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| {{#Wiki_filter:REGULATORYINFORMATIONDISTRIBUTIONSYSTEM(RIDS)ACCESSIONNBR:8907120017DOC.DATE:89/07/05NOTARIZED:NOFACIL:50-389St.LuciePlant,Unit2,FloridaPower&LightCo.AUTH.NAME'UTHORAFFILIATIONHOLIFIELD,C.D..FloridaPower&LightCo.WOODY,C.O.FloridaPower&LightCo.RECIP.NAME'RECIPIENTAFFILIATION | | {{#Wiki_filter:REGULATORY INFORMATION DISTRIBUTION SYSTEM(RIDS)ACCESSION NBR:8907120017 DOC.DATE: |
| | 89/07/05NOTARIZED: |
| | NOFACIL:50-389 St.LuciePlant,Unit2,FloridaPower&LightCo.AUTH.NAME'UTHORAFFILIATION HOLIFIELD,C.D.. |
| | FloridaPower&LightCo.WOODY,C.O. |
| | FloridaPower&LightCo.RECIP.NAME |
| | 'RECIPIENT AFFILIATION |
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| ==SUBJECT:== | | ==SUBJECT:== |
| LER89-004-00:on890605,containmentlocalleakrateexceedsTSduetovalveclosurestopoutofadjustment.DISTRIBUTIONCODE:IE22TCOPIESRECEIVED:LTRENCLSIZE:TITLE:50.73/50.9LicenseeEventReport(LER),ncidentRpt,etc.t~tNOTES'OPIESLTTRENCL1111COPIESLTTRENCL11RECIPIENTIDCODE/NAMEPD2-2LANORRIS,JRECIPIENTIDCODE/NAMEPD2-2PDINTERNAL:ACRSMICHELSON.ACRSWYLIEAEOD/DSP/TPABDEDRONRR/DEST/ADE,8HNRR/DEST/CEB8HNRR/DEST/ICSB7NRR/DEST/MTB9HNRR/DEST/RSB8ENRR/DLPQ/HFB10NRR/DOEA/EAB11NUDOCS-ABSTRACTRES/DSIR/EIBRGN2FILE011111'11111111111111111,.111ACRSMOELLER'EOD/DOAAEOD/ROAB/DSPIRM/DCTS/DABNRR/DEST/ADS7ENRR/DEST/ESB8DNRR/DEST/MEB9HNRR/DESTO''PSB8DNRR/DEST/SGB8DNRR/DLPQ/PEB10NRR~REP/PB10REG02RES/DSR/PRAB22112'21'10111111"1111221.111DOCKET05000389RIDDDEXTERNALEG&GWILLIAMSgSLSTLOBBY'WARDNRCPDRNSICMURPHYgGA4411111'FORDBLDGHOY,ALPDRNSICMAYS,GD'SNOIR'ZOALL''RIDS"R1KXEKENIS:EEZASEHELPUS'IOREDOCE%ASTH!CGMIRCZGHE1XXUMEÃZCDÃGRLDESK,RXNP1-37(EZT.20079)KlEKaIHQQZBACRNAHBPKHDI895GEPXXQNLISTSEQRDOCUMEÃISYOUDCSERTNERD!FULLTEXTCONVERSIONREQUIREDTOTALNUMBEROFCOPIES.REQUIRED:LTTR43ENCL42DD P.O.Box14000,JunoBeach,FL33408.0420JULY,51989L-89-23810CFR50.73U.S.NuclearRegulatoryCommissionAttn:DocumentControlDeskWashington,D.C.20555Gentlemen:Re:St.LucieUnit2DocketNo.50-389ReportableEvent:89-04DateofEvent:'June5,1989ContainmentLocalLeakRateExceedsTechnicalSpecificationsDuetoValveClosureStoOutofAd'ustmentDuetoPersonnelErrorTheattachedLicenseeEventReportisbeingsubmittedpursuanttotherequirementsof10CFR50.73toprovidenotificationofthesubjectevent.Verytrulyyours,.C.0.WoActingniorVicePresident-NuclearCOW/JRH/cmAttachmentcc:StewartD.Ebneter,RegionalAdministrator,RegionII,USNRCSeniorResidentInspector,USNRC,St.LuciePlant/-:907120017S9070PDRADGCK05000389PDCallIlla>><I NRCfornr34494)31LICENSEEEVENTREPORT{LER)U.S.NUCLEARREOULATORYCOMMISSIONAPPROVEDOMSNO,3150410CEXPIRES,'~/31/$5FACILITYNAMElllSt.Lucie,Unit2OOCKEtNUMSER(2)osooo38PAOI1OFTITLE<<)Contaqnmenoca+aaexceesecnacapeericanClosureStoputofAdjustmentDuetoPersonnelErrorEVENTDATE(5ILERNUMSER(5)REtORTDATE(7)OTHERFACILITIESINVOLVEDISIMONTeDAYYEARYEARS40u4N7IAI.NVMSSA"SYR~MONTHOAYNVMSSRYEARFACILITYNAMESN/AOOCRETNuMEER(s>050000598900400078905000OPS.AT(NO1MODE(~I~DIVERypp(10)20.402(4)20A05(~)(IIIII20.405(~)(Il(4)20AOS(~I(Il(ryl)20A05(eIllIIItI20A05(cIIll(yl20AOS(cl50.