-25025 November 1998 LER 98-005-01:on 980807,discovered That New MOV Methodology Caused Past PORV Block Valve Operability Problem.Caused by Inadequacies in Original Vendor MOV Methodology.Planned Valve Mods Will Be Implemented During Cycle 11 1998 Outage ML17229A9021998-11-0404 November 1998 LER 98-008-00:on 981008,inadequate Reactor Protection Sys Trip Bypass TS Was Noted.Caused by Poorly Worded Ts. Submitted LAR to Clarify Power Requirements for High Rate of Power Trips.With 981104 Ltr ML17241A4931998-11-0101 November 1998 Statement of Account for Period of 981101-990930 for Suntrust Bank,As Trustee for Florida Municipal Power Agency Nuclear Decommissioning Trust (St Lucie Project). ML17229A9051998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for St Lucie,Units 1 & 2.With 981110 Ltr ML17229A8871998-10-19019 October 1998 Part 21 Rept Re Potential Defect in Swagelok Stainless Steel Front Ferrule,Part Number SS-503-1 Which Was Machined with Improper Length.C/A Includes Insp Equipment That Will 100% Identify Short Length ML17229A8781998-10-19019 October 1998 Part 21 Rept Re Potential Defect in Swagelok Stainless Steel Front Ferrule,Part Number SS-503-1,which Was Machined with Improper Length.Insp Equipment That Will 100% Identify Short Length ML17229A8771998-10-14014 October 1998 LER 98-006-00:on 980918,inadvertent Afas Actuation Was Noted.Caused by Degradation of Multiple Afas Power Supplies. Replaced Afas Power Supplies & Revised Procedures.With 981014 Ltr ML17229A8761998-10-14014 October 1998 LER 98-007-00:on 980918,identified Discrepancies Between Fire Protection Design Requirements & Field Conditions. Caused by Inadequate Translation & Implementation of Fire Protection Requirements.Procedures Revised.With 981014 Ltr ML17229A8721998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for St Lucie Units 1 & 2.With 981009 Ltr ML17229A8511998-09-0202 September 1998 LER 98-005-00:on 980807,discovered That PORV Margins Were Insufficient to Accommodate Addl Conservatism.Caused by Inadequacies in Original Vendor MOV Methodology.Will Implement Planned Valve Actuator mods.W/980902 Ltr ML17229A8611998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for St Lucie,Units 1 & 2.With 980911 Ltr ML18066A2771998-08-13013 August 1998 Part 21 Rept Re Deficiency in CE Current Screening Methodology for Determining Limiting Fuel Assembly for Detailed PWR thermal-hydraulic Sa.Evaluations Were Performed for Affected Plants to Determine Effect of Deficiency ML17229A8481998-08-0707 August 1998 Rev 1 to PSL-ENG-SEFJ-98-013, St Lucie Unit 2,Cycle 10 Colr. ML17229A9461998-08-0707 August 1998 Rev 0 to PCM 98016, St Lucie Unit 2,Cycle 11 Colr. ML17229A8301998-07-31031 July 1998 Monthly Operating Repts for July 1998 for St Lucie,Units 1 & 2.W/980814 Ltr ML17229A8201998-07-29029 July 1998 LER 98-007-00:on 980630,inadequate Procedure May Have Resulted in SBO Recovery Complications.Caused by Inadequate Procedures.Attached Caution Tags to Appropriate Control switches.W/980729 Ltr ML17229A7981998-06-30030 June 1998 Monthly Operating Repts for June 1998 for St Lucie,Units 1 & 2.W/980713 Ltr ML17229A7701998-05-31031 May 1998 Monthly Operating Repts for May 1998 for St Lucie,Units 1 & 2.W/980612 Ltr ML17229A7411998-05-28028 May 1998 LER 98-004-00:on 980430,discovered Waste Gas Decay Tank Operation W/O Available Oxygen Analyzers,Which Is Prohibited by Ts.Caused by Inadequate Licensee Review of License Amend. Oxygen Analyzer recalibrated.W/980528 Ltr 1999-09-30
[Table view] |
Text
CATEGORY1REGULATORY INFORMATION DISTRIBUTION SYSTEM(RIDS)ACCESSION NBR:9811130285 DOC.DATE:
98/11/04NOTARIZED:
NOFACZL:50-335 St.LuciePlant,Unit1,FloridaPower6LightCo.AUTH.NAMEAUTHORAFFILIATION FREK<FER,K.W.
