|
|
| Line 16: |
Line 16: |
|
| |
|
| =Text= | | =Text= |
| {{#Wiki_filter:ACCELERATED DISTRIBUTION DEMONS~TION SYSTEMREGULATORY INFORMATION DISTRIBUTION SYSTEM(RIDS)'ACCESSION NBR:9105060103 DOC.DATE: | | {{#Wiki_filter:ACCELERATED DISTRIBUTION DEMONS~TION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)'ACCESSION NBR:9105060103 DOC.DATE: 91/04/30 NOTARIZED: |
| 91/04/30NOTARIZED: | | NO FACIL:50-389 St.Lucie Plant, Unit 2, Flor'ida Power&Light Co.AUTH.NAME AUTHOR AFFILIATION, LAUVER,C.Florida Power&Light Co.SAGER,D.A. |
| NOFACIL:50-389 St.LuciePlant,Unit2,Flor'idaPower&LightCo.AUTH.NAMEAUTHORAFFILIATION, LAUVER,C.
| | Florida Power&Light Co.~RECIP.NAME RECIPIENT AFFILIATION DOCKET 05000389 |
| FloridaPower&LightCo.SAGER,D.A.
| |
| FloridaPower&LightCo.~RECIP.NAME RECIPIENT AFFILIATION DOCKET05000389
| |
|
| |
|
| ==SUBJECT:== | | ==SUBJECT:== |
| LER91-003-00:on 910426,2A shutdowncoolingheatexchanger outof.svcduetomispositioned component coolingwatervalve.Causedbypersonnel error.Valvecorrectly realigned
| | LER 91-003-00:on 910426,2A shutdown cooling heat exchanger out of.svc due to mispositioned component cooling water valve.Caused by personnel error.Valve correctly realigned&redundant train's valve checked.W/910430 ltr.DISTRIBUTION CODE: IE22T COPIES RECEIVED:LTR J ENCL J SIZE: ,.TITLE: 50.73/50.9 Licensee Event Report (LER), Incident Rpt, etc.1 NOTES: A RECIPIENT ID CODE/NAME PD2-2 LA NORRIS,J INTERNAL: ACNW AEOD/DOA.AEOD/ROAB/DSP NRR/DET/EMEB 7E NRR/DLPQ/LPEB10 NRR/DREP/PRPB11 |
| &redundant train'svalvechecked.W/910430 ltr.DISTRIBUTION CODE:IE22TCOPIESRECEIVED:LTR JENCLJSIZE:,.TITLE:50.73/50.9 LicenseeEventReport(LER),IncidentRpt,etc.1NOTES:ARECIPIENT IDCODE/NAME PD2-2LANORRIS,JINTERNAL: | | 'RR/DST/SICB 7E NRR/DST/SRXB 8E RES/DS IR/EI B EXTERNAL: EG&G BRYCE,J.H NRC PDR NSIC POOREEW COPIES LTTR ENCL 1 1 1 1 2 2 1 1 2 2 1 1 1 1 2 2 1 1 1 1 1 1 3 3 1 1 1 1 RECIPIENT ID CODE/NAME PD2-2 PD ACRS~AEOD/DS P/TPAB NRR/DET/ECMB 9H NRR/DLPQ/LHFB11 NRR/DOEA/OEAB NRR/DST/SELB 8D NRR/DST 2LBBJ31 RE 0M RGN2 FILE 01 L ST LOBBY WARD NSIC MURPHY,G.A NUDOCS FULL TXT'COPIES LTTR ENCL 1 1 2 2 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 D D'D NOTE TO ALL"RIDS" RECIPIENTS: |
| ACNWAEOD/DOA.AEOD/ROAB/DSP NRR/DET/EMEB 7ENRR/DLPQ/LPEB10 NRR/DREP/PRPB11
| | D D PLEASE HELP US TO REDUCE WASTE!CONTACT THE DOCUMENT CONTROL DESK, ROOM P 1-37 (EXT.20079)TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!FULL TEXT CONVERSION REQUIRED TOTAL NUMBER OF COPIES REQUIRED: LTTR 33 ENCL 33 P.O.Box 128, Ft.Pierce, FL 34954-0128 FPL APR 3 0 199'-91-133 10 CFR 50.73 U.S.Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C.20555 Gentlemen: |
| 'RR/DST/SICB 7ENRR/DST/SRXB 8ERES/DSIR/EIBEXTERNAL: | | Re: St.Lucie Unit 2 Docket No.50-389'Reportable Event 91-03 Date of Event: April 26, 1991 2A Shutdown Cooling Heat Exchanger Out of Service Due to Mispositioned Component Coolin Water Outlet Valve Caused b Personnel Error The attached Licensee Event Report is being submitted pursuant to the requirements of 10 CFR 50.73 to provide notification of the subject event.A supplemental report will be submitted at the usual 30 day time interval.Very truly yours, D.A.S ger Vice sident St.Lucie Plant DAS:GRM:kw Attachment cc: Stewart D.Ebneter,.Regional Administrator, USNRC Region II Senior Resident Inspector, USNRC, St.Lucie Plant DAS/PSL N423 9g0c0rr0i03 910430 PDF ADOCK 0 000~89 PDR'"~~men FPL Group company:.:.=t.287&gag FPL FacsilliIC OI.NRCFNITT 666<coy U.S.NUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT (LER)~AffNOIIO CAO NO 01 004100 4000%4: lOtH 0 CSTNHITO 000OOI POI IKKOOC IO DC040T 00TN TN0 04Cf0AATTITI DCUE CDITI IOITNCD 000 1000 ICNWNCT CCINCNTC IKCNIIO CIITXN CTTAIATC TO TIC ICDITITT NO NEIDNTC IWNAINICNI OIANGN I040IL IAL IACITAl IKCIIATOIT |
| EG&GBRYCE,J.H NRCPDRNSICPOOREEWCOPIESLTTRENCL1111221122111122111111331111RECIPIENT IDCODE/NAME PD2-2PDACRS~AEOD/DSP/TPABNRR/DET/ECMB 9HNRR/DLPQ/LHFB11 NRR/DOEA/OEAB NRR/DST/SELB 8DNRR/DST2LBBJ31RE0MRGN2FILE01LSTLOBBYWARDNSICMURPHY,G.A NUDOCSFULLTXT'COPIESLTTRENCL11221111111111111111111111DD'DNOTETOALL"RIDS"RECIPIENTS: | |