$5(~)Ill50.35(c)LTI50.73(~I(2(III50.7$(e)(2)(4)50.73(el(21(9(lLICENSEECONTACTFORTHISLER02)50.7$(el(2)IN)50.7$(e)12)(y)50.7$(el(2)(or()50.7$(cl(2)(ySI)(AI50.73(e)12)(y(4)(~I50.7$(~l(2)(el0THEREOUIREMENTSOF10CfR(IrIChtcetiltoririoi'0/lhtltr/owrnf/IllTHISREPORTISSUSMITTEOtuRSUANTT7$.71(~I7$.71I~I0'tHERISotciryinicollrtclOt/OryendinTtet,NRCFOnn3FFllNAMECharlesD.Holifield,ShiftTechnicalAdvisorTELE/NONENUMSERAREACODE407465-35pCOMPLETEONELINEFOREACHCOMPONENTFAILUREDESCRI~EOINTHISREtOR'T(1$lCAUSESYSTEMCOMPONENTMANUFAC.TVRERftORtASLETONPROSYACAVSfSYSTEMCOMtONENTMANVFACTVREREPORTASLETONPROSSuttLEMKNTALRftORTEXtECTEO(1iuEXPECTEDSUSMISSIONDATEUSIMONTiiOAVYEARYESIIIyn,CtetrtrtEXPECTEDSUSMISSIOAIDATE/NOASSTRACTILieitlolc00roectl,I~,,toproeietltryIrlletnpetitIotctcyotwn(NnrinNIll~IOnJune5,1989,at1220,withUnit2inMode1at,100%power,aroutinelocalleakratesurveillancetestwasperformedonContainmentPenetration10.Thispenetration,whichcontainstheexhaustlinefortheContainment.PurgeSystem,issubjecttoTypeCtestingandrevealedan"as-found"leakagerateacrossFCV-25-5inexcessof3,171,840standardcubiccentimetersperminute(SCCM).Thisleakagerateisinexcessoftheallowableleakageof.05La,or48,500SCCM,asperTechnicalSpecification4.6.1.7''herootcauseofthehighmeasuredleakagewaspersonnelerrorinthatthevalveadjustmentstopwasnotproperlylockeddownbycontractorpersonnelwhenthevalvewaspreviouslyadjusted.Acontributingfactorwaslackofguidanceinthetechnicalmanualonhowtotightentheadjustmentscrewlocknut.CorrectiveactionsincludedconfirmingthatthefusesforFCV-25-6(asecondvalveinthecontainmentpurgeexhaustline)werepulled,leaktestingFCV-25-6,adjustingandlockingdownthestopforclosingofFCV-25-5,andre-testingFCV-25-5,withsatisfactoryresults.Atechnicalmanualchangerequestwillalsobesubmitted.NRCfore344/953~ | | LER89-004-00:on 890605,containment localleakrateexceedsTSduetovalveclosurestopoutofadjustment. |
| NRCForm3SSA(943(LICENSEEEVENTREPORTtLER)TEXTCONTINUATIONU.S.NUCLEARRECULATORYCOMMISSICAPPROVEDOMBNO,3150-0(04EXPIRES.'8/31/88FACILITYNAME((IDOCKETNUMBER(2(LERNUMBER(SI~YEAR>>MSECUCNTIAIIN/INUMBERRCvrsroNNUMSC/I~ACE(3)St.Lucie,Unit2TEXTllfmoresrreseiseorrired,rrsosddrdorro/HRC%%drm3/(SA's/((TIosooo89-0040002oF03DESCRIPTIONOFTHEEVENTOnJune5,1989,at1220,withUnit.2inMode1at1004power,aroutinelocalleakratesurveillancetestonContainmentPenetration10revealedaleakagerateacrossFCV-25-5(EIIS:ISV)inexcessof3,171,840StandardCubicCentimetersperMinute(SCCM)whichisthecapacityofthetestequipment.Penetration10containsa48inchexhaustlinefortheContainmentPurgeSystem,withthreebutterflyvalves,twoofwhich(FCV-25-4andFCV-25-5)aresubjecttoTypeCtesting,asperUnit2TechnicalSpecification3.6.1.2.b,Table3.6.-1andSurveillance4.6.1.7.3.LocalleakratetestingisperformedbypressurizingthepipingbetweenFCV-2S-4andFCV-25-5.Testinstrumentationisconnectedtoatesttapbetweenthetwovalves,andthechangeinpressureovertimeisrecordedandusedtocalculatetheleakagerate.Theas-foundleakageofthepenetrationwasinexcessoftheallowableleakageof.05La,or48,500SCCM.InaccordancewithTechnicalSpecification3.6.1.1.7,actionwasundertakentorestoretheleakageratetowithinthespecifiedlimitwithin24hours.AlsoinaccordancewithTechnicalSpecification3.6.3.,thefusesonFCV-25-6,anadditionalvalve.inserieswithFCV-25-5,wereverifiedtobepulledandthisvalvewasleaktested.Followinganadjustment,thevalveseatstopadjustmentscrewwaslockeddown-,andtheleakagerateacrossFCV-25-5wasreducedto200SCCM.CAUSEOFTHEEVENTTherootcauseofthiseventwaspersonnelerrorbycontractormaintenancepersonnelinthatthevalvetraveladjustmentscrewlocknutwasonlyhandtightenedthelasttimethevalvetravelwasadjusted.AcontributingfactortothiseventisthelackofguidanceintheTechnicalManualonhowtotightentheadjustmentscrewlocknut.ThehandtightlocknutallowedthevalvetraveltodriftandresultedintheexcessiveleakageacrossFCV-25-S.Therewerenounusualcharacteristicsoftheworklocationthatdirectlycontributedtothepersonnelerror. | | DISTRIBUTION CODE:IE22TCOPIESRECEIVED:LTR ENCLSIZE:TITLE:50.73/50.9 LicenseeEventReport(LER),ncidentRpt,etc.t~tNOTES'OPIES LTTRENCL1111COPIESLTTRENCL11RECIPIENT IDCODE/NAME PD2-2LANORRIS,JRECIPIENT IDCODE/NAME PD2-2PDINTERNAL: |
| NRCform344AI9431LICENSEENTREPORTILER)TEXTCONTINIONU.S.NUCLEARREOULATORYCOMMISSIOAPPROVEOOMSNO.3I50&I04EXPIRES:4/31/bbPACILITYNAMEIIIOOCKETNUMSERIEILERNUMSERISIYEARIN+l44ovENTIALgP'lfvleloN*'>+rNVM44R~'vNVM44RPACEI3)St.Lucie,Unit2TEXT///moveopocerooovrvorLooo~/enovvo///RCfr>>rrr3/34A9/IITIosooo38989-004-0003oF03ANALYSISOFTHEEVENTThis,eventhasbeendeemedreportableaspertherequirementsof10CFR50.73(a)(2)(i)(B),anyoperationorconditionprohibitedbytheplant'sTechnicalSpecifications.ThepreviouslocalleakratetestingonPenetration10wasperformedwithsatisfactoryresultsduringthenormallyscheduledrefuelingoutagewhichranfromearlyFebruarythroughAprilof1989.Unit2TechnicalSpecificationSurveillanceRequirement4.6.1.7.3"requirestestingof.thePurgeValvestobeconductedat-intervalsofatleastonceper6monthsonastaggeredtestbasis.Therefore,thecontainmentleakagerates,accordingtotherequirementsofthisTechnicalSpecification,weretestedwellwithintheboundsofthespecifiedsurveillanceinterval.ThelimitsforcontainmentleakageratesintheUnit2TechnicalSpecificationsarederivedfromtherequirementsofAppendixJto10CFR50.SincetheothertwovalvesintheContainmentPurgeexhaustlines(FCV-25-4andFCV-25-6)wereoperable,the,containmentisolationsafetyfunctionwasmaintainedandthehealthandsafetyofthepublicwasnotthreatened.CORRECTIVEACTIONS2)3)4)5)OperationspersonnelconfirmedthatthefuseswerepulledonFCV-25-6.TheTechnicalStaffTestGroupleaktestedFCV-25-6.I&CadjustedandlockeddownthestopforclosingofFCV-25-5.TheTechnicalStaffTestGroupre-testedFCV-25-5.TheInstrument-&ControldepartmentwillsubmitachangerequesttovendorTechManual2998-4508toprovidemoreguidanceonadjustingthevalvetravelandlockingdowntheadjustmentscrew..ADDITIONALINFORMATION1~2~ComonentIdentif'cat'onThiseventdidnotinvolveanNPRDSreportablecomponentfailure.PreviousSimilarEventsrForasimilarevent,seeLERN335-87-005,whichpertainstoexcessiveleakagepastacontainmentpurgevalveonUnit.Nl.IIN/lcPO/IM344AI943I}} | | ACRSMICHELSON. |
| | ACRSWYLIEAEOD/DSP/TPAB DEDRONRR/DEST/ADE, 8HNRR/DEST/CEB 8HNRR/DEST/ICSB 7NRR/DEST/MTB 9HNRR/DEST/RSB 8ENRR/DLPQ/HFB 10NRR/DOEA/EAB 11NUDOCS-ABSTRACT RES/DSIR/EIB RGN2FILE011111'11111111111111111,.111ACRSMOELLER'EOD/DOA AEOD/ROAB/DSP IRM/DCTS/DAB NRR/DEST/ADS 7ENRR/DEST/ESB 8DNRR/DEST/MEB 9HNRR/DESTO''PSB 8DNRR/DEST/SGB 8DNRR/DLPQ/PEB 10NRR~REP/PB10REG02RES/DSR/PRAB 22112'21'10111111"1111221.111DOCKET05000389RIDDDEXTERNALEG&GWILLIAMSgSLSTLOBBY'WARDNRCPDRNSICMURPHYgGA4411111'FORDBLDGHOY,ALPDRNSICMAYS,GD'SNOIR'ZOALL''RIDS"R1KXEKENIS: |
