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| | issue date = 06/18/1992 | | | issue date = 06/18/1992 |
| | title = LER 92-004-00:on 920521,relay Time Delay Settings Altered Due to Personnel Error.Remaining Load Sequence Timers on Both Units 1 & 2 Were Inspected to Ensure Thumbwheel Switches Were Set correctly.W/920618 Ltr | | | title = LER 92-004-00:on 920521,relay Time Delay Settings Altered Due to Personnel Error.Remaining Load Sequence Timers on Both Units 1 & 2 Were Inspected to Ensure Thumbwheel Switches Were Set correctly.W/920618 Ltr |
| | author name = SAGER D A, WACHTEL P K | | | author name = Sager D, Wachtel P |
| | author affiliation = FLORIDA POWER & LIGHT CO. | | | author affiliation = FLORIDA POWER & LIGHT CO. |
| | addressee name = | | | addressee name = |
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| {{#Wiki_filter:DOCKET05000335ACCELERATED'STIUBUTIONDEMONSATIONSYSTEMREGULATYINFORMATIONDISTRIBUTIONSYSTEM(RIDS)jagACCESSIONNBR:9206250161DOC.DATE:92/06/18NOTARIZED:NOFACIL:50-335St.LuciePlant,Unit1,FloridaPower&LightCo.AUTH.NAMEAUTHORAFFILIAT10NWACHT'EL,P.K.FloridaPower&LightCo.SAGER,D.A.FloridaPower&LightCo.RECIP.NAMERECIPIENTAFFILIATION | | {{#Wiki_filter:ACCELERATED 'STIUBUTION DEMONSATION SYSTEM REGULAT Y INFORMATION DISTRIBUTION SYSTEM (RIDS) jag DOC.DATE: 92/06/18 NOTARIZED: NO DOCKET ACCESSION NBR:9206250161 FACIL:50-335 St. Lucie Plant, Unit 1, Florida Power & Light Co. 05000335 AUTH. NAME AUTHOR AFFILIAT10N WACHT'EL,P.K. Florida Power & Light Co. |
| | SAGER,D.A. Florida Power & Light Co. |
| | RECIP.NAME RECIPIENT AFFILIATION |
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| ==SUBJECT:== | | ==SUBJECT:== |
| LER92-004-00:on920521,relaytimedelaysettingsalteredduetopersonnelerror.RemainingloadsequencetimersonbothUnit1&Unit2wereinspectedtoensurethumbwheelswitchesweresetcorrectly.W/920618ltr.DISTRIBUTIONCODE:IE22TCOPIESRECEIVED:LTRrENCLgSIZE:TITLE:50.73/50.9LicenseeEventReport(LER),IncidentRpt,etc.NOTES:RECIPIENTIDCODE/NAMEPD2-2LANORRIS,J1NTERNAL:ACNWAEOD/DOAAEOD/ROAB/DSPNRR/DLPQ/LHFB10NRR/DOEA/OEABNRR/DST/SELB8DNRRfDSSPLB8D1REGFILE02RLE01EXTERNAL:EG&GBRYCEiJ.HNRCPDRNSICPOORETW.COPIESLTTRENCL1111221122111111111111331111RECIPIENTIDCODE/NAMEPD2-2PDACRSAEOD/DSP/TPABNRR/DET/EMEB7ENRR/DLPQ/LPEB10NRR/DREP/PRPB11NRR/DST/SICB8H3NRR/DST/SRXB8ERES/DSIR/EIBLSTLOBBYWARDNSICMURPHY,G.ANUDOCSFULLTXTCOPIESLTTRENCL11221111112211111111111NOTETOALL"RIDS"RECIPIENTS:PLEASEHELPUSTOREDUCEWASTE!CONTACI'HEDOCUMENTCONTROLDESK,ROOMPl-37(EXT.20079)TOELIMINATEYOURNAMEFROMDISTRIBUTIONLINISFORDOCUMENTSYOUDON'TNEED!FULLTEXTCONVERSIONREQUIREDTOTALNUMBEROFCOPIESREQUIRED:LTTR32ENCL32 P.O.Box128,Ft.Pierce,FL34954-0128June18,1992L-92-16710CFR50.73U.S.NuclearRegulatoryCommissionAttn:DocumentControlDeskwashington,D.C.20555Re:St.LucieUnit1DocketNo.50-335ReportableEvent:92-004DateofEvent:May21,1992RelayTimeDelaySettingsAlteredduetoPersonnelErrorcausesConditionProhibitedbTechnicalSecificationsTheattachedLicenseeEventReportisbeingsubmittedpursuanttotherequirementsof10CFR50.73toprovidenotificationofthesubjectevent.Verytrulyyours,D.A.gerVicersidentSt.LuePlantDAS/JWH/kwAttachmentcc:StewartD.Ebneter,RegionalAdministrator,USNRCRegionIISeniorResidentInspector,USNRC,St.LuciePlantDAS/PSLN715-929206250161920618PDRADOCK050003358PDRanFPLGroupcompany FPLFcccirrTlcdIFICForm380US.NUCLEARREGNATORYCOMMISSIONLICENSEEEVENTREPORT(LER)ATTIXXCOCACIICX0IICCI0100CCCC00000CCICIATTOOACCCIOIImCCXCCTO00XCTTTCOI~0CTXCIATXCIIXXITCT0XIICXACCT:000ICTATOCCAIXICCICCXICICCAICCXIIAACXIIICICIAIClolloICCIXTXIAICIICTCCICINAIXTCNfITMCIXI+44QLIIXIAAXCACICOAAT0XITCASSAVAWIS44lRW,OC00MCrCDloTHC00tIICCX00ICOUCTXXIICOCCT0IICCICC.CIIICIOIIWNODCICIIXIIMXXTAOCXCIXAOC00001FACILITYNAME(1)St.LucieUnit1DOCKETNUMBER(2)PAGE305000335104~(4)RelayTimeDelaySettingsAlteredduetoPersonnelErrorCausesConditionProhibitedbyPlantTechnicalSpecificationsEVENTDATE(5)LERNUMBER(6)REPORTDATEmOTHERFACILITIESINVOLVED(8)05DAY21YEAR92SALR920040006DAYYEAR1892FACILITYNAMESN/AN/ADOCKETNUMBER(S)05000OPERATINGMODE(9)20.402(b)20.405(c)50.73(a)(2)(iv)THISREPORTISSUBMITIEDPURSUANTTOTHEREQUIREMENTSOF10CFR:Checkoneormoreofthefollowin(11)73.71(b)POWERLEVEL(10)10020.405(a)(1)(i)20.405(a)(1)(ii)20.405(a)(1)(iii)20.405(a)(1)(iv)20.405(a)(1)(v)50.36(c)(1)50.36(c)(2)50.73(a)(2)(I)50.73(a)(2)(ii)50.73(a)(2)(iii)50.73(a)(2)(v)50.73(a)(2)(vii)50.73(a)(2)(viii)(A)50.73(a)(2)(viii)(B)50.73(a)(2)(x)73.71(