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| {{#Wiki_filter:~CATEGORY10REGULATORYINFORMATIONDISTRIBUTIONSYSTEM(RIDS)ACCESSIONNBR:9907120142DOC.DATE:99/07/06NOTARIZED:NOFACIL:50-389St.LuciePlant,Unit2,FloridaPower&,LightCo.AUTH.NAMEAUTHORAFFILIATIONFREHAFER,K.W.FloridaPower&.LightCo.STALL,J.A.FloridaPower&LightCo.RECIP.NAMERECIPIENTAFFILIATIONDOCKET05000389 | | {{#Wiki_filter:~CATEGORY10REGULATORY INFORMATION DISTRIBUTION SYSTEM(RIDS)ACCESSION NBR:9907120142 DOC.DATE: |
| | 99/07/06NOTARIZED: |
| | NOFACIL:50-389 St.LuciePlant,Unit2,FloridaPower&,LightCo.AUTH.NAMEAUTHORAFFILIATION FREHAFER,K.W. |
| | FloridaPower&.LightCo.STALL,J.A. |
| | FloridaPower&LightCo.RECIP.NAME RECIPIENT AFFILIATION DOCKET05000389 |
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| ==SUBJECT:== | | ==SUBJECT:== |
| LER99-005-00:on990604,CEAdropresultedinmanualreactortrip.Causedbyproceduralinadequacies.ProcedurechangesareplannedtocorrectlackofproceduralguidanceforCEAsub-grouppowerswitchreplacement.DISTRIBUTIONCODE:IE22TCOPIESRECEIVED:LTRLENCLISIZE:TITLE:50.73/50.9LicenseeEventReport(LER),IncidentRpt,etc.NOTES:ARECIPIENTIDCODE/NAMELPD2-2PDINTERNAL:ACRSNRR/DZPM/IOLBNRR/DSSA/SPLBRES/DRAA/OERABEXTERNAL:LSTLOBBYWARDNOACPOORE,W.NRCPDRCOPIESLTTRENCL1111111111111111RECIPIENTIDCODE/NAMEGLEAVES,WFILECENTE~RNRR'/DRIP/REXBRES/DET/ERABRGN2PILE01LMZTCOMARSHALLNOACQUEENER,DSNUDOCSFULLTXTCOPIESLTTRENCL11111111111111110DNNOTETOALL"RiDS"RFCIPiEN;S:PLEASEHELPUSTOREDUCEWASTE.TOHAVEYOURNAMEORORGAN:ZATiONREMOVEDFROMDiSTRiBUTiONLISTSORREDUCETHENUMBEROFCOPiESRECE:VE".YOUOFLOURCRGANiZATON,CONTACTTHEDOCUMENTCONTROLDESK(DCD)ONEXTENSION415-2063PULLTEXTCONVERSIONREQUIREDTO.ALNUMBEROFCOPIESREQUIRED:LTTR16ENCL16 FloridaPower&LightCompany,6351S.OceanDrive,JensenBeach,FL34967July6,1999L-99-14910CFR550.73U.S.NuclearRegulatoryCommissionAttn:DocumentControlDeskWashington,D.C.20555Re:St.LucieUnit2DocketNo.50-389ReportableEvent:1999-005-00DateofEvent:June4,1999CEADropsResultinManualReactorTriTheattachedLicenseeEventReport1999-005isbeingsubmittedpursuanttotherequirementsof10CFR$50.73toprovidenotificationofthesubjectevent.Verytrulyyours,J.A.StallVicePresidentSt.LucieNuclearPlantJAS/EJW/KWFAttachmentcc:RegionalAdministrator,USNRC,RegionIISeniorResidentInspector,USNRC,St.LucieNuclearPlant'ir907i20i42990706PDRADOCtr050003898PDRanFPLGroupcompany | | LER99-005-00:on 990604,CEA dropresultedinmanualreactortrip.Causedbyprocedural inadequacies. |
| ,f NRCFORM366(6-1996)LICENSEEEVENTREPORT(LER)(Seereverseforrequirednumberofdigits/charactersforeachblock)Estimatedburdenperresponsetocomplywiththismandatoryhfonnsgoncollectionrequest:50hrs.Reportedlessonslearnedsreincorporatedintolhegcenstngprocessandfedbackloindustry.ForwardcommentsregsngngburdenesbmstelotheRecordsManagementBranch(TWF33),US.RudearReguhtoryCommission,Washington,1)C205554001,andlolhePaperworkRer)octanProject(315041M(,OfficeofManagementsndBudget,Washington,DC20503.IfanInformathncollecgondoesnotdisplayacurrentlyvalidOMBcontrolnumber,theNRCmaynotconductorsponsor,andapersonhrnotrequiredlorespondlo,theInfonnsthncollection.U.S.NUCLEARREGULATORYCOMMISSIONAPPROVEDBYOMBNO.3150.0104EXPIRES06/30/2001FACIUTYNAME(1)St.LucieUnit2DOCKETNUMBER(2)05000389PAGE(3)Page1of4TITLE(4)CEADropsResultinManualReactorTripEVENTDATE(5)DAYYEARLERNUMBER6)REPORTDATE7YEARSEQUENTIALREVISIONMONTHNUMBERNUMBERDAYYEARFACIUTyNAMEOTHERFACILITIESINVOLVED(BIDOCKETNUMBER060419991999-005-000706FACiUTYNAMEDOCKETNUMBEROPERATINGMODE(9)POWERLEVEL(10)04950.73(s)(2)(viii)50.73(e)(2)(x)50.73(a)(2)(i)50.73(e)(2)(ii)50.73(e)(2)(ui)20.2203(e)(2)(v)20.2203(s)(3)(i)20.2203(a)(3)(ii)20.2201(b)20.2203(e)(1)20.2203(e)(2)(i)73.71THISREPORTISSUBMITTEDPURSUANTTOTHEREQUIREMENTSOF10CFR5:(Checkoneormore)(11)20.2203(e)(2)(ii)20.2203(a)(2)(iii)20.2203(s)(2)(iv)20.2203(s)(4)50.36(c)(1)50.36(c)(2)50.73(e)(2)(iv)50.73(s)(2)(v)50.73(e)(2)(vii)OTHERSpecifyinAbstractbeloworlnNACForm366ANAMELICENSEECONTACTFORTHISLER(12)TELEPHONENUMSERtiricrvtroAreeCodatKennethW.Frehafer,LicensingEngineer(561)467-7748COMPLETEONELINEFOREACHCOMPONENTFAILUREDESCRIBEDINTHISREPORT13CAUSESYSTEMCOMPONENTMANUFACTURERAEPOATABLETOEPIXCAUSESYSTEMCOMPONENTMANUFACTURERREPORTABLEToEPIXC490YESDSUPPLEMENTALREPORTEXPECTED(14)YES(Ifyes,completeEXPECTEDSUBMISSIONDATE).XNOEXPECTEDSUBMISSIONDATE(15)MONTHDAYABSTRACT/Limitto1400speces,le.,approximately15single-spacedtypewrittenlines/(16)OnJune4,1999,St.LucieUnit2wasinMode1atapproximately49percentreactorpower.Aneventresponseteamwasintheprocessoftroubleshootingrecentcontrolelementassemblyanomalies.Unit2washeldinreducedpowerpendingtheeventresponseteamtroubleshootingresults.At0313hours,foursubgroup21controlelementassembliesfullyinsertedintothecoreduringreplacementofthesubgroup21powersupply.AUtilitylicensedoperator,thenuclearplantsupervisor,immediatelydirectedamanualreactortrip.TheplantwasstabilizedinMode3forrepairs.Repairswereimplemented,andplantrestartandpowerascensioncommencedonJune11,1999.Thecontrolelementassemblydropeventwascausedbyproceduralinadequaciesthatdidnotrequireverificationoftheproperseatingofapowerswitch.Thisresultedinlossofpowertothecontrolelementassemblieswhentheirsubgroupwastransferredofftheholdbus.Lossofpowertothesubgroup21controlelementassemblieswascorrectedbyreseatingthesubgroup21powerswitch.ProcedurechangesareplannedtocorrectthelackofproceduralguidanceforCEAsubgrouppowerswitchreplacement.Theeventresponseteamconductedothercorrectiveactionsrelatedtotheoriginalcontrolelementassemblyanomalies.NACF0AM366(6-1999) | | Procedure changesareplannedtocorrectlackofprocedural guidanceforCEAsub-grouppowerswitchreplacement. |
| NRCFORM366A(6-19991LICENSEEEVENTREPORT(LER)TEXTCONTINUATIONU.S.NUCLEARREGULATORYCOMMISSIONFACILITYNAME(1)St.LucieUnit2DOCKETNUMBERI2)05000389LERNUMBERIS)SEQUENTIALREVISIONNUMBERNUMBER1999-005-00PAGE(3)Page2of4TEXT(Ifmorespeceisrequired,useedditionelcopiesofNRCForm366A/(17)DescriptionoftheEventOnJune4,1999,St.LucieUnit2wasinMode1atapproximately49percentreactorpower.Aneventresponseteam(ERT)wasintheprocessofinvestigatingrecentcontrolelementassembly(CEA)[EIIS:AA]events(aCEAdroptwodaysearlierandCEAsspontaneouslytransferringtotheirlowergrippers).Unit2wasbeingheldinreducedpowerpendingtheERTtroubleshootingresults.TheUnit2controlelementdrivemechani.smcontrolsystem(CEDMCS)isdesignedtocontrolthemovementofthe91controlroddrivemechanisms.Eachcontrolrodmechanismhas5coils,whichengagevariousgripperswithintheCEDMmotortocontrolCEAmovement.Undernormalconditions,theuppergrippermaintainstheCEAinitslastposition.Shouldpowerberemovedfromthisgripper,andtheothergrippersnotengagetoprovidemovement,theCEAwilldropintothecore.Powerforthegrippercoilsisprovidedbymotorgenerator(MG)setsthroughthereactortripswitchgear~TheCEDMpowersourceisthreephase240VACandi.sdesi.gnedasafloatingsystemtotoleratesinglegroundconditions.EachCEAsubgrouputilizesapowerswitchthatpxovidesthree-phasepowerforuptofourCEAs.ThepowerswitchiscontrolledbylogictimingboardsandanautomaticCEAtimingmodule(ACTM)whichdecideswhichcoilstofireduringmovementorholdingofeachCEA.TheACTMreceivesinformationastotheenergyprovidedtothecoilthroughaHalleffecttransduceraroundeachcoilpowercable.ShouldtheACTMseethepossibilityofaroddropitwillautomaticallyapplyadditionalpowerortransfertheCEAtothelowergrippertopreventtherodfromdropping.Thisactionisannunciatedinthecontrolroom.Duringtroubleshootingadecisionwasmadetoinstallasparepowerswitch[EIIS:AA:JX]insubgroup21,whichrequiredtheaffectedCEAstobetransferredtothemaintenanceholdbus.Afterthepowerswitchwasreplaced,,thesubgroup21CEAswereremovedfromtheholdbusandtransferredtosubgroup21whilecoiltraceswereobtained.Itwasobservedthatwiththesubgroup21CEAsontheholdbus,thevisicordertracesimprovedandwiththeCEAspoweredbythesubgroupthetraceswerestilldegraded.TheCEAswereplacedbackonthemaintenanceholdbus.Afterfurthertestingandreplacementofalogicboard,subgroup.21wasremovedfromtheholdbusandtransferredtothesubgroup.At0313hours,allfoursubgroup21CEAsfullyinsertedintothecoreupondeenergizationofthemaintenanceholdbus.Thenuclearplantsupervisor(NPS)immediatelydirectedamanualreactortripandentryintoEmergencyOperatingProcedure(EOP)-1,"StandardPostTripActi.ons".AllsafetyfunctionswereverifiedasbeingmaintainedandEOP-2,"ReactorTripRecovery",wasenteredat0323hours.TheplantwasstabilizedinMode3.Thetripwasdeterminedtobeuncomplicatedwiththeexceptionthefollowingissues:DuringtheperformanceofEOP-1,the2Cmainsteamreheater(MSR)temperaturecontrolvalve(TCV)blockvalve[EIIS:SB:V],MV-08-10,wouldnotclose.Inaccordancewithcontingencyactions,theMSRTCVswereclosed.MV-08-10wassubsequentlyde-energizedandmanuallyclosed.~The"A"sidepressurizerheaters[EIIS:AB:PZR1EHTR]werede-energizedduetoalo-lolevelsignalfromthepressurizerlevel"X"channel.However,thesignalwasnotresetwhenpressurizerlevelwasraisedabovethesetpoint.A72-houractionNRCFOIIMSBBA(9-1999) | | DISTRIBUTION CODE:IE22TCOPIESRECEIVED:LTR LENCLISIZE:TITLE:50.73/50.9 LicenseeEventReport(LER),IncidentRpt,etc.NOTES:ARECIPIENT IDCODE/NAME LPD2-2PDINTERNAL: |
| | ACRSNRR/DZPM/IOLB NRR/DSSA/SPLB RES/DRAA/OERAB EXTERNAL: |
| | LSTLOBBYWARDNOACPOORE,W.NRCPDRCOPIESLTTRENCL1111111111111111RECIPIENT IDCODE/NAME GLEAVES,W FILECENTE~RNRR'/DRIP/REXB RES/DET/ERAB RGN2PILE01LMZTCOMARSHALLNOACQUEENER,DS NUDOCSFULLTXTCOPIESLTTRENCL11111111111111110DNNOTETOALL"RiDS"RFCIPiEN;S: |
| | PLEASEHELPUSTOREDUCEWASTE.TOHAVEYOURNAMEORORGAN:ZATiON REMOVEDFROMDiSTRiBUTiON LISTSORREDUCETHENUMBEROFCOPiESRECE:VE".YOUOFLOURCRGANiZAT ON,CONTACTTHEDOCUMENTCONTROLDESK(DCD)ONEXTENSION 415-2063PULLTEXTCONVERSION REQUIREDTO.ALNUMBEROFCOPIESREQUIRED: |
