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| {{#Wiki_filter:CA,'l'K(iUKXJ.REGUDATO%TNFORMATYONDYSTRIBUTYONAYSTEM(RYDS)IACCESSIONNBR:9708050269DOC.DATE:97/07/29NOTARIZED:NOFACIL:50-389St.LuciePlant,Unit2,FloridaPower&LightCo.AUTH.NAMEAUTHORAFFILIA'TIONBENKEN,E.J.FloridaPower&.LightCo.STALL,J.A.FloridaPower&LightCo.RECIP.NAMERECIPIENTAFFILIATIONDOCKET¹05000389 | | {{#Wiki_filter:CA,'l'K(iUK XJ.REGUDATO% |
| | TNFORMATYON DYSTRIBUTYONAYSTEM (RYDS)IACCESSION NBR:9708050269 DOC.DATE: |
| | 97/07/29NOTARIZED: |
| | NOFACIL:50-389 St.LuciePlant,Unit2,FloridaPower&LightCo.AUTH.NAMEAUTHORAFFILIA'TION BENKEN,E.J. |
| | FloridaPower&.LightCo.STALL,J.A. |
| | FloridaPower&LightCo.RECIP.NAME RECIPIENT AFFILIATION DOCKET¹05000389 |
|
| |
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| ==SUBJECT:== | | ==SUBJECT:== |
| LER97-006-00: on970630, discoveredinadequatetestingofengineeredsafetyfeaturessubgrouprelays. CausedbyinadequacyinimplementingTSrequirementsinsurveillanceprocedures. Revisedsurveillanceprocedures.W/ 970729ltr. DISTRIBUTIONCODE:IE22TCOPIESRECEIVED: LTRENCLSIZE:TITLE:50.73/50. 9LicenseeEventReport(LER),IncidentRpt,etc..NOTES: RECIPIENTIDCODE/ NAMEPD2-3PDINTERNAL:ACRSAEOD/SPD/ RRABNRR/DE/ ECGBNRR/DE/ EMEBNRR/DRCH/ HICBNRR/DRCH/ HQMBNRR/DSSA/SPLB.RES/DET/ EIBEXTERNAL:LSTLOBBYWARDNOACPOOREFW. NRCPDRCOPIESLTTRENCL11111111111111111111111RECIPIENTIDCODE/ NAMEWIENS,L.AEEPPESECENRRDE/EELBNRR/DRCH/ HHFBNRR/DRCH/ HOLBNRR/DRPM/ PECBNRR/DSSA/ SRXBRGN2FILE01LITCOBRYCEFJHNOACQUEENERFDS.NUDOCSFULLTXTCOPIESLTTRENCL1122111111111.1111~1111111NOTETOALL"RIDS"RECIPIENTS:PLEASEHELPUSTOREDUCEWASTETHCONTACTTHEDOCUMENTCONTROLDESK,ROOMOWFN5D-5(EXT.415-2083) TOELIMINATEYOURNAMEPROMDISTRIBUTIONLISTSFORDOCUMENTSYOUDON' TNEEDlFULLTEXTCONVERSIONREQUIREDTOTALNUMBEROFCOPIESREQUIRED:LTTR25ENCL25 FloridaPower8LightCompany,6501SouthOceanOrive,JensenBeach,FL34957July29,1997L-97-19010CFR50.73U.S. NuclearRegulatoryCommissionAttn:DocumentControlDeskWashington,D.C.20555Re:St.LucieUnit2DocketNo.50- 389ReportableEvent:97-006DateofEvent:June30, 1997OperationProhibitedbyTechnicalSpecificationsduetoInadequateTheattachedLicenseeEventReportisbeingsubmittedpursuanttotherequirementsof10CFR50. 73toprovidenotificationofthesubjectevent.Verytrulyyours,J.A. StallVicePresidentSt.LuciePlantJAS/ EJBAttachmentcc:RegionalAdministrator,USNRCRegionIISeniorResidentInspector,USNRC,St. LuciePlant9708050269970729' DRADQCK05000$89SPDR0!llll!llll!Illl! IlllllllllllllllllllllanFPLGroupcompany NRCFORM366(4-95)U.S. NUCLEARREGULATORYCOMMISSIONLICENSEEEVENTREPORT(LER)ISBBreverseforrequirednumberofdigits/ charactersforeachblock)APPROVEDBYOMSNO.3'l60%( 04EXPIRES04/30/ SSESTIMATEDBURDENPERRESPONSEToCOMPLYWITHTHISMANDATORINFORMATIONCOLLECTIONREQUEST:60.0HRS. REPORTEDLESSONLEARNEDAREINCORPORATEDINTOTHEUCENSINGPROCESSANOFsACKToINDUSTRY.FO/r/t/ ARDCOMMENTSREGARDINGBURoENEst/ MATToTHEINFORMATIONANDRECORDSMANAGEMENTBRANCH(T-0F33)U.S. NUCLEARREGULATORYCOMMISSION,WASHINGTON,DC20$6$% 001ANDToTHEPAPERWORKREDUCTIONPROJECT(3160%104), OFFICE0MANAGEMENTANDBUDGET,WASHINGTON,DC20603.FACIUTyNAME(1)STLUCIEUNIT2DOCKETNUMBER(2)05000389PAGE(3)1OF4TITLE(4) OperationProhibitedbyTechnicalSpecificationsduetoInadequateSurveillanceTestingofEngineeredSafetyFeaturesSubgroupRelaysMONTH06DAYYEAR3097YEARSEQUENTIALREVISIONNUMBERNUMBER97-006-00MONTH07OAY29YEAR97FACIUTYNAMEFACIUTYNAMEN/AN/ ADOCKETNUMBERDOCKETNUMBEROPERATINGMODE(9)POWERLEVEL(10)10020.2201(b)20.2203(a)(2)(i)20.2203(a)(2)(v)20.2203(a)(3)(ii)50.73(a)(2)(i)50.73(a)(2)(iii)50.73(a)(2)(viii)73.71OTHERp./y~~~~iiagm// 2j';...Y@~y<a'ayr20.2203(a)(2)(iii)20.2203(a)(2)(iv)50.36(c)(1)50.36(c)(2)50.73(0)(2)(v)50.73(a)(2)(vii)SpecifyinAbstractbeloworinNRCForm366ANAMEEdwinJ.Benken, LicensingEngineerTELEPHONENUMBERBoo/udeAreaCode)(561)467- 7156CAUSESYSTEMCOMPONENTMANUFACTURERREPORTABLEToNPRDSCAUSESYSTEMCOMPONENTMANUFACTURERREPORTABLEToNPRDSYES,(lfyes, completeEXPECTEDSUBMISSIONDATE). XNoEXPECTEDSUBMISSIONDATE(15)MONTHDAYYEARABSTRACT(Limitto1400spaces,i.e., approximately15single- spacedtypewrittenlines)(16)OnJune30,1997,St. LucieUnit2wasoperatinginMode1at100percentpower. AnengineeringreviewidentifiedadeficiencyintheperformanceofEngineeredSafetyFeatures(ESF) logictestingassociatedwithtwosubgrouprelaysforthecontainmentisolationsystem.Thesubgrouprelayswererequiredtobetested' atasemi- annualfrequency,buthadinsteadbeentestedonceper18months. ThisrepresentedafailuretoperformasurveillancerequirementwithintheallowedsurveillanceintervalandthereforeaconditionprohibitedbytheplantTechnicalSpecifications. Thesubjectrelaysfunctiontosecuretheoperationofthecontainmentpurgefansandtoclosethecontainmentpurgeisolationvalvesduringactuationofacontainmentisolationsignal. Sincethesecontainmentpurgecomponentsarerequiredtobemaintainedintheirpost- accidentconfigurationduringreactoroperation,themissedtesting' wasnotsafetysignificant. Thesubgrouprelayswererecentlytestedsatisfactorilyandarecurrentlywithintheallowablesurveillanceinterval. ThefailuretotesttheESFASsubgrouprelaysattherequiredsurveillanceintervalwascausedbyaninadequacyinimplementingtheTSrequirementsintheplantsurveillanceprocedures. CorrectiveActionsinclude:1) Plantsurveillanceprocedureswillberevisedtoincludetheappropriaterequirementsforsurveillancetestingofthesubgrouprelays.2) Surveillancetestingistobeperformedinaccordancewithrevisedproceduralinstructionsandwithintheallowablesurveillanceinterval.3) LogiccircuittestproceduresarecontinuingtobereviewedatSt.LucieUnit1forproperTSimplementation.NRCFOAM366(4-95) | | LER97-006-00:on 970630,discovered inadequate testingofengineered safetyfeaturessubgrouprelays.Causedbyinadequacy inimplementing TSrequirements insurveillance procedures. |