c)OTHER(SpecifyinAbstractbelowandinTextNRCForm388A)LICENSEECONTACTFORTHISLER12PatriciaK.Wachtel,ShiftTechnicalAdvisorTELEPONENUMBERAREACODE407465-3550COMPLETEONELINEFOREACHCOMPONENTFAILUREDESCRIBEDINTHISREPORT13SYSTEMCOMPONENTMANUFAC-REPORTABLETURERTONPRDSCAUSESYSTEMCOMPONENTMANUFAC-TURERREPORTABLETONPRDSSUPPLEMENTALREPORTEXPECTED14YES(Ifyes,completeEXPECTEDSUBMISSIONDATE)NOEXPECTEDMONTHDAYYEARSUBMISSIONDATE(15)ABSTRACT(Limitto1400spaces.I.e.approximatelyfifteensingle-spacetypewrittenlines)(16)OnMay21,1992,St.LucieUnit1wasinmode1,operatingat100%steadystatepower.AutilityengineerwasinspectingthetimedelaysettingsonAgastatrelaysInspecifhelectricalbuseswhenitwasdiscoveredthatthetimerthumbwheelsettingsforthe1AComponentCoolingWaterpumpandthe18ContainmentSpraypumpwereverydosetothe+I-onesecondTechnicalSpecificathnsurveillancetolerancefordieselgeneratorloadsequencing.Subsequentinvestigationrevealedthatthetimedelaysettingshadbeenaltered.Thecauseofthiseventwaspersonnel,error.Whilecleaningthecubidesinwhhhtheserelayswerelocated,acontractmaintenanceworkerinadvertentlychangedthetimesettingsonthethumbwheelswitcheswhilecleaningthefacesoftherelays.Correctiveactionstakeninclude:1)theAgastatrelayswereresettocomplywithTechnicalSpecifications,2)themaintenancecrewswerecounseledonhowtocleantherelaysandnotdisturbthehadsequencetimersettings,3)theswitchgearcleaningprocedurewaschangedtoensurethecorrectthumbwheelswitchsettingisverifiedpriortoreturningtheelectricalbustoservice,and4)theremaininghadsequencetimersonbothUnit1andUnit2wereinspectedtoensurethethumbwheelswitchesweresetcorrectly.FPLFacsimileofNRCForm366(M9)
| | LER 92-004-00:on 920521,relay time delay settings altered due to personnel error. Remaining load sequence timers on both Unit 1 & Unit 2 were inspected to ensure thumbwheel switches were set correctly.W/920618 ltr. |
| FPLFffcaffffleDiACFOffff$$IMolUa.NUCLEARREGULATORYCOMMfssfONUCENSEEEVENTREPORT(LER)TEXTCONTINUATIONITTCTTTDCCCIICLTINCIfl~AIICCTTCTCIATKDTAICIINICIIICWCtfNTOCCACCTTCTIITICICCCICIATIIWCCIICCTII7IICCIXCT:TOCIITATCITWNCTCTACCNTCICCNICNCTA/ITINCCTCIAIClOllCICCNCCNCIICTCSNCNINAINICNTCDANCE~IACMX1CARICOAAICITTCNIICIIAWANDCITCN,DCTIINCAKIlOTINtNTTIATÃTICTACT11IIICICCTffIICCICCCITICCCfIWWCINNTNCTIACIICTWAIADKflDADCTCICAFACILITYNAME(1)St.LucieUnit1DOCKETNUMBER(2)LERNUMBER(6)EQUENTIALREVISIONUMBERNUMBERPAGE(3)0500033592TEXT(limorespaceisrequired,useadditionalNRCForm366A's)(17)004000204OnMay21,1992,St.LucieUnit1wasinmode1at100%steadystatepower.Autilityengineerwasinspectingthe1A3and1B3electricalbuses(EIIS:EB)tocheckthetimedelaysettingsonspecificAgastatrelays.Thisinspectionwasbeingperformedinresponsetoanengineeringassessmentrelatingtorecentindustryeventsonloadsequencetimers.TheinvestigationatSt.LucieUnit1revealedthatthetimedelaysettingsforthe1AComponentCoolingWaterpump(EIIS:CG)(CGW)andthe1BContainmentSpraypump(EIIS:BE)(CS)wereIncorrect.Thefollowingdatawasprovkledfollowingtheinspection:1ACCW1BCSREQUIREDTIMEAS-FOUND(4-1second)Tl-IUMBWHEELSETIING6.007.0112.001298AS-FOUNDTlME(05-2142)7.1713.11A%AFTTIME6.12secords12.16secondsThisindicatedthatboththe1ACGWand1BCSpumpshadtheirtimedelaysettingsoutskfeofthe+/-onesecondloadsequencingsettingrequiredbyTechnicalSpecificationsutveillancerequirement4.8.1.1.2.e.11.ThetimeswerelastverifiedduringtheUnit1PeriodicIntegratedTestoftheEngineeredSafetyFeaturesperformedinOctober,1991.Thefollowingtimesettingsweredocumentedforthesepumps:1ACGWpump-6.18seconds;1BCSpump-12.16seconds.EachofthesetimeswaswithintheacceptabletoleranceallowedbyplantTechnicalSpecifications.Thecauseofthiseventhasbeenattributedtopersonnelerror.Theinadvertentchangingofthetimerthumbwheelswitchesappearstohaveoccurredwhenthecubfciesonthe4160voltbusescontainingtheserelayswerecleanedduringthelastUnit1refuelingoutage.Whenthebusseswerecleaned,theworkercouldcomeincontactwiththethumbwheeiandinadvertentlyalterthetimedelaysettings.Therewerenounusualworkconditionswhichmayhavecontributedtothiseventnorwasthereanyspecificproceduralgukfancetocautionthecontractmaintenancepersonnelnottodisturbtheloadsequencetimersettingswhencleaningtherelays.Thiseventisreportableundertherequirementsof10CFR50.73.a.2.i.Bas"anyoperationorconditionprohibitedbytheplantTechnicalSpecTiications."TechnicalSpecificationsurveillancerequirement4.8.1.1.2.e.5requiresthatoncepereighteenmonths,alossofoff-sitepowerinconjunctionwithanengineeredsafetyfeatureactuationtestsignaI(EIIS:JE)besimulated.Followingthestartoftheemergencydieselgenerator(EDG)(EIIS:EK),theemergencybusseswithpermanentlyconnectedloadsenergizationandtheauto~nnectedemetgency(accident)loadsenergizationthroughtheauto-sequencermustbeverified.VerificationthattheautomaticloadFPLFacsimiieofNRCForm366(649)