| | LTTR16ENCL16 FloridaPower&LightCompany,6351S.OceanDrive,JensenBeach,FL34967July6,1999L-99-14910CFR550.73U.S.NuclearRegulatory Commission Attn:DocumentControlDeskWashington, D.C.20555Re:St.LucieUnit2DocketNo.50-389Reportable Event:1999-005-00 DateofEvent:June4,1999CEADropsResultinManualReactorTriTheattachedLicenseeEventReport1999-005isbeingsubmitted pursuanttotherequirements of10CFR$50.73toprovidenotification ofthesubjectevent.Verytrulyyours,J.A.StallVicePresident St.LucieNuclearPlantJAS/EJW/KWF Attachment cc:RegionalAdministrator, USNRC,RegionIISeniorResidentInspector, USNRC,St.LucieNuclearPlant'ir907i20i42 990706PDRADOCtr050003898PDRanFPLGroupcompany |
| | ,f NRCFORM366(6-1996)LICENSEEEVENTREPORT(LER)(Seereverseforrequirednumberofdigits/characters foreachblock)Estimated burdenperresponsetocomplywiththismandatory hfonnsgon collection request:50hrs.Reportedlessonslearnedsreincorporated intolhegcenstngprocessandfedbackloindustry. |
| | ForwardcommentsregsngngburdenesbmstelotheRecordsManagement Branch(TWF33),US.RudearReguhtory Commission, Washington, 1)C205554001, andlolhePaperwork Rer)octan Project(315041M(, |
| | OfficeofManagement sndBudget,Washington, DC20503.IfanInformathn collecgon doesnotdisplayacurrently validOMBcontrolnumber,theNRCmaynotconductorsponsor,andapersonhrnotrequiredlorespondlo,theInfonnsthn collection. |
| | U.S.NUCLEARREGULATORY COMMISSION APPROVEDBYOMBNO.3150.0104 EXPIRES06/30/2001 FACIUTYNAME(1)St.LucieUnit2DOCKETNUMBER(2)05000389PAGE(3)Page1of4TITLE(4)CEADropsResultinManualReactorTripEVENTDATE(5)DAYYEARLERNUMBER6)REPORTDATE7YEARSEQUENTIAL REVISIONMONTHNUMBERNUMBERDAYYEARFACIUTyNAMEOTHERFACILITIES INVOLVED(BIDOCKETNUMBER060419991999-005-000706FACiUTYNAMEDOCKETNUMBEROPERATING MODE(9)POWERLEVEL(10)04950.73(s)(2)(viii) 50.73(e)(2)(x)50.73(a)(2)(i)50.73(e)(2)(ii)50.73(e)(2)(ui) 20.2203(e) |
| | (2)(v)20.2203(s) |
| | (3)(i)20.2203(a)(3) |
| | (ii)20.2201(b) 20.2203(e)(1) 20.2203(e)(2)(i) 73.71THISREPORTISSUBMITTED PURSUANTTOTHEREQUIREMENTS OF10CFR5:(Checkoneormore)(11)20.2203(e)(2)(ii)20.2203(a)(2)(iii)20.2203(s)(2)(iv)20.2203(s)(4) 50.36(c)(1) 50.36(c)(2) 50.73(e)(2)(iv) 50.73(s)(2)(v)50.73(e)(2) |
| | (vii)OTHERSpecifyinAbstractbeloworlnNACForm366ANAMELICENSEECONTACTFORTHISLER(12)TELEPHONE NUMSERtiricrvtro AreeCodatKennethW.Frehafer, Licensing Engineer(561)467-7748COMPLETEONELINEFOREACHCOMPONENT FAILUREDESCRIBED INTHISREPORT13CAUSESYSTEMCOMPONENT MANUFACTURER AEPOATABLE TOEPIXCAUSESYSTEMCOMPONENT MANUFACTURER REPORTABLE ToEPIXC490YESDSUPPLEMENTAL REPORTEXPECTED(14)YES(Ifyes,completeEXPECTEDSUBMISSION DATE).XNOEXPECTEDSUBMISSION DATE(15)MONTHDAYABSTRACT/Limitto1400speces,le.,approximately 15single-spaced typewritten lines/(16)OnJune4,1999,St.LucieUnit2wasinMode1atapproximately 49percentreactorpower.Aneventresponseteamwasintheprocessoftroubleshootingrecentcontrolelementassemblyanomalies. |
| | Unit2washeldinreducedpowerpendingtheeventresponseteamtroubleshootingresults.At0313hours,foursubgroup21controlelementassemblies fullyinsertedintothecoreduringreplacement ofthesubgroup21powersupply.AUtilitylicensedoperator, thenuclearplantsupervisor, immediately directedamanualreactortrip.Theplantwasstabilized inMode3forrepairs.Repairswereimplemented, andplantrestartandpowerascension commenced onJune11,1999.Thecontrolelementassemblydropeventwascausedbyprocedural inadequacies thatdidnotrequireverification oftheproperseatingofapowerswitch.Thisresultedinlossofpowertothecontrolelementassemblies whentheirsubgroupwastransferred offtheholdbus.Lossofpowertothesubgroup21controlelementassemblies wascorrected byreseating thesubgroup21powerswitch.Procedure changesareplannedtocorrectthelackofprocedural guidanceforCEAsubgrouppowerswitchreplacement. |
| | Theeventresponseteamconducted othercorrective actionsrelatedtotheoriginalcontrolelementassemblyanomalies. |
| | NACF0AM366(6-1999) |
| | NRCFORM366A(6-19991LICENSEEEVENTREPORT(LER)TEXTCONTINUATION U.S.NUCLEARREGULATORY COMMISSION FACILITYNAME(1)St.LucieUnit2DOCKETNUMBERI2)05000389LERNUMBERIS)SEQUENTIAL REVISIONNUMBERNUMBER1999-005-00PAGE(3)Page2of4TEXT(Ifmorespeceisrequired, useedditionel copiesofNRCForm366A/(17)Description oftheEventOnJune4,1999,St.LucieUnit2wasinMode1atapproximately 49percentreactorpower.Aneventresponseteam(ERT)wasintheprocessofinvestigating recentcontrolelementassembly(CEA)[EIIS:AA] |
| | events(aCEAdroptwodaysearlierandCEAsspontaneously transferring totheirlowergrippers). |
| | Unit2wasbeingheldinreducedpowerpendingtheERTtroubleshootingresults.TheUnit2controlelementdrivemechani.sm controlsystem(CEDMCS)isdesignedtocontrolthemovementofthe91controlroddrivemechanisms. |
