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| {{#Wiki_filter:ACCELERANTDOCUMENTDISTRj:UTIONSYSTEMREGULATINFORMATIONDISTRIBUTIONSTEM(RIDS)ACCESSIONNBR:9305180328DOC.DATE:93/05/10NOTARIZED:NOFACIL:50-335St.LuciePlant,Unit1,FloridaPower&LightCo.AUTH.NAMEAUTHORAFFILIATIONYOUNG,R.J.FloridaPower&LightCo.SAGER,D.A.FloridaPower&LightCo.RECIP.NAMERECIPIENTAFFILIATIONDOCKET¹05000335 | | {{#Wiki_filter:ACCELERANT DOCUMENTDISTRj:UTIONSYSTEMREGULATINFORMATION DISTRIBUTION STEM(RIDS)ACCESSION NBR:9305180328 DOC.DATE: |
| | 93/05/10NOTARIZED: |
| | NOFACIL:50-335 St.LuciePlant,Unit1,FloridaPower&LightCo.AUTH.NAMEAUTHORAFFILIATION YOUNG,R.J. |
| | FloridaPower&LightCo.SAGER,D.A. |
| | FloridaPower&LightCo.RECIP.NAME RECIPIENT AFFILIATION DOCKET¹05000335 |
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| ==SUBJECT:== | | ==SUBJECT:== |
| LER93-004-00:on930409,typodiscoveredinreptusedtodetermineRPSlowRCSflowtripsetpoint.ErrorexistedsinceAug1988.Causedbydesigncontrolinadequacy.Engineeringpackagedevelopedtocorrectcalculations.W/930510ltr.DZSTRZSUTZONCODE:IE22TCOPIESRECEIVED:LTRIENCL/SIZE:TITIE:50.73/50.9LicenseeEventReport(LER),IncidentRpt,etc.NOTES:DRECIPIENTIDCODE/NAMEPD2-2LANORRISgJINTERNAL:ACNWAEOD/DOAAEOD/ROAB/DSPNRR/DE/EMEBNRR/DRCH/HHFBNRR/DRCH/HOLBNRR/DRSS/PRPBNRR/DSSA/SRXBRES/DSIR/EIBEXTERNAL:EG&GBRYCEPJ.HNRCPDRNSICPOOREPW.COPIESLTTRENCL1111221122111111221111221111RECIPIENTIDCODE/NAMEPD2-2PDACRSAEOD/DSP/TPABNRR/DE/EELBNRR/DORS/OEABNRR/DRCH/HICBNRR/DRIL/RPEBNRR.DSSA/SPLB02RGN2FILE01LSTLOBBYWARDNSICMURPHY,G.ANUDOCSFULLTXTCOPIESLTTRENCL11221111111,111111111111.111DDDDNOTETOALL"RIDS"RECIPIENTS:PLEASEHELPUSTOREDUCEWASTE!CONTACTTHEDOCUMENTCONTROLDESK,ROOMPl-37(EXT.504-2065)TOELIMINATEYOURNAMEFROMDISTRIBUTIONLISTSFORDOCUMENTSYOUDON'TNEED!DFULLTEXTCONVERSIONREQUIREDTOTALNUMBEROFCOPIESREQUIRED:LTTR32ENCL32 PP'fMay10,1993L-93-12910CFR50.73U.S.NuclearRegulatoryCommissionAttn:DocumentControlDeskWashington,D.C.20555Re:.St.LucieUnit1DocketNo.50-335ReportableEvent:93-004DateofEvent:April9,1993IncorrectRCSLowFlowTripSetpointduetoaDesinErrorTheattachedLicenseeEventReportisbeingsubmittedpursuanttotherequirementsof10CFR50.73toprovidenotificationofthesubjectevent.Verytrulyyours,4A8a~D.A.gerVicersidentSt.LuePlantDAS/JWH/kwAttachmentcc:StewartD.Ebneter,RegionalAdministrator,USNRCRegionIISeniorResidentInspector,USNRC,St.LuciePlantDAS/PSL8917-931700339305i803289305i0PDRADOCK05000335SPDRanFPLGroupcompany PPPFPLFEOElmloolNRCFormK6(M9)L.S.tEUCLEARREGULATORYCOMMISSIONLICENSEEEVENTREPORT(LER)APPROYOTONENCk0110010IENNPEE'NHNTEETPIATE0NAaENPENINEPCNTETOCEPNCYWITHTI00NfOIEAATlONCCATECSTINTINCEEET.>>0HTESONWNaCONNENTESNONEPNOTAfaENEETTwIEToTHEINOCla0ANTPEPONTENANAKINNTEAANCHTPANIAIANIANAENIPEIANATCNY~WATPNarol.OCIPHENaToTHEPPENWITTNSEOOCTONPNOECTo'110010PACfSCEOfNAMOEIENTPIEIOAXNT.WASPNeOTCPCOCITNELFACILITYNAME(1)St.LucieUnit1DOCKETNUMBER(2)PAGE305000335104(4)IncorrectReactorCoolantSystemLowFlowTripSetpointresultsinaconditionprohibitedbyTechnicalSpecificationsduetoaDesignControlInadequacy.EVENTDATE(5)LERNUMBER(6)REPORTDATE(7)OTHERFACILITIESINVOLVED(8)MOMlHDAY0409OPERATINGMODE(9)YEARYEAR9393SIAL004MONTHDAYYEAR00051093FACILITYNAMESN/AN/A20.402(b)20.405(c)50.73(a)(2)(iv)THISREPORTISSUBMITTEDPURSUANTTOTHEREQUIREMENTSOF10CFR:Checkoneormoreofthefollowin(11)DOCKETNUMBER(S)050000500073.71(b)POWERLEVEL(10)20.405(a)(1)(i)20.405(a)(1)(ii)20.405(a)(1)(iii)20.405(a)(1)(iv)20.405(a)(1)(v)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)(v)50.73(a)(2)(vii)50.73(a)(2)(viii)(A)50.73(a)(2)(viii)(B)50.73(a)(2)(x)73.71(c)OTHER(SpecifyinAbstractbelowandinTextNRCForm366A)NAMELICENSEECONTACTFORTHISLER12RobertJ.Young,ShiftTechnicalAdvisorTELEPONENUMBERAREACODE407465.3550COMPLETEONELINEFOREACHCOMPONENTFAILUREDESCRIBEDINTHISREPORT13CAUSESYSTEMCOMPONENTMANUFAG-REPORTABLETURERTONPRDSCAUSESYSTEMCOMPONENTMANUFAC-REPORTABLElURERTONPRDSSUPPLEMENTALREPORTEXPECTED14IIIEXPECTEDMONIHDAYYEARSUBMISSIONDATE(15)YES(Ifyes,completeEXPECTEDSUBMISSIONDATE)ABSTRACT(Limitto1400spaces.ie.approximatelyfifteensingle-spacetypewrittenlines)(16)OnApril9,1993,St.LucieUnit1wasinMode6whenatypographicalerrorwasdiscoveredbyFPLNuclearEngineeringinareportusedtodeterminetheReactorProtectionSystem(RPS)lowReactorCoolantSystem(RCS)flowtripsetpoint.TechnicalSpecification2.2.1,Table2.2-1statesthatthetripsetpointwillbegreaterthanorequalto95%ofdesignreactorcoolantflow.TheFPLNuclearEngineeringreport,whichdescribedtheconversionofpressuredropacrossthesteamgeneratorstotheRPSlowRCSflowtripsetpoint,containedanincorrectconstant.ThereportwassubsequentlytransmittedtotheplantstaffandtheInstrumentandControlDepartmentadjustedtheRCSlowflowsetpoint.ThiserrorcausedthesettingoftheRCSlowflowtripsetpointtoavalueapproximately3%belowtheminimum95%ofdesignflow.ThissetpointerrorexistedsinceAugust1988.Therootcauseofthiseventwasadesigncontrolinadequacy.Atypographicalerrorwasmadeinthereporttransmittedtotheplantstaff.Theerrorwouldhavebeendiscoveredifthereviewprocessforthetransmittedreporthadundergoneanindependentreview.TheNuclearEngineeringprocesscurrentlyinplacepreventsasimilareventfromoccurringbyrequiringindependentreviewoftransmittedsetpoints.Correctiveactionsforthisevent:AnengineeringevaluationwasperformedthatconcludedthattheoperationofUnit1duringthistimeperiodwaswithintheboundsofthesafetyanalysis.AreviewoftheprocedureusedtodeterminetheUnit2lowRCSflowsetpointverifiedthatitdidnotcontainasimilarerror.Afterareviewofinternalrecords,NuclearEngineeringverifiedthatnootherUnit1or2RPSsetpointchangesweretransmittedtotheplantinerror.AnengineeringpackagewasdevelopedtoprovidethecorrectedcalculationsfordeterminationoftheRPSreactorcoolantsystemlowflowtripsetpoint.InstrumentationandControlpersonnelwillreviseappropriateproceduresandinstallthecorrecttripsetpointintheUnit1RPSpriortoenteringmode2.Priortodiscoveryofthisevent,Engineeringadoptedaprocessrequiringindependentreviewofsetpointsbeforetransmittaltotheplantstaff.FPLFacsimileofNRGForm366(6-89) | | LER93-004-00:on 930409,typo discovered inreptusedtodetermine RPSlowRCSflowtripsetpoint.Error existedsinceAug1988.Caused bydesigncontrolinadequacy. |
| FPLFsaslnilsofNRCFormSEI(&89)U.S.NUCLEARREGULATORYCOMMISSIONLICENSEEEVENTREPORT(LER)TEXTCONTINUATIONAsswosf0oeIxsssssCIssfxssus'asssfSTAIATf0OATCENsfilINSAONsfToCOINETWITHsissSfCWNATTCNCasEfCOONIfoUECTIsfsIsxsssxswNecoNNENTsIKOANowoEssesNfsoNATEToTIOINcsxsssNeISAONTSNANACEsfNTfssANCHTASTCEuaNXXENTIuauATEXTT~wAEINeTON.OossssfNeToTIOSNEIIwowIsoucwoNTwofcsETIsseIsssasrscfosswNACEISNTNeTseofs.WANNesfsfocssexsFACILITYNAME(1)St.LucieUnit1DOCKETNUMBER(2)YEARLERNUMBER(6)gEQUENTIALNUMBERREVISIONNUMBERPAGE(3)0500033593TEXT(lfmorespaceisrequired,useadditionalNRCForm366A's)(1/)004000204OnApril9,1993,withUnit1inMode6,FPLNuclearEngineeringperformedareviewofthecalculationsthatarecontainedintheSt.LucieUnit1LowFlowTripSetpointCalibrationGuidelines.Thereviewwasbeingperformedtosupportaproposedchangetothesteamgeneratortubepluggingcriteria.Duringthisreview,atypographicalerrorinareportthatdescribedconversionofpressuredropacrosstheSteamGenerators(EIIS:AB)totheReactorProtectionSystem(RPS)(EIIS:JC)ReactorCoolantSystem(RCS)lowflowtripsetpointwasfound.Theerrorresultedinthecalculationofanon-conservativesetpointwithwhichtheRPScreatesanautomaticreactortriptoprotectagainstalossofRCSflow.ThiserrorcausedtheRPSlowRCSflowtripsetpointtobeapproximately3percentbelowtheTechnicalSpecificationminimumof95percentofdesignflow.In1987thereportcontainingtheincorrectinformationwassenttotheplantstafftosupportamodificationtotheRPS.InAugust1988,thereportwasreferencedwhenthemodificationtotheRPSwasimplementedandwasusedtomodifyplantproceduresfortheinitialsettingandsubsequentmonthlychecksofthisRPSlowflowtripsetpoint.ThisconditionwasdiscoveredinAprilof1993.Therootcauseofthiseventwasadesigncontrolinadequacy.AtypographicalerrorwasmadebyFPLNuclearEngineeringinthetransmittalofacalculatedsetpointtotheplantstaff.Duringatransferofinformationfromanindependentlyverifiedengineeringcalculationtoareport,atranscriptionerrorcausedaconstantthatconvertspressuredropacrosstheSteamGeneratorstothelowRCSflowtripsetpointtobenon-conservative.Theincorrectreportwouldhavebeendiscoveredandcorrectedhadthetransmittedreporttotheplantstaffreceivedthesameindependentreviewthattheoriginalcalculationhadreceived.Priortothediscoveryofthisevent,FPLNuclearEngineeringadoptedtheprocessforrequiringindependentreviewofallsetpointsbeforetransmittaltotheplantstaff.Thiseventisreportableunder10CFR50.73(a)(2)(i)(B),as"Anyoperationorconditionprohibitedbytheplant'sTechnicalSpecifications."TechnicalSpecification2.2.1requiresthattheRPStripsetpointforRCSlowflowbesetatorabove95percentofdesignflow(370,000gpm).Forcycles9,10and11ofUnit1operation,theRCSlowflowtripwaserroneouslysetatslightlyhigherthan92percentofdesignflow.TheRCSlowflowtripsetpointensuresthatforadegradationofRCSflowresultingfromanalyzedtransients,areactortripoccurstopreventdeparturefromnucleateboilingratio(DNBR)safetylimits.TheprocesssignalforthisfunctionisdevelopedfromfourindependentdifferentialpressurechannelswhichmeasurethepressuredropacrosstheprimarysideofbothSteamGenerators.ThetotalSteamGeneratorpressuredropiscomparedwiththelowRCSflowtripsetpoint.Iftwochannelsindicateaflowwhichislessthanthetripsetpoint,anRPStripsignalisinitiated.FPLFacsimileofNRCForm366(6-89)