| | DISTRIBUTION CODE: IE22T COPIES RECEIVED:LTR r ENCL TITLE: 50.73/50.9 Licensee Event Report (LER), Incident Rpt, etc. |
| AILFarmlrrffoofIRCFcrrrr368gHffrjU.S.NUCLEARREGULATORYCOMMfSSIoffLICENSEEEVENTREPORT(LER)TEXTCONTTNUATTONAARTORoOWIRILTIRCITlcTTORRACAOTTCTTAATTOILROTRITITICIATTCRTdOCARLTTATllTIRIOCCICIATCRCCLITOTICTRIARCH:RANTLICRWARTCOWRRTCIRONCRAIIMTRRICRRATCldIIRICOCICRRDICICRTCRANI/RIRRTCRAROIrRRRLIIRILCLTARICCRAATCRTOISRRRTLWRRATR7I.OCRRRLHoIoTIRPARRRCIRlCITUCTCRIROCCTTTIIOCIRLCTRCCEÃAMRARTRRTRORAXRT,WARRRROROCTOOLFACILITYNAME(1)St.LucieUnit1DOCKETNUMBER(2)LERNUMBER(6)EQUENTIALNUMBERREVISIONUMBERPAGE(3)05000335TEXT(Ifmorespaceisrequired,useadditionalNRCForm366A's)(17)92004000304sequencetimersareoperablewiththeintervalbetweeneachloadbkckwithin+/-onesecondofitsdesignintervalisrequiredasperTechnicalSpecificationsurveillancerequirement4.8.1.1.2.e.11.AlthoughthissurveillancewasperformedsatisfactorilysevenmonthsagoduringtheUnit1refuelingoutage,theas-foundsettingsforthe1AComponentCoolingWaterandthe1BContainmentSpraypumpsindicatethattheywouldnothaveloadedontotheEDGinthepropersequence.Adetailedengineeringevaluation(JPN-PSL-SEEP-92-031)wasperfomedtodemonstratethattheEDGwouldhaveperformedacceptablywiththeas-'foundtimersettings.ConclusionsfromthisevaluationindicatedthatthetimersettingsdidnotadverselyaffecttheabilityoftheEmergencyDieselGeneratorstosupplypowertotherequiredEngineeredSafetyFeatureloadsunderdesignbasislossofoff-sitepowerandaccidentconditions.Thehealthandsafetyofthepublicwasnotatriskatanytimewhileinthiscondition.1.Therequiredtimedelaysettingswererestoredforthetwoalteredloadsequencetime+.2.TheremainingloadsequencetimersonbothUnit1andUnit2wereinspectedtoensurethethumbwheelswitchesweresetcorrectly.Allwereunchanged.3.ElectricalmaintenancewillvisuallyverifythatallloadsequencetimersaresetcorrectlypriortoenteringMode4subsequenttoarefuelingoutage.Thisverificationwillbeincorporatedintoplantprocedures.4.TheswitchgearcleaningprocedurewaschangedtoincludestepstoverifythetimerthumbwheelswitchsettingiswithinTechnicalSpecificationslimitsbeforereleasingthebusforsoNice.5.Electricalmaintenancesupervisorscounseledcontractorandutilitymaintenancepersonnelnottodisturbtheloadsequencetimerswhilecleaningtheswitchgearcubicles.6.ThePlantMaintenanceDepartmentsevaluatedotherpreventativemaintenancecleaningproceduresforthepotentialtodisturbthesettingsofloadsequencetimers.FPLFacsimileofNRCForm366(649)
| | g SIZE: |
| | NOTES: |
| | RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD2-2 LA 1 1 PD2-2 PD 1 1 NORRIS,J 1 1 1NTERNAL: ACNW 2 2 ACRS 2 2 AEOD/DOA 1 1 AEOD/DSP/TPAB 1 1 AEOD/ROAB/DSP 2 2 NRR/DET/EMEB 7E 1 1 NRR/DLPQ/LHFB10 1 1 NRR/DLPQ/LPEB10 1 1 NRR/DOEA/OEAB 1 1 NRR/DREP/PRPB11 2 2 NRR/DST/SELB 8D 1 1 NRR/DST/SICB8H3 1 1 NRRfDSSPLB8D1 1 1 NRR/DST/SRXB 8E 1 1 REG FILE 02 1 1 RES/DSIR/EIB 1 R LE 01 1 1 EXTERNAL: EG&G BRYCE i J. H 3 3 L ST LOBBY WARD 1 1 NRC PDR 1 1 NSIC MURPHY,G.A 1 1 NSIC POORETW. 1 1 NUDOCS FULL TXT 1 1 NOTE TO ALL "RIDS" RECIPIENTS: |
| | PLEASE HELP US TO REDUCE WASTE! CONTACI'HE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT. 20079) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LINIS FOR DOCUMENTS YOU DON'T NEED! |
| | FULL TEXT CONVERSION REQUIRED TOTAL NUMBER OF COPIES REQUIRED: LTTR 32 ENCL 32 |
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| FPLFscttmleatPICFomlSOBIMQjU.S.NUCLEARREGULATORYCOMMSSTONLICENSEEEVENTREPORT(LER)TEXTCONTINUATIONI¹IWOIOOt¹eIOITIWOIOICOTWATI¹J¹IC¹OCIII¹OKN¹TOOOWLTTOTIIll¹IOOCCCCAlla¹Ot1ICOODII¹cl¹oo¹I>II¹cTawwtccloC¹o¹¹l1I¹olc¹two¹JsolIoo¹AI¹lollcI¹cccooHCII¹¹C¹T1¹AHAI¹I¹IITOIIA¹CHt¹CCOLII¹IA¹CCA¹l¹C¹CATI¹IICOO+O¹t¹CAAOIOICW.OOTIOOAIIDTOTIOTJIUC¹WOIWICCCCICHIIOC¹OTCIIWAIL%OIIICOI¹¹AKIÃA¹¹TNO¹AX¹T.WA¹¹et¹t¹COO$0¹CLFACILUYNAME(1)St.LucieUnit1DOCKETNUMBER(2)LERNUMBER(6)EQUENTIALREVISIONUMBER.NUMBERPAGE(3)0500033592TEXT(Ifmorespaceisrequired,useadditionalNRCForm366A's)(17)004000404Therewasnocomponentfailureduringthisevent;however,specificcomponentidentificationisincludedforinformationalpurposes.Relay:PartNumber.Manufacturer:Agastat7tmingRelayDSBXXOI25SPAXAAAmeraceCorporationTherehavebeennopreviouseventsinwhichmaintenancepersonnelhaveinadvertentlyalteredrelaytimedelaysettings.FPLFacsimileofNRCForm366(649)