| DDPLEASEHELPUSTOREDUCEWASTE!CONTACTTHEDOCUMENTCONTROLDESK,ROOMP1-37(EXT.20079)TOELIMINATE YOURNAMEFROMDISTRIBUTION LISTSFORDOCUMENTS YOUDON'TNEED!FULLTEXTCONVERSION REQUIREDTOTALNUMBEROFCOPIESREQUIRED:
| |
| LTTR33ENCL33 P.O.Box128,Ft.Pierce,FL34954-0128 FPLAPR30199'-91-133 10CFR50.73U.S.NuclearRegulatory Commission Attn:DocumentControlDeskWashington, D.C.20555Gentlemen:
| |
| Re:St.LucieUnit2DocketNo.50-389'Reportable Event91-03DateofEvent:April26,19912AShutdownCoolingHeatExchanger OutofServiceDuetoMispositioned Component CoolinWaterOutletValveCausedbPersonnel ErrorTheattachedLicenseeEventReportisbeingsubmitted pursuanttotherequirements of10CFR50.73toprovidenotification ofthesubjectevent.Asupplemental reportwillbesubmitted attheusual30daytimeinterval. | |
| Verytrulyyours,D.A.SgerVicesidentSt.LuciePlantDAS:GRM:kw Attachment cc:StewartD.Ebneter,.Regional Administrator, USNRCRegionIISeniorResidentInspector, USNRC,St.LuciePlantDAS/PSLN4239g0c0rr0i03 910430PDFADOCK0000~89PDR'"~~menFPLGroupcompany:.:.=t.287&gag FPLFacsilliIC OI.NRCFNITT666<coyU.S.NUCLEARREGULATORY COMMISSION LICENSEEEVENTREPORT(LER)~AffNOIIOCAONO010041004000%4:lOtH0CSTNHITO000OOIPOIIKKOOCIODC040T00TNTN004Cf0AATTITI DCUECDITIIOITNCD0001000ICNWNCTCCINCNTCIKCNIIOCIITXNCTTAIATCTOTICICDITITTNONEIDNTCIWNAINICNI OIANGNI040ILIALIACITAlIKCIIATOIT
| |
| ~WANNNDDN. | | ~WANNNDDN. |
| DCSXk4AIOTOTINPAOIACITI ICDUGTIDN ffCICCTI01NI4OC,CfINNCfWNAGTACNT NOILA0GCTWAONIGTDK DCIIIClFACILITYNAME(1)St.LucieUnit2DOCKETNUMBER(2)PAGE3050003891 004'(4)2AShutdownCoolingHeatExchanger OutofServiceDuetoMispositioned Component CoolingWaterValveCausedbyPersonnel ErrorEVENTDATE(5)LERNUMBER(6)REPORTDATE(7)OTHERFACILITIES INVOLVED(8)MONTHDAY0426YEAR91.91003YEARSIALMONTHDAY00430YEAR91FACILITYNAMESN/AN/ADOCKETNUMBER(S) 50005000.OPERATING MODE(9)POWERLEVEL,(10)100201402(b) 20.405(a)(1)(i) 20.405(a)(1)(ii) 20.405(a)
| | DC SXk4 AIOTO TIN PAOIACITI ICDUGTIDN ffCICCT I 01NI4OC, Cf INN Cf WNAGTACNT NO ILA0GCT WAONIGTDK DC IIICl FACILITY NAME (1)St.Lucie Unit 2 DOCKET NUMBER (2)PAGE 3 050003891 0 0 4'(4)2A Shutdown Cooling Heat Exchanger Out of Service Due to Mispositioned Component Cooling Water Valve Caused by Personnel Error EVENT DATE (5)LER NUMBER (6)REPORT DATE (7)OTHER FACILITIES INVOLVED (8)MONTH DAY 0 4 2 6 YEAR 9 1.9 1 0 0 3 YEAR S IAL MONTH DAY 0 0 4 3 0 YEAR 9 1 FACILITY NAMES N/A N/A DOCKET NUMBER(S)5 0 0 05000.OPERATING MODE (9)POWER LEVEL, (10)1 0 0 201402(b)20.405(a)(1)(i) 20.405(a)(1)(ii) 20.405(a)(1)(iii)201405(a)(1)(iv) 20.405(c)50.36(c)(1) 50.36(c)(2) 50.73(a)(2)(i) 50.73(a)(2)(ii)50.73(a)(2)(iv) 50.73(a)(2)(v) 50.73(a)(2)(vii) 50.73(a)(2)(viii)(A) 50.73(a)(2)(viii)(B) |
| (1)(iii)201405(a)(1)(iv) 20.405(c) 50.36(c)(1) 50.36(c)(2) 50.73(a)(2)(i) 50.73(a)(2) | | ~THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR: Check one or more of the followin (11)73.71(b)73.71(c)OTHER (Specify in Abstract beloIvandin Text NRC Form 366A)20.405(a)(1)(v) 50.73(a)(2)(iii) 50.73(a)(2)(x) |
| (ii)50.73(a)(2)(iv) 50.73(a)(2)(v) 50.73(a)(2)(vii) 50.73(a)(2)(viii)(A) 50.73(a)(2)(viii)(B) | | NAME LICENSEE CONTACT FOR THIS LER 12 Catherine Lauver, Shift Technical Advisor TELEP ONE NUMBER AREA CODE 4 0 7 465-3550 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT 13 CAUSE SYSTEM COMPONENT MANUFAC-TURER B E I S V P 3 4 0 REPORTABLE TO NPRDS CAUSE SYSTEM COMPONENT I I I REPORTABLE TO NPRDS SUPPLEMENTAL REPORT EXPECTED 14 YES (If yes;complete EXPECTED SUBMISSION DATE)NO EXPECTED MONTH DAY YEAR SUBMISSION DATE (15)0 5 2 6 9 ABSTRACT (Limit to f400 spaces.i.e. |
| ~THISREPORTISSUBMITTED PURSUANTTOTHEREQUIREMENTS OF10CFR:Checkoneormoreofthefollowin(11)73.71(b)73.71(c)OTHER(SpecifyinAbstractbeloIvandin TextNRCForm366A)20.405(a)(1)(v) 50.73(a)(2)(iii) 50.73(a)(2)(x) | | approximately fifteen single-space typewritten lines)(16)This is an interim report.A followup report will be submitted. |
| NAMELICENSEECONTACTFORTHISLER12Catherine Lauver,ShiftTechnical AdvisorTELEPONENUMBERAREACODE407465-3550COMPLETEONELINEFOREACHCOMPONENT FAILUREDESCRIBED INTHISREPORT13CAUSESYSTEMCOMPONENT MANUFAC-TURERBEISVP340REPORTABLE TONPRDSCAUSESYSTEMCOMPONENT IIIREPORTABLE TONPRDSSUPPLEMENTAL REPORTEXPECTED14YES(Ifyes;completeEXPECTEDSUBMISSION DATE)NOEXPECTEDMONTHDAYYEARSUBMISSION DATE(15)05269ABSTRACT(Limittof400spaces.i.e.