| | Engineering packagedeveloped tocorrectcalculations.W/930510 ltr.DZSTRZSUTZON CODE:IE22TCOPIESRECEIVED:LTR IENCL/SIZE:TITIE:50.73/50.9 LicenseeEventReport(LER),IncidentRpt,etc.NOTES:DRECIPIENT IDCODE/NAME PD2-2LANORRISgJINTERNAL: |
| FPLFacstmloolNRCFormS66($89)U.S.NUCLEARREGULATORYCOMMrSSIONUCENSEEEVENTREPORT(LER)TEXTCONTINUATION,AAINorrocooNI$$$$oerorcofrfoarrfoeooeTAIATToofvcrNITNIoefcfocToccoe$vTATNoooofrfvAACONcouococNIacracTl$04IeoafoNwrfoccrrrNTofccfrlooroIAATIENoeoNATcToTtoIocofoowo$fafomoNANACT$CNTONANCNreeTCAuaNOCITANIN$$AATONv~wANNIOTCN,oc$0$$aANITollofATNAwrovrIacucocNffvoacI$$$Ioeror$cffICEofIIANAccoaNTAfo$$$$ccr,wANNrcrcfoocToooaFACILITYNAME(1)St.LucieUnit1DOCKETNUMBER(2)YEARLERNUMBER(6)EQUENTIAL-rREVISIONNUMBER4NUMBERPAGE(3)0500033593TEXT(Ifmorespaceisrequired,useadditionalNRCForm366A's)(17)004000304Anevaluation(JPN-PSL1-SEFJ-93-006)wasperformedbyFPLEngineeringtodeterminetheavailablesafetyanalysismarginforthemostlimitingtransients(lossofoffsitepowerandlossofRCSflow)forwhichprotectionisprovidedbytheRCSlowflowtrip.Theresultsshowthattheapproximate3percentsetpointerrorissufficientlyoffsetbyavailableflowmargin.Thus,violationoftheDNBRlimitforalossofoffsitepoweroralossofRCSfloweventwouldnothaveoccurrediftherehadbeenadegradationofRCSfloweventduringthetimeperiodthatthesetpointerrorwasinplace.(AreviewofUnit1reactortripsshowedthattheRCSlowflowtripfunctionwasnotchallengedduringcycles9,10and11.Anadditionalreviewofactualoperatingconditionsduringcycles9,10,and11wasperformedtoensurethatnootherconditionexistedthatwouldfurtheraggravatetheconditiondescribedinthisLER).TheReactorCoolantPump(RCP)(EIIS:P)seizedrotoreventhasbeenreanalyzedbythefuelvendorfora4percentreductionindesignflowandthecorresponding4percentreductionintheRCSlowflowtripsetpoint.TheanalysisshowsthattheacceptancecriteriaforthepostulatedRCPseizedrotoreventwasnotviolated.Therefore,thehealthandsafetyofthepublicwasnotaffectedbythiscondition.1.Priortothediscoveryofthisevent,NuclearEngineeringproceduralizedareviewprocesstoensuretheaccuracyofsetpointsandplantchanges.Thisprocessrequiresanindependentverificationofsetpointsandplantchangesbeforetransmittaltotheplantstaff,andwouldhavedetectedtheerrordescribedinthisreport.2.NuclearEngineeringpreparedanengineeringevaluationanddeterminedthatoperationofUnit1wasboundedbythesafetyanalysesforCycles9,10,and11.3.NuclearEngineeringreviewedinternalrecordsandverifiedthatnootherUnit1or2RPSsetpointchangesweretransmittedtotheplantstaffinerror.4.NuclearEngineeringreviewedtheUnit2RCSLowFlowTripSetpointDeterminationprocedureandverifiedthatitdidnotuseerroneousdata.5.AFPLengineeringpackagewasdevelopedtodocumentandtransmitthecorrectedcalculationfortheUnit1RPSIowRCSflowtripsetpoint.6.TheI&CDepartmentwillreviseprocedures1-0120050and1-1400050~toreflectthecorrectRCSlowflowtripsetpointspriortoUnit1enteringMode2.7.TheI&CDepartmentwillmaketheRPSlowRCSflowtripsetpointchangespriortoUnit1enteringMode2.FPLFacsimileofNRCForm366(6-89) | | ACNWAEOD/DOAAEOD/ROAB/DSP NRR/DE/EMEB NRR/DRCH/HHFB NRR/DRCH/HOLB NRR/DRSS/PRPB NRR/DSSA/SRXB RES/DSIR/EIB EXTERNAL: |
| | EG&GBRYCEPJ.H NRCPDRNSICPOOREPW.COPIESLTTRENCL1111221122111111221111221111RECIPIENT IDCODE/NAME PD2-2PDACRSAEOD/DSP/TPAB NRR/DE/EELB NRR/DORS/OEAB NRR/DRCH/HICB NRR/DRIL/RPEB NRR.DSSA/SPLB 02RGN2FILE01LSTLOBBYWARDNSICMURPHY,G.A NUDOCSFULLTXTCOPIESLTTRENCL11221111111,111111111111.111DDDDNOTETOALL"RIDS"RECIPIENTS: |
| | PLEASEHELPUSTOREDUCEWASTE!CONTACTTHEDOCUMENTCONTROLDESK,ROOMPl-37(EXT.504-2065) |
| | TOELIMINATE YOURNAMEFROMDISTRIBUTION LISTSFORDOCUMENTS YOUDON'TNEED!DFULLTEXTCONVERSION REQUIREDTOTALNUMBEROFCOPIESREQUIRED: |
| | LTTR32ENCL32 PP'fMay10,1993L-93-12910CFR50.73U.S.NuclearRegulatory Commission Attn:DocumentControlDeskWashington, D.C.20555Re:.St.LucieUnit1DocketNo.50-335Reportable Event:93-004DateofEvent:April9,1993Incorrect RCSLowFlowTripSetpointduetoaDesinErrorTheattachedLicenseeEventReportisbeingsubmitted pursuanttotherequirements of10CFR50.73toprovidenotification ofthesubjectevent.Verytrulyyours,4A8a~D.A.gerVicersidentSt.LuePlantDAS/JWH/kw Attachment cc:StewartD.Ebneter,RegionalAdministrator, USNRCRegionIISeniorResidentInspector, USNRC,St.LuciePlantDAS/PSL8917-931700339305i80328 9305i0PDRADOCK05000335SPDRanFPLGroupcompany PPPFPLFEOElmloolNRCFormK6(M9)L.S.tEUCLEARREGULATORY COMMISSION LICENSEEEVENTREPORT(LER)APPROYOTONENCk0110010IENNPEE'NHNT EETPIATE0NAaENPENINEPCNTETOCEPNCYWITHTI00NfOIEAATlON CCATECSTINTINCEEET.>>0 HTESONWNaCONNENTESNONEPNOTAfaENEETTwIE ToTHEINOCla0ANTPEPONTENANAKINNTEAANCHTPANIAIANIANAENIPEIANATCNY~WATPNarol. |