| | P.O. Box 128, Ft. Pierce, FL 34954-0128 June 18, 1992 L-92-167 10 CFR 50.73 U. S. Nuclear Regulatory Commission Attn: Document Control Desk washington, D. C. 20555 Re: St. Lucie Unit 1 Docket No. 50-335 Reportable Event: 92-004 Date of Event: May 21, 1992 Relay Time Delay Settings Altered due to Personnel Error causes Condition Prohibited b Technical S ecifications The attached Licensee Event Report is being submitted pursuant to the requirements of 10 CFR 50.73 to provide notification of the subject event. |
| }} | | Very truly yours, D. A. ger Vice r sident St. Lu e Plant DAS/JWH/kw Attachment cc: Stewart D. Ebneter, Regional Administrator, USNRC Region II Senior Resident Inspector, USNRC, St. Lucie Plant DAS/PSL N715-92 9206250161 920618 PDR ADOCK 05000335 8 PDR an FPL Group company |
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| | FPL FcccirrTlc d US. NUCLEAR REGNATORY COMMISSION ATTIXXCOCACIICX0IICCI01 IFIC Form 380 00CCCC 00000 CCICIATTOOACCC IOI ImCCXCC TO 00XCTT TCOI ~ 0CTXCIATXCIIXXITCT0XI lo llo LICENSEE EVENT REPORT (LER) ICXACCT:000 ICTA TOCCAIXICCICCXIC ICCAICCXIIAACXIIICICIAIC ICCIXTXIAICIICTCCIC INAIXTCNfITMCIXI+44QL IIXIAAXCAC IC OAAT0XIT lo CASSAVAWIS44lRW, OC 00MC rCD THC 00tIICCX00 ICOUCTXXIICOCCT 0IICCICC. CIIICIOI IWNODCICIIXIIMXXT AOCXCIXAOC 00001 FACILITYNAME (1) DOCKET NUMBER (2) PAGE 3 St. Lucie Unit 1 050003351 |
| | ~ (4) Relay Time Delay Settings Altered due to Personnel Error Causes Condition Prohibited 0 4 by Plant Technical Specifications EVENT DATE (5) LER NUMBER (6) REPORT DATE m OTHER FACILITIES INVOLVED(8) |
| | DAY YEAR S AL R DAY YEAR FACILITYNAMES DOCKET NUMBER(S) |
| | N/A 0 5 21 9 2 9 2 0 0 4 0 0 0 6 1 8 9 2 N/A 05000 THIS REPORT IS SUBMITIEDPURSUANTTOTHE REQUIREMENTS OF 10 CFR: |
| | OPERATING Check one or more of the followin (11) |
| | MODE (9) 20.402(b) 20.405(c) 50.73(a)(2)(iv) 73.71(b) |
| | POWER 20.405(a)(1)(i) 50.36(c)(1) 50.73(a)(2)(v) 73.71(c) |
| | LEVEL (10) 1 0 0 20.405(a) (1)(ii) 50.36(c)(2) 50.73(a)(2)(vii) OTHER (Specify in Abstract 20.405(a)(1)(iii) 50.73(a)(2) (I) 50.73(a)(2)(viii)(A) below andin Text 20.405(a)(1)(iv) 50.73(a)(2)(viii)(B) NRC Form 388A) 50.73(a)(2)(ii) 20.405(a)(1)(v) 50.73(a)(2)(iii) 50.73(a)(2)(x) |
| | LICENSEE CONTACT FOR THIS LER 12 TELEP ONE NUMBER AREA CODE Patricia K. Wachtel, Shift Technical Advisor 4 0 7 465 -3550 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT 13 REPORTABLE MANUFAC- REPORTABLE SYSTEM COMPONENT MANUFAC- TURER TO NPRDS CAUSE SYSTEM COMPONENT TURER TO NPRDS SUPPLEMENTAL REPORT EXPECTED 14 EXPECTED MONTH DAY YEAR SUBMISSION YES (Ifyes, complete EXPECTED SUBMISSION DATE) NO DATE (15) |
| | ABSTRACT (Limit to 1400 spaces. I.e. approximately fifteen single-space typewritten lines) (1 6) |
| | On May 21, 1992, St. Lucie Unit 1 was in mode 1, operating at 100% steady state power. A utility engineer was inspecting the time delay settings on Agastat relays In specifh electrical buses when it was discovered that the timer thumbwheel settings for the 1A Component Cooling Water pump and the 18 Containment Spray pump were very dose to the+I- one second Technical Specificathn surveillance tolerance for diesel generator load sequencing. Subsequent investigation revealed that the time delay settings had been altered. |
| | The cause of this event was personnel, error. While cleaning the cubides in whhh these relays were located, a contract maintenance worker inadvertently changed the time settings on the thumbwheel switches while cleaning the faces of the relays. |
| | Corrective actions taken include: 1) the Agastat relays were reset to comply with Technical Specifications, 2) the maintenance crews were counseled on how to clean the relays and not disturb the had sequence timer settings, 3) the switchgear cleaning procedure was changed to ensure the correct thumbwheel switch setting is verified prior to returning the electrical bus to service, and 4) the remaining had sequence timers on both Unit 1 and Unit 2 were inspected to ensure the thumbwheel switches were set correctly. |
| | FPL Facsimile of NRC Form 366 (M9) |
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| | FPL FffcaffffleDi AC FOffff$$ |
| | IMol Ua. NUCLEAR REGULATORYCOMMfssfON |
| | ~ |