| | Corrective actions include: the valve was correctly realigned; the redundant train's valve was checked;both units performed a full Valve Status Check.At 0110 on April 26, 1991, with Unit 2 at 100%power, Operations personnel began searching for a DC ground.At 0400, per plant procedure, Operations cycled HCV-14-3A, Component Cooling Water (CCW)outlet from the 2A Shutdown Cooling (SDC)Heat Exchanger (HX)to de-energize its solenoid operator in an effort to locate the DC ground.After the valve opened, no flow through the heat exchanger was indicated. |
| approximately fifteensingle-space typewritten lines)(16)Thisisaninterimreport.Afollowupreportwillbesubmitted. | | Upon investigation, the 2A SDC HX CCW return isolation valve SB-14365 was found to be locked closed.This valve is required to be Locked Open.It had been entered into the Valve Switch Deviation Log on October 23, 1990 as Locked Throttled and restored November 29, 1990.As this is the most recent documented manipulation date, it is assumed to have been mispositioned at this time.The valve position pointer was broken and indicated open.The cause of the mispositioning is under investigation. |
| Corrective actionsinclude:thevalvewascorrectly realigned; theredundant train'svalvewaschecked;bothunitsperformed afullValveStatusCheck.At0110onApril26,1991,withUnit2at100%power,Operations personnel begansearching foraDCground.At0400,perplantprocedure, Operations cycledHCV-14-3A, Component CoolingWater(CCW)outletfromthe2AShutdownCooling(SDC)HeatExchanger (HX)tode-energize itssolenoidoperatorinanefforttolocatetheDCground.Afterthevalveopened,noflowthroughtheheatexchanger wasindicated. | | FPL Facsimile of NRC Form 366 (6-89) |
| Uponinvestigation, the2ASDCHXCCWreturnisolation valveSB-14365wasfoundtobelockedclosed.ThisvalveisrequiredtobeLockedOpen.IthadbeenenteredintotheValveSwitchDeviation LogonOctober23,1990asLockedThrottled andrestoredNovember29,1990.Asthisisthemostrecentdocumented manipulation date,itisassumedtohavebeenmispositioned atthistime.Thevalvepositionpointerwasbrokenandindicated open.Thecauseofthemispositioning isunderinvestigation.
| |
| FPLFacsimile ofNRCForm366(6-89)
| |
|
| |
|
| FPLFacslmraorNROForm666(6-69)~U.S.NUCLEARREGULATORY COMMISSION LICENSEEEVENTREPORT(LER)TEXTCONTINUATION ASSASNTOCAOISA$1500105EITfsabaAITI505ssrsfATTO usTWNseatKspQNscTocCANLTwlTHTNsssofsfATcN SouseTISHMOICST:500ISTSICONf505CASAOITSfNCAIONOTASSXNSafWATSTOTINraxSSIiNetcSCTTTSuuNAmSNT TNANCH5Caaua55ASSNTNSOAATNTT ofaIASNSN wAsHNCION.
| | FPL Facslmra or NRO Form 666 (6-69)~U.S.NUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT (LER)TEXT CONTINUATION ASSASNTO CAO ISA$150 0105 EITf saba AITI505 ssrsfATTO usTWN sea tKspQNsc To cCANLT wlTH TNs ssofsfATcN Souse TISH MOICST: 50 0 ISTS ICON f505 CASAOITS fNCAIONO TASSXN Saf WATS TO TIN raxSSIiNetcSCTTTSuuNAmSNT TNANCH 5 Caa ua 55ASSNT NSOAATNTT ofaIASNSN wAsHNCION. |
| oc505faNclToTIcsfsTIINcfN MTTucllQH NT55'ciI'150010150frICC ofIMWdDCNfAIST55$5CCTWNSINSTTSAOC 5050$FACILITYNAME(1)DOCKETNUMBER(2)LERNUMBER(6)PAGE(3)St.LucieUnit205000389YEAR91EQUENTIAL NUMBER003REVISIONNUMBER0002004TEXT(Ifmorespaceisreriuired, useadditional NRCForm366A's)(17)Thisisaninterimreport.Afollowupreportwillbesubmitted At0110onApril26,1991,withUnit2at100%power,Operations personnel begantosearchforaDCground.Tofindaground,planttoadsareindividually isolated.
| | oc 505fa Ncl To TIc sfsTIINcfN MTTucllQH NT55'ci I'150010150frICC of IMWdDCNf AIST 55$5CCT WNSINSTTSAOC 5050$FACILITY NAME (1)DOCKET NUMBER (2)LER NUMBER (6)PAGE (3)St.Lucie Unit 2 05000389 YEAR 9 1 EQUENTIAL NUMBER 0 0 3 REVISION NUMBER 0 0 0 2 0 0 4 TEXT (If more spaceis reriuired, use additional NRC Form 366A's)(17)This is an interim report.A followup report will be submitted At 0110 on April 26, 1991, with Unit 2 at 100%power, Operations personnel began to search for a DC ground.To find a ground, plant toads are individually isolated.Per plant procedure, Operations cycled HCV-14-3A, Component Cooling Water (CCW)(EIIS:CC)from the 2A Shutdown Cooling (SDC)Heat Exchanger (HX)(EIIS:BP). |
| Perplantprocedure, Operations cycledHCV-14-3A, Component CoolingWater(CCW)(EIIS:CC) fromthe2AShutdownCooling(SDC)HeatExchanger (HX)(EIIS:BP).
| | During normal operations there is no flow through the shutdown heat exchanger; opening the valve should have resulted in 4000 gpm flow.There was no flow indicated through the HX.Operations. |
| Duringnormaloperations thereisnoflowthroughtheshutdownheatexchanger; openingthevalveshouldhaveresultedin4000gpmflow.Therewasnoflowindicated throughtheHX.Operations.
| | locally verified movement of HCV-14-3A and position of CCW inlet isolation valve SB-14348.CCW outlet isolation valve SB-14365 is required to be Locked Open, was indicating open by its valve position indicator, but was in fact Locked Closed.The valve was reopened to its proper position.The redundant train's CCW outlet isolation valve position was checked as a precaution. |
| locallyverifiedmovementofHCV-14-3A andpositionofCCWinletisolation valveSB-14348.
| | The valve was in its proper Locked Open position, but its position indicator was also faulty.An investigation revealed that SB-14365 was entered into the Valve Switch Deviation Log on October 23, 1990, when placed in a Locked Throttled position to balance CCW flow.On November 25, 1990, as Unit 2 was completing a refueling outage, the CCW system was placed in its operating alignment. |
| CCWoutletisolation valveSB-14365isrequiredtobeLockedOpen,wasindicating openbyitsvalvepositionindicator, butwasinfactLockedClosed.Thevalvewasreopenedtoitsproperposition.