| | OCIPHENaToTHEPPENWITTN SEOOCTONPNOECTo'110010PA CfSCEOfNAMOEIENT PIEIOAXNT.WASPNeOTCPC OCITNELFACILITYNAME(1)St.LucieUnit1DOCKETNUMBER(2)PAGE3050003351 04(4)Incorrect ReactorCoolantSystemLowFlowTripSetpointresultsinacondition prohibited byTechnical Specifications duetoaDesignControlInadequacy. |
| | EVENTDATE(5)LERNUMBER(6)REPORTDATE(7)OTHERFACILITIES INVOLVED(8)MOMlHDAY0409OPERATING MODE(9)YEARYEAR9393SIAL004MONTHDAYYEAR00051093FACILITYNAMESN/AN/A20.402(b) 20.405(c) 50.73(a)(2)(iv) |
| | THISREPORTISSUBMITTED PURSUANTTOTHEREQUIREMENTS OF10CFR:Checkoneormoreofthefollowin(11)DOCKETNUMBER(S) 050000500073.71(b)POWERLEVEL(10)20.405(a)(1 |
| | )(i)20.405(a)(1 |
| | )(ii)20.405(a)(1)(iii) 20.405(a)(1)(iv) 20.405(a)(1)(v) 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)(v) 50.73(a)(2)(vii) 50.73(a)(2)(viii)(A) 50.73(a)(2)(viii)(B) 50.73(a)(2)(x) 73.71(c)OTHER(SpecifyinAbstractbelowandinTextNRCForm366A)NAMELICENSEECONTACTFORTHISLER12RobertJ.Young,ShiftTechnical AdvisorTELEPONENUMBERAREACODE407465.3550COMPLETEONELINEFOREACHCOMPONENT FAILUREDESCRIBED INTHISREPORT13CAUSESYSTEMCOMPONENT MANUFAG-REPORTABLE TURERTONPRDSCAUSESYSTEMCOMPONENT MANUFAC-REPORTABLE lURERTONPRDSSUPPLEMENTAL REPORTEXPECTED14IIIEXPECTEDMONIHDAYYEARSUBMISSION DATE(15)YES(Ifyes,completeEXPECTEDSUBMISSION DATE)ABSTRACT(Limitto1400spaces.ie.approximately fifteensingle-space typewritten lines)(16)OnApril9,1993,St.LucieUnit1wasinMode6whenatypographical errorwasdiscovered byFPLNuclearEngineering inareportusedtodetermine theReactorProtection System(RPS)lowReactorCoolantSystem(RCS)flowtripsetpoint. |
| | Technical Specification 2.2.1,Table2.2-1statesthatthetripsetpointwillbegreaterthanorequalto95%ofdesignreactorcoolantflow.TheFPLNuclearEngineering report,whichdescribed theconversion ofpressuredropacrossthesteamgenerators totheRPSlowRCSflowtripsetpoint, contained anincorrect constant. |
| | Thereportwassubsequently transmitted totheplantstaffandtheInstrument andControlDepartment adjustedtheRCSlowflowsetpoint. |
| | ThiserrorcausedthesettingoftheRCSlowflowtripsetpointtoavalueapproximately 3%belowtheminimum95%ofdesignflow.ThissetpointerrorexistedsinceAugust1988.Therootcauseofthiseventwasadesigncontrolinadequacy. |
| | Atypographical errorwasmadeinthereporttransmitted totheplantstaff.Theerrorwouldhavebeendiscovered ifthereviewprocessforthetransmitted reporthadundergone anindependent review.TheNuclearEngineering processcurrently inplacepreventsasimilareventfromoccurring byrequiring independent reviewoftransmitted setpoints. |
| | Corrective actionsforthisevent:Anengineering evaluation wasperformed thatconcluded thattheoperation ofUnit1duringthistimeperiodwaswithintheboundsofthesafetyanalysis. |
| | Areviewoftheprocedure usedtodetermine theUnit2lowRCSflowsetpointverifiedthatitdidnotcontainasimilarerror.Afterareviewofinternalrecords,NuclearEngineering verifiedthatnootherUnit1or2RPSsetpointchangesweretransmitted totheplantinerror.Anengineering packagewasdeveloped toprovidethecorrected calculations fordetermination oftheRPSreactorcoolantsystemlowflowtripsetpoint. |
| | Instrumentation andControlpersonnel willreviseappropriate procedures andinstallthecorrecttripsetpointintheUnit1RPSpriortoenteringmode2.Priortodiscovery ofthisevent,Engineering adoptedaprocessrequiring independent reviewofsetpoints beforetransmittal totheplantstaff.FPLFacsimile ofNRGForm366(6-89) |
| | FPLFsaslnilsof NRCFormSEI(&89)U.S.NUCLEARREGULATORY COMMISSION LICENSEEEVENTREPORT(LER)TEXTCONTINUATION Asswosf0oeIxsssssCIssfxssus'ass sfSTAIATf0OATCENsfilINSAONsfToCOINETWITHsissSfCWNATTCNCasEfCOONIfoUECTIsfsIsxsssxswNecoNNENTsIKOANowoEssesNfsoNATEToTIOINcsxsssNeISAONTSNANACEsfNTfssANCHTASTCEuaNXXENTIuauATEXTT |
| | ~wAEINeTON.OossssfNeToTIOSNEIIwowIsoucwoNTwofcsETIsseIsssasrscfosswNACEISNT NeTseofs.WANNesfsf ocssexsFACILITYNAME(1)St.LucieUnit1DOCKETNUMBER(2)YEARLERNUMBER(6)gEQUENTIAL NUMBERREVISIONNUMBERPAGE(3)0500033593TEXT(lfmorespaceisrequired, useadditional NRCForm366A's)(1/)004000204OnApril9,1993,withUnit1inMode6,FPLNuclearEngineering performed areviewofthecalculations thatarecontained intheSt.LucieUnit1LowFlowTripSetpointCalibration Guidelines. |
| | Thereviewwasbeingperformed tosupportaproposedchangetothesteamgenerator tubepluggingcriteria. |
| | Duringthisreview,atypographical errorinareportthatdescribed conversion ofpressuredropacrosstheSteamGenerators (EIIS:AB) totheReactorProtection System(RPS)(EIIS:JC)ReactorCoolantSystem(RCS)lowflowtripsetpointwasfound.Theerrorresultedinthecalculation ofanon-conservative setpointwithwhichtheRPScreatesanautomatic reactortriptoprotectagainstalossofRCSflow.ThiserrorcausedtheRPSlowRCSflowtripsetpointtobeapproximately 3percentbelowtheTechnical Specification minimumof95percentofdesignflow.In1987thereportcontaining theincorrect information wassenttotheplantstafftosupportamodification totheRPS.InAugust1988,thereportwasreferenced whenthemodification totheRPSwasimplemented andwasusedtomodifyplantprocedures fortheinitialsettingandsubsequent monthlychecksofthisRPSlowflowtripsetpoint. |