FloridaPower&LightCo.STALL,J.A.
FloridaPower6LightCo.RECZP.NAME
.RECIPIENT AFFILIATION DOCKET05000335
SUBJECT:
LER98-008-'00:on 981008,inadequate reactorprotection systripbypassTSwasnoted.CausedbypoorlywordedTS.Submitted LARtoclarifypowerrequirements forhighrateofpowertrips.With981104ltr.DISTRIBUTION CODE:IE22TCOPIESRECEIVED:LTR ENCLSIZE:TITLE:50.73/50.9 LicenseeEventReport(LER),ncidentRpt,etc.NOTES:ERECIPIENT IDCODE/NAME PD2-3PDINTERNAL:
ACRSAEOD/SPD/RRABNRR/DE/ECGB NRR/DE/EMEB NRR/DRCH/HOHB NRR/DRPM/PECB RES/DET/EIB EXTERNAL:
LSTLOBBYWARDNOACPOORE,W.NRCPDRCOPIESLTTRENCL1111111111111111111111RECIPIENT ZDCODE/NAME GLEAVES,W AEOD/SPD/RAB CDEEELBNRR/DRCH/HZCB NRR/DRCH/HQMB NRR/DSSA/SPLB RGN2FILE01LZTCOBRYCE,JHNOACQUEENER,DS NUDOCSFULLTXTCOPIESLTTRENCL11221111111111111'1111RD0MI'NOTETOALE"RIDS"RECIPIENTS:
PLEASEHELPUSTOREDUCEWASTE.TOHAVEYOURNAMEORORGANIZATION REMOVEDFROMDISTRIBUTION LISTSORREDUCETHENUMBEROFCOPIESRECEIVEDBYYOUORYOURORGANIZATION, CONTACTTHEDOCUMENTCONTROLDESK(DCD)ONEXTENSION 415-2083FULLTEXTCONVERSION REQUIREDTOTAL,NUMBEROFCOPIESREQUIRED:
LTTR23ENCL23 FloridaPower&LightCompany,6351 S.OceanDrive,JensenBeach.FL34957APLNovember4,1998L-98-28010CFRg50.73U.S.NuclearRegulatory Commission Attn:DocumentControlDeskWashington, D.C.20555Re:St.LucieUnits1and2DocketNos.50-335/389 Reportable Event:1998-008-00 DateofEvent:October8,1998Inadequate ReactorProtection emTriBTechni1ification h.,';",f~.~".;":".+e attachedLicŽensee Eve.'.,;j~>v>
.".p~l0,CFR$
50,73toprovideanttotherequirements ofntReport1998-008isbeingsubmitted pursunotification ofthesubjectevent.ia,-P~Verytrulyyours,J.A.StallVicePresident St.LucieNuclearPlantJAS/EJW/KWF Attachment cc:RegionalAdministrator, USNRCRegionIISeniorResidentInspector, USNRC,St.LucieNuclearPlant98ii130285 98ii04PDRAMCK05000:335 SPDRanFPLGroupcompany
NRCFORM366IS-1999)U.S.NUCLEARREGULATORY COMMISSION LICENSEEEVENTREPORT(LER){Seereverseforrequirednumberofdigits/characters foreachblock)APPROVEDBYOMBNO.3150.0104 EXPIRES06I30l2001 Estimated burdenperresponsetocomplywiththismandalory btfcrmagon collecbon requesl:50hrs.Reportedlessonslearnedareincorporated intoIhelicensing processandfedbacktoIndusby.Fonvardcommentsregarding burdenestimatelotheRecordsManagement Branch(TWF33),US.NudearRegulatory Commission.