| | Eachcontrolrodmechanism has5coils,whichengagevariousgripperswithintheCEDMmotortocontrolCEAmovement. |
| | Undernormalconditions, theuppergrippermaintains theCEAinitslastposition. |
| | Shouldpowerberemovedfromthisgripper,andtheothergrippersnotengagetoprovidemovement, theCEAwilldropintothecore.Powerforthegrippercoilsisprovidedbymotorgenerator (MG)setsthroughthereactortripswitchgear |
| | ~TheCEDMpowersourceisthreephase240VACandi.sdesi.gned asafloatingsystemtotoleratesinglegroundconditions. |
| | EachCEAsubgrouputilizesapowerswitchthatpxovidesthree-phase powerforuptofourCEAs.Thepowerswitchiscontrolled bylogictimingboardsandanautomatic CEAtimingmodule(ACTM)whichdecideswhichcoilstofireduringmovementorholdingofeachCEA.TheACTMreceivesinformation astotheenergyprovidedtothecoilthroughaHalleffecttransducer aroundeachcoilpowercable.ShouldtheACTMseethepossibility ofaroddropitwillautomatically applyadditional powerortransfertheCEAtothelowergrippertopreventtherodfromdropping. |
| | Thisactionisannunciated inthecontrolroom.Duringtroubleshootingadecisionwasmadetoinstallasparepowerswitch[EIIS:AA:JX] |
| | insubgroup21,whichrequiredtheaffectedCEAstobetransferred tothemaintenance holdbus.Afterthepowerswitchwasreplaced,, |
| | thesubgroup21CEAswereremovedfromtheholdbusandtransferred tosubgroup21whilecoiltraceswereobtained. |
| | Itwasobservedthatwiththesubgroup21CEAsontheholdbus,thevisicorder tracesimprovedandwiththeCEAspoweredbythesubgroupthetraceswerestilldegraded. |
| | TheCEAswereplacedbackonthemaintenance holdbus.Afterfurthertestingandreplacement ofalogicboard,subgroup.21wasremovedfromtheholdbusandtransferred tothesubgroup.At0313hours,allfoursubgroup21CEAsfullyinsertedintothecoreupondeenergization ofthemaintenance holdbus.Thenuclearplantsupervisor (NPS)immediately directedamanualreactortripandentryintoEmergency Operating Procedure (EOP)-1,"Standard PostTripActi.ons". |
| | Allsafetyfunctions wereverifiedasbeingmaintained andEOP-2,"ReactorTripRecovery", |
| | wasenteredat0323hours.Theplantwasstabilized inMode3.Thetripwasdetermined tobeuncomplicated withtheexception thefollowing issues:Duringtheperformance ofEOP-1,the2Cmainsteamreheater(MSR)temperature controlvalve(TCV)blockvalve[EIIS:SB:V], |
| | MV-08-10, wouldnotclose.Inaccordance withcontingency actions,theMSRTCVswereclosed.MV-08-10wassubsequently de-energized andmanuallyclosed.~The"A"sidepressurizer heaters[EIIS:AB:PZR1EHTR] |
| | werede-energized duetoalo-lolevelsignalfromthepressurizer level"X"channel.However,thesignalwasnotresetwhenpressurizer levelwasraisedabovethesetpoint. |
| | A72-houractionNRCFOIIMSBBA(9-1999) |
|
| |
|
| NRCFORM366A(6.1998)LICENSEEEVENTREPORT(LER)TEXTCONTINUATIONU.S.NUCLEARREGUIATORYCOMMISSIONFACILITYNAME(1)St.LucieUnit2DOCKETNUMBER(2)05000389LERNUMBER(6)SEQUENTIALREVISIONNUMBERNUMBER1999-005-00PAGE(3)Page3of4TEXTIifmorespacoisrequired,useaddidonalcopiesofNRCPerm366AI(17)DescriptionoftheEvent(cont'd)statementwasenteredinaccordancewithTechnicalSpecification3.4.3at0313hoursonJune4,1999,duetohavinglessthantherequirednumberofpressurizerheatersbeingcapableofbeingpoweredfromaClass1Eelectricbus.CauseoftheEventCEAIssuesSubgroup21CEAsspontaneouslytransferringtotheirlowergripperswascausedbynoisegeneratedbythefailureofthesubgroup21powerswitch.Disassemblyofthepowerswitchindicatedashort,whichmost,likelydevelopedovertimebetweena"C"phasesiliconcontrolledrectifier(SCR)(Q125)anodeandground.Measurementsofthepowerswitch"C"phasetogroundindicateashortedconditionanddetailedinspectionoftheSCR'smylarinsulatingwashershowavisiblebreakdownoftheinsulationandanarcpathtoground.Becausethisconditioncontinuedforsometime,inducinghighnoiselevelsintothesystem,variousACTMcardsinterpretedthisabnormalconditionasunfavorableuppergrippervoltage.Asdesigned,theACTMcardstransferredtheCEAstotheirlowergripperstopreventroddrops.Uponreplacementofthesubgroup21powerswitchandthefailedfuseassociatedwithphase"C"thenoisewasnolongerseenonthesubgroup21CEAs.TheJune4,1999roddropeventwascausedbyalackofproceduralguidancethatshouldhaveverifiedthatthereplacementCEAsubgroup21powerswitchwasproperlyseatedduringtroubleshootingactivities.Theimproperseatingofthepowerswitchwasnotapparentbecausetwicebeforethesubgroup21CEAsweresuccessfullytransferredfromtheholdbustothesubgrouppowerswitchandback.Thezewerenoindicationsthatthepowerswitchwasnotproperlyseated,andthatintermittentpowerwasbeingdeliveredtotheCEAs.Eventually,thelatentintermittentelectricalpowerledtothefullinsertionofthesupgroup21CEAswhentheholdbuswasdeenergized.Post-TriIssuesThefailureofthe2CMSRTCVblockvalve,MV-08-10,toclosewascausedbydirtyauxiliarycontactsintheMCCcontrolcircuit.Thefailureofthe