| NRCFORM366AI4-95)LICENSEEEVENTREPORT(LER)TEXTCONTINUATIONU.S.NUCLEARREGULATORYCOMMISSIOST.LUCIEUNIT205000389YEARSEQUENTIALREVISION97-006-002OF4TEXTilfmorespaceisrequired,useadditionalcopiesofhlRCForm366AiI17ISt.LucieUnit2TechnicalSpecifications(TS)fortheEngineeredSafetyFeaturesActuationSystem(ESFAS)[EIIS:JEjrequirethatasubgrouprelaytestbeperformedsemi-annuallytoverifyoperabilityoftheautomaticactuationlogicforthecontainmentisolationsystem(CIS).TheUnit2UpdatedFinalSafetyAnalysisReport(UFSAR),Table7.3-9a,identifiesspecificsubgrouprelayswhichcannotbetestedwiththereactoratpowerduetothepotentialimpacttoplantoperation.Fortheserelays,surveillancetestingisperformedwhentheunitisshutdown.OnJune30,1997,adiscrepancywasidentifiedregardingtheplantTSsurveillancerequirement(TS4.3.2.1)fortheESFASsubgrouprelays,theUFSARtable7.3-9a,andcurrentplanttestingpractices.AreviewoftheplanttestingproceduresperformedbyFPLengineeringpersonneldeterminedthattwoESFASsubgrouprelays(K512AandK612A)[EIIS:JE:RLYJwerenotbeingappropriatelytestedwithinthesemi-annualperiodasrequiredbyTSandthattheserelayswerenotexemptfromtestingatpowerasdescribedintheUFSARtable.Therelayswerebeingfunctionallytestedonan18monthbasisduringperformanceoftheEngineeredSafetyFeatures(ESF)periodictestandnotona6monthfrequencyasrequired.SubgrouprelaysK512AandK612AfunctionuponreceiptofaContainmentIsolationActuationSystem(CIAS)signaltosecurethecontainmentpurgefans,HVE-8AandHVE-88[EIIS:VA:FAN),andto'closethecontainmentpurgeisolationvalvesFCV-25-1throughFCV-25-6[EIIS:VA:ISVJ.Thepurgefansandisolationvalvesaremaintainedintheirpost-accidentconfigurationwhentheUnitisatpower.St.LucieUnit2wasoperatinginMode1at100percentpowerwhenthetestingdiscrepancieswereidentified.Performanceofthe18monthintegratedESFtest,completedMay19,1997,currentlysatisfiesthesixmonthsurveillancerequirement.TheidentificationoftheESFASsubgrouprelaytestdiscrepancywasmadeduringthepreparationofanengineeringevaluationforaplantlicenseamendmentdesignedtoclarifytheplantTSwithregardtosubgrouprelaytesting.ThiswasafollowupactionbeingimplementedsubsequenttoFPL'sreviewofelectricallogiccircuittestingforSt.LucieUnit2,whichwasperformedinaccordancewiththerecommendationsofGenericLetter96-01.ThefailuretotestESFASsubgrouprelaysK512AandK612Awascausedbyaninadequatesurveillancetestprocedure.SurveillanceOperatingProcedure2-0400053,"EngineeredSafeguardsRelayTest,"containstheinstructionsrequiredforverifyingtheproperfunctioningofESFrelaysasrequiredbytheplantTechnicalSpecifications.ThesurveillanceprocedureaswrittendidnotprovideaconclusivetestofoperabilityforsubgrouprelaysK512AandK612Abyverifyingcomponentactuationortheoperationofoutputcontactsfromtherelays.Justificationfornotincludingtestinstructionsforthesubgrouprelaysintheprocedurewasinsufficient,inthatitwasbasedupontherequirementthatthecontainmentpurgeisolationvalvesmustremainintheirclosed(safe)positionduringpoweroperation.SincethevalvescouldnotbeopenedinModes'1through4,andthepurgefanswererequiredtobemaintaineddeenergized,itwasincorrectlyassumedthattestingforthecontainmentisolationfunctionwasnotrequiredintheseModes. | | Revisedsurveillance procedures.W/970729 ltr.DISTRIBUTION CODE:IE22TCOPIESRECEIVED:LTR ENCLSIZE:TITLE:50.73/50.9 LicenseeEventReport(LER),IncidentRpt,etc..NOTES:RECIPIENT IDCODE/NAME PD2-3PDINTERNAL: |
| NRCFORM366A(4-95)LICENSEEEVENTREPORT(LER)TEXTCONTINUATIONU.S.NUCLEARREGULATORYCOMMISSIOFACILITYNAME1ST.LUCIEUNIT2TEXTflfmoreepecelerequired,ueeeddidonelcopleeofNRCForm366AJ(17)DOCKET05000389LERNUMBER(6SEQUENTIALREVISIONNUMBERNUMBER97-006-00PAGE33OF4ESFAStestingisconductedperiodicallyduringnormalplantoperationinaccordancewiththeSt.LucieUnit2TechnicalSpecificationstoverifyoperability.TSsurveillancerequirement4.3.2.1,requiresthateachESFASinstrumentchannelbedemonstratedoperablebytheperformanceoftheChannelCheck,ChannelCalibrationandChannelFunctionaltestoperationsfortheModesandatthefrequencies'escribedinTSTable4.3-2.Note2ofthistablespecifiesthatfortheautomaticactuationlogicassociatedwithCIAS,asubgrouprelaytestshallbeperformedtoincludetheenergizationordeenergizationofeachsubgrouprelayandverificationoftheoperabilityforeachrelay.ThefrequencyspecifiedbytheTSforperformanceofthissurveillanceissemi-annual(SA)~ThisconditiondoesnotapplytoSt.LucieUnit1,astheESFASinstrumentationTechnicalSpecificationsatUnit1donotcontainthesamerequirementforsemi-annualtestingoftheCIASsubgrouprelays.TheESFASactuationdeviceswhicharenottestedduringreactoroperation,duetotheirimpacttotheplant,aretestedduringscheduledreactorshutdownstoassurethattheyarecapableofperformingtheirintendedfunction.ThisisdescribedintheSt.LucieUnit2UFSAR,Table7.3-9a,whichliststheESFASactuationrelaydevicesnottestedduringnormaloperatingconditions.SubgrouprelaysK512AandK612Aarenotincludedinthetableandarecapableofbeingtestedduringpoweroperation,byverificationofoutputcontactstatususingadigitalvoltmeter(DVM).Theserelaysarethereforerequiredtobetestedonasemi-annualbasis.SubgrouprelaysK512AandK612AactuatecomponentsofthecontainmentpurgesystemuponreceiptofaCIASsignal.Specifically,therelaysfunctiontoclosethecontainmentpurgeisolationvalvesFCV-25-1,2,3,4,5and6,andtostopcontainmentpurgefansHVE8Aand8B.Therelaysarecycledduringthesemi-annualsurveillancetest,howeververificationofcomponentactuationoroutputcontactstatusisnotperformed.Althoughacompleteverificationofoperabilityfortheserelayswasnotperformedonasemi-annualbasis,therelayswerefunctionallytestedevery18monthsduringtheperformanceoftheintegratedEngineeredSafetyFeaturesPeriodicTestandhadbeensatisfactorilytestedduringthelastperformanceofthistest,completedMay19,1997.Asaresultoftheprevioussurveillance,currentsystemoperationiswithintheallowablesixmonthsurveillanceintervalandtherefore,nooperabilityconcernexists.ThefailuretopreviouslytestESFASsubgrouprelaysK512AandK612Aonasemi-annualbasis,asrequiredbyTS4,3.2,1,representsaconditionprohibitedbytheplantTechnicalSpecificationsandisthereforereportableunder50.73(a)(2)(i)(B).ESFASsubgrouprelaysK512AandK612Aaffectonlythecontainmentpurgecomponentspreviouslydescribed.With'theexceptionofthecontainmentisolationfunction,thecontainmentpurgesystemisanon-safetyrelatedandnon-seismicsystemusedtoprovideventilationofthecontainmentbuildingforpersonnelaccessduringshutdownandrefueling.Thesystemisnotusedatpowerandisthereforenotrequiredtooperatefollowingadesignbasisaccident. | | ACRSAEOD/SPD/RRAB NRR/DE/ECGB NRR/DE/EMEB NRR/DRCH/HICB NRR/DRCH/HQMB NRR/DSSA/SPLB. |
| NRCFORM366AI4-8SILICENSEEEVENT.REPORT(LER)TEXTCONTINUATIONU.S.NUCLEARREGULATORYCOMMISSIOST.LUCIEUNIT205000389YEARSEQUENTIALREVISION97-006-004OF4TEXT(Ifmorespecsisrequired,useedditionelcopiesofNRCFarm386AiI17lThecontainmentpurgeexhaustfans,HVE-8AandHVE-88aremaintaineddeenergizedduringplantoperation.Additionally,TS3.6.1.7requiresthateachcontainmentpurgeisolationvalvebesealedclosedwhenoperatinginModes1,2,3or4.Asaresultoftheabovemeasures,thecontainmentpurgesystemismaintainedinitspost-accidentconfigurationduringpoweroperation(Modes1through4)andisnotrequiredtorepositionintheeventofanESFASactuationduringtheseModes.TheactuationofCIScomponentsbysubgrouprelaysK512AandK612AwassatisfactorilytestedduringanintegratedESFperiodicsurveillancecompletedonMay19,1997.ThefailuretotesttheESFASsubgrouprelays,K512AandK612A,atasemi-annualfrequencyisnotsafetysignificantsincethecomponentsaffectedbytheserelaysarerequiredtobemaintainedintheirpost-accidentconfigurationduringModes1through4.Plantoperatingprocedure2-0400053,"EngineeredSafeguardsRelayTest"willberevisedtoincludesurveillancetestingfortheoutputcontactstatusofsubgrouprelaysK512AandK612Awhichaffectthecontainmentpurgecomponents.2.ESFASsurveillancetestingfortheUnit2containmentpurgeisolationvalvesandfanswillbeconductedinaccordancewiththerevisedprocedureandwithintheallowablesurveillanceintervalbasedonthelastsurveillancetestcompletedforthesecomponents.3.FPLiscontinuingtoperformareviewoftheSt.LucieUnit1ESFASsurveillancetestproceduresand'logiccircuittestinginaccordance.withtherecommendationsofGenericLetter(GL)96-01toensurethatTSrequirementsarebeingadequatelyimplemented.4,InordertoreemphasizetheexpectationthatplantsurveillancesandproceduresfullyimplementtheTechnicalSpecificationrequirementsinaverbatimmanner,trainingbriefsarebeingissuedtokeymaintenanceandsiteengineeringpersonnel.Inaddition,thiseventwillbeincludedintothecontinuingtrainingprogramforlicensedoperatorsasareviewoflessonslearned.-NonePreviousSimilarEvents-LERs389/96-005and389/96-006describesurveillanceinadequaciespreviouslyidentifiedbyFPLduringlogiccircuitrytestingreviewsperformedinaccordancewiththerecommendationsofGL96-01.}} | | RES/DET/EIB EXTERNAL: |
| | LSTLOBBYWARDNOACPOOREFW.NRCPDRCOPIESLTTRENCL11111111111111111111111RECIPIENT IDCODE/NAME WIENS,L.AEEPPESECENRRDE/EELBNRR/DRCH/HHFB NRR/DRCH/HOLB NRR/DRPM/PECB NRR/DSSA/SRXB RGN2FILE01LITCOBRYCEFJHNOACQUEENERFDS |
| | .NUDOCSFULLTXTCOPIESLTTRENCL1122111111111.1111~1111111NOTETOALL"RIDS"RECIPIENTS: |
| | PLEASEHELPUSTOREDUCEWASTETHCONTACTTHEDOCUMENTCONTROLDESK,ROOMOWFN5D-5(EXT. |
| | 415-2083) |
| | TOELIMINATE YOURNAMEPROMDISTRIBUTION LISTSFORDOCUMENTS YOUDON'TNEEDlFULLTEXTCONVERSION REQUIREDTOTALNUMBEROFCOPIESREQUIRED: |