| | Operating Procedure 2-0310020,"Component Cooling Water-Normal Operation," was performed. |
| Theredundant train'sCCWoutletisolation valvepositionwascheckedasaprecaution.
| | SB-14365 was verified to be Locked Open at this time;On November 29, 1990, the Valve Switch Deviation Log showed that the valve was restored to its Locked Open position.As November 29 is the last recorded date that SB-14365 was manipulated, it is assumed that the valve has been mispositioned since this time.The lack of an OPERABLE 2A SDC HX causes the 2A train of the Containment Spray System (EIIS:BE)to be administratively out of service.From 0455 on February 19 through 0315 on February 20 and 2208 on February 20 through 1700 on February 21, 1991, the 2B Containment Spray System was out of service for routine maintenance and testing.Plant records are being reviewed to see if there are any other periods of time where both trains of the Containment Spray System were out of service.CCW outlet isolation valve SB-14365 is a manually operated butterfly valve located in a horizontal line about twelve feet above the floor.Valve position indication is provided by a pointer which is supposed to move with the valve stem.The pointer was broken.A Plant Work Order was written October 21, 1990 to repair the pointer and was apparently worked January 17, 1991.At the time the mispositioning was discovered, the pointer erroneously indicated Open.Investigation into this valve position indicator failure will continue.A Standing Night Order states that to check the position of a Locked Open valve, the valve shall be unlocked, closed slightly, reopened, and relocked.While the position indicated by the pointer was inaccurate and misleading, the handwheel on the valve indicates which way to turn to open the valve.Since November of 1990, the position of this valve has been checked twice during the quarterly performance of Administrative Procedure 2-0010123,"Administrative Control of Valves, Locks, and Switches," and weekly during Administrative Procedure 2-0010125A,"Surveillance Data Sheets," FPL Facsimile of NRC Form 366 (6-69) |
| ThevalvewasinitsproperLockedOpenposition, butitspositionindicator wasalsofaulty.Aninvestigation revealedthatSB-14365wasenteredintotheValveSwitchDeviation LogonOctober23,1990,whenplacedinaLockedThrottled positiontobalanceCCWflow.OnNovember25,1990,asUnit2wascompleting arefueling outage,theCCWsystemwasplacedinitsoperating alignment.
| |
| Operating Procedure 2-0310020, "Component CoolingWater-Normal Operation," | |
| wasperformed.
| |
| SB-14365wasverifiedtobeLockedOpenatthistime;OnNovember29,1990,theValveSwitchDeviation LogshowedthatthevalvewasrestoredtoitsLockedOpenposition. | |
| AsNovember29isthelastrecordeddatethatSB-14365wasmanipulated, itisassumedthatthevalvehasbeenmispositioned sincethistime.ThelackofanOPERABLE2ASDCHXcausesthe2AtrainoftheContainment SpraySystem(EIIS:BE) tobeadministratively outofservice.From0455onFebruary19through0315onFebruary20and2208onFebruary20through1700onFebruary21,1991,the2BContainment SpraySystemwasoutofserviceforroutinemaintenance andtesting.PlantrecordsarebeingreviewedtoseeifthereareanyotherperiodsoftimewherebothtrainsoftheContainment SpraySystemwereoutofservice.CCWoutletisolation valveSB-14365isamanuallyoperatedbutterfly valvelocatedinahorizontal lineabouttwelvefeetabovethefloor.Valvepositionindication isprovidedbyapointerwhichissupposedtomovewiththevalvestem.Thepointerwasbroken.APlantWorkOrderwaswrittenOctober21,1990torepairthepointerandwasapparently workedJanuary17,1991.Atthetimethemispositioning wasdiscovered, thepointererroneously indicated Open.Investigation intothisvalvepositionindicator failurewillcontinue.
| |
| AStandingNightOrderstatesthattocheckthepositionofaLockedOpenvalve,thevalveshallbeunlocked, closedslightly,
| |
| : reopened, andrelocked.
| |
| Whilethepositionindicated bythepointerwasinaccurate andmisleading, thehandwheel onthevalveindicates whichwaytoturntoopenthevalve.SinceNovemberof1990,thepositionofthisvalvehasbeencheckedtwiceduringthequarterly performance ofAdministrative Procedure 2-0010123, "Administrative ControlofValves,Locks,andSwitches,"
| |
| andweeklyduringAdministrative Procedure 2-0010125A, "Surveillance DataSheets,"FPLFacsimile ofNRCForm366(6-69)
| |
|
| |
|
| FPLFccEIIIIAI olNR"Form666(649)VU.S.NUCLEARREGUlATORY COMMrsslON LICENSEEEVENTREPORT(LER)'EXTCONTINUATION APPICNTOCAONCk$100010IEPIKR00000ECIPNCTo$$oENPETIfKSPCtSEToCIEPETPRIITIICISPÃNAATEPI COUECCIPIIET$ECP.$1$100$RANNOCOWRIEIKCAfoRCRTeolECTCIATEToTIEIECOT$$NoIEPOlr$NANIEIEIIT NNN001+0$
| | FPL FccEIIIIAI ol NR" Form 666 (649)V U.S.NUCLEAR REGUlATORY COMMrsslON LICENSEE EVENT REPORT (LER)'EXT CONTINUATION APPICNTO CAO NCk$1 000 10I E PIKR 00000 ECIPNCTo$$oEN PETI fKSPCtSE To CIEPET PRII TIIC ISPÃNAATEPI COUEC CIPI IET$ECP.$1$100$RANNO COWRIE IK CAfoRC RTeol ECTCIATE To TIE IECOT$$No IEPOlr$NANIEIEIIT NNN001+0$E oC IAAEEAEIKOAATCAP |
| EoCIAAEEAEIKOAATCAP
| | ~~.ocPEN,~TooEP~RoccRP RE0EETI$1$001000 cffcE cP MNIAEEAENT AIA MxET, sEIPATlcR cc$050$FACILITY NAME (1)St.Lucie Unit 2 DOCKET NUMBER (2)YEAR 0500038991 LER NUMBER (6)EQUENTIAL NUMBER 0 0 3 REVISIO NUMBER 0 0 PAGE (3)0 30 0 4 TEXT (lf more spaceis required, use additional NRC Form 366A's)'17) |
| ~~.ocPEN,~TooEP~RoccRP RE0EETI$1$001000cffcEcPMNIAEEAENT AIAMxET,sEIPATlcR cc$050$FACILITYNAME(1)St.LucieUnit2DOCKETNUMBER(2)YEAR0500038991 LERNUMBER(6)EQUENTIAL NUMBER003REVISIONUMBER00PAGE(3)03004TEXT(lfmorespaceisrequired, useadditional NRCForm366A's)'17) | | ...Data Sheet 36, I At all times it was reported to be Locked Open.The root cause of the event is under investigation. |
| ...DataSheet36,IAtalltimesitwasreportedtobeLockedOpen.Therootcauseoftheeventisunderinvestigation. | | A review of plant records, including operator logs, clearances, and Plant Work Orders, is being conducted. |
| Areviewofplantrecords,including operatorlogs,clearances, andPlantWorkOrders,isbeingconducted.