"A"sidepressurizerheaterstoresetonrisingpressurizerlevelwascausedbyafaultycrimpedconnectioninFoxboromoduleLC-1110X.AnalysisoftheEventThiseventisreportableunder10CFR50.73(a)(2)(iv)as"anyeventorconditionthatresultedinamanualorautomaticactuationofanyEngineeredSafetyFeature(ESF),includingtheReactorProtectionSystem(RPS)."AnalysisofSafetySignificanceTheCEDMcontrolsystemdoesnotprovi.deanysafetyrelat'edfunctionsandtheidentifiedproblemswouldnothavepreventedtheaffectedrodsfromdroppingintothecoretoshutdownthereactor.Additionally,thedropofaCEAsubgroupisananalyzedevent.Therefore,thecondit'ionsdescribedabovedidnotpresentanoperabilityconcern.Additionally,duringCEAtroubleshootingactiviti.es,apre-evolutiontailboardwasconductedwithOperationstoinstallasparepower'switchinNRCFORM366A(6.1998) | | NRCFORM366A(6.1998)LICENSEEEVENTREPORT(LER)TEXTCONTINUATION U.S.NUCLEARREGUIATORY COMMISSION FACILITYNAME(1)St.LucieUnit2DOCKETNUMBER(2)05000389LERNUMBER(6)SEQUENTIAL REVISIONNUMBERNUMBER1999-005-00PAGE(3)Page3of4TEXTIifmorespacoisrequired, useaddidonal copiesofNRCPerm366AI(17)Description oftheEvent(cont'd)statement wasenteredinaccordance withTechnical Specification 3.4.3at0313hoursonJune4,1999,duetohavinglessthantherequirednumberofpressurizer heatersbeingcapableofbeingpoweredfromaClass1Eelectricbus.CauseoftheEventCEAIssuesSubgroup21CEAsspontaneously transferring totheirlowergripperswascausedbynoisegenerated bythefailureofthesubgroup21powerswitch.Disassembly ofthepowerswitchindicated ashort,whichmost,likelydeveloped overtimebetweena"C"phasesiliconcontrolled rectifier (SCR)(Q125)anodeandground.Measurements ofthepowerswitch"C"phasetogroundindicateashortedcondition anddetailedinspection oftheSCR'smylarinsulating washershowavisiblebreakdown oftheinsulation andanarcpathtoground.Becausethiscondition continued forsometime,inducinghighnoiselevelsintothesystem,variousACTMcardsinterpreted thisabnormalcondition asunfavorable uppergrippervoltage.Asdesigned, theACTMcardstransferred theCEAstotheirlowergripperstopreventroddrops.Uponreplacement ofthesubgroup21powerswitchandthefailedfuseassociated withphase"C"thenoisewasnolongerseenonthesubgroup21CEAs.TheJune4,1999roddropeventwascausedbyalackofprocedural guidancethatshouldhaveverifiedthatthereplacement CEAsubgroup21powerswitchwasproperlyseatedduringtroubleshootingactivities. |
| ~NRCFORM366A(6-1998)LICENSEEEVENTREPORT(LER)TEXTCONTINUATIONU.S.NUCLEARREGULATORYCOMMISSIONFACILITYNAME('I)St.LucieUnit2DOCKETNUMBER2)05000389LERNUMBER(6)SEQUENTIALREVISIONNUMBERNUMBER1999-005-00PAGE(3)Page4of4TEXT(Ifmorespeceisrequired,useeddi(ionelcopiesofNRCForm366AJ(17)AnalysisofSafetySignificance(cont')subgroup21.Whenallfoursubgroup21CEAsfullyinsertedi,ntothecore,Operationsconfirmedtheroddropindicationandmanuallytrippedthereactorinaccordancewiththepre-evoluti.ontailboard.Basedontheabove,thiseventhadnoimpactonthehealthandsafetyofthepublic.CorrectiveActionsl.AllCEDMCSsubgrouppowerswitcheswereverifiedtohaveproperelectricalandmechanicalcontactunderworkorder(WO)99010204.2.Thesystem(CEAcoils,CEDMpowerdistributionandpowerswitchcomponentsforeachofthe24subgroups)wasverifiedtobefreeofgroundsbyameggerof250Vorgreatertoground.3.Coiltraceswereobtainedduringrodmovementandverifiedtobeofproperwaveform,timing,andthatallphaseswereoperatingsatisfactorily.4.TheauxiliarycontactsforMV-08-10werecleanedunderWO99010433.5.ThepressurizerheatercontrolcircuitrywasrepairedunderWO99010873'.PostmaintenancetestrequirementsazebeingdevelopedforCEAsubgrouppowerswitchesandminimumcheckstobeperformedpriortoremovingaCEAsubgroupfromtheholdbus.7.GuidelinesarebeingdevelopedfortherepairofCEDMCSpowerswitchmodulesincludingproperremovalandinstallation.AdditionalInformationFailedComonentsIdentifiedComponent:Manufacturer:Model:PowerSwitchAssemblyCombustionEngineeringPartNo.35200SimilarEventsNoneNROFOAM3BBA(B.1998)}} | | Theimproperseatingofthepowerswitchwasnotapparentbecausetwicebeforethesubgroup21CEAsweresuccessfully transferred fromtheholdbustothesubgrouppowerswitchandback.Thezewerenoindications thatthepowerswitchwasnotproperlyseated,andthatintermittent powerwasbeingdelivered totheCEAs.Eventually, thelatentintermittent electrical powerledtothefullinsertion ofthesupgroup21CEAswhentheholdbuswasdeenergized. |
| | Post-TriIssuesThefailureofthe2CMSRTCVblockvalve,MV-08-10, toclosewascausedbydirtyauxiliary contactsintheMCCcontrolcircuit.Thefailureofthe"A"sidepressurizer heaterstoresetonrisingpressurizer levelwascausedbyafaultycrimpedconnection inFoxboromoduleLC-1110X. |