| | LTTR25ENCL25 FloridaPower8LightCompany,6501SouthOceanOrive,JensenBeach,FL34957July29,1997L-97-19010CFR50.73U.S.NuclearRegulatory Commission Attn:DocumentControlDeskWashington, D.C.20555Re:St.LucieUnit2DocketNo.50-389Reportable Event:97-006DateofEvent:June30,1997Operation Prohibited byTechnical Specifications duetoInadequate TheattachedLicenseeEventReportisbeingsubmitted pursuanttotherequirements of10CFR50.73toprovidenotification ofthesubjectevent.Verytrulyyours,J.A.StallVicePresident St.LuciePlantJAS/EJBAttachment cc:RegionalAdministrator, USNRCRegionIISeniorResidentInspector, USNRC,St.LuciePlant9708050269 970729'DR ADQCK05000$89SPDR0!llll!llll! |
| | Illl!Illlllllllllllllllllll anFPLGroupcompany NRCFORM366(4-95)U.S.NUCLEARREGULATORY COMMISSION LICENSEEEVENTREPORT(LER)ISBBreverseforrequirednumberofdigits/characters foreachblock)APPROVEDBYOMSNO.3'l60%(04 EXPIRES04/30/SSESTIMATED BURDENPERRESPONSEToCOMPLYWITHTHISMANDATORINFORMATION COLLECTION REQUEST:60.0HRS.REPORTEDLESSONLEARNEDAREINCORPORATED INTOTHEUCENSINGPROCESSANOFsACKToINDUSTRY. |
| | FO/r/t/ARD COMMENTSREGARDING BURoENEst/MATToTHEINFORMATION ANDRECORDSMANAGEMENT BRANCH(T-0F33)U.S.NUCLEARREGULATORY COMMISSION, WASHINGTON, DC20$6$%001ANDToTHEPAPERWORK REDUCTION PROJECT(3160%104), |
| | OFFICE0MANAGEMENT ANDBUDGET,WASHINGTON, DC20603.FACIUTyNAME(1)STLUCIEUNIT2DOCKETNUMBER(2)05000389PAGE(3)1OF4TITLE(4)Operation Prohibited byTechnical Specifications duetoInadequate Surveillance TestingofEngineered SafetyFeaturesSubgroupRelaysMONTH06DAYYEAR3097YEARSEQUENTIAL REVISIONNUMBERNUMBER97-006-00MONTH07OAY29YEAR97FACIUTYNAMEFACIUTYNAMEN/AN/ADOCKETNUMBER DOCKETNUMBER OPERATING MODE(9)POWERLEVEL(10)10020.2201(b)20.2203(a) |
| | (2)(i)20.2203(a) |
| | (2)(v)20.2203(a) |
| | (3)(ii)50.73(a)(2)(i)50.73(a)(2)(iii)50.73(a)(2)(viii) 73.71OTHERp./y~~~~iiagm// 2 j';...Y@~y<a'ayr20.2203(a) |
| | (2)(iii)20.2203(a)(2) |
| | (iv)50.36(c)(1) 50.36(c)(2) 50.73(0)(2)(v)50.73(a)(2)(vii) |
| | SpecifyinAbstractbeloworinNRCForm366ANAMEEdwinJ.Benken,Licensing EngineerTELEPHONE NUMBERBoo/udeAreaCode)(561)467-7156CAUSESYSTEMCOMPONENT MANUFACTURER REPORTABLE ToNPRDSCAUSESYSTEMCOMPONENT MANUFACTURER REPORTABLE ToNPRDSYES,(lfyes,completeEXPECTEDSUBMISSION DATE).XNoEXPECTEDSUBMISSION DATE(15)MONTHDAYYEARABSTRACT(Limitto1400spaces,i.e.,approximately 15single-spaced typewritten lines)(16)OnJune30,1997,St.LucieUnit2wasoperating inMode1at100percentpower.Anengineering reviewidentified adeficiency intheperformance ofEngineered SafetyFeatures(ESF)logictestingassociated withtwosubgrouprelaysforthecontainment isolation system.Thesubgrouprelayswererequiredtobetested'at asemi-annual frequency, buthadinsteadbeentestedonceper18months.Thisrepresented afailuretoperformasurveillance requirement withintheallowedsurveillance intervalandtherefore acondition prohibited bytheplantTechnical Specifications. |
| | Thesubjectrelaysfunctiontosecuretheoperation ofthecontainment purgefansandtoclosethecontainment purgeisolation valvesduringactuation ofacontainment isolation signal.Sincethesecontainment purgecomponents arerequiredtobemaintained intheirpost-accident configuration duringreactoroperation, themissedtesting'was notsafetysignificant. |
| | Thesubgrouprelayswererecentlytestedsatisfactorily andarecurrently withintheallowable surveillance interval. |
| | ThefailuretotesttheESFASsubgrouprelaysattherequiredsurveillance intervalwascausedbyaninadequacy inimplementing theTSrequirements intheplantsurveillance procedures. |
| | Corrective Actionsinclude:1)Plantsurveillance procedures willberevisedtoincludetheappropriate requirements forsurveillance testingofthesubgrouprelays.2)Surveillance testingistobeperformed inaccordance withrevisedprocedural instructions andwithintheallowable surveillance interval. |
| | 3)Logiccircuittestprocedures arecontinuing tobereviewedatSt.LucieUnit1forproperTSimplementation. |
| | NRCFOAM366(4-95) |
| | NRCFORM366AI4-95)LICENSEEEVENTREPORT(LER)TEXTCONTINUATION U.S.NUCLEARREGULATORY COMMISSIO ST.LUCIEUNIT205000389YEARSEQUENTIAL REVISION97-006-002OF4TEXTilfmorespaceisrequired, useadditional copiesofhlRCForm366AiI17ISt.LucieUnit2Technical Specifications (TS)fortheEngineered SafetyFeaturesActuation System(ESFAS)[EIIS:JEj requirethatasubgrouprelaytestbeperformed semi-annually toverifyoperability oftheautomatic actuation logicforthecontainment isolation system(CIS).TheUnit2UpdatedFinalSafetyAnalysisReport(UFSAR),Table7.3-9a,identifies specificsubgrouprelayswhichcannotbetestedwiththereactoratpowerduetothepotential impacttoplantoperation. |
| | Fortheserelays,surveillance testingisperformed whentheunitisshutdown. |
| | OnJune30,1997,adiscrepancy wasidentified regarding theplantTSsurveillance requirement (TS4.3.2.1)fortheESFASsubgrouprelays,theUFSARtable7.3-9a,andcurrentplanttestingpractices. |
| | Areviewoftheplanttestingprocedures performed byFPLengineering personnel determined thattwoESFASsubgrouprelays(K512AandK612A)[EIIS:JE:RLYJ werenotbeingappropriately testedwithinthesemi-annual periodasrequiredbyTSandthattheserelayswerenotexemptfromtestingatpowerasdescribed intheUFSARtable.Therelayswerebeingfunctionally testedonan18monthbasisduringperformance oftheEngineered SafetyFeatures(ESF)periodictestandnotona6monthfrequency asrequired. |