| | Personnel will be interviewed to determine the specific nature and cause of the error.An INPO Human Performance Enhancement System evaluation will also be performed. |
| Personnel willbeinterviewed todetermine thespecificnatureandcauseoftheerror.AnINPOHumanPerformance Enhancement Systemevaluation willalsobeperformed. | | V NT This event is reportable under the requirements of 10CFR50.73.a.2.i.B, any condition or operation prohibited by Technical Specifications. |
| VNTThiseventisreportable undertherequirements of10CFR50.73.a.2.i.B, anycondition oroperation prohibited byTechnical Specifications.
| | Technical Specification 3.6.2.1"Containment Spray System" requires two independent Containment Spray Systems to be OPERABLE with an OPERABLE Shutdown Cooling Heat Exchanger. |
| Technical Specification 3.6.2.1"Containment SpraySystem"requirestwoindependent Containment SpraySystemstobeOPERABLEwithanOPERABLEShutdownCoolingHeatExchanger. | | A While the exact date of the mispositioning of the CCW outlet isolation valve to the 2A SDC HX is not yet known, November 29, 1990 is the last recorded date of a manipulation of the valve and is assumed to be the date of the mispositioning. |
| AWhiletheexactdateofthemispositioning oftheCCWoutletisolation valvetothe2ASDCHXisnotyetknown,November29,1990isthelastrecordeddateofamanipulation ofthevalveandisassumedtobethedateofthemispositioning.
| | Over a three day period in February 1991, the 2B Containment Spray System was taken out of service for routine maintenance and testing.The SDC HX is not used until the recirculation phase for decay heat removal.The 2A Containment Spray System was always available to receive cool water from the Refueling Water Tank and deliver it to containment to mitigate a post-LOCA containment pressure rise.An alternate safety system for Containment Heat Removal, the Containment Cooling System, is being further evaluated for decay heat removal capability. |
| OverathreedayperiodinFebruary1991,the2BContainment SpraySystemwastakenoutofserviceforroutinemaintenance andtesting.TheSDCHXisnotuseduntiltherecirculation phasefordecayheatremoval.The2AContainment SpraySystemwasalwaysavailable toreceivecoolwaterfromtheRefueling WaterTankanddeliverittocontainment tomitigateapost-LOCA containment pressurerise.Analternate safetysystemforContainment HeatRemoval,theContainment CoolingSystem,isbeingfurtherevaluated fordecayheatremovalcapability.
| | St.Lucie equipment sizing is such that the four containment fan coolers will provide the containment heat removal capability necessary to limit and reduce accident containment pressure and temperature during the recirculation phase.Additional analysis are in progress, assuming a single failure, to demonstrate that two containment fan coolers can also remove Large Break LOCA containment heat load during the recirculation phase.This result is expected because of the PSL containment design in which the free standing steel vessel will transfer heat to the environment. |
| St.Lucieequipment sizingissuchthatthefourcontainment fancoolerswillprovidethecontainment heatremovalcapability necessary tolimitandreduceaccidentcontainment pressureandtemperature duringtherecirculation phase.Additional analysisareinprogress, assumingasinglefailure,todemonstrate thattwocontainment fancoolerscanalsoremoveLargeBreakLOCAcontainment heatloadduringtherecirculation phase.ThisresultisexpectedbecauseofthePSLcontainment designinwhichthefreestandingsteelvesselwilltransferheattotheenvironment. | | FPL Engineering has performed a first order risk assessment of the CCW to the SDC HX valve being in the closed position.For a medium or large break LOCA, the frequency associated with the loss of the decay heat removal function only increases from 3.6E-8 per reactor year with a normal SDC HX lineup, to 5.8E-7 per reactor year with the shutdown heat exchanger isolated.With operator action to open the valve, the frequency is reduced to 1.5E-7 per reactor year.Therefore, the health and safety of the public was not affected during this condition. |
| FPLEngineering hasperformed afirstorderriskassessment oftheCCWtotheSDCHXvalvebeingintheclosedposition.
| | FPL Facsimile of NRC Form 366 (6-89) |
| ForamediumorlargebreakLOCA,thefrequency associated withthelossofthedecayheatremovalfunctiononlyincreases from3.6E-8perreactoryearwithanormalSDCHXlineup,to5.8E-7perreactoryearwiththeshutdownheatexchanger isolated.
| | "t III FPL FocsIITS'AT o.'RC Form 666 (649)U.S.NUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT (LER)TEXT CONTINUAllON 0 FFFHOFCO CAO IAS SH0410l CSFSHO: AOWT CNSIATtOOACIHFCHFKSFCSOC TOCCAOSTWOHTIESSFOFSAATCIOOUECSOI FCCACSv:a4 WTS FCHA1AIO CCAACTOSFHOAFOWOHASHH tSISAAIC TOHC FCOrftfS FIAT FCFOITS NQACCAASIT OIAHCH IF4$$OOSrrltAR FHOAAIOHT 00$40$CAI WAOOHOCW.OC TlÃOL FFST To SIC FFCFFINASW SDVCOCH FFTSCCT ($110410AS Cf FISC OF AAOCACTITAFO IIAXCT,WASH HOTOA OC SH0$FACILITY NAME (1)St.Lucie Unit 2 DOCKET NUMBER (2)YEAR LER NUMBER (6)EQUENTIAL NUMBER REVISION NUMBER PAGE (3)0500038991 TEXT (If more spaceis rerluired, use additional NRC Form 366A's)(17)0 0 3 0 0 0 4 0 0 4 1.Operations restored SB-14365 to its proper position and verified the position of the redundant train's CCW outlet isolation valve.2.Plant Work Orders were submitted to repair the faulty pointers on each valve and determine the root cause of the faulty pointer.3.All Operations personnel were counseled on the use of the Standing Night Order.Operations is investigating further methods to enhance independent verification. |
| Withoperatoractiontoopenthevalve,thefrequency isreducedto1.5E-7perreactoryear.Therefore, thehealthandsafetyofthepublicwasnotaffectedduringthiscondition.