| | AnalysisoftheEventThiseventisreportable under10CFR50.73(a)(2)(iv) as"anyeventorcondition thatresultedinamanualorautomatic actuation ofanyEngineered SafetyFeature(ESF),including theReactorProtection System(RPS)."AnalysisofSafetySignificance TheCEDMcontrolsystemdoesnotprovi.deanysafetyrelat'edfunctions andtheidentified problemswouldnothaveprevented theaffectedrodsfromdroppingintothecoretoshutdownthereactor.Additionally, thedropofaCEAsubgroupisananalyzedevent.Therefore, thecondit'ions described abovedidnotpresentanoperability concern.Additionally, duringCEAtroubleshootingactiviti.es, apre-evolution tailboard wasconducted withOperations toinstallasparepower'switch inNRCFORM366A(6.1998) |
| | ~NRCFORM366A(6-1998)LICENSEEEVENTREPORT(LER)TEXTCONTINUATION U.S.NUCLEARREGULATORY COMMISSION FACILITYNAME('I)St.LucieUnit2DOCKETNUMBER2)05000389LERNUMBER(6)SEQUENTIAL REVISIONNUMBERNUMBER1999-005-00PAGE(3)Page4of4TEXT(Ifmorespeceisrequired, useeddi(ionel copiesofNRCForm366AJ(17)AnalysisofSafetySignificance (cont')subgroup21.Whenallfoursubgroup21CEAsfullyinsertedi,ntothecore,Operations confirmed theroddropindication andmanuallytrippedthereactorinaccordance withthepre-evoluti.on tailboard. |
| | Basedontheabove,thiseventhadnoimpactonthehealthandsafetyofthepublic.Corrective Actionsl.AllCEDMCSsubgrouppowerswitcheswereverifiedtohaveproperelectrical andmechanical contactunderworkorder(WO)99010204. |
| | 2.Thesystem(CEAcoils,CEDMpowerdistribution andpowerswitchcomponents foreachofthe24subgroups)wasverifiedtobefreeofgroundsbyameggerof250Vorgreatertoground.3.Coiltraceswereobtainedduringrodmovementandverifiedtobeofproperwaveform, timing,andthatallphaseswereoperating satisfactorily. |
| | 4.Theauxiliary contactsforMV-08-10werecleanedunderWO99010433. |
| | 5.Thepressurizer heatercontrolcircuitry wasrepairedunderWO99010873'.Postmaintenance testrequirements azebeingdeveloped forCEAsubgrouppowerswitchesandminimumcheckstobeperformed priortoremovingaCEAsubgroupfromtheholdbus.7.Guidelines arebeingdeveloped fortherepairofCEDMCSpowerswitchmodulesincluding properremovalandinstallation. |
| | Additional Information FailedComonentsIdentified Component: |
| | Manufacturer: |
| | Model:PowerSwitchAssemblyCombustion Engineering PartNo.35200SimilarEventsNoneNROFOAM3BBA(B.1998)}} |
|
|---|
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
~CATEGORY10REGULATORY INFORMATION DISTRIBUTION SYSTEM(RIDS)ACCESSION NBR:9907120142 DOC.DATE:
99/07/06NOTARIZED:
NOFACIL:50-389 St.LuciePlant,Unit2,FloridaPower&,LightCo.AUTH.NAMEAUTHORAFFILIATION FREHAFER,K.W.
FloridaPower&.LightCo.STALL,J.A.
FloridaPower&LightCo.RECIP.NAME RECIPIENT AFFILIATION DOCKET05000389
SUBJECT:
LER99-005-00:on 990604,CEA dropresultedinmanualreactortrip.Causedbyprocedural inadequacies.
Procedure changesareplannedtocorrectlackofprocedural guidanceforCEAsub-grouppowerswitchreplacement.
DISTRIBUTION CODE:IE22TCOPIESRECEIVED:LTR LENCLISIZE:TITLE:50.73/50.9 LicenseeEventReport(LER),IncidentRpt,etc.NOTES:ARECIPIENT IDCODE/NAME LPD2-2PDINTERNAL:
ACRSNRR/DZPM/IOLB NRR/DSSA/SPLB RES/DRAA/OERAB EXTERNAL:
LSTLOBBYWARDNOACPOORE,W.NRCPDRCOPIESLTTRENCL1111111111111111RECIPIENT IDCODE/NAME GLEAVES,W FILECENTE~RNRR'/DRIP/REXB RES/DET/ERAB RGN2PILE01LMZTCOMARSHALLNOACQUEENER,DS NUDOCSFULLTXTCOPIESLTTRENCL11111111111111110DNNOTETOALL"RiDS"RFCIPiEN;S:
PLEASEHELPUSTOREDUCEWASTE.TOHAVEYOURNAMEORORGAN:ZATiON REMOVEDFROMDiSTRiBUTiON LISTSORREDUCETHENUMBEROFCOPiESRECE:VE".YOUOFLOURCRGANiZAT ON,CONTACTTHEDOCUMENTCONTROLDESK(DCD)ONEXTENSION 415-2063PULLTEXTCONVERSION REQUIREDTO.ALNUMBEROFCOPIESREQUIRED:
LTTR16ENCL16 FloridaPower&LightCompany,6351S.OceanDrive,JensenBeach,FL34967July6,1999L-99-14910CFR550.73U.S.NuclearRegulatory Commission Attn:DocumentControlDeskWashington, D.C.20555Re:St.LucieUnit2DocketNo.50-389Reportable Event:1999-005-00 DateofEvent:June4,1999CEADropsResultinManualReactorTriTheattachedLicenseeEventReport1999-005isbeingsubmitted pursuanttotherequirements of10CFR$50.73toprovidenotification ofthesubjectevent.Verytrulyyours,J.A.StallVicePresident St.LucieNuclearPlantJAS/EJW/KWF Attachment cc:RegionalAdministrator, USNRC,RegionIISeniorResidentInspector, USNRC,St.LucieNuclearPlant'ir907i20i42 990706PDRADOCtr050003898PDRanFPLGroupcompany
,f NRCFORM366(6-1996)LICENSEEEVENTREPORT(LER)(Seereverseforrequirednumberofdigits/characters foreachblock)Estimated burdenperresponsetocomplywiththismandatory hfonnsgon collection request:50hrs.Reportedlessonslearnedsreincorporated intolhegcenstngprocessandfedbackloindustry.
ForwardcommentsregsngngburdenesbmstelotheRecordsManagement Branch(TWF33),US.RudearReguhtory Commission, Washington, 1)C205554001, andlolhePaperwork Rer)octan Project(315041M(,
OfficeofManagement sndBudget,Washington, DC20503.IfanInformathn collecgon doesnotdisplayacurrently validOMBcontrolnumber,theNRCmaynotconductorsponsor,andapersonhrnotrequiredlorespondlo,theInfonnsthn collection.