| | SubgrouprelaysK512AandK612AfunctionuponreceiptofaContainment Isolation Actuation System(CIAS)signaltosecurethecontainment purgefans,HVE-8AandHVE-88[EIIS:VA:FAN), |
| | andto'closethecontainment purgeisolation valvesFCV-25-1throughFCV-25-6[EIIS:VA:ISVJ. |
| | Thepurgefansandisolation valvesaremaintained intheirpost-accident configuration whentheUnitisatpower.St.LucieUnit2wasoperating inMode1at100percentpowerwhenthetestingdiscrepancies wereidentified. |
| | Performance ofthe18monthintegrated ESFtest,completed May19,1997,currently satisfies thesixmonthsurveillance requirement. |
| | Theidentification oftheESFASsubgrouprelaytestdiscrepancy wasmadeduringthepreparation ofanengineering evaluation foraplantlicenseamendment designedtoclarifytheplantTSwithregardtosubgrouprelaytesting.Thiswasafollowupactionbeingimplemented subsequent toFPL'sreviewofelectrical logiccircuittestingforSt.LucieUnit2,whichwasperformed inaccordance withtherecommendations ofGenericLetter96-01.ThefailuretotestESFASsubgrouprelaysK512AandK612Awascausedbyaninadequate surveillance testprocedure. |
| | Surveillance Operating Procedure 2-0400053, "Engineered Safeguards RelayTest,"containstheinstructions requiredforverifying theproperfunctioning ofESFrelaysasrequiredbytheplantTechnical Specifications. |
| | Thesurveillance procedure aswrittendidnotprovideaconclusive testofoperability forsubgrouprelaysK512AandK612Abyverifying component actuation ortheoperation ofoutputcontactsfromtherelays.Justification fornotincluding testinstructions forthesubgrouprelaysintheprocedure wasinsufficient, inthatitwasbasedupontherequirement thatthecontainment purgeisolation valvesmustremainintheirclosed(safe)positionduringpoweroperation. |
| | SincethevalvescouldnotbeopenedinModes'1through4,andthepurgefanswererequiredtobemaintained deenergized, itwasincorrectly assumedthattestingforthecontainment isolation functionwasnotrequiredintheseModes. |
| | NRCFORM366A(4-95)LICENSEEEVENTREPORT(LER)TEXTCONTINUATION U.S.NUCLEARREGULATORY COMMISSIO FACILITYNAME1ST.LUCIEUNIT2TEXTflfmoreepecelerequired, ueeeddidonel copleeofNRCForm366AJ(17)DOCKET05000389LERNUMBER(6SEQUENTIAL REVISIONNUMBERNUMBER97-006-00PAGE33OF4ESFAStestingisconducted periodically duringnormalplantoperation inaccordance withtheSt.LucieUnit2Technical Specifications toverifyoperability. |
| | TSsurveillance requirement 4.3.2.1,requiresthateachESFASinstrument channelbedemonstrated operablebytheperformance oftheChannelCheck,ChannelCalibration andChannelFunctional testoperations fortheModesandatthefrequencies |
| | 'escribed inTSTable4.3-2.Note2ofthistablespecifies thatfortheautomatic actuation logicassociated withCIAS,asubgrouprelaytestshallbeperformed toincludetheenergization ordeenergization ofeachsubgrouprelayandverification oftheoperability foreachrelay.Thefrequency specified bytheTSforperformance ofthissurveillance issemi-annual (SA)~Thiscondition doesnotapplytoSt.LucieUnit1,astheESFASinstrumentation Technical Specifications atUnit1donotcontainthesamerequirement forsemi-annual testingoftheCIASsubgrouprelays.TheESFASactuation deviceswhicharenottestedduringreactoroperation, duetotheirimpacttotheplant,aretestedduringscheduled reactorshutdowns toassurethattheyarecapableofperforming theirintendedfunction. |
| | Thisisdescribed intheSt.LucieUnit2UFSAR,Table7.3-9a,whichliststheESFASactuation relaydevicesnottestedduringnormaloperating conditions. |
| | SubgrouprelaysK512AandK612Aarenotincludedinthetableandarecapableofbeingtestedduringpoweroperation, byverification ofoutputcontactstatususingadigitalvoltmeter(DVM).Theserelaysaretherefore requiredtobetestedonasemi-annual basis.SubgrouprelaysK512AandK612Aactuatecomponents ofthecontainment purgesystemuponreceiptofaCIASsignal.Specifically, therelaysfunctiontoclosethecontainment purgeisolation valvesFCV-25-1,2,3,4,5and6,andtostopcontainment purgefansHVE8Aand8B.Therelaysarecycledduringthesemi-annual surveillance test,howeververification ofcomponent actuation oroutputcontactstatusisnotperformed. |
| | Althoughacompleteverification ofoperability fortheserelayswasnotperformed onasemi-annual basis,therelayswerefunctionally testedevery18monthsduringtheperformance oftheintegrated Engineered SafetyFeaturesPeriodicTestandhadbeensatisfactorily testedduringthelastperformance ofthistest,completed May19,1997.Asaresultoftheprevioussurveillance, currentsystemoperation iswithintheallowable sixmonthsurveillance intervalandtherefore, nooperability concernexists.Thefailuretopreviously testESFASsubgrouprelaysK512AandK612Aonasemi-annual basis,asrequiredbyTS4,3.2,1,represents acondition prohibited bytheplantTechnical Specifications andistherefore reportable under50.73(a)(2)(i)(B).ESFASsubgrouprelaysK512AandK612Aaffectonlythecontainment purgecomponents previously described. |
| | With'theexception ofthecontainment isolation |