| | ITTCTTTDCCCI ICL TINCI AIICCT fl UCENSEE EVENT REPORT (LER) |
| | TEXT CONTINUATION NCI ICTCSNC NINAINICNTCDANCE WANDCITCN,DC TIINC AKIlO TIN |
| | ~ |
| | TCTCIATKDTAICIINICIIICWCtfNTO CCACCT TCTIITICICCCICIATIIWCCIICCTII7I ICCIXCT:TOC IITATCITWNCT CTACCNTC ICCNICNC TA/ITINCCTCIAIC lO llC ICCNCC tN IAC MX1CARICOAAICITT Cf IWWCINNTNCT IACIICT WAIADKflDADC TCICA ff CNIICIIA TTIATÃTI CTACT11I IICICCT IICCICC CITICC FACILITYNAME (1) DOCKET NUMBER (2) LER NUMBER (6) PAGE (3) |
| | EQUENTIAL REVISIO St. Lucie Unit 1 NUMBER NUMBER 0500033592 0 0 4 0 0 0 2 0 4 TEXT (limore spaceis required, use additional NRC Form 366A's) (17) |
| | On May 21, 1992, St. Lucie Unit 1 was in mode 1 at 100% steady state power. A utility engineer was inspecting the 1A3 and 1B3 electrical buses (EIIS:EB) to check the time delay settings on specific Agastat relays. This inspection was being performed in response to an engineering assessment relating to recent industry events on load sequence timers. The investigation at St. Lucie Unit 1 revealed that the time delay settings for the 1A Component Cooling Water pump (EIIS:CG) (CGW) and the 1B Containment Spray pump (EIIS:BE) (CS) were Incorrect. The following data was provkled following the inspection: |
| | REQUIRED TIME AS- FOUND AS-FOUND TlME A%AFT (4-1 second) Tl-IUMBWHEEL (05-2142) TIME SETIING 1ACCW 6.00 7.01 7.17 6.12 secords 1B CS 12.00 1298 13.11 12.16 seconds This indicated that both the 1A CGW and 1B CS pumps had their time delay settings outskfe of the |
| | +/- one second load sequencing setting required by Technical Specification sutveillance requirement 4.8.1.1.2.e.11. |
| | The times were last verified during the Unit 1 Periodic Integrated Test of the Engineered Safety Features performed in October, 1991. The following time settings were documented for these pumps: 1A CGW pump- 6.18 seconds; 1B CS pump -12.16 seconds. Each of these times was within the acceptable tolerance allowed by plant Technical Specifications. |
| | The cause of this event has been attributed to personnel error. The inadvertent changing of the timer thumbwheel switches appears to have occurred when the cubfcies on the 4160 volt buses containing these relays were cleaned during the last Unit 1 refueling outage. When the busses were cleaned, the worker could come in contact with the thumbwheei and inadvertently alter the time delay settings. There were no unusual work conditions which may have contributed to this event nor was there any specific procedural gukfance to caution the contract maintenance personnel not to disturb the load sequence timer settings when cleaning the relays. |
| | This event is reportable under the requirements of 10CFR50.73.a.2.i.B as "any operation or condition prohibited by the plant Technical Spec Tiications." Technical Specification surveillance requirement 4.8.1.1.2.e.5 requires that once per eighteen months, a loss of off-site power in conjunction with an engineered safety feature actuation test signaI (EIIS:JE) be simulated. |
| | Following the start of the emergency diesel generator (EDG) (EIIS:EK), the emergency busses with permanently connected loads energization and the auto~nnected emetgency (accident) loads energization through the auto-sequencer must be verified. Verification that the automatic load FPL Facsimiie of NRC Form 366 (649) |
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| | AILFarmlrrffo of U.S. NUCLEAR REGULATORY COMM fSS Ioff AARTORo OWI RIL TIRCI Tl IRC Fcrrrr 368 cTTORR ACAOT gHffrj LICENSEE EVENT REPORT (LER) TCTTAATTOILROTR ITIT ICIATTCRTd OCARLTTATllTIRIOCCICIATCR CCLIT OTIC TRIARCH:RA NTL ICRWART COWRRTC IRONCRAI IMTRR ICRRATC ld IIR ICOCICR RD ICICRTC RANI/RIR RT CRAROI rRRRL IIR ILCLTARICCRAATCRTOISRRRTL TEXT CONTTNUATTON W RRATR7I. OC RRRL Ho Io TIR PARRRCIR lCITUCTCR IROCCT TTIIOCIRLCTRCC EÃ AMRARTRRTRO RAXRT,WARRRROR OC TOOL FACILITYNAME (1 ) DOCKET NUMBER (2) LER NUMBER (6) PAGE (3) |
| | EQUENTIAL REVISIO St. Lucie Unit1 NUMBER NUMBER 0 500 0335 9 2 0 0 4 0 0 0 3 0 4 TEXT (Ifmore spaceis required, use additional NRC Form 366A's) (17) sequence timers are operable with the interval between each load bkck within+/- one second of its design interval is required as per Technical Specification surveillance requirement 4.8.1.1.2.e.11. |