| | EEZASEHELPUS'IOREDOCE%ASTH!CGMIRCZGHE1XXUMEÃZCDÃGRLDESK,RXNP1-37(EZT.20079)KlEKaIHQQZB ACRNAHBPKHDI895GEPXXQN LISTSEQRDOCUMEÃIS YOUDCSERTNERD!FULLTEXTCONVERSION REQUIREDTOTALNUMBEROFCOPIES.REQUIRED: |
| | LTTR43ENCL42DD P.O.Box14000, JunoBeach,FL33408.0420 JULY,51989L-89-23810CFR50.73U.S.NuclearRegulatory Commission Attn:DocumentControlDeskWashington, D.C.20555Gentlemen: |
| | Re:St.LucieUnit2DocketNo.50-389Reportable Event:89-04DateofEvent:'June5,1989Containment LocalLeakRateExceedsTechnical Specifications DuetoValveClosureStoOutofAd'ustment DuetoPersonnel ErrorTheattachedLicenseeEventReportisbeingsubmitted pursuanttotherequirements of10CFR50.73toprovidenotification ofthesubjectevent.Verytrulyyours,.C.0.WoActingniorVicePresident |
| | -NuclearCOW/JRH/cm Attachment cc:StewartD.Ebneter,RegionalAdministrator, RegionII,USNRCSeniorResidentInspector, USNRC,St.LuciePlant/-:907120017 S9070PDRADGCK05000389PDCallIlla>><I NRCfornr34494)31LICENSEEEVENTREPORT{LER)U.S.NUCLEARREOULATORY COMMISSION APPROVEDOMSNO,3150410CEXPIRES,'~/31/$5FACILITYNAMElllSt.Lucie,Unit2OOCKEtNUMSER(2)osooo38PAOI1OFTITLE<<)Contaqnmen oca+aaexceesecnacapeericanClosureStoputofAdjustment DuetoPersonnel ErrorEVENTDATE(5ILERNUMSER(5)REtORTDATE(7)OTHERFACILITIES INVOLVEDISIMONTeDAYYEARYEARS40u4N7IAI.NVMSSA"SYR~MONTHOAYNVMSSRYEARFACILITYNAMESN/AOOCRETNuMEER(s> |
| | 050000598900400078905000OPS.AT(NO 1MODE(~I~DIVERypp(10)20.402(4) 20A05(~)(IIIII20.405(~)(Il(4)20AOS(~I(Il(ryl)20A05(eIllIIItI20A05(cIIll(yl20AOS(cl50.$5(~)Ill50.35(c)LTI 50.73(~I(2(III50.7$(e)(2)(4) 50.73(el(21(9(lLICENSEECONTACTFORTHISLER02)50.7$(el(2)IN)50.7$(e)12)(y)50.7$(el(2)(or()50.7$(cl(2)(ySI)(AI50.73(e)12)(y(4) |
| | (~I50.7$(~l(2)(el0THEREOUIREMENTS OF10CfR(IrIChtcetiltoririoi'0/lhtltr/owrnf/ |
| | IllTHISREPORTISSUSMITTEO tuRSUANTT7$.71(~I7$.71I~I0'tHERISotciryinicollrtcl Ot/OryendinTtet,NRCFOnn3FFllNAMECharlesD.Holifield, ShiftTechnical AdvisorTELE/NONENUMSERAREACODE407465-35pCOMPLETEONELINEFOREACHCOMPONENT FAILUREDESCRI~EOINTHISREtOR'T(1$lCAUSESYSTEMCOMPONENT MANUFAC.TVRERftORtASLE TONPROSYACAVSfSYSTEMCOMtONENT MANVFACTVREREPORTASLE TONPROSSuttLEMKNTAL RftORTEXtECTEO(1iuEXPECTEDSUSMISSION DATEUSIMONTiiOAVYEARYESIIIyn,CtetrtrtEXPECTEDSUSMISSIOAI DATE/NOASSTRACTILieitlolc00roectl,I~,,toproeietltry IrlletnpetitIotctcyotwn(Nn rinNIll~IOnJune5,1989,at1220,withUnit2inMode1at,100%power,aroutinelocalleakratesurveillance testwasperformed onContainment Penetration 10.Thispenetration, whichcontainstheexhaustlinefortheContainment. |
| | PurgeSystem,issubjecttoTypeCtestingandrevealedan"as-found" leakagerateacrossFCV-25-5inexcessof3,171,840 standardcubiccentimeters perminute(SCCM).Thisleakagerateisinexcessoftheallowable leakageof.05La,or48,500SCCM,asperTechnical Specification 4.6.1.7''herootcauseofthehighmeasuredleakagewaspersonnel errorinthatthevalveadjustment stopwasnotproperlylockeddownbycontractor personnel whenthevalvewaspreviously adjusted. |