Washington.
DC205554001
~andloIhePapenvrsk RedudionProiect(31500104
]OlrceofManagement andBudget,Washington.
OC20503.Ifaninformation cogecgondoesnoldisplayacurrently validOMBcontrolnumber,theNRCmaynotconductorsponsor,sndapersonisnolrequiredtorespondlo,thehformation collection.
FACIUTYNAME(1)St.LucieUnit1DOCKETNUMBER{2)05000335PAGE(3)Page1of4TITLE(4)Inadequate ReactorProtection SystemTripBypassTechnical Specification MONTHDAY10081998EVENTDATE(5LERNUMBER6REPORTDATE7)SEQUENTIAL REVISIONMONTHNUMBERNUMBER1998-008-00OAY041998DOCKETNUMatn05000389DOCKETNUMSERFACIUTVNAMESt.LucieUnit2FACIUTVNAMEOTHERFACILITIES INVOLVED6OPERATING MODE(9)POWERLEVEL{10)10020.2201(b)20.2203(a)
{I)20.2203(a)(2)
(i)20.2203(e)(2)(ii)20.2203(a)(2)
(iii)20.2203(a)(2)
(iv)20.2203(e)
{2)(v)20.2203(a)(3)(i)20.2203(e)(3)
(Ii)20.2203(a)
{4)50.36(c)(1) 50.36(c)(2) 50.73(a)(2)(i)50.73(a)(2)(ii)50.73(a)(2)(iii) 50.73(a)(2)(iv)50.73(a)(2)(v)50.73{a)(2)(vii)50.73(a)(2)(viii)50.73(a)(2)(x)73.71OTHERSpecifyInAbstractbeloworInNRCForm3SSAUIREMENTS OF10CFR9:(Checkoneormoro){11)THISREPORTISSUBMITTEDPURSUANTTOTHEREQNAMEUCENSEECONTACTFORTHISLER12TELEPHONE NUMBERSncludeAresCocci~K.W.Frehafer, Licensing Engineer(561)467-7748COMPLETEONELINEFOREACHCOMPONENT FAILUREDESCRIBED INTHISREPORT13CAUSESYSTEMCOMPONENT MANUFACTURER REPORTABLE TOEPIXCAUSESYSTEMCOMPONENT MANUFACTURER REPORTABLE TOEPIXJCn/aN/ANO6PPTALRORTXPECTED(14)YES(IfYoe,completeEXPECTEDSUBMISSION DATE).NOEXPECTEDSUBMISSION DATE(15)ABSTRACT[Limitto1400spaces,ie.,approximately 15singlespeced typewritten lines/{16)OnOctober8,1998,St.LucieUnits1and2wereinMODE1at100percentreactorpower.FPLdetermined thattheTechnical Specification governing thetripbypasssetpoints forthehighrateofchangeofpowerreactorprotection systemtripwasinerror.TheexplicittermTHERMALPOWERusedintheaffectedTechnical Specification tablenotationrelativetothehighrateofchangeofpowertripbypassfunctioncannotbesatisfied priortoent'ryintoMODE2fromaMODE3condition duetothenormallevelofheattransfertothereactorcoolantasaresultofreactorcoredecayheat.Thetermsofthespecification cannotbeachievedsincedecayheatisnotadirectlymeasurable parameter andthe.operative parameter forremovalofthebypassisexcoreneutronfluxthatismeasuredbythewiderangelogarithmic neutronfluxmonitors.