| | Although this surveillance was performed satisfactorily seven months ago during the Unit 1 refueling outage, the as-found settings for the 1A Component Cooling Water and the 1B Containment Spray pumps indicate that they would not have loaded onto the EDG in the proper sequence. |
| | A detailed engineering evaluation (JPN-PSL-SEEP-92-031) was perfomed to demonstrate that the EDG would have performed acceptably with the as-'found timer settings. Conclusions from this evaluation indicated that the timer settings did not adversely affect the ability of the Emergency Diesel Generators to supply power to the required Engineered Safety Feature loads under design basis loss of off-site power and accident conditions. The health and safety of the public was not at risk at any time while in this condition. |
| | : 1. The required time delay settings were restored for the two altered load sequence time+. |
| | : 2. The remaining load sequence timers onboth Unit1 and Unit 2 were inspected to ensure the thumbwheel switches were set correctly. All were unchanged. |
| | : 3. Electrical maintenance will visually verify that all load sequence timers are set correctly prior to entering Mode 4 subsequent to a refueling outage. This verification will be incorporated into plant procedures. |
| | : 4. The switchgear cleaning procedure was changed to include steps to verify the timer thumbwheel switch setting is within Technical Specifications limits before releasing the bus for soNice. |
| | : 5. Electrical maintenance supervisors counseled contractor and utility maintenance personnel not to disturb the load sequence timers while cleaning the switchgear cubicles. |
| | : 6. The Plant Maintenance Departments evaluated other preventative maintenance cleaning procedures for the potential to disturb the settings of load sequence timers. |
| | FPL Facsimile of NRC Form 366 (649) |
| | |
| | FPL Fscttmle at U.S. NUCLEAR REGULATORY COMMSS TON I¹IWOIOOt¹e IOI TIWOI OI PIC Foml SOB IMQj LICENSEE EVENT REPORT (LER) COTWATI¹J¹IC¹ OCII I¹OKN¹TO OOWLTTOTII ll¹IOOCCCCAlla¹ Ot1ICOODI I¹cl¹oo ¹I> II¹c Tawwtccl oC¹o¹¹l1 I¹olc¹two ¹Jsol Ioo¹AI¹lo llc I¹cccoo HCI I¹¹C¹T1 ¹AHAI¹I¹IITOIIA¹CHt¹CCOL II¹ IA¹CCA¹ l¹C¹CATI¹IICOO+O¹t¹C TEXT CONTINUATION AAOIOICW.OO TIOOAIIDTO TIO TJIUC¹WOIW ICCCCICH IIOC¹OT CII WAIL% OIIICO I¹ ¹AKIÃA¹¹TNO ¹AX¹T.WA¹¹et¹t¹C OO $ 0¹CL FACILUYNAME (1) DOCKET NUMBER (2) LER NUMBER (6) PAGE (3) |
| | EQUENTIAL REVISIO St. Lucie Unit 1 NUMBER . NUMBER 0 500 0335 9 2 0 0 4 0 0 0 4 0 4 TEXT (Ifmore spaceis required, use additional NRC Form 366A's) (17) |
| | There was no component failure during this event; however, specific component identification is included for informational purposes. |
| | Relay: Agastat 7tming Relay Part Number. DSB XXO I 25SPAXAA Manufacturer: Amerace Corporation There have been no previous events in which maintenance personnel have inadvertently altered relay time delay settings. |
| | FPL Facsimile of NRC Form 366 (649)}} |
|
|---|
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
ACCELERATED 'STIUBUTION DEMONSATION SYSTEM REGULAT Y INFORMATION DISTRIBUTION SYSTEM (RIDS) jag DOC.DATE: 92/06/18 NOTARIZED: NO DOCKET ACCESSION NBR:9206250161 FACIL:50-335 St. Lucie Plant, Unit 1, Florida Power & Light Co. 05000335 AUTH. NAME AUTHOR AFFILIAT10N WACHT'EL,P.K. Florida Power & Light Co.
SAGER,D.A. Florida Power & Light Co.
RECIP.NAME RECIPIENT AFFILIATION
SUBJECT:
LER 92-004-00:on 920521,relay time delay settings altered due to personnel error. Remaining load sequence timers on both Unit 1 & Unit 2 were inspected to ensure thumbwheel switches were set correctly.W/920618 ltr.
DISTRIBUTION CODE: IE22T COPIES RECEIVED:LTR r ENCL TITLE: 50.73/50.9 Licensee Event Report (LER), Incident Rpt, etc.
g SIZE:
NOTES:
RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD2-2 LA 1 1 PD2-2 PD 1 1 NORRIS,J 1 1 1NTERNAL: ACNW 2 2 ACRS 2 2 AEOD/DOA 1 1 AEOD/DSP/TPAB 1 1 AEOD/ROAB/DSP 2 2 NRR/DET/EMEB 7E 1 1 NRR/DLPQ/LHFB10 1 1 NRR/DLPQ/LPEB10 1 1 NRR/DOEA/OEAB 1 1 NRR/DREP/PRPB11 2 2 NRR/DST/SELB 8D 1 1 NRR/DST/SICB8H3 1 1 NRRfDSSPLB8D1 1 1 NRR/DST/SRXB 8E 1 1 REG FILE 02 1 1 RES/DSIR/EIB 1 R LE 01 1 1 EXTERNAL: EG&G BRYCE i J. H 3 3 L ST LOBBY WARD 1 1 NRC PDR 1 1 NSIC MURPHY,G.A 1 1 NSIC POORETW. 1 1 NUDOCS FULL TXT 1 1 NOTE TO ALL "RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE! CONTACI'HE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT. 20079) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LINIS FOR DOCUMENTS YOU DON'T NEED!