| | Acontributing factorwaslackofguidanceinthetechnical manualonhowtotightentheadjustment screwlocknut.Corrective actionsincludedconfirming thatthefusesforFCV-25-6(asecondvalveinthecontainment purgeexhaustline)werepulled,leaktestingFCV-25-6, adjusting andlockingdownthestopforclosingofFCV-25-5, andre-testing FCV-25-5, withsatisfactory results.Atechnical manualchangerequestwillalsobesubmitted. |
| | NRCfore344/953~ |
| | NRCForm3SSA(943(LICENSEEEVENTREPORTtLER)TEXTCONTINUATION U.S.NUCLEARRECULATORY COMMISSIC APPROVEDOMBNO,3150-0(04 EXPIRES.'8/31/88FACILITYNAME((IDOCKETNUMBER(2(LERNUMBER(SI~YEAR>>MSECUCNTIAI IN/INUMBERRCvrsroNNUMSC/I~ACE(3)St.Lucie,Unit2TEXTllfmoresrreseiseorrired, rrsosddrdorro/ |
| | HRC%%drm3/(SA's/((TIosooo89-0040002oF03DESCRIPTION OFTHEEVENTOnJune5,1989,at1220,withUnit.2inMode1at1004power,aroutinelocalleakratesurveillance testonContainment Penetration 10revealedaleakagerateacrossFCV-25-5(EIIS:ISV) inexcessof3,171,840 StandardCubicCentimeters perMinute(SCCM)whichisthecapacityofthetestequipment. |
| | Penetration 10containsa48inchexhaustlinefortheContainment PurgeSystem,withthreebutterfly valves,twoofwhich(FCV-25-4 andFCV-25-5) aresubjecttoTypeCtesting,asperUnit2Technical Specification 3.6.1.2.b, Table3.6.-1andSurveillance 4.6.1.7.3. |
| | Localleakratetestingisperformed bypressurizing thepipingbetweenFCV-2S-4andFCV-25-5. |
| | Testinstrumentation isconnected toatesttapbetweenthetwovalves,andthechangeinpressureovertimeisrecordedandusedtocalculate theleakagerate.Theas-foundleakageofthepenetration wasinexcessoftheallowable leakageof.05La,or48,500SCCM.Inaccordance withTechnical Specification 3.6.1.1.7, actionwasundertaken torestoretheleakageratetowithinthespecified limitwithin24hours.Alsoinaccordance withTechnical Specification 3.6.3.,thefusesonFCV-25-6, anadditional valve.inserieswithFCV-25-5, wereverifiedtobepulledandthisvalvewasleaktested.Following anadjustment, thevalveseatstopadjustment screwwaslockeddown-,andtheleakagerateacrossFCV-25-5wasreducedto200SCCM.CAUSEOFTHEEVENTTherootcauseofthiseventwaspersonnel errorbycontractor maintenance personnel inthatthevalvetraveladjustment screwlocknutwasonlyhandtightened thelasttimethevalvetravelwasadjusted. |
| | Acontributing factortothiseventisthelackofguidanceintheTechnical Manualonhowtotightentheadjustment screwlocknut.Thehandtightlocknutallowedthevalvetraveltodriftandresultedintheexcessive leakageacrossFCV-25-S. |
| | Therewerenounusualcharacteristics oftheworklocationthatdirectlycontributed tothepersonnel error. |
| | NRCform344AI9431LICENSEENTREPORTILER)TEXTCONTINIONU.S.NUCLEARREOULATORY COMMISSIO APPROVEOOMSNO.3I50&I04EXPIRES:4/31/bbPACILITYNAMEIIIOOCKETNUMSERIEILERNUMSERISIYEARIN+l44ovENTIAL gP'lfvleloN |
| | *'>+rNVM44R~'vNVM44RPACEI3)St.Lucie,Unit2TEXT///moveopocerooovrvorLooo~/enovvo///RC fr>>rrr3/34A9/IITIosooo38989-004-0003oF03ANALYSISOFTHEEVENTThis,eventhasbeendeemedreportable aspertherequirements of10CFR50.73(a)(2)(i)(B),anyoperation orcondition prohibited bytheplant'sTechnical Specifications. |
| | ThepreviouslocalleakratetestingonPenetration 10wasperformed withsatisfactory resultsduringthenormallyscheduled refueling outagewhichranfromearlyFebruarythroughAprilof1989.Unit2Technical Specification Surveillance Requirement 4.6.1.7.3"requires testingof.thePurgeValvestobeconducted at-intervals ofatleastonceper6monthsonastaggered testbasis.Therefore, thecontainment leakagerates,according totherequirements ofthisTechnical Specification, weretestedwellwithintheboundsofthespecified surveillance interval. |