Duringpastreactorstartups, literalcompliance withtheTechnical Specifications forthehighrateofchangeofpowertripwasnotmet.ThecauseofthiseventwasapoorlywordedTechnical Specification thatdidnotexplicitly excludedecayheatfromthepowerlevelatwhichthehighrateofchangeofpowertripbypassisrequiredtoberemoved.Asacorrective action,St.Luciehasdeveloped andsubmitted anamendment tothelicensetoclarifythepowerrequirements forthehighrateofchangeofpowertrip.Therevisionensuresthatthemeaningof'explicit termsusedintheaffectedTechnical Specifications areconsistent withtheintentofthestatedrequirements basedoneachSt.LuciePlantdesign.NACFORM3SSIS.1999)
INRCFORM366AI8-I888)LICENSEEEVENTREPORT(LER)TEXTCONTINUATION U.S.NUCLEARREGULATORY COMMISSION FAGIUTYNAMEI1)St.LucieUnit1DocKETNUMBER205000335LERNUMBER(6)SEQUENTIAL REVISIONNUMBERNUMBER1998-008-00PAGEI3)Page2of4TEXT(ffmorespeceisrequired, useedditionelcopiesofNRCForm366A/I17)Description ofEventOnOctober8,1998,St.LucieUnits1and2wereinMODE1at100percentreactorpower.FPLdetermined thattheTechnical Specification governing thetripandbypasssetpoints forthehighrateofchangeofpower(HRCP)reactorprotection system(RPS)[BZISIJC]
tripbypasswasinerror.Specifically, theTechnical Specification incorrectly definestheHRCPtripbypassasafunctionofTHERMALPOWER,insteadofindicated widerangelogrithmic power.Therateofchangeofreactorpowerismeasuredbyfourwiderangelogarithmic channels.
Eachchannelindependently monitorstheneutronfluxbyprocessing signalsfromfissionchamberslocatedexternaltothereactorcoreandcoversatendecaderangefromapproximately 10percenttoover100percentoffullpower.Theexcoreneutronfluxinthevicinityofthefissionchambersisproportional totheincorenuclearfissionrateandisnotsignificantly influenced byheattransferfromthecoretothecoolantfromthelong-term decayofradioactive fissionproducts.
Thelogarithmic powerlevelsignalisdifferentiated toproviderateofchangeofpowerinformation.
fromapproximately
-1to+7decadesperminute(DPM)~Theratesignalisprocessed andinputtoabistablethatactuatestheHRCPtripwhentherateofchangeofreactorpowerexceeds2.49decadesperminute.Areactortripisinitiated whenreactorpowerexceedsthesetpointasmeasuredbyanytwowiderangechannels.
Eachwiderangelogarithmic neutronfluxmonitoralsooperatesabistabletodisablethistripbelow10percentpowerand,conversely, ensurethatthisbypassisautomatically removedatgreaterthanorequalto10percentpower.Thetripfeaturemayalsobebypassedabove15percentpower,butsettingandremovingthisbypassisaccomplished bythepowerrangechannels(linear,narrowrangeneutronfluxmonitors) whichalsomonitortheexcoreneutronflux.TheTechnical Specifications defineTHERMALPOWERasthetotalreactorcoreheattransferratetothereactorcoolant.Inadditiontotheheatgenerated bytheincorefissionrate,thisdefinition ofTHERMALPOWBRincludesdecayheatwhichisproducedfromtheradioactive decayofcorefissionproducts.
Forapreviously operatedreactor,decayheatcontinues toexistduringreactorshutdownandwouldtakeseveralyearstodecaytoalevelwherethecoreheattransferratecorresponds to10percent,orless,ofRATEDTHERMALPOWER.Decay'heat isnotadirectlymeasureable parameter, doesnotreflectthereactivity condition ofthereactor,andisnotavariablenormallyassociated withtherateofchangeofreactorpower.Therefore, decayheatisnotsuitableforuseasanoperative parameter forautomatic protective actionsandthereisnoevidencetoindicatethatdecayheatwasconsidered inthedesignoftheHRCPtripfunction.