| | : function, thecontainment purgesystemisanon-safety relatedandnon-seismic systemusedtoprovideventilation ofthecontainment buildingforpersonnel accessduringshutdownandrefueling. |
| | Thesystemisnotusedatpowerandistherefore notrequiredtooperatefollowing adesignbasisaccident. |
| | NRCFORM366AI4-8SILICENSEEEVENT.REPORT(LER)TEXTCONTINUATION U.S.NUCLEARREGULATORY COMMISSIO ST.LUCIEUNIT205000389YEARSEQUENTIAL REVISION97-006-004OF4TEXT(Ifmorespecsisrequired, useedditionel copiesofNRCFarm386AiI17lThecontainment purgeexhaustfans,HVE-8AandHVE-88aremaintained deenergized duringplantoperation. |
| | Additionally, TS3.6.1.7requiresthateachcontainment purgeisolation valvebesealedclosedwhenoperating inModes1,2,3or4.Asaresultoftheabovemeasures, thecontainment purgesystemismaintained initspost-accident configuration duringpoweroperation (Modes1through4)andisnotrequiredtoreposition intheeventofanESFASactuation duringtheseModes.Theactuation ofCIScomponents bysubgrouprelaysK512AandK612Awassatisfactorily testedduringanintegrated ESFperiodicsurveillance completed onMay19,1997.ThefailuretotesttheESFASsubgrouprelays,K512AandK612A,atasemi-annual frequency isnotsafetysignificant sincethecomponents affectedbytheserelaysarerequiredtobemaintained intheirpost-accident configuration duringModes1through4.Plantoperating procedure 2-0400053, "Engineered Safeguards RelayTest"willberevisedtoincludesurveillance testingfortheoutputcontactstatusofsubgrouprelaysK512AandK612Awhichaffectthecontainment purgecomponents. |
| | 2.ESFASsurveillance testingfortheUnit2containment purgeisolation valvesandfanswillbeconducted inaccordance withtherevisedprocedure andwithintheallowable surveillance intervalbasedonthelastsurveillance testcompleted forthesecomponents. |
| | 3.FPLiscontinuing toperformareviewoftheSt.LucieUnit1ESFASsurveillance testprocedures and'logic circuittestinginaccordance. |
| | withtherecommendations ofGenericLetter(GL)96-01toensurethatTSrequirements arebeingadequately implemented. |
| | 4,Inordertoreemphasize theexpectation thatplantsurveillances andprocedures fullyimplement theTechnical Specification requirements inaverbatimmanner,trainingbriefsarebeingissuedtokeymaintenance andsiteengineering personnel. |
| | Inaddition, thiseventwillbeincludedintothecontinuing trainingprogramforlicensedoperators asareviewoflessonslearned.-NonePreviousSimilarEvents-LERs389/96-005 and389/96-006 describesurveillance inadequacies previously identified byFPLduringlogiccircuitry testingreviewsperformed inaccordance withtherecommendations ofGL96-01.}} |
|
|---|
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
CA,'l'K(iUK XJ.REGUDATO%
TNFORMATYON DYSTRIBUTYONAYSTEM (RYDS)IACCESSION NBR:9708050269 DOC.DATE:
97/07/29NOTARIZED:
NOFACIL:50-389 St.LuciePlant,Unit2,FloridaPower&LightCo.AUTH.NAMEAUTHORAFFILIA'TION BENKEN,E.J.
FloridaPower&.LightCo.STALL,J.A.
FloridaPower&LightCo.RECIP.NAME RECIPIENT AFFILIATION DOCKET¹05000389
SUBJECT:
LER97-006-00:on 970630,discovered inadequate testingofengineered safetyfeaturessubgrouprelays.Causedbyinadequacy inimplementing TSrequirements insurveillance procedures.
Revisedsurveillance procedures.W/970729 ltr.DISTRIBUTION CODE:IE22TCOPIESRECEIVED:LTR ENCLSIZE:TITLE:50.73/50.9 LicenseeEventReport(LER),IncidentRpt,etc..NOTES:RECIPIENT IDCODE/NAME PD2-3PDINTERNAL:
ACRSAEOD/SPD/RRAB NRR/DE/ECGB NRR/DE/EMEB NRR/DRCH/HICB NRR/DRCH/HQMB NRR/DSSA/SPLB.
RES/DET/EIB EXTERNAL:
LSTLOBBYWARDNOACPOOREFW.NRCPDRCOPIESLTTRENCL11111111111111111111111RECIPIENT IDCODE/NAME WIENS,L.AEEPPESECENRRDE/EELBNRR/DRCH/HHFB NRR/DRCH/HOLB NRR/DRPM/PECB NRR/DSSA/SRXB RGN2FILE01LITCOBRYCEFJHNOACQUEENERFDS
.NUDOCSFULLTXTCOPIESLTTRENCL1122111111111.1111~1111111NOTETOALL"RIDS"RECIPIENTS:
PLEASEHELPUSTOREDUCEWASTETHCONTACTTHEDOCUMENTCONTROLDESK,ROOMOWFN5D-5(EXT.
415-2083)
TOELIMINATE YOURNAMEPROMDISTRIBUTION LISTSFORDOCUMENTS YOUDON'TNEEDlFULLTEXTCONVERSION REQUIREDTOTALNUMBEROFCOPIESREQUIRED:
LTTR25ENCL25 FloridaPower8LightCompany,6501SouthOceanOrive,JensenBeach,FL34957July29,1997L-97-19010CFR50.73U.S.NuclearRegulatory Commission Attn:DocumentControlDeskWashington, D.C.20555Re:St.LucieUnit2DocketNo.50-389Reportable Event:97-006DateofEvent:June30,1997Operation Prohibited byTechnical Specifications duetoInadequate TheattachedLicenseeEventReportisbeingsubmitted pursuanttotherequirements of10CFR50.73toprovidenotification ofthesubjectevent.Verytrulyyours,J.A.StallVicePresident St.LuciePlantJAS/EJBAttachment cc:RegionalAdministrator, USNRCRegionIISeniorResidentInspector, USNRC,St.LuciePlant9708050269 970729'DR ADQCK05000$89SPDR0!llll!llll!
Illl!Illlllllllllllllllllll anFPLGroupcompany NRCFORM366(4-95)U.S.NUCLEARREGULATORY COMMISSION LICENSEEEVENTREPORT(LER)ISBBreverseforrequirednumberofdigits/characters foreachblock)APPROVEDBYOMSNO.3'l60%(04 EXPIRES04/30/SSESTIMATED BURDENPERRESPONSEToCOMPLYWITHTHISMANDATORINFORMATION COLLECTION REQUEST:60.0HRS.REPORTEDLESSONLEARNEDAREINCORPORATED INTOTHEUCENSINGPROCESSANOFsACKToINDUSTRY.