FULL TEXT CONVERSION REQUIRED TOTAL NUMBER OF COPIES REQUIRED: LTTR 32 ENCL 32
P.O. Box 128, Ft. Pierce, FL 34954-0128 June 18, 1992 L-92-167 10 CFR 50.73 U. S. Nuclear Regulatory Commission Attn: Document Control Desk washington, D. C. 20555 Re: St. Lucie Unit 1 Docket No. 50-335 Reportable Event: 92-004 Date of Event: May 21, 1992 Relay Time Delay Settings Altered due to Personnel Error causes Condition Prohibited b Technical S ecifications The attached Licensee Event Report is being submitted pursuant to the requirements of 10 CFR 50.73 to provide notification of the subject event.
Very truly yours, D. A. ger Vice r sident St. Lu e Plant DAS/JWH/kw Attachment cc: Stewart D. Ebneter, Regional Administrator, USNRC Region II Senior Resident Inspector, USNRC, St. Lucie Plant DAS/PSL N715-92 9206250161 920618 PDR ADOCK 05000335 8 PDR an FPL Group company
FPL FcccirrTlc d US. NUCLEAR REGNATORY COMMISSION ATTIXXCOCACIICX0IICCI01 IFIC Form 380 00CCCC 00000 CCICIATTOOACCC IOI ImCCXCC TO 00XCTT TCOI ~ 0CTXCIATXCIIXXITCT0XI lo llo LICENSEE EVENT REPORT (LER) ICXACCT:000 ICTA TOCCAIXICCICCXIC ICCAICCXIIAACXIIICICIAIC ICCIXTXIAICIICTCCIC INAIXTCNfITMCIXI+44QL IIXIAAXCAC IC OAAT0XIT lo CASSAVAWIS44lRW, OC 00MC rCD THC 00tIICCX00 ICOUCTXXIICOCCT 0IICCICC. CIIICIOI IWNODCICIIXIIMXXT AOCXCIXAOC 00001 FACILITYNAME (1) DOCKET NUMBER (2) PAGE 3 St. Lucie Unit 1 050003351
~ (4) Relay Time Delay Settings Altered due to Personnel Error Causes Condition Prohibited 0 4 by Plant Technical Specifications EVENT DATE (5) LER NUMBER (6) REPORT DATE m OTHER FACILITIES INVOLVED(8)
DAY YEAR S AL R DAY YEAR FACILITYNAMES DOCKET NUMBER(S)
N/A 0 5 21 9 2 9 2 0 0 4 0 0 0 6 1 8 9 2 N/A 05000 THIS REPORT IS SUBMITIEDPURSUANTTOTHE REQUIREMENTS OF 10 CFR:
OPERATING Check one or more of the followin (11)
MODE (9) 20.402(b) 20.405(c) 50.73(a)(2)(iv) 73.71(b)
POWER 20.405(a)(1)(i) 50.36(c)(1) 50.73(a)(2)(v) 73.71(c)
LEVEL (10) 1 0 0 20.405(a) (1)(ii) 50.36(c)(2) 50.73(a)(2)(vii) OTHER (Specify in Abstract 20.405(a)(1)(iii) 50.73(a)(2) (I) 50.73(a)(2)(viii)(A) below andin Text 20.405(a)(1)(iv) 50.73(a)(2)(viii)(B) NRC Form 388A) 50.73(a)(2)(ii) 20.405(a)(1)(v) 50.73(a)(2)(iii) 50.73(a)(2)(x)
LICENSEE CONTACT FOR THIS LER 12 TELEP ONE NUMBER AREA CODE Patricia K. Wachtel, Shift Technical Advisor 4 0 7 465 -3550 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT 13 REPORTABLE MANUFAC- REPORTABLE SYSTEM COMPONENT MANUFAC- TURER TO NPRDS CAUSE SYSTEM COMPONENT TURER TO NPRDS SUPPLEMENTAL REPORT EXPECTED 14 EXPECTED MONTH DAY YEAR SUBMISSION YES (Ifyes, complete EXPECTED SUBMISSION DATE) NO DATE (15)
ABSTRACT (Limit to 1400 spaces. I.e. approximately fifteen single-space typewritten lines) (1 6)
On May 21, 1992, St. Lucie Unit 1 was in mode 1, operating at 100% steady state power. A utility engineer was inspecting the time delay settings on Agastat relays In specifh electrical buses when it was discovered that the timer thumbwheel settings for the 1A Component Cooling Water pump and the 18 Containment Spray pump were very dose to the+I- one second Technical Specificathn surveillance tolerance for diesel generator load sequencing. Subsequent investigation revealed that the time delay settings had been altered.
The cause of this event was personnel, error. While cleaning the cubides in whhh these relays were located, a contract maintenance worker inadvertently changed the time settings on the thumbwheel switches while cleaning the faces of the relays.
Corrective actions taken include: 1) the Agastat relays were reset to comply with Technical Specifications, 2) the maintenance crews were counseled on how to clean the relays and not disturb the had sequence timer settings, 3) the switchgear cleaning procedure was changed to ensure the correct thumbwheel switch setting is verified prior to returning the electrical bus to service, and 4) the remaining had sequence timers on both Unit 1 and Unit 2 were inspected to ensure the thumbwheel switches were set correctly.