| | Thelimitsforcontainment leakageratesintheUnit2Technical Specifications arederivedfromtherequirements ofAppendixJto10CFR50.SincetheothertwovalvesintheContainment Purgeexhaustlines(FCV-25-4 andFCV-25-6) wereoperable, the,containment isolation safetyfunctionwasmaintained andthehealthandsafetyofthepublicwasnotthreatened. |
| | CORRECTIVE ACTIONS2)3)4)5)Operations personnel confirmed thatthefuseswerepulledonFCV-25-6. |
| | TheTechnical StaffTestGroupleaktestedFCV-25-6. |
| | I&CadjustedandlockeddownthestopforclosingofFCV-25-5.TheTechnical StaffTestGroupre-tested FCV-25-5. |
| | TheInstrument |
| | -&Controldepartment willsubmitachangerequesttovendorTechManual2998-4508 toprovidemoreguidanceonadjusting thevalvetravelandlockingdowntheadjustment screw..ADDITIONAL INFORMATION 1~2~ComonentIdentif'cat'on ThiseventdidnotinvolveanNPRDSreportable component failure.PreviousSimilarEventsrForasimilarevent,seeLERN335-87-005, whichpertainstoexcessive leakagepastacontainment purgevalveonUnit.Nl.IIN/lcPO/IM344AI943I}} |
|
|---|
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
REGULATORY INFORMATION DISTRIBUTION SYSTEM(RIDS)ACCESSION NBR:8907120017 DOC.DATE:
89/07/05NOTARIZED:
NOFACIL:50-389 St.LuciePlant,Unit2,FloridaPower&LightCo.AUTH.NAME'UTHORAFFILIATION HOLIFIELD,C.D..
FloridaPower&LightCo.WOODY,C.O.
FloridaPower&LightCo.RECIP.NAME
'RECIPIENT AFFILIATION
SUBJECT:
LER89-004-00:on 890605,containment localleakrateexceedsTSduetovalveclosurestopoutofadjustment.
DISTRIBUTION CODE:IE22TCOPIESRECEIVED:LTR ENCLSIZE:TITLE:50.73/50.9 LicenseeEventReport(LER),ncidentRpt,etc.t~tNOTES'OPIES LTTRENCL1111COPIESLTTRENCL11RECIPIENT IDCODE/NAME PD2-2LANORRIS,JRECIPIENT IDCODE/NAME PD2-2PDINTERNAL:
ACRSMICHELSON.
ACRSWYLIEAEOD/DSP/TPAB DEDRONRR/DEST/ADE, 8HNRR/DEST/CEB 8HNRR/DEST/ICSB 7NRR/DEST/MTB 9HNRR/DEST/RSB 8ENRR/DLPQ/HFB 10NRR/DOEA/EAB 11NUDOCS-ABSTRACT RES/DSIR/EIB RGN2FILE011111'11111111111111111,.111ACRSMOELLER'EOD/DOA AEOD/ROAB/DSP IRM/DCTS/DAB NRR/DEST/ADS 7ENRR/DEST/ESB 8DNRR/DEST/MEB 9HNRR/DESTOPSB 8DNRR/DEST/SGB 8DNRR/DLPQ/PEB 10NRR~REP/PB10REG02RES/DSR/PRAB 22112'21'10111111"1111221.111DOCKET05000389RIDDDEXTERNALEG&GWILLIAMSgSLSTLOBBY'WARDNRCPDRNSICMURPHYgGA4411111'FORDBLDGHOY,ALPDRNSICMAYS,GD'SNOIR'ZOALLRIDS"R1KXEKENIS:
EEZASEHELPUS'IOREDOCE%ASTH!CGMIRCZGHE1XXUMEÃZCDÃGRLDESK,RXNP1-37(EZT.20079)KlEKaIHQQZB ACRNAHBPKHDI895GEPXXQN LISTSEQRDOCUMEÃIS YOUDCSERTNERD!FULLTEXTCONVERSION REQUIREDTOTALNUMBEROFCOPIES.REQUIRED:
LTTR43ENCL42DD P.O.Box14000, JunoBeach,FL33408.0420 JULY,51989L-89-23810CFR50.73U.S.NuclearRegulatory Commission Attn:DocumentControlDeskWashington, D.C.20555Gentlemen:
Re:St.LucieUnit2DocketNo.50-389Reportable Event:89-04DateofEvent:'June5,1989Containment LocalLeakRateExceedsTechnical Specifications DuetoValveClosureStoOutofAd'ustment DuetoPersonnel ErrorTheattachedLicenseeEventReportisbeingsubmitted pursuanttotherequirements of10CFR50.73toprovidenotification ofthesubjectevent.Verytrulyyours,.C.0.WoActingniorVicePresident