CauseoftheEventThecauseofthiseventwasapoorlywordedTechnical Specification thatdidnotexplicitly excludedecayheatfromthepowerlevelatwhichtheHRCPtripbypassisrequiredtoberemoved.AnalysisoftheEvent,Thiseventisreportable under10CFR50.73(a)(2)(i)(B) as"anyoperation orcondition prohibited bytheplant'sTechnical Specifications."
Thefollowing NRCFORM388A(8.1888)
NRCFDRM366A(6-1998)LlCENSEEEVENTREPORT(LER)TEXTCONTINUATION U.S.NUCLEARREGULATORY COMMISSION FACILITYNAME(1)St.LucieUnit1DOCKETNUMBER(2)05000335LERNUMBER(8)SEQUENTIAL REVISION'UMBERNUMBER1998-008-00PAGE(3)Page3of4TEXT(ifmorespeceisrequired, useedditionel copiesofiIfRCForm366AI(17)FTechnical Specification tablenotations applytothewiderangelogarithmic neutronfluxmonitorfunctional unit:ForbothUnits:TS1.25:RATEDTHERMALPOWERshallbeatotalreactorcoreheattransferratetothereactorcoolantof2700MWt.TS1.33:THERMALPOWERshallbethetotalreactorcoreheattransferratetothereactorcoolant.TS1.20,OPERATZOMAL MODE:AnOPBRATZOHAL MODE(i.e.,MODE)shallcorrespond toanyoneinclusive combination ofcorereactivity condition, powerlevel,andaveragereactorcoolanttemperature specified inTSTable1'.ZnTABLE1.2,theterm0RATEDTHERMALPOWERismodifiedwithafootnotethatstates,*Excluding decayheat.Unit1:TABLE2.2-1,NOTE(4):Tripmaybebypassedbelow10%andabove15%ofRATEDTHERMALPOWERTABLE3.3-1,Note(d):Tripmaybebypassedbelow100andabove15%ofRATEDTHERMALPOWER)bypassshallbeautomatically removedwhenTHERMALpowerisabove100orbelow15%ofRATEDTHBRKQPOWBR.Unit2:TABLE2.2-2,NOTE(4)andTABLE3.3-7,NOTE(e):Tripmaybebypassedbelow10andabove15%.ofRATEDTHERMALPOWBR;bypassshallbeautomatically removedwhenTHERMALpowerisabove10%orbelow15%ofRATBDTHERMALPOWER.TheHRCPtripwasprovidedwiththeSt.LucieUnit1andUnit2analogRPSas"backupprotection againstpowerexcursion eventsinitiated fromsubcritical conditions.
Thetripisrequiredtobeoperablei.nModes1and2,butmaybebypassedbelow10percentandabove15percentofreactorpower.Assuch,thetripisbasedonboththeOPBRATZONAL MODBofthereactorandonhowfastthemeasuredparameter representing reactorpowerchangesinagiventimeperiod.Thesetpointisspecified inunitsofreactorstartuprate,i.e.,indecadesperminute(DPM).Thestartuprateisobtainedfromthewiderangelogarithmic neutronfluxmonitorswhichmonitortheexcoreneutronflux.Theexcoreneutronfluxisproportional totheincorefissionrate,andtherefore, isproportional tothereactorpowerproducedfromtheincorefissionrate.Duringstartupofacommercial nuclearreactorfromsubcritical conditions, heattransfertothereactorcoolantasaresultofonlythefissionrateistypically insufficient tosignificantly affectthereactorcoolanttemperature whenlessthanapproximately 0.1percentoffullpowerandtherateofchangeofneutronfluxisessentially theonlymeasureable parameter thatprovidesrateofchangeofpowerinformation.
Table1.2ofthefacilityTechnical Specifications definestheOPBRATZOHAL MODBSofplantoperation intermsofreactivity, thermalpower,andaveragecoolanttemperature.