U.S.NUCLEARREGULATORY COMMISSION APPROVEDBYOMBNO.3150.0104 EXPIRES06/30/2001 FACIUTYNAME(1)St.LucieUnit2DOCKETNUMBER(2)05000389PAGE(3)Page1of4TITLE(4)CEADropsResultinManualReactorTripEVENTDATE(5)DAYYEARLERNUMBER6)REPORTDATE7YEARSEQUENTIAL REVISIONMONTHNUMBERNUMBERDAYYEARFACIUTyNAMEOTHERFACILITIES INVOLVED(BIDOCKETNUMBER060419991999-005-000706FACiUTYNAMEDOCKETNUMBEROPERATING MODE(9)POWERLEVEL(10)04950.73(s)(2)(viii) 50.73(e)(2)(x)50.73(a)(2)(i)50.73(e)(2)(ii)50.73(e)(2)(ui) 20.2203(e)
(2)(v)20.2203(s)
(3)(i)20.2203(a)(3)
(ii)20.2201(b) 20.2203(e)(1) 20.2203(e)(2)(i) 73.71THISREPORTISSUBMITTED PURSUANTTOTHEREQUIREMENTS OF10CFR5:(Checkoneormore)(11)20.2203(e)(2)(ii)20.2203(a)(2)(iii)20.2203(s)(2)(iv)20.2203(s)(4) 50.36(c)(1) 50.36(c)(2) 50.73(e)(2)(iv) 50.73(s)(2)(v)50.73(e)(2)
(vii)OTHERSpecifyinAbstractbeloworlnNACForm366ANAMELICENSEECONTACTFORTHISLER(12)TELEPHONE NUMSERtiricrvtro AreeCodatKennethW.Frehafer, Licensing Engineer(561)467-7748COMPLETEONELINEFOREACHCOMPONENT FAILUREDESCRIBED INTHISREPORT13CAUSESYSTEMCOMPONENT MANUFACTURER AEPOATABLE TOEPIXCAUSESYSTEMCOMPONENT MANUFACTURER REPORTABLE ToEPIXC490YESDSUPPLEMENTAL REPORTEXPECTED(14)YES(Ifyes,completeEXPECTEDSUBMISSION DATE).XNOEXPECTEDSUBMISSION DATE(15)MONTHDAYABSTRACT/Limitto1400speces,le.,approximately 15single-spaced typewritten lines/(16)OnJune4,1999,St.LucieUnit2wasinMode1atapproximately 49percentreactorpower.Aneventresponseteamwasintheprocessoftroubleshootingrecentcontrolelementassemblyanomalies.
Unit2washeldinreducedpowerpendingtheeventresponseteamtroubleshootingresults.At0313hours,foursubgroup21controlelementassemblies fullyinsertedintothecoreduringreplacement ofthesubgroup21powersupply.AUtilitylicensedoperator, thenuclearplantsupervisor, immediately directedamanualreactortrip.Theplantwasstabilized inMode3forrepairs.Repairswereimplemented, andplantrestartandpowerascension commenced onJune11,1999.Thecontrolelementassemblydropeventwascausedbyprocedural inadequacies thatdidnotrequireverification oftheproperseatingofapowerswitch.Thisresultedinlossofpowertothecontrolelementassemblies whentheirsubgroupwastransferred offtheholdbus.Lossofpowertothesubgroup21controlelementassemblies wascorrected byreseating thesubgroup21powerswitch.Procedure changesareplannedtocorrectthelackofprocedural guidanceforCEAsubgrouppowerswitchreplacement.
Theeventresponseteamconducted othercorrective actionsrelatedtotheoriginalcontrolelementassemblyanomalies.
NACF0AM366(6-1999)
NRCFORM366A(6-19991LICENSEEEVENTREPORT(LER)TEXTCONTINUATION U.S.NUCLEARREGULATORY COMMISSION FACILITYNAME(1)St.LucieUnit2DOCKETNUMBERI2)05000389LERNUMBERIS)SEQUENTIAL REVISIONNUMBERNUMBER1999-005-00PAGE(3)Page2of4TEXT(Ifmorespeceisrequired, useedditionel copiesofNRCForm366A/(17)Description oftheEventOnJune4,1999,St.LucieUnit2wasinMode1atapproximately 49percentreactorpower.Aneventresponseteam(ERT)wasintheprocessofinvestigating recentcontrolelementassembly(CEA)[EIIS:AA]
events(aCEAdroptwodaysearlierandCEAsspontaneously transferring totheirlowergrippers).
Unit2wasbeingheldinreducedpowerpendingtheERTtroubleshootingresults.TheUnit2controlelementdrivemechani.sm controlsystem(CEDMCS)isdesignedtocontrolthemovementofthe91controlroddrivemechanisms.
Eachcontrolrodmechanism has5coils,whichengagevariousgripperswithintheCEDMmotortocontrolCEAmovement.
Undernormalconditions, theuppergrippermaintains theCEAinitslastposition.
Shouldpowerberemovedfromthisgripper,andtheothergrippersnotengagetoprovidemovement, theCEAwilldropintothecore.Powerforthegrippercoilsisprovidedbymotorgenerator (MG)setsthroughthereactortripswitchgear
~TheCEDMpowersourceisthreephase240VACandi.sdesi.gned asafloatingsystemtotoleratesinglegroundconditions.
EachCEAsubgrouputilizesapowerswitchthatpxovidesthree-phase powerforuptofourCEAs.Thepowerswitchiscontrolled bylogictimingboardsandanautomatic CEAtimingmodule(ACTM)whichdecideswhichcoilstofireduringmovementorholdingofeachCEA.TheACTMreceivesinformation astotheenergyprovidedtothecoilthroughaHalleffecttransducer aroundeachcoilpowercable.ShouldtheACTMseethepossibility ofaroddropitwillautomatically applyadditional powerortransfertheCEAtothelowergrippertopreventtherodfromdropping.
Thisactionisannunciated inthecontrolroom.Duringtroubleshootingadecisionwasmadetoinstallasparepowerswitch[EIIS:AA:JX]
insubgroup21,whichrequiredtheaffectedCEAstobetransferred tothemaintenance holdbus.Afterthepowerswitchwasreplaced,,
thesubgroup21CEAswereremovedfromtheholdbusandtransferred tosubgroup21whilecoiltraceswereobtained.
Itwasobservedthatwiththesubgroup21CEAsontheholdbus,thevisicorder tracesimprovedandwiththeCEAspoweredbythesubgroupthetraceswerestilldegraded.
TheCEAswereplacedbackonthemaintenance holdbus.Afterfurthertestingandreplacement ofalogicboard,subgroup.21wasremovedfromtheholdbusandtransferred tothesubgroup.At0313hours,allfoursubgroup21CEAsfullyinsertedintothecoreupondeenergization ofthemaintenance holdbus.Thenuclearplantsupervisor (NPS)immediately directedamanualreactortripandentryintoEmergency Operating Procedure (EOP)-1,"Standard PostTripActi.ons".