| | 4.Operations performed the entire Weekly Valve Status Check on both Unit 1 and Unit 2.No further discepancies were noted.5.An INPO Human Performance Enhancement System evaluation will be performed on this event.'he review will include human factors and work conditions. |
| FPLFacsimile ofNRCForm366(6-89)
| | Affected Component Identification: |
| "tIII FPLFocsIITS'AT o.'RCForm666(649)U.S.NUCLEARREGULATORY COMMISSION LICENSEEEVENTREPORT(LER)TEXTCONTINUAllON 0FFFHOFCOCAOIASSH0410lCSFSHO:AOWTCNSIATtOOACIHFCHFKSFCSOC TOCCAOSTWOHTIESSFOFSAATCIOOUECSOI FCCACSv:a4 WTSFCHA1AIOCCAACTOSFHOAFOWOHASHH tSISAAICTOHCFCOrftfSFIATFCFOITSNQACCAASIT OIAHCHIF4$$OOSrrltAR FHOAAIOHT 00$40$CAIWAOOHOCW. | | Henry Prat t 14H Butterfly Valve Nuclear MK II with Manual Operator MDT-3 HW Model Number 1001 78 Serial Number C140 Previous Similar Licensee Event Reports: 335-89-002"Inoperable 1B Diesel Generator Due to Fuel Oil System Valve Misalignment" 335-87-012"Loss of Component Cooling Water Redundancy-1A and 1B Component Cooling Water Cross-tie Valves in Open Position" FPL Facsimile of NRC Form 366 (6-69)}} |
| OCTlÃOLFFSTToSICFFCFFINASW SDVCOCHFFTSCCT($110410ASCfFISCOFAAOCACTITAFO IIAXCT,WASH HOTOAOCSH0$FACILITYNAME(1)St.LucieUnit2DOCKETNUMBER(2)YEARLERNUMBER(6)EQUENTIAL NUMBERREVISIONNUMBERPAGE(3)0500038991 TEXT(Ifmorespaceisrerluired, useadditional NRCForm366A's)(17)00300040041.Operations restoredSB-14365toitsproperpositionandverifiedthepositionoftheredundant train'sCCWoutletisolation valve.2.PlantWorkOrdersweresubmitted torepairthefaultypointersoneachvalveanddetermine therootcauseofthefaultypointer.3.AllOperations personnel werecounseled ontheuseoftheStandingNightOrder.Operations isinvestigating furthermethodstoenhanceindependent verification.
| |
| 4.Operations performed theentireWeeklyValveStatusCheckonbothUnit1andUnit2.Nofurtherdiscepancies werenoted.5.AnINPOHumanPerformance Enhancement Systemevaluation willbeperformed onthisevent.'hereviewwillincludehumanfactorsandworkconditions. | |
| AffectedComponent Identification:
| |
| HenryPratt14HButterfly ValveNuclearMKIIwithManualOperatorMDT-3HWModelNumber100178SerialNumberC140PreviousSimilarLicenseeEventReports:335-89-002 "Inoperable 1BDieselGenerator DuetoFuelOilSystemValveMisalignment" 335-87-012 "LossofComponent CoolingWaterRedundancy-1A and1BComponent CoolingWaterCross-tie ValvesinOpenPosition" FPLFacsimile ofNRCForm366(6-69)}}
| |
|
|---|
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 DISTRIBUTION DEMONS~TION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)'ACCESSION NBR:9105060103 DOC.DATE: 91/04/30 NOTARIZED:
NO FACIL:50-389 St.Lucie Plant, Unit 2, Flor'ida Power&Light Co.AUTH.NAME AUTHOR AFFILIATION, LAUVER,C.Florida Power&Light Co.SAGER,D.A.
Florida Power&Light Co.~RECIP.NAME RECIPIENT AFFILIATION DOCKET 05000389
SUBJECT:
LER 91-003-00:on 910426,2A shutdown cooling heat exchanger out of.svc due to mispositioned component cooling water valve.Caused by personnel error.Valve correctly realigned&redundant train's valve checked.W/910430 ltr.DISTRIBUTION CODE: IE22T COPIES RECEIVED:LTR J ENCL J SIZE: ,.TITLE: 50.73/50.9 Licensee Event Report (LER), Incident Rpt, etc.1 NOTES: A RECIPIENT ID CODE/NAME PD2-2 LA NORRIS,J INTERNAL: ACNW AEOD/DOA.AEOD/ROAB/DSP NRR/DET/EMEB 7E NRR/DLPQ/LPEB10 NRR/DREP/PRPB11
'RR/DST/SICB 7E NRR/DST/SRXB 8E RES/DS IR/EI B EXTERNAL: EG&G BRYCE,J.H NRC PDR NSIC POOREEW COPIES LTTR ENCL 1 1 1 1 2 2 1 1 2 2 1 1 1 1 2 2 1 1 1 1 1 1 3 3 1 1 1 1 RECIPIENT ID CODE/NAME PD2-2 PD ACRS~AEOD/DS P/TPAB NRR/DET/ECMB 9H NRR/DLPQ/LHFB11 NRR/DOEA/OEAB NRR/DST/SELB 8D NRR/DST 2LBBJ31 RE 0M RGN2 FILE 01 L ST LOBBY WARD NSIC MURPHY,G.A NUDOCS FULL TXT'COPIES LTTR ENCL 1 1 2 2 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 D D'D NOTE TO ALL"RIDS" RECIPIENTS:
D D PLEASE HELP US TO REDUCE WASTE!CONTACT THE DOCUMENT CONTROL DESK, ROOM P 1-37 (EXT.20079)TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!FULL TEXT CONVERSION REQUIRED TOTAL NUMBER OF COPIES REQUIRED: LTTR 33 ENCL 33 P.O.Box 128, Ft.Pierce, FL 34954-0128 FPL APR 3 0 199'-91-133 10 CFR 50.73 U.S.Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C.20555 Gentlemen:
Re: St.Lucie Unit 2 Docket No.50-389'Reportable Event 91-03 Date of Event: April 26, 1991 2A Shutdown Cooling Heat Exchanger Out of Service Due to Mispositioned Component Coolin Water Outlet Valve Caused b Personnel Error The attached Licensee Event Report is being submitted pursuant to the requirements of 10 CFR 50.73 to provide notification of the subject event.A supplemental report will be submitted at the usual 30 day time interval.Very truly yours, D.A.S ger Vice sident St.Lucie Plant DAS:GRM:kw Attachment cc: Stewart D.Ebneter,.Regional Administrator, USNRC Region II Senior Resident Inspector, USNRC, St.Lucie Plant DAS/PSL N423 9g0c0rr0i03 910430 PDF ADOCK 0 000~89 PDR'"~~men FPL Group company:.:.=t.287&gag FPL FacsilliIC OI.NRCFNITT 666<coy U.S.NUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT (LER)~AffNOIIO CAO NO 01 004100 4000%4: lOtH 0 CSTNHITO 000OOI POI IKKOOC IO DC040T 00TN TN0 04Cf0AATTITI DCUE CDITI IOITNCD 000 1000 ICNWNCT CCINCNTC IKCNIIO CIITXN CTTAIATC TO TIC ICDITITT NO NEIDNTC IWNAINICNI OIANGN I040IL IAL IACITAl IKCIIATOIT
~WANNNDDN.