| | Thiscondition wasdiscovered inAprilof1993.Therootcauseofthiseventwasadesigncontrolinadequacy. |
| | Atypographical errorwasmadebyFPLNuclearEngineering inthetransmittal ofacalculated setpointtotheplantstaff.Duringatransferofinformation fromanindependently verifiedengineering calculation toareport,atranscription errorcausedaconstantthatconvertspressuredropacrosstheSteamGenerators tothelowRCSflowtripsetpointtobenon-conservative. |
| | Theincorrect reportwouldhavebeendiscovered andcorrected hadthetransmitted reporttotheplantstaffreceivedthesameindependent reviewthattheoriginalcalculation hadreceived. |
| | Priortothediscovery ofthisevent,FPLNuclearEngineering adoptedtheprocessforrequiring independent reviewofallsetpoints beforetransmittal totheplantstaff.Thiseventisreportable under10CFR50.73(a)(2)(i)(B), |
| | as"Anyoperation orcondition prohibited bytheplant'sTechnical Specifications." |
| | Technical Specification 2.2.1requiresthattheRPStripsetpointforRCSlowflowbesetatorabove95percentofdesignflow(370,000gpm).Forcycles9,10and11ofUnit1operation, theRCSlowflowtripwaserroneously setatslightlyhigherthan92percentofdesignflow.TheRCSlowflowtripsetpointensuresthatforadegradation ofRCSflowresulting fromanalyzedtransients, areactortripoccurstopreventdeparture fromnucleateboilingratio(DNBR)safetylimits.Theprocesssignalforthisfunctionisdeveloped fromfourindependent differential pressurechannelswhichmeasurethepressuredropacrosstheprimarysideofbothSteamGenerators. |
| | ThetotalSteamGenerator pressuredropiscomparedwiththelowRCSflowtripsetpoint. |
| | Iftwochannelsindicateaflowwhichislessthanthetripsetpoint, anRPStripsignalisinitiated. |
| | FPLFacsimile ofNRCForm366(6-89) |
| | FPLFacstmloolNRCFormS66($89)U.S.NUCLEARREGULATORY COMMrSSIONUCENSEEEVENTREPORT(LER)TEXTCONTINUATION |
| | ,AAINorrocooNI$ |
| | $$$oerorcofrfoarrfoeooeTAIATToofvcrNITNIoefcfocToccoe$vTATNoooofrfvAACON couococNIacracTl$04IeoafoNwrfoccrrrNTofccfrlooro IAATIENoeoNATcToTtoIocofoowo$fafomoNANACT$CNTONANCNreeTCAuaNOCITANIN$$AATONv~wANNIOTCN, oc$0$$aANITollofATNAwrovr IacucocNffvoacI$$$Ioeror$cffICEofIIANAccoaNT Afo$$$$ccr,wANNrcrcfo ocToooaFACILITYNAME(1)St.LucieUnit1DOCKETNUMBER(2)YEARLERNUMBER(6)EQUENTIAL |
| | -rREVISIONNUMBER4NUMBERPAGE(3)0500033593 TEXT(Ifmorespaceisrequired, useadditional NRCForm366A's)(17)004000304Anevaluation (JPN-PSL1-SEFJ-93-006) wasperformed byFPLEngineering todetermine theavailable safetyanalysismarginforthemostlimitingtransients (lossofoffsitepowerandlossofRCSflow)forwhichprotection isprovidedbytheRCSlowflowtrip.Theresultsshowthattheapproximate 3percentsetpointerrorissufficiently offsetbyavailable flowmargin.Thus,violation oftheDNBRlimitforalossofoffsitepoweroralossofRCSfloweventwouldnothaveoccurrediftherehadbeenadegradation ofRCSfloweventduringthetimeperiodthatthesetpointerrorwasinplace.(AreviewofUnit1reactortripsshowedthattheRCSlowflowtripfunctionwasnotchallenged duringcycles9,10and11.Anadditional reviewofactualoperating conditions duringcycles9,10,and11wasperformed toensurethatnoothercondition existedthatwouldfurtheraggravate thecondition described inthisLER).TheReactorCoolantPump(RCP)(EIIS:P) seizedrotoreventhasbeenreanalyzed bythefuelvendorfora4percentreduction indesignflowandthecorresponding 4percentreduction intheRCSlowflowtripsetpoint. |
| | Theanalysisshowsthattheacceptance criteriaforthepostulated RCPseizedrotoreventwasnotviolated. |
| | Therefore, thehealthandsafetyofthepublicwasnotaffectedbythiscondition. |
| | 1.Priortothediscovery ofthisevent,NuclearEngineering proceduralized areviewprocesstoensuretheaccuracyofsetpoints andplantchanges.Thisprocessrequiresanindependent verification ofsetpoints andplantchangesbeforetransmittal totheplantstaff,andwouldhavedetectedtheerrordescribed inthisreport.2.NuclearEngineering preparedanengineering evaluation anddetermined thatoperation ofUnit1wasboundedbythesafetyanalysesforCycles9,10,and11.3.NuclearEngineering reviewedinternalrecordsandverifiedthatnootherUnit1or2RPSsetpointchangesweretransmitted totheplantstaffinerror.4.NuclearEngineering reviewedtheUnit2RCSLowFlowTripSetpointDetermination procedure andverifiedthatitdidnotuseerroneous data.5.AFPLengineering packagewasdeveloped todocumentandtransmitthecorrected calculation fortheUnit1RPSIowRCSflowtripsetpoint. |