FO/r/t/ARD COMMENTSREGARDING BURoENEst/MATToTHEINFORMATION ANDRECORDSMANAGEMENT BRANCH(T-0F33)U.S.NUCLEARREGULATORY COMMISSION, WASHINGTON, DC20$6$%001ANDToTHEPAPERWORK REDUCTION PROJECT(3160%104),
OFFICE0MANAGEMENT ANDBUDGET,WASHINGTON, DC20603.FACIUTyNAME(1)STLUCIEUNIT2DOCKETNUMBER(2)05000389PAGE(3)1OF4TITLE(4)Operation Prohibited byTechnical Specifications duetoInadequate Surveillance TestingofEngineered SafetyFeaturesSubgroupRelaysMONTH06DAYYEAR3097YEARSEQUENTIAL REVISIONNUMBERNUMBER97-006-00MONTH07OAY29YEAR97FACIUTYNAMEFACIUTYNAMEN/AN/ADOCKETNUMBER DOCKETNUMBER OPERATING MODE(9)POWERLEVEL(10)10020.2201(b)20.2203(a)
(2)(i)20.2203(a)
(2)(v)20.2203(a)
(3)(ii)50.73(a)(2)(i)50.73(a)(2)(iii)50.73(a)(2)(viii) 73.71OTHERp./y~~~~iiagm//2 j';...Y@~y<a'ayr20.2203(a)
(2)(iii)20.2203(a)(2)
(iv)50.36(c)(1) 50.36(c)(2) 50.73(0)(2)(v)50.73(a)(2)(vii)
SpecifyinAbstractbeloworinNRCForm366ANAMEEdwinJ.Benken,Licensing EngineerTELEPHONE NUMBERBoo/udeAreaCode)(561)467-7156CAUSESYSTEMCOMPONENT MANUFACTURER REPORTABLE ToNPRDSCAUSESYSTEMCOMPONENT MANUFACTURER REPORTABLE ToNPRDSYES,(lfyes,completeEXPECTEDSUBMISSION DATE).XNoEXPECTEDSUBMISSION DATE(15)MONTHDAYYEARABSTRACT(Limitto1400spaces,i.e.,approximately 15single-spaced typewritten lines)(16)OnJune30,1997,St.LucieUnit2wasoperating inMode1at100percentpower.Anengineering reviewidentified adeficiency intheperformance ofEngineered SafetyFeatures(ESF)logictestingassociated withtwosubgrouprelaysforthecontainment isolation system.Thesubgrouprelayswererequiredtobetested'at asemi-annual frequency, buthadinsteadbeentestedonceper18months.Thisrepresented afailuretoperformasurveillance requirement withintheallowedsurveillance intervalandtherefore acondition prohibited bytheplantTechnical Specifications.
Thesubjectrelaysfunctiontosecuretheoperation ofthecontainment purgefansandtoclosethecontainment purgeisolation valvesduringactuation ofacontainment isolation signal.Sincethesecontainment purgecomponents arerequiredtobemaintained intheirpost-accident configuration duringreactoroperation, themissedtesting'was notsafetysignificant.
Thesubgrouprelayswererecentlytestedsatisfactorily andarecurrently withintheallowable surveillance interval.
ThefailuretotesttheESFASsubgrouprelaysattherequiredsurveillance intervalwascausedbyaninadequacy inimplementing theTSrequirements intheplantsurveillance procedures.
Corrective Actionsinclude:1)Plantsurveillance procedures willberevisedtoincludetheappropriate requirements forsurveillance testingofthesubgrouprelays.2)Surveillance testingistobeperformed inaccordance withrevisedprocedural instructions andwithintheallowable surveillance interval.
3)Logiccircuittestprocedures arecontinuing tobereviewedatSt.LucieUnit1forproperTSimplementation.
NRCFOAM366(4-95)
NRCFORM366AI4-95)LICENSEEEVENTREPORT(LER)TEXTCONTINUATION U.S.NUCLEARREGULATORY COMMISSIO ST.LUCIEUNIT205000389YEARSEQUENTIAL REVISION97-006-002OF4TEXTilfmorespaceisrequired, useadditional copiesofhlRCForm366AiI17ISt.LucieUnit2Technical Specifications (TS)fortheEngineered SafetyFeaturesActuation System(ESFAS)[EIIS:JEj requirethatasubgrouprelaytestbeperformed semi-annually toverifyoperability oftheautomatic actuation logicforthecontainment isolation system(CIS).TheUnit2UpdatedFinalSafetyAnalysisReport(UFSAR),Table7.3-9a,identifies specificsubgrouprelayswhichcannotbetestedwiththereactoratpowerduetothepotential impacttoplantoperation.
Fortheserelays,surveillance testingisperformed whentheunitisshutdown.
OnJune30,1997,adiscrepancy wasidentified regarding theplantTSsurveillance requirement (TS4.3.2.1)fortheESFASsubgrouprelays,theUFSARtable7.3-9a,andcurrentplanttestingpractices.
Areviewoftheplanttestingprocedures performed byFPLengineering personnel determined thattwoESFASsubgrouprelays(K512AandK612A)[EIIS:JE:RLYJ werenotbeingappropriately testedwithinthesemi-annual periodasrequiredbyTSandthattheserelayswerenotexemptfromtestingatpowerasdescribed intheUFSARtable.Therelayswerebeingfunctionally testedonan18monthbasisduringperformance oftheEngineered SafetyFeatures(ESF)periodictestandnotona6monthfrequency asrequired.
SubgrouprelaysK512AandK612AfunctionuponreceiptofaContainment Isolation Actuation System(CIAS)signaltosecurethecontainment purgefans,HVE-8AandHVE-88[EIIS:VA:FAN),
andto'closethecontainment purgeisolation valvesFCV-25-1throughFCV-25-6[EIIS:VA:ISVJ.
Thepurgefansandisolation valvesaremaintained intheirpost-accident configuration whentheUnitisatpower.St.LucieUnit2wasoperating inMode1at100percentpowerwhenthetestingdiscrepancies wereidentified.
Performance ofthe18monthintegrated ESFtest,completed May19,1997,currently satisfies thesixmonthsurveillance requirement.
Theidentification oftheESFASsubgrouprelaytestdiscrepancy wasmadeduringthepreparation ofanengineering evaluation foraplantlicenseamendment designedtoclarifytheplantTSwithregardtosubgrouprelaytesting.Thiswasafollowupactionbeingimplemented subsequent toFPL'sreviewofelectrical logiccircuittestingforSt.LucieUnit2,whichwasperformed inaccordance withtherecommendations ofGenericLetter96-01.ThefailuretotestESFASsubgrouprelaysK512AandK612Awascausedbyaninadequate surveillance testprocedure.
Surveillance Operating Procedure 2-0400053, "Engineered Safeguards RelayTest,"containstheinstructions requiredforverifying theproperfunctioning ofESFrelaysasrequiredbytheplantTechnical Specifications.