FPL Facsimile of NRC Form 366 (M9)
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EQUENTIAL REVISIO St. Lucie Unit 1 NUMBER NUMBER 0500033592 0 0 4 0 0 0 2 0 4 TEXT (limore spaceis required, use additional NRC Form 366A's) (17)
On May 21, 1992, St. Lucie Unit 1 was in mode 1 at 100% steady state power. A utility engineer was inspecting the 1A3 and 1B3 electrical buses (EIIS:EB) to check the time delay settings on specific Agastat relays. This inspection was being performed in response to an engineering assessment relating to recent industry events on load sequence timers. The investigation at St. Lucie Unit 1 revealed that the time delay settings for the 1A Component Cooling Water pump (EIIS:CG) (CGW) and the 1B Containment Spray pump (EIIS:BE) (CS) were Incorrect. The following data was provkled following the inspection:
REQUIRED TIME AS- FOUND AS-FOUND TlME A%AFT (4-1 second) Tl-IUMBWHEEL (05-2142) TIME SETIING 1ACCW 6.00 7.01 7.17 6.12 secords 1B CS 12.00 1298 13.11 12.16 seconds This indicated that both the 1A CGW and 1B CS pumps had their time delay settings outskfe of the
+/- one second load sequencing setting required by Technical Specification sutveillance requirement 4.8.1.1.2.e.11.
The times were last verified during the Unit 1 Periodic Integrated Test of the Engineered Safety Features performed in October, 1991. The following time settings were documented for these pumps: 1A CGW pump- 6.18 seconds; 1B CS pump -12.16 seconds. Each of these times was within the acceptable tolerance allowed by plant Technical Specifications.
The cause of this event has been attributed to personnel error. The inadvertent changing of the timer thumbwheel switches appears to have occurred when the cubfcies on the 4160 volt buses containing these relays were cleaned during the last Unit 1 refueling outage. When the busses were cleaned, the worker could come in contact with the thumbwheei and inadvertently alter the time delay settings. There were no unusual work conditions which may have contributed to this event nor was there any specific procedural gukfance to caution the contract maintenance personnel not to disturb the load sequence timer settings when cleaning the relays.
This event is reportable under the requirements of 10CFR50.73.a.2.i.B as "any operation or condition prohibited by the plant Technical Spec Tiications." Technical Specification surveillance requirement 4.8.1.1.2.e.5 requires that once per eighteen months, a loss of off-site power in conjunction with an engineered safety feature actuation test signaI (EIIS:JE) be simulated.
Following the start of the emergency diesel generator (EDG) (EIIS:EK), the emergency busses with permanently connected loads energization and the auto~nnected emetgency (accident) loads energization through the auto-sequencer must be verified. Verification that the automatic load FPL Facsimiie of NRC Form 366 (649)
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EQUENTIAL REVISIO St. Lucie Unit1 NUMBER NUMBER 0 500 0335 9 2 0 0 4 0 0 0 3 0 4 TEXT (Ifmore spaceis required, use additional NRC Form 366A's) (17) sequence timers are operable with the interval between each load bkck within+/- one second of its design interval is required as per Technical Specification surveillance requirement 4.8.1.1.2.e.11.
Although this surveillance was performed satisfactorily seven months ago during the Unit 1 refueling outage, the as-found settings for the 1A Component Cooling Water and the 1B Containment Spray pumps indicate that they would not have loaded onto the EDG in the proper sequence.
A detailed engineering evaluation (JPN-PSL-SEEP-92-031) was perfomed to demonstrate that the EDG would have performed acceptably with the as-'found timer settings. Conclusions from this evaluation indicated that the timer settings did not adversely affect the ability of the Emergency Diesel Generators to supply power to the required Engineered Safety Feature loads under design basis loss of off-site power and accident conditions. The health and safety of the public was not at risk at any time while in this condition.
- 1. The required time delay settings were restored for the two altered load sequence time+.
- 2. The remaining load sequence timers onboth Unit1 and Unit 2 were inspected to ensure the thumbwheel switches were set correctly. All were unchanged.
- 3. Electrical maintenance will visually verify that all load sequence timers are set correctly prior to entering Mode 4 subsequent to a refueling outage. This verification will be incorporated into plant procedures.
- 4. The switchgear cleaning procedure was changed to include steps to verify the timer thumbwheel switch setting is within Technical Specifications limits before releasing the bus for soNice.
- 5. Electrical maintenance supervisors counseled contractor and utility maintenance personnel not to disturb the load sequence timers while cleaning the switchgear cubicles.
- 6. The Plant Maintenance Departments evaluated other preventative maintenance cleaning procedures for the potential to disturb the settings of load sequence timers.
FPL Facsimile of NRC Form 366 (649)
FPL Fscttmle at U.S. NUCLEAR REGULATORY COMMSS TON I¹IWOIOOt¹e IOI TIWOI OI PIC Foml SOB IMQj LICENSEE EVENT REPORT (LER) COTWATI¹J¹IC¹ OCII I¹OKN¹TO OOWLTTOTII ll¹IOOCCCCAlla¹ Ot1ICOODI I¹cl¹oo ¹I> II¹c Tawwtccl oC¹o¹¹l1 I¹olc¹two ¹Jsol Ioo¹AI¹lo llc I¹cccoo HCI I¹¹C¹T1 ¹AHAI¹I¹IITOIIA¹CHt¹CCOL II¹ IA¹CCA¹ l¹C¹CATI¹IICOO+O¹t¹C TEXT CONTINUATION AAOIOICW.OO TIOOAIIDTO TIO TJIUC¹WOIW ICCCCICH IIOC¹OT CII WAIL% OIIICO I¹ ¹AKIÃA¹¹TNO ¹AX¹T.WA¹¹et¹t¹C OO $ 0¹CL FACILUYNAME (1) DOCKET NUMBER (2) LER NUMBER (6) PAGE (3)
EQUENTIAL REVISIO St. Lucie Unit 1 NUMBER . NUMBER 0 500 0335 9 2 0 0 4 0 0 0 4 0 4 TEXT (Ifmore spaceis required, use additional NRC Form 366A's) (17)
There was no component failure during this event; however, specific component identification is included for informational purposes.
Relay: Agastat 7tming Relay Part Number. DSB XXO I 25SPAXAA Manufacturer: Amerace Corporation There have been no previous events in which maintenance personnel have inadvertently altered relay time delay settings.
FPL Facsimile of NRC Form 366 (649)