ThetermpercentRATEDTHERMALPOWERisclearlyannotated andfootnoted withanasterisktoclarifythatthenumerical valuesusedinthetableexcludedecayheat.Thisexclusion appliestothepowerlevelthat,inpart,definesMODE2whereintheHRCPtripisrequiredtobeoperableduringreactorstartup.NAGFOAM386A(6-1998)
NRCFORM366A18-1998)LICENSEEEVENTREPORT(LER)TEXTCONTINUATION U.S.NUCUARREGULATORY COMMlSSlON FACIUTYNAMEt1)0OCKETNUMBER2lt.ERNUMBER(6)PAGE(3)St.LucieUnit1SEQUENTIAL REVISIONNUMBERNUMBER050003351998-008-00Page4of4TEXTllfmorespecsisreguired, useedditionel copiesofNRCFerm36&i/I17)Theuseofexcoreneutronfluxasthemeasuredparameter toimplement theHRCPtripfunctionisappropriate, andtheRPSnuclearinstrumentation channelsdesignedtocoverthestartuprangesoftheSt.Luciereactorsarethewiderangelogarithmic neutronfluxmonitors.
Similartodesignfeaturesofthetrip,thepowerlevelatwhichthetripfunctionbypassmustberemovedduringareactorstartupisassociated withtheOPERATIONAL MODBofthereactorandmustbeinarangeofreactorpowerthatwillassuresuccessoftheprotective action.Theonsetofoperability fortheHRCPtripinMODE2duringstartupisatanexcoreneutronfluxthatcorresponds toapproximately 10percentoftheincorefull-power fissionrate.However,thethermalpowerproducedfromthisfissionrateistypically belowtheTHEMQPOWERdefinedbyTS1.33which,absentanexplicitmodifiertoindicateotherwise, includesdecayheat.IntheSt.Luciereactorsfollowing shutdownfromextendedpoweroperations tobelowMODE2,thethermalpowerproducedfromdecayheatistypically higherthanthethermalpowerproducedonlybythefi.ssionrate.Althoughtheexclusion ofdecayheatfromtheHRCptripisimpliedbythedefinition ofOPERATIONAL MODE,literalcompliance withtheTechnical Specification requirements fordefiningtheHRCPtripbypasssetpointasafunctionofTHERMALPOWERwasnotmet.AnalysisofSafetySignificance TheTechnical Specification inadequacy doesnotapplyduringshutdownreactoroperations orMODB1reactoroperation above15percentpower.Currently, bothSt.Lucieunitsareoperating inMIODE1above15percentpower,sonocurrentTechnical Specification compliance issueexists.Duringpastreactorstartups, literalcompliance withtheTechnical Specifications fortheHRCPtripwasnotmet.However,thedesignoftheHRCPtripfunctionanditsautomatic bypassremovalfeatureareassociated withthereactorpowergenerated onlybythefissionprocessandexcludesconsideration ofdecayheat.Decayheatisnotadirectlymeasureable parameter, doesnotreflectthereactivity condition ofthereactor,andisnotavariablenormallyassociated withtherateofchangeofreactorpower.Therefore, thehealthandsafetyofthepublicwerenotaffectedbythisevent.Corrective Actions1.St.Luciehasdeveloped andsubmitted anamendment tothelicensestoclarifythepowerrequirements forthe'HRCPtrip.TheTechni.cal Specification changeswillneedtobeapprovedbytheNRCpriortoanysubsequent unitstartup.2.FPLreviewedtheTechnical Specifications governing theautomatic removalof,andpermissives for,otherRPStripbypassesfortheincorrect useofTHERMALPOWERanddecayheat.Thelicenseamendments submitted inaction(1)abovealsoreplacesthetermTHERMALPOWERwiththepowermeasuredbytheappropriate neutronfluxmonitorforthetripbypassesassociated withtheRPSzeropowermodebypass,localpowerdensitytripbypass,andturbinetripbypass.Additional Information NoneNRCFORM3BBA18-1998)