| | 6.TheI&CDepartment willreviseprocedures 1-0120050 and1-1400050 |
| | ~toreflectthecorrectRCSlowflowtripsetpoints priortoUnit1enteringMode2.7.TheI&CDepartment willmaketheRPSlowRCSflowtripsetpointchangespriortoUnit1enteringMode2.FPLFacsimile ofNRCForm366(6-89) |
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| FPLF55cslrrlloolNRCFormS6BU.S.NUCLEARREGULATORYCOMMrSSION~LICENSEEEVENTREPORT(LER)TEXTCONTINUATIONAPAN5TITOCAONCI$1500505fAASNS:IO00550TWATToTAANNN05IIINSAONICTOGTANAYWoilTIIS005$0AAOONCOTITCOONISISNST:500ITISICAINNoOONNANT0NTOAIIONOTAAoCNTSTYAATSloTININGTAYISAIAIINICNTSNANAGSISNTSNANCHTNINaIASIANATAIIINGAAATGNY~WANNNTTGN.OG505$5N05TOONAAIYNWCa<ISTACTTGNTNOXGTTITIOSTINTTYNCSTNINNAGSINNTAI05TAOGCT,WAONKITTYAOO5050$.FACILITYNAME(1)DOCKETNUMBER(2)LERNUMBER(6)PAGE(3)St.LucieUnit1YEAR':0500033593EQUENTIALNUMBER004.REVISIONUMBER000404TEXT(Ifmorespaceisrequired,useadditionalNRCForm366A's)(1/)NoneAprevioussimilarLERatSt.LucieinvolvingadesignerrorfortheRPSwas:LER335-79-30SteamGeneratorLowLevelRPStripsetpointslessthanTechnicalSpecificationsduetoadesignermr.FPLFacsimileofNRCForm366(6-89)}}
| | FPLF55cslrrllo olNRCFormS6BU.S.NUCLEARREGULATORY COMMrSSION |
| | ~LICENSEEEVENTREPORT(LER)TEXTCONTINUATION APAN5TITO CAONCI$1500505fAASNS:IO00550TWATToTAANNN05IIINSAONICTOGTANAYWoilTIIS005$0AAOONCOTITCOONISISNST:500ITISICAINNoOONNANT0NTOAIIONO TAAoCNTSTYAATSloTININGTAYISAIAIINICNTSNANAGSISNTSNANCHTNINa IASIANATAIIINGAAATGNY |
| | ~WANNNTTGN.OG505$ |
| | 5N05TOONAAIYNWCa<ISTACTTGNTNOXGTTITIOSTINTTYNCS TNINNAGSINNT AI05TAOGCT,WAONKITTYA OO5050$.FACILITYNAME(1)DOCKETNUMBER(2)LERNUMBER(6)PAGE(3)St.LucieUnit1YEAR':0500033593EQUENTIAL NUMBER004.REVISIONUMBER000404TEXT(Ifmorespaceisrequired, useadditional NRCForm366A's)(1/)NoneAprevioussimilarLERatSt.Lucieinvolving adesignerrorfortheRPSwas:LER335-79-30 SteamGenerator LowLevelRPStripsetpoints lessthanTechnical Specifications duetoadesignermr.FPLFacsimile ofNRCForm366(6-89)}} |
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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
ACCELERANT DOCUMENTDISTRj:UTIONSYSTEMREGULATINFORMATION DISTRIBUTION STEM(RIDS)ACCESSION NBR:9305180328 DOC.DATE:
93/05/10NOTARIZED:
NOFACIL:50-335 St.LuciePlant,Unit1,FloridaPower&LightCo.AUTH.NAMEAUTHORAFFILIATION YOUNG,R.J.
FloridaPower&LightCo.SAGER,D.A.
FloridaPower&LightCo.RECIP.NAME RECIPIENT AFFILIATION DOCKET¹05000335
SUBJECT:
LER93-004-00:on 930409,typo discovered inreptusedtodetermine RPSlowRCSflowtripsetpoint.Error existedsinceAug1988.Caused bydesigncontrolinadequacy.
Engineering packagedeveloped tocorrectcalculations.W/930510 ltr.DZSTRZSUTZON CODE:IE22TCOPIESRECEIVED:LTR IENCL/SIZE:TITIE:50.73/50.9 LicenseeEventReport(LER),IncidentRpt,etc.NOTES:DRECIPIENT IDCODE/NAME PD2-2LANORRISgJINTERNAL:
ACNWAEOD/DOAAEOD/ROAB/DSP NRR/DE/EMEB NRR/DRCH/HHFB NRR/DRCH/HOLB NRR/DRSS/PRPB NRR/DSSA/SRXB RES/DSIR/EIB EXTERNAL:
EG&GBRYCEPJ.H NRCPDRNSICPOOREPW.COPIESLTTRENCL1111221122111111221111221111RECIPIENT IDCODE/NAME PD2-2PDACRSAEOD/DSP/TPAB NRR/DE/EELB NRR/DORS/OEAB NRR/DRCH/HICB NRR/DRIL/RPEB NRR.DSSA/SPLB 02RGN2FILE01LSTLOBBYWARDNSICMURPHY,G.A NUDOCSFULLTXTCOPIESLTTRENCL11221111111,111111111111.111DDDDNOTETOALL"RIDS"RECIPIENTS:
PLEASEHELPUSTOREDUCEWASTE!CONTACTTHEDOCUMENTCONTROLDESK,ROOMPl-37(EXT.504-2065)
TOELIMINATE YOURNAMEFROMDISTRIBUTION LISTSFORDOCUMENTS YOUDON'TNEED!DFULLTEXTCONVERSION REQUIREDTOTALNUMBEROFCOPIESREQUIRED:
LTTR32ENCL32 PP'fMay10,1993L-93-12910CFR50.73U.S.NuclearRegulatory Commission Attn:DocumentControlDeskWashington, D.C.20555Re:.St.LucieUnit1DocketNo.50-335Reportable Event:93-004DateofEvent:April9,1993Incorrect RCSLowFlowTripSetpointduetoaDesinErrorTheattachedLicenseeEventReportisbeingsubmitted pursuanttotherequirements of10CFR50.73toprovidenotification ofthesubjectevent.Verytrulyyours,4A8a~D.A.gerVicersidentSt.LuePlantDAS/JWH/kw Attachment cc:StewartD.Ebneter,RegionalAdministrator, USNRCRegionIISeniorResidentInspector, USNRC,St.LuciePlantDAS/PSL8917-931700339305i80328 9305i0PDRADOCK05000335SPDRanFPLGroupcompany PPPFPLFEOElmloolNRCFormK6(M9)L.S.tEUCLEARREGULATORY COMMISSION LICENSEEEVENTREPORT(LER)APPROYOTONENCk0110010IENNPEE'NHNT EETPIATE0NAaENPENINEPCNTETOCEPNCYWITHTI00NfOIEAATlON CCATECSTINTINCEEET.>>0 HTESONWNaCONNENTESNONEPNOTAfaENEETTwIE ToTHEINOCla0ANTPEPONTENANAKINNTEAANCHTPANIAIANIANAENIPEIANATCNY~WATPNarol.
OCIPHENaToTHEPPENWITTN SEOOCTONPNOECTo'110010PA CfSCEOfNAMOEIENT PIEIOAXNT.WASPNeOTCPC OCITNELFACILITYNAME(1)St.LucieUnit1DOCKETNUMBER(2)PAGE3050003351 04(4)Incorrect ReactorCoolantSystemLowFlowTripSetpointresultsinacondition prohibited byTechnical Specifications duetoaDesignControlInadequacy.