Allsafetyfunctions wereverifiedasbeingmaintained andEOP-2,"ReactorTripRecovery",
wasenteredat0323hours.Theplantwasstabilized inMode3.Thetripwasdetermined tobeuncomplicated withtheexception thefollowing issues:Duringtheperformance ofEOP-1,the2Cmainsteamreheater(MSR)temperature controlvalve(TCV)blockvalve[EIIS:SB:V],
MV-08-10, wouldnotclose.Inaccordance withcontingency actions,theMSRTCVswereclosed.MV-08-10wassubsequently de-energized andmanuallyclosed.~The"A"sidepressurizer heaters[EIIS:AB:PZR1EHTR]
werede-energized duetoalo-lolevelsignalfromthepressurizer level"X"channel.However,thesignalwasnotresetwhenpressurizer levelwasraisedabovethesetpoint.
A72-houractionNRCFOIIMSBBA(9-1999)
NRCFORM366A(6.1998)LICENSEEEVENTREPORT(LER)TEXTCONTINUATION U.S.NUCLEARREGUIATORY COMMISSION FACILITYNAME(1)St.LucieUnit2DOCKETNUMBER(2)05000389LERNUMBER(6)SEQUENTIAL REVISIONNUMBERNUMBER1999-005-00PAGE(3)Page3of4TEXTIifmorespacoisrequired, useaddidonal copiesofNRCPerm366AI(17)Description oftheEvent(cont'd)statement wasenteredinaccordance withTechnical Specification 3.4.3at0313hoursonJune4,1999,duetohavinglessthantherequirednumberofpressurizer heatersbeingcapableofbeingpoweredfromaClass1Eelectricbus.CauseoftheEventCEAIssuesSubgroup21CEAsspontaneously transferring totheirlowergripperswascausedbynoisegenerated bythefailureofthesubgroup21powerswitch.Disassembly ofthepowerswitchindicated ashort,whichmost,likelydeveloped overtimebetweena"C"phasesiliconcontrolled rectifier (SCR)(Q125)anodeandground.Measurements ofthepowerswitch"C"phasetogroundindicateashortedcondition anddetailedinspection oftheSCR'smylarinsulating washershowavisiblebreakdown oftheinsulation andanarcpathtoground.Becausethiscondition continued forsometime,inducinghighnoiselevelsintothesystem,variousACTMcardsinterpreted thisabnormalcondition asunfavorable uppergrippervoltage.Asdesigned, theACTMcardstransferred theCEAstotheirlowergripperstopreventroddrops.Uponreplacement ofthesubgroup21powerswitchandthefailedfuseassociated withphase"C"thenoisewasnolongerseenonthesubgroup21CEAs.TheJune4,1999roddropeventwascausedbyalackofprocedural guidancethatshouldhaveverifiedthatthereplacement CEAsubgroup21powerswitchwasproperlyseatedduringtroubleshootingactivities.
Theimproperseatingofthepowerswitchwasnotapparentbecausetwicebeforethesubgroup21CEAsweresuccessfully transferred fromtheholdbustothesubgrouppowerswitchandback.Thezewerenoindications thatthepowerswitchwasnotproperlyseated,andthatintermittent powerwasbeingdelivered totheCEAs.Eventually, thelatentintermittent electrical powerledtothefullinsertion ofthesupgroup21CEAswhentheholdbuswasdeenergized.
Post-TriIssuesThefailureofthe2CMSRTCVblockvalve,MV-08-10, toclosewascausedbydirtyauxiliary contactsintheMCCcontrolcircuit.Thefailureofthe"A"sidepressurizer heaterstoresetonrisingpressurizer levelwascausedbyafaultycrimpedconnection inFoxboromoduleLC-1110X.
AnalysisoftheEventThiseventisreportable under10CFR50.73(a)(2)(iv) as"anyeventorcondition thatresultedinamanualorautomatic actuation ofanyEngineered SafetyFeature(ESF),including theReactorProtection System(RPS)."AnalysisofSafetySignificance TheCEDMcontrolsystemdoesnotprovi.deanysafetyrelat'edfunctions andtheidentified problemswouldnothaveprevented theaffectedrodsfromdroppingintothecoretoshutdownthereactor.Additionally, thedropofaCEAsubgroupisananalyzedevent.Therefore, thecondit'ions described abovedidnotpresentanoperability concern.Additionally, duringCEAtroubleshootingactiviti.es, apre-evolution tailboard wasconducted withOperations toinstallasparepower'switch inNRCFORM366A(6.1998)
~NRCFORM366A(6-1998)LICENSEEEVENTREPORT(LER)TEXTCONTINUATION U.S.NUCLEARREGULATORY COMMISSION FACILITYNAME('I)St.LucieUnit2DOCKETNUMBER2)05000389LERNUMBER(6)SEQUENTIAL REVISIONNUMBERNUMBER1999-005-00PAGE(3)Page4of4TEXT(Ifmorespeceisrequired, useeddi(ionel copiesofNRCForm366AJ(17)AnalysisofSafetySignificance (cont')subgroup21.Whenallfoursubgroup21CEAsfullyinsertedi,ntothecore,Operations confirmed theroddropindication andmanuallytrippedthereactorinaccordance withthepre-evoluti.on tailboard.
Basedontheabove,thiseventhadnoimpactonthehealthandsafetyofthepublic.Corrective Actionsl.AllCEDMCSsubgrouppowerswitcheswereverifiedtohaveproperelectrical andmechanical contactunderworkorder(WO)99010204.
2.Thesystem(CEAcoils,CEDMpowerdistribution andpowerswitchcomponents foreachofthe24subgroups)wasverifiedtobefreeofgroundsbyameggerof250Vorgreatertoground.3.Coiltraceswereobtainedduringrodmovementandverifiedtobeofproperwaveform, timing,andthatallphaseswereoperating satisfactorily.
4.Theauxiliary contactsforMV-08-10werecleanedunderWO99010433.
5.Thepressurizer heatercontrolcircuitry wasrepairedunderWO99010873'.Postmaintenance testrequirements azebeingdeveloped forCEAsubgrouppowerswitchesandminimumcheckstobeperformed priortoremovingaCEAsubgroupfromtheholdbus.7.Guidelines arebeingdeveloped fortherepairofCEDMCSpowerswitchmodulesincluding properremovalandinstallation.
Additional Information FailedComonentsIdentified Component:
Manufacturer:
Model:PowerSwitchAssemblyCombustion Engineering PartNo.35200SimilarEventsNoneNROFOAM3BBA(B.1998)