-NuclearCOW/JRH/cm Attachment cc:StewartD.Ebneter,RegionalAdministrator, RegionII,USNRCSeniorResidentInspector, USNRC,St.LuciePlant/-:907120017 S9070PDRADGCK05000389PDCallIlla>><I NRCfornr34494)31LICENSEEEVENTREPORT{LER)U.S.NUCLEARREOULATORY COMMISSION APPROVEDOMSNO,3150410CEXPIRES,'~/31/$5FACILITYNAMElllSt.Lucie,Unit2OOCKEtNUMSER(2)osooo38PAOI1OFTITLE<<)Contaqnmen oca+aaexceesecnacapeericanClosureStoputofAdjustment DuetoPersonnel ErrorEVENTDATE(5ILERNUMSER(5)REtORTDATE(7)OTHERFACILITIES INVOLVEDISIMONTeDAYYEARYEARS40u4N7IAI.NVMSSA"SYR~MONTHOAYNVMSSRYEARFACILITYNAMESN/AOOCRETNuMEER(s>
050000598900400078905000OPS.AT(NO 1MODE(~I~DIVERypp(10)20.402(4) 20A05(~)(IIIII20.405(~)(Il(4)20AOS(~I(Il(ryl)20A05(eIllIIItI20A05(cIIll(yl20AOS(cl50.$5(~)Ill50.35(c)LTI 50.73(~I(2(III50.7$(e)(2)(4) 50.73(el(21(9(lLICENSEECONTACTFORTHISLER02)50.7$(el(2)IN)50.7$(e)12)(y)50.7$(el(2)(or()50.7$(cl(2)(ySI)(AI50.73(e)12)(y(4)
(~I50.7$(~l(2)(el0THEREOUIREMENTS OF10CfR(IrIChtcetiltoririoi'0/lhtltr/owrnf/
IllTHISREPORTISSUSMITTEO tuRSUANTT7$.71(~I7$.71I~I0'tHERISotciryinicollrtcl Ot/OryendinTtet,NRCFOnn3FFllNAMECharlesD.Holifield, ShiftTechnical AdvisorTELE/NONENUMSERAREACODE407465-35pCOMPLETEONELINEFOREACHCOMPONENT FAILUREDESCRI~EOINTHISREtOR'T(1$lCAUSESYSTEMCOMPONENT MANUFAC.TVRERftORtASLE TONPROSYACAVSfSYSTEMCOMtONENT MANVFACTVREREPORTASLE TONPROSSuttLEMKNTAL RftORTEXtECTEO(1iuEXPECTEDSUSMISSION DATEUSIMONTiiOAVYEARYESIIIyn,CtetrtrtEXPECTEDSUSMISSIOAI DATE/NOASSTRACTILieitlolc00roectl,I~,,toproeietltry IrlletnpetitIotctcyotwn(Nn rinNIll~IOnJune5,1989,at1220,withUnit2inMode1at,100%power,aroutinelocalleakratesurveillance testwasperformed onContainment Penetration 10.Thispenetration, whichcontainstheexhaustlinefortheContainment.
PurgeSystem,issubjecttoTypeCtestingandrevealedan"as-found" leakagerateacrossFCV-25-5inexcessof3,171,840 standardcubiccentimeters perminute(SCCM).Thisleakagerateisinexcessoftheallowable leakageof.05La,or48,500SCCM,asperTechnical Specification 4.6.1.7herootcauseofthehighmeasuredleakagewaspersonnel errorinthatthevalveadjustment stopwasnotproperlylockeddownbycontractor personnel whenthevalvewaspreviously adjusted.
Acontributing factorwaslackofguidanceinthetechnical manualonhowtotightentheadjustment screwlocknut.Corrective actionsincludedconfirming thatthefusesforFCV-25-6(asecondvalveinthecontainment purgeexhaustline)werepulled,leaktestingFCV-25-6, adjusting andlockingdownthestopforclosingofFCV-25-5, andre-testing FCV-25-5, withsatisfactory results.Atechnical manualchangerequestwillalsobesubmitted.
NRCfore344/953~
NRCForm3SSA(943(LICENSEEEVENTREPORTtLER)TEXTCONTINUATION U.S.NUCLEARRECULATORY COMMISSIC APPROVEDOMBNO,3150-0(04 EXPIRES.'8/31/88FACILITYNAME((IDOCKETNUMBER(2(LERNUMBER(SI~YEAR>>MSECUCNTIAI IN/INUMBERRCvrsroNNUMSC/I~ACE(3)St.Lucie,Unit2TEXTllfmoresrreseiseorrired, rrsosddrdorro/
HRC%%drm3/(SA's/((TIosooo89-0040002oF03DESCRIPTION OFTHEEVENTOnJune5,1989,at1220,withUnit.2inMode1at1004power,aroutinelocalleakratesurveillance testonContainment Penetration 10revealedaleakagerateacrossFCV-25-5(EIIS:ISV) inexcessof3,171,840 StandardCubicCentimeters perMinute(SCCM)whichisthecapacityofthetestequipment.