Thesurveillance procedure aswrittendidnotprovideaconclusive testofoperability forsubgrouprelaysK512AandK612Abyverifying component actuation ortheoperation ofoutputcontactsfromtherelays.Justification fornotincluding testinstructions forthesubgrouprelaysintheprocedure wasinsufficient, inthatitwasbasedupontherequirement thatthecontainment purgeisolation valvesmustremainintheirclosed(safe)positionduringpoweroperation.
SincethevalvescouldnotbeopenedinModes'1through4,andthepurgefanswererequiredtobemaintained deenergized, itwasincorrectly assumedthattestingforthecontainment isolation functionwasnotrequiredintheseModes.
NRCFORM366A(4-95)LICENSEEEVENTREPORT(LER)TEXTCONTINUATION U.S.NUCLEARREGULATORY COMMISSIO FACILITYNAME1ST.LUCIEUNIT2TEXTflfmoreepecelerequired, ueeeddidonel copleeofNRCForm366AJ(17)DOCKET05000389LERNUMBER(6SEQUENTIAL REVISIONNUMBERNUMBER97-006-00PAGE33OF4ESFAStestingisconducted periodically duringnormalplantoperation inaccordance withtheSt.LucieUnit2Technical Specifications toverifyoperability.
TSsurveillance requirement 4.3.2.1,requiresthateachESFASinstrument channelbedemonstrated operablebytheperformance oftheChannelCheck,ChannelCalibration andChannelFunctional testoperations fortheModesandatthefrequencies
'escribed inTSTable4.3-2.Note2ofthistablespecifies thatfortheautomatic actuation logicassociated withCIAS,asubgrouprelaytestshallbeperformed toincludetheenergization ordeenergization ofeachsubgrouprelayandverification oftheoperability foreachrelay.Thefrequency specified bytheTSforperformance ofthissurveillance issemi-annual (SA)~Thiscondition doesnotapplytoSt.LucieUnit1,astheESFASinstrumentation Technical Specifications atUnit1donotcontainthesamerequirement forsemi-annual testingoftheCIASsubgrouprelays.TheESFASactuation deviceswhicharenottestedduringreactoroperation, duetotheirimpacttotheplant,aretestedduringscheduled reactorshutdowns toassurethattheyarecapableofperforming theirintendedfunction.
Thisisdescribed intheSt.LucieUnit2UFSAR,Table7.3-9a,whichliststheESFASactuation relaydevicesnottestedduringnormaloperating conditions.
SubgrouprelaysK512AandK612Aarenotincludedinthetableandarecapableofbeingtestedduringpoweroperation, byverification ofoutputcontactstatususingadigitalvoltmeter(DVM).Theserelaysaretherefore requiredtobetestedonasemi-annual basis.SubgrouprelaysK512AandK612Aactuatecomponents ofthecontainment purgesystemuponreceiptofaCIASsignal.Specifically, therelaysfunctiontoclosethecontainment purgeisolation valvesFCV-25-1,2,3,4,5and6,andtostopcontainment purgefansHVE8Aand8B.Therelaysarecycledduringthesemi-annual surveillance test,howeververification ofcomponent actuation oroutputcontactstatusisnotperformed.
Althoughacompleteverification ofoperability fortheserelayswasnotperformed onasemi-annual basis,therelayswerefunctionally testedevery18monthsduringtheperformance oftheintegrated Engineered SafetyFeaturesPeriodicTestandhadbeensatisfactorily testedduringthelastperformance ofthistest,completed May19,1997.Asaresultoftheprevioussurveillance, currentsystemoperation iswithintheallowable sixmonthsurveillance intervalandtherefore, nooperability concernexists.Thefailuretopreviously testESFASsubgrouprelaysK512AandK612Aonasemi-annual basis,asrequiredbyTS4,3.2,1,represents acondition prohibited bytheplantTechnical Specifications andistherefore reportable under50.73(a)(2)(i)(B).ESFASsubgrouprelaysK512AandK612Aaffectonlythecontainment purgecomponents previously described.
With'theexception ofthecontainment isolation
- function, thecontainment purgesystemisanon-safety relatedandnon-seismic systemusedtoprovideventilation ofthecontainment buildingforpersonnel accessduringshutdownandrefueling.
Thesystemisnotusedatpowerandistherefore notrequiredtooperatefollowing adesignbasisaccident.
NRCFORM366AI4-8SILICENSEEEVENT.REPORT(LER)TEXTCONTINUATION U.S.NUCLEARREGULATORY COMMISSIO ST.LUCIEUNIT205000389YEARSEQUENTIAL REVISION97-006-004OF4TEXT(Ifmorespecsisrequired, useedditionel copiesofNRCFarm386AiI17lThecontainment purgeexhaustfans,HVE-8AandHVE-88aremaintained deenergized duringplantoperation.
Additionally, TS3.6.1.7requiresthateachcontainment purgeisolation valvebesealedclosedwhenoperating inModes1,2,3or4.Asaresultoftheabovemeasures, thecontainment purgesystemismaintained initspost-accident configuration duringpoweroperation (Modes1through4)andisnotrequiredtoreposition intheeventofanESFASactuation duringtheseModes.Theactuation ofCIScomponents bysubgrouprelaysK512AandK612Awassatisfactorily testedduringanintegrated ESFperiodicsurveillance completed onMay19,1997.ThefailuretotesttheESFASsubgrouprelays,K512AandK612A,atasemi-annual frequency isnotsafetysignificant sincethecomponents affectedbytheserelaysarerequiredtobemaintained intheirpost-accident configuration duringModes1through4.Plantoperating procedure 2-0400053, "Engineered Safeguards RelayTest"willberevisedtoincludesurveillance testingfortheoutputcontactstatusofsubgrouprelaysK512AandK612Awhichaffectthecontainment purgecomponents.
2.ESFASsurveillance testingfortheUnit2containment purgeisolation valvesandfanswillbeconducted inaccordance withtherevisedprocedure andwithintheallowable surveillance intervalbasedonthelastsurveillance testcompleted forthesecomponents.
3.FPLiscontinuing toperformareviewoftheSt.LucieUnit1ESFASsurveillance testprocedures and'logic circuittestinginaccordance.
withtherecommendations ofGenericLetter(GL)96-01toensurethatTSrequirements arebeingadequately implemented.
4,Inordertoreemphasize theexpectation thatplantsurveillances andprocedures fullyimplement theTechnical Specification requirements inaverbatimmanner,trainingbriefsarebeingissuedtokeymaintenance andsiteengineering personnel.
Inaddition, thiseventwillbeincludedintothecontinuing trainingprogramforlicensedoperators asareviewoflessonslearned.-NonePreviousSimilarEvents-LERs389/96-005 and389/96-006 describesurveillance inadequacies previously identified byFPLduringlogiccircuitry testingreviewsperformed inaccordance withtherecommendations ofGL96-01.