DC SXk4 AIOTO TIN PAOIACITI ICDUGTIDN ffCICCT I 01NI4OC, Cf INN Cf WNAGTACNT NO ILA0GCT WAONIGTDK DC IIICl FACILITY NAME (1)St.Lucie Unit 2 DOCKET NUMBER (2)PAGE 3 050003891 0 0 4'(4)2A Shutdown Cooling Heat Exchanger Out of Service Due to Mispositioned Component Cooling Water Valve Caused by Personnel Error EVENT DATE (5)LER NUMBER (6)REPORT DATE (7)OTHER FACILITIES INVOLVED (8)MONTH DAY 0 4 2 6 YEAR 9 1.9 1 0 0 3 YEAR S IAL MONTH DAY 0 0 4 3 0 YEAR 9 1 FACILITY NAMES N/A N/A DOCKET NUMBER(S)5 0 0 05000.OPERATING MODE (9)POWER LEVEL, (10)1 0 0 201402(b)20.405(a)(1)(i) 20.405(a)(1)(ii) 20.405(a)(1)(iii)201405(a)(1)(iv) 20.405(c)50.36(c)(1) 50.36(c)(2) 50.73(a)(2)(i) 50.73(a)(2)(ii)50.73(a)(2)(iv) 50.73(a)(2)(v) 50.73(a)(2)(vii) 50.73(a)(2)(viii)(A) 50.73(a)(2)(viii)(B)
~THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR: Check one or more of the followin (11)73.71(b)73.71(c)OTHER (Specify in Abstract beloIvandin Text NRC Form 366A)20.405(a)(1)(v) 50.73(a)(2)(iii) 50.73(a)(2)(x)
NAME LICENSEE CONTACT FOR THIS LER 12 Catherine Lauver, Shift Technical Advisor TELEP ONE NUMBER AREA CODE 4 0 7 465-3550 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT 13 CAUSE SYSTEM COMPONENT MANUFAC-TURER B E I S V P 3 4 0 REPORTABLE TO NPRDS CAUSE SYSTEM COMPONENT I I I REPORTABLE TO NPRDS SUPPLEMENTAL REPORT EXPECTED 14 YES (If yes;complete EXPECTED SUBMISSION DATE)NO EXPECTED MONTH DAY YEAR SUBMISSION DATE (15)0 5 2 6 9 ABSTRACT (Limit to f400 spaces.i.e.
approximately fifteen single-space typewritten lines)(16)This is an interim report.A followup report will be submitted.
Corrective actions include: the valve was correctly realigned; the redundant train's valve was checked;both units performed a full Valve Status Check.At 0110 on April 26, 1991, with Unit 2 at 100%power, Operations personnel began searching for a DC ground.At 0400, per plant procedure, Operations cycled HCV-14-3A, Component Cooling Water (CCW)outlet from the 2A Shutdown Cooling (SDC)Heat Exchanger (HX)to de-energize its solenoid operator in an effort to locate the DC ground.After the valve opened, no flow through the heat exchanger was indicated.
Upon investigation, the 2A SDC HX CCW return isolation valve SB-14365 was found to be locked closed.This valve is required to be Locked Open.It had been entered into the Valve Switch Deviation Log on October 23, 1990 as Locked Throttled and restored November 29, 1990.As this is the most recent documented manipulation date, it is assumed to have been mispositioned at this time.The valve position pointer was broken and indicated open.The cause of the mispositioning is under investigation.
FPL Facsimile of NRC Form 366 (6-89)
FPL Facslmra or NRO Form 666 (6-69)~U.S.NUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT (LER)TEXT CONTINUATION ASSASNTO CAO ISA$150 0105 EITf saba AITI505 ssrsfATTO usTWN sea tKspQNsc To cCANLT wlTH TNs ssofsfATcN Souse TISH MOICST: 50 0 ISTS ICON f505 CASAOITS fNCAIONO TASSXN Saf WATS TO TIN raxSSIiNetcSCTTTSuuNAmSNT TNANCH 5 Caa ua 55ASSNT NSOAATNTT ofaIASNSN wAsHNCION.
oc 505fa Ncl To TIc sfsTIINcfN MTTucllQH NT55'ci I'150010150frICC of IMWdDCNf AIST 55$5CCT WNSINSTTSAOC 5050$FACILITY NAME (1)DOCKET NUMBER (2)LER NUMBER (6)PAGE (3)St.Lucie Unit 2 05000389 YEAR 9 1 EQUENTIAL NUMBER 0 0 3 REVISION NUMBER 0 0 0 2 0 0 4 TEXT (If more spaceis reriuired, use additional NRC Form 366A's)(17)This is an interim report.A followup report will be submitted At 0110 on April 26, 1991, with Unit 2 at 100%power, Operations personnel began to search for a DC ground.To find a ground, plant toads are individually isolated.Per plant procedure, Operations cycled HCV-14-3A, Component Cooling Water (CCW)(EIIS:CC)from the 2A Shutdown Cooling (SDC)Heat Exchanger (HX)(EIIS:BP).
During normal operations there is no flow through the shutdown heat exchanger; opening the valve should have resulted in 4000 gpm flow.There was no flow indicated through the HX.Operations.
locally verified movement of HCV-14-3A and position of CCW inlet isolation valve SB-14348.CCW outlet isolation valve SB-14365 is required to be Locked Open, was indicating open by its valve position indicator, but was in fact Locked Closed.The valve was reopened to its proper position.The redundant train's CCW outlet isolation valve position was checked as a precaution.
The valve was in its proper Locked Open position, but its position indicator was also faulty.An investigation revealed that SB-14365 was entered into the Valve Switch Deviation Log on October 23, 1990, when placed in a Locked Throttled position to balance CCW flow.On November 25, 1990, as Unit 2 was completing a refueling outage, the CCW system was placed in its operating alignment.
Operating Procedure 2-0310020,"Component Cooling Water-Normal Operation," was performed.