Penetration 10containsa48inchexhaustlinefortheContainment PurgeSystem,withthreebutterfly valves,twoofwhich(FCV-25-4 andFCV-25-5) aresubjecttoTypeCtesting,asperUnit2Technical Specification 3.6.1.2.b, Table3.6.-1andSurveillance 4.6.1.7.3.
Localleakratetestingisperformed bypressurizing thepipingbetweenFCV-2S-4andFCV-25-5.
Testinstrumentation isconnected toatesttapbetweenthetwovalves,andthechangeinpressureovertimeisrecordedandusedtocalculate theleakagerate.Theas-foundleakageofthepenetration wasinexcessoftheallowable leakageof.05La,or48,500SCCM.Inaccordance withTechnical Specification 3.6.1.1.7, actionwasundertaken torestoretheleakageratetowithinthespecified limitwithin24hours.Alsoinaccordance withTechnical Specification 3.6.3.,thefusesonFCV-25-6, anadditional valve.inserieswithFCV-25-5, wereverifiedtobepulledandthisvalvewasleaktested.Following anadjustment, thevalveseatstopadjustment screwwaslockeddown-,andtheleakagerateacrossFCV-25-5wasreducedto200SCCM.CAUSEOFTHEEVENTTherootcauseofthiseventwaspersonnel errorbycontractor maintenance personnel inthatthevalvetraveladjustment screwlocknutwasonlyhandtightened thelasttimethevalvetravelwasadjusted.
Acontributing factortothiseventisthelackofguidanceintheTechnical Manualonhowtotightentheadjustment screwlocknut.Thehandtightlocknutallowedthevalvetraveltodriftandresultedintheexcessive leakageacrossFCV-25-S.
Therewerenounusualcharacteristics oftheworklocationthatdirectlycontributed tothepersonnel error.
NRCform344AI9431LICENSEENTREPORTILER)TEXTCONTINIONU.S.NUCLEARREOULATORY COMMISSIO APPROVEOOMSNO.3I50&I04EXPIRES:4/31/bbPACILITYNAMEIIIOOCKETNUMSERIEILERNUMSERISIYEARIN+l44ovENTIAL gP'lfvleloN
- '>+rNVM44R~'vNVM44RPACEI3)St.Lucie,Unit2TEXT///moveopocerooovrvorLooo~/enovvo///RC fr>>rrr3/34A9/IITIosooo38989-004-0003oF03ANALYSISOFTHEEVENTThis,eventhasbeendeemedreportable aspertherequirements of10CFR50.73(a)(2)(i)(B),anyoperation orcondition prohibited bytheplant'sTechnical Specifications.
ThepreviouslocalleakratetestingonPenetration 10wasperformed withsatisfactory resultsduringthenormallyscheduled refueling outagewhichranfromearlyFebruarythroughAprilof1989.Unit2Technical Specification Surveillance Requirement 4.6.1.7.3"requires testingof.thePurgeValvestobeconducted at-intervals ofatleastonceper6monthsonastaggered testbasis.Therefore, thecontainment leakagerates,according totherequirements ofthisTechnical Specification, weretestedwellwithintheboundsofthespecified surveillance interval.
Thelimitsforcontainment leakageratesintheUnit2Technical Specifications arederivedfromtherequirements ofAppendixJto10CFR50.SincetheothertwovalvesintheContainment Purgeexhaustlines(FCV-25-4 andFCV-25-6) wereoperable, the,containment isolation safetyfunctionwasmaintained andthehealthandsafetyofthepublicwasnotthreatened.
CORRECTIVE ACTIONS2)3)4)5)Operations personnel confirmed thatthefuseswerepulledonFCV-25-6.
TheTechnical StaffTestGroupleaktestedFCV-25-6.
I&CadjustedandlockeddownthestopforclosingofFCV-25-5.TheTechnical StaffTestGroupre-tested FCV-25-5.
TheInstrument
-&Controldepartment willsubmitachangerequesttovendorTechManual2998-4508 toprovidemoreguidanceonadjusting thevalvetravelandlockingdowntheadjustment screw..ADDITIONAL INFORMATION 1~2~ComonentIdentif'cat'on ThiseventdidnotinvolveanNPRDSreportable component failure.PreviousSimilarEventsrForasimilarevent,seeLERN335-87-005, whichpertainstoexcessive leakagepastacontainment purgevalveonUnit.Nl.IIN/lcPO/IM344AI943I