EVENTDATE(5)LERNUMBER(6)REPORTDATE(7)OTHERFACILITIES INVOLVED(8)MOMlHDAY0409OPERATING MODE(9)YEARYEAR9393SIAL004MONTHDAYYEAR00051093FACILITYNAMESN/AN/A20.402(b) 20.405(c) 50.73(a)(2)(iv)
THISREPORTISSUBMITTED PURSUANTTOTHEREQUIREMENTS OF10CFR:Checkoneormoreofthefollowin(11)DOCKETNUMBER(S) 050000500073.71(b)POWERLEVEL(10)20.405(a)(1
)(i)20.405(a)(1
)(ii)20.405(a)(1)(iii) 20.405(a)(1)(iv) 20.405(a)(1)(v) 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)(v) 50.73(a)(2)(vii) 50.73(a)(2)(viii)(A) 50.73(a)(2)(viii)(B) 50.73(a)(2)(x) 73.71(c)OTHER(SpecifyinAbstractbelowandinTextNRCForm366A)NAMELICENSEECONTACTFORTHISLER12RobertJ.Young,ShiftTechnical AdvisorTELEPONENUMBERAREACODE407465.3550COMPLETEONELINEFOREACHCOMPONENT FAILUREDESCRIBED INTHISREPORT13CAUSESYSTEMCOMPONENT MANUFAG-REPORTABLE TURERTONPRDSCAUSESYSTEMCOMPONENT MANUFAC-REPORTABLE lURERTONPRDSSUPPLEMENTAL REPORTEXPECTED14IIIEXPECTEDMONIHDAYYEARSUBMISSION DATE(15)YES(Ifyes,completeEXPECTEDSUBMISSION DATE)ABSTRACT(Limitto1400spaces.ie.approximately fifteensingle-space typewritten lines)(16)OnApril9,1993,St.LucieUnit1wasinMode6whenatypographical errorwasdiscovered byFPLNuclearEngineering inareportusedtodetermine theReactorProtection System(RPS)lowReactorCoolantSystem(RCS)flowtripsetpoint.
Technical Specification 2.2.1,Table2.2-1statesthatthetripsetpointwillbegreaterthanorequalto95%ofdesignreactorcoolantflow.TheFPLNuclearEngineering report,whichdescribed theconversion ofpressuredropacrossthesteamgenerators totheRPSlowRCSflowtripsetpoint, contained anincorrect constant.
Thereportwassubsequently transmitted totheplantstaffandtheInstrument andControlDepartment adjustedtheRCSlowflowsetpoint.
ThiserrorcausedthesettingoftheRCSlowflowtripsetpointtoavalueapproximately 3%belowtheminimum95%ofdesignflow.ThissetpointerrorexistedsinceAugust1988.Therootcauseofthiseventwasadesigncontrolinadequacy.
Atypographical errorwasmadeinthereporttransmitted totheplantstaff.Theerrorwouldhavebeendiscovered ifthereviewprocessforthetransmitted reporthadundergone anindependent review.TheNuclearEngineering processcurrently inplacepreventsasimilareventfromoccurring byrequiring independent reviewoftransmitted setpoints.
Corrective actionsforthisevent:Anengineering evaluation wasperformed thatconcluded thattheoperation ofUnit1duringthistimeperiodwaswithintheboundsofthesafetyanalysis.
Areviewoftheprocedure usedtodetermine theUnit2lowRCSflowsetpointverifiedthatitdidnotcontainasimilarerror.Afterareviewofinternalrecords,NuclearEngineering verifiedthatnootherUnit1or2RPSsetpointchangesweretransmitted totheplantinerror.Anengineering packagewasdeveloped toprovidethecorrected calculations fordetermination oftheRPSreactorcoolantsystemlowflowtripsetpoint.
Instrumentation andControlpersonnel willreviseappropriate procedures andinstallthecorrecttripsetpointintheUnit1RPSpriortoenteringmode2.Priortodiscovery ofthisevent,Engineering adoptedaprocessrequiring independent reviewofsetpoints beforetransmittal totheplantstaff.FPLFacsimile ofNRGForm366(6-89)
FPLFsaslnilsof NRCFormSEI(&89)U.S.NUCLEARREGULATORY COMMISSION LICENSEEEVENTREPORT(LER)TEXTCONTINUATION Asswosf0oeIxsssssCIssfxssus'ass sfSTAIATf0OATCENsfilINSAONsfToCOINETWITHsissSfCWNATTCNCasEfCOONIfoUECTIsfsIsxsssxswNecoNNENTsIKOANowoEssesNfsoNATEToTIOINcsxsssNeISAONTSNANACEsfNTfssANCHTASTCEuaNXXENTIuauATEXTT
~wAEINeTON.OossssfNeToTIOSNEIIwowIsoucwoNTwofcsETIsseIsssasrscfosswNACEISNT NeTseofs.WANNesfsf ocssexsFACILITYNAME(1)St.LucieUnit1DOCKETNUMBER(2)YEARLERNUMBER(6)gEQUENTIAL NUMBERREVISIONNUMBERPAGE(3)0500033593TEXT(lfmorespaceisrequired, useadditional NRCForm366A's)(1/)004000204OnApril9,1993,withUnit1inMode6,FPLNuclearEngineering performed areviewofthecalculations thatarecontained intheSt.LucieUnit1LowFlowTripSetpointCalibration Guidelines.
Thereviewwasbeingperformed tosupportaproposedchangetothesteamgenerator tubepluggingcriteria.
Duringthisreview,atypographical errorinareportthatdescribed conversion ofpressuredropacrosstheSteamGenerators (EIIS:AB) totheReactorProtection System(RPS)(EIIS:JC)ReactorCoolantSystem(RCS)lowflowtripsetpointwasfound.Theerrorresultedinthecalculation ofanon-conservative setpointwithwhichtheRPScreatesanautomatic reactortriptoprotectagainstalossofRCSflow.ThiserrorcausedtheRPSlowRCSflowtripsetpointtobeapproximately 3percentbelowtheTechnical Specification minimumof95percentofdesignflow.In1987thereportcontaining theincorrect information wassenttotheplantstafftosupportamodification totheRPS.InAugust1988,thereportwasreferenced whenthemodification totheRPSwasimplemented andwasusedtomodifyplantprocedures fortheinitialsettingandsubsequent monthlychecksofthisRPSlowflowtripsetpoint.
Thiscondition wasdiscovered inAprilof1993.Therootcauseofthiseventwasadesigncontrolinadequacy.
Atypographical errorwasmadebyFPLNuclearEngineering inthetransmittal ofacalculated setpointtotheplantstaff.Duringatransferofinformation fromanindependently verifiedengineering calculation toareport,atranscription errorcausedaconstantthatconvertspressuredropacrosstheSteamGenerators tothelowRCSflowtripsetpointtobenon-conservative.