SB-14365 was verified to be Locked Open at this time;On November 29, 1990, the Valve Switch Deviation Log showed that the valve was restored to its Locked Open position.As November 29 is the last recorded date that SB-14365 was manipulated, it is assumed that the valve has been mispositioned since this time.The lack of an OPERABLE 2A SDC HX causes the 2A train of the Containment Spray System (EIIS:BE)to be administratively out of service.From 0455 on February 19 through 0315 on February 20 and 2208 on February 20 through 1700 on February 21, 1991, the 2B Containment Spray System was out of service for routine maintenance and testing.Plant records are being reviewed to see if there are any other periods of time where both trains of the Containment Spray System were out of service.CCW outlet isolation valve SB-14365 is a manually operated butterfly valve located in a horizontal line about twelve feet above the floor.Valve position indication is provided by a pointer which is supposed to move with the valve stem.The pointer was broken.A Plant Work Order was written October 21, 1990 to repair the pointer and was apparently worked January 17, 1991.At the time the mispositioning was discovered, the pointer erroneously indicated Open.Investigation into this valve position indicator failure will continue.A Standing Night Order states that to check the position of a Locked Open valve, the valve shall be unlocked, closed slightly, reopened, and relocked.While the position indicated by the pointer was inaccurate and misleading, the handwheel on the valve indicates which way to turn to open the valve.Since November of 1990, the position of this valve has been checked twice during the quarterly performance of Administrative Procedure 2-0010123,"Administrative Control of Valves, Locks, and Switches," and weekly during Administrative Procedure 2-0010125A,"Surveillance Data Sheets," FPL Facsimile of NRC Form 366 (6-69)
FPL FccEIIIIAI ol NR" Form 666 (649)V U.S.NUCLEAR REGUlATORY COMMrsslON LICENSEE EVENT REPORT (LER)'EXT CONTINUATION APPICNTO CAO NCk$1 000 10I E PIKR 00000 ECIPNCTo$$oEN PETI fKSPCtSE To CIEPET PRII TIIC ISPÃNAATEPI COUEC CIPI IET$ECP.$1$100$RANNO COWRIE IK CAfoRC RTeol ECTCIATE To TIE IECOT$$No IEPOlr$NANIEIEIIT NNN001+0$E oC IAAEEAEIKOAATCAP
~~.ocPEN,~TooEP~RoccRP RE0EETI$1$001000 cffcE cP MNIAEEAENT AIA MxET, sEIPATlcR cc$050$FACILITY NAME (1)St.Lucie Unit 2 DOCKET NUMBER (2)YEAR 0500038991 LER NUMBER (6)EQUENTIAL NUMBER 0 0 3 REVISIO NUMBER 0 0 PAGE (3)0 30 0 4 TEXT (lf more spaceis required, use additional NRC Form 366A's)'17)
...Data Sheet 36, I At all times it was reported to be Locked Open.The root cause of the event is under investigation.
A review of plant records, including operator logs, clearances, and Plant Work Orders, is being conducted.
Personnel will be interviewed to determine the specific nature and cause of the error.An INPO Human Performance Enhancement System evaluation will also be performed.
V NT This event is reportable under the requirements of 10CFR50.73.a.2.i.B, any condition or operation prohibited by Technical Specifications.
Technical Specification 3.6.2.1"Containment Spray System" requires two independent Containment Spray Systems to be OPERABLE with an OPERABLE Shutdown Cooling Heat Exchanger.
A While the exact date of the mispositioning of the CCW outlet isolation valve to the 2A SDC HX is not yet known, November 29, 1990 is the last recorded date of a manipulation of the valve and is assumed to be the date of the mispositioning.
Over a three day period in February 1991, the 2B Containment Spray System was taken out of service for routine maintenance and testing.The SDC HX is not used until the recirculation phase for decay heat removal.The 2A Containment Spray System was always available to receive cool water from the Refueling Water Tank and deliver it to containment to mitigate a post-LOCA containment pressure rise.An alternate safety system for Containment Heat Removal, the Containment Cooling System, is being further evaluated for decay heat removal capability.
St.Lucie equipment sizing is such that the four containment fan coolers will provide the containment heat removal capability necessary to limit and reduce accident containment pressure and temperature during the recirculation phase.Additional analysis are in progress, assuming a single failure, to demonstrate that two containment fan coolers can also remove Large Break LOCA containment heat load during the recirculation phase.This result is expected because of the PSL containment design in which the free standing steel vessel will transfer heat to the environment.
FPL Engineering has performed a first order risk assessment of the CCW to the SDC HX valve being in the closed position.For a medium or large break LOCA, the frequency associated with the loss of the decay heat removal function only increases from 3.6E-8 per reactor year with a normal SDC HX lineup, to 5.8E-7 per reactor year with the shutdown heat exchanger isolated.With operator action to open the valve, the frequency is reduced to 1.5E-7 per reactor year.Therefore, the health and safety of the public was not affected during this condition.
FPL Facsimile of NRC Form 366 (6-89)
"t III FPL FocsIITS'AT o.'RC Form 666 (649)U.S.NUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT (LER)TEXT CONTINUAllON 0 FFFHOFCO CAO IAS SH0410l CSFSHO: AOWT CNSIATtOOACIHFCHFKSFCSOC TOCCAOSTWOHTIESSFOFSAATCIOOUECSOI FCCACSv:a4 WTS FCHA1AIO CCAACTOSFHOAFOWOHASHH tSISAAIC TOHC FCOrftfS FIAT FCFOITS NQACCAASIT OIAHCH IF4$$OOSrrltAR FHOAAIOHT 00$40$CAI WAOOHOCW.OC TlÃOL FFST To SIC FFCFFINASW SDVCOCH FFTSCCT ($110410AS Cf FISC OF AAOCACTITAFO IIAXCT,WASH HOTOA OC SH0$FACILITY NAME (1)St.Lucie Unit 2 DOCKET NUMBER (2)YEAR LER NUMBER (6)EQUENTIAL NUMBER REVISION NUMBER PAGE (3)0500038991 TEXT (If more spaceis rerluired, use additional NRC Form 366A's)(17)0 0 3 0 0 0 4 0 0 4 1.Operations restored SB-14365 to its proper position and verified the position of the redundant train's CCW outlet isolation valve.2.Plant Work Orders were submitted to repair the faulty pointers on each valve and determine the root cause of the faulty pointer.3.All Operations personnel were counseled on the use of the Standing Night Order.Operations is investigating further methods to enhance independent verification.
4.Operations performed the entire Weekly Valve Status Check on both Unit 1 and Unit 2.No further discepancies were noted.5.An INPO Human Performance Enhancement System evaluation will be performed on this event.'he review will include human factors and work conditions.
Affected Component Identification:
Henry Prat t 14H Butterfly Valve Nuclear MK II with Manual Operator MDT-3 HW Model Number 1001 78 Serial Number C140 Previous Similar Licensee Event Reports: 335-89-002"Inoperable 1B Diesel Generator Due to Fuel Oil System Valve Misalignment" 335-87-012"Loss of Component Cooling Water Redundancy-1A and 1B Component Cooling Water Cross-tie Valves in Open Position" FPL Facsimile of NRC Form 366 (6-69)