Theincorrect reportwouldhavebeendiscovered andcorrected hadthetransmitted reporttotheplantstaffreceivedthesameindependent reviewthattheoriginalcalculation hadreceived.
Priortothediscovery ofthisevent,FPLNuclearEngineering adoptedtheprocessforrequiring independent reviewofallsetpoints beforetransmittal totheplantstaff.Thiseventisreportable under10CFR50.73(a)(2)(i)(B),
as"Anyoperation orcondition prohibited bytheplant'sTechnical Specifications."
Technical Specification 2.2.1requiresthattheRPStripsetpointforRCSlowflowbesetatorabove95percentofdesignflow(370,000gpm).Forcycles9,10and11ofUnit1operation, theRCSlowflowtripwaserroneously setatslightlyhigherthan92percentofdesignflow.TheRCSlowflowtripsetpointensuresthatforadegradation ofRCSflowresulting fromanalyzedtransients, areactortripoccurstopreventdeparture fromnucleateboilingratio(DNBR)safetylimits.Theprocesssignalforthisfunctionisdeveloped fromfourindependent differential pressurechannelswhichmeasurethepressuredropacrosstheprimarysideofbothSteamGenerators.
ThetotalSteamGenerator pressuredropiscomparedwiththelowRCSflowtripsetpoint.
Iftwochannelsindicateaflowwhichislessthanthetripsetpoint, anRPStripsignalisinitiated.
FPLFacsimile ofNRCForm366(6-89)
FPLFacstmloolNRCFormS66($89)U.S.NUCLEARREGULATORY COMMrSSIONUCENSEEEVENTREPORT(LER)TEXTCONTINUATION
,AAINorrocooNI$
$$$oerorcofrfoarrfoeooeTAIATToofvcrNITNIoefcfocToccoe$vTATNoooofrfvAACON couococNIacracTl$04IeoafoNwrfoccrrrNTofccfrlooro IAATIENoeoNATcToTtoIocofoowo$fafomoNANACT$CNTONANCNreeTCAuaNOCITANIN$$AATONv~wANNIOTCN, oc$0$$aANITollofATNAwrovr IacucocNffvoacI$$$Ioeror$cffICEofIIANAccoaNT Afo$$$$ccr,wANNrcrcfo ocToooaFACILITYNAME(1)St.LucieUnit1DOCKETNUMBER(2)YEARLERNUMBER(6)EQUENTIAL
-rREVISIONNUMBER4NUMBERPAGE(3)0500033593 TEXT(Ifmorespaceisrequired, useadditional NRCForm366A's)(17)004000304Anevaluation (JPN-PSL1-SEFJ-93-006) wasperformed byFPLEngineering todetermine theavailable safetyanalysismarginforthemostlimitingtransients (lossofoffsitepowerandlossofRCSflow)forwhichprotection isprovidedbytheRCSlowflowtrip.Theresultsshowthattheapproximate 3percentsetpointerrorissufficiently offsetbyavailable flowmargin.Thus,violation oftheDNBRlimitforalossofoffsitepoweroralossofRCSfloweventwouldnothaveoccurrediftherehadbeenadegradation ofRCSfloweventduringthetimeperiodthatthesetpointerrorwasinplace.(AreviewofUnit1reactortripsshowedthattheRCSlowflowtripfunctionwasnotchallenged duringcycles9,10and11.Anadditional reviewofactualoperating conditions duringcycles9,10,and11wasperformed toensurethatnoothercondition existedthatwouldfurtheraggravate thecondition described inthisLER).TheReactorCoolantPump(RCP)(EIIS:P) seizedrotoreventhasbeenreanalyzed bythefuelvendorfora4percentreduction indesignflowandthecorresponding 4percentreduction intheRCSlowflowtripsetpoint.
Theanalysisshowsthattheacceptance criteriaforthepostulated RCPseizedrotoreventwasnotviolated.
Therefore, thehealthandsafetyofthepublicwasnotaffectedbythiscondition.
1.Priortothediscovery ofthisevent,NuclearEngineering proceduralized areviewprocesstoensuretheaccuracyofsetpoints andplantchanges.Thisprocessrequiresanindependent verification ofsetpoints andplantchangesbeforetransmittal totheplantstaff,andwouldhavedetectedtheerrordescribed inthisreport.2.NuclearEngineering preparedanengineering evaluation anddetermined thatoperation ofUnit1wasboundedbythesafetyanalysesforCycles9,10,and11.3.NuclearEngineering reviewedinternalrecordsandverifiedthatnootherUnit1or2RPSsetpointchangesweretransmitted totheplantstaffinerror.4.NuclearEngineering reviewedtheUnit2RCSLowFlowTripSetpointDetermination procedure andverifiedthatitdidnotuseerroneous data.5.AFPLengineering packagewasdeveloped todocumentandtransmitthecorrected calculation fortheUnit1RPSIowRCSflowtripsetpoint.
6.TheI&CDepartment willreviseprocedures 1-0120050 and1-1400050
~toreflectthecorrectRCSlowflowtripsetpoints priortoUnit1enteringMode2.7.TheI&CDepartment willmaketheRPSlowRCSflowtripsetpointchangespriortoUnit1enteringMode2.FPLFacsimile ofNRCForm366(6-89)
FPLF55cslrrllo olNRCFormS6BU.S.NUCLEARREGULATORY COMMrSSION
~LICENSEEEVENTREPORT(LER)TEXTCONTINUATION APAN5TITO CAONCI$1500505fAASNS:IO00550TWATToTAANNN05IIINSAONICTOGTANAYWoilTIIS005$0AAOONCOTITCOONISISNST:500ITISICAINNoOONNANT0NTOAIIONO TAAoCNTSTYAATSloTININGTAYISAIAIINICNTSNANAGSISNTSNANCHTNINa IASIANATAIIINGAAATGNY
~WANNNTTGN.OG505$
5N05TOONAAIYNWCa<ISTACTTGNTNOXGTTITIOSTINTTYNCS TNINNAGSINNT AI05TAOGCT,WAONKITTYA OO5050$.FACILITYNAME(1)DOCKETNUMBER(2)LERNUMBER(6)PAGE(3)St.LucieUnit1YEAR':0500033593EQUENTIAL NUMBER004.REVISIONUMBER000404TEXT(Ifmorespaceisrequired, useadditional NRCForm366A's)(1/)NoneAprevioussimilarLERatSt.Lucieinvolving adesignerrorfortheRPSwas:LER335-79-30 SteamGenerator LowLevelRPStripsetpoints lessthanTechnical Specifications duetoadesignermr.FPLFacsimile ofNRCForm366(6-89)
