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| | issue date = 05/10/1993 | | | issue date = 05/10/1993 |
| | title = LER 93-004-00:on 930409,typo Discovered in Rept Used to Determine RPS Low RCS Flow Trip Setpoint.Error Existed Since Aug 1988.Caused by Design Control Inadequacy.Engineering Package Developed to Correct calculations.W/930510 Ltr | | | title = LER 93-004-00:on 930409,typo Discovered in Rept Used to Determine RPS Low RCS Flow Trip Setpoint.Error Existed Since Aug 1988.Caused by Design Control Inadequacy.Engineering Package Developed to Correct calculations.W/930510 Ltr |
| | author name = SAGER D A, YOUNG R J | | | author name = Sager D, Young R |
| | author affiliation = FLORIDA POWER & LIGHT CO. | | | author affiliation = FLORIDA POWER & LIGHT CO. |
| | addressee name = | | | addressee name = |
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| {{#Wiki_filter:ACCELERANT DOCUMENTDISTRj:UTIONSYSTEMREGULATINFORMATION DISTRIBUTION STEM(RIDS)ACCESSION NBR:9305180328 DOC.DATE: | | {{#Wiki_filter:ACCELERANT DOCUMENT DISTRj: UTION SYSTEM REGULAT INFORMATION DISTRIBUTION STEM (RIDS) |
| 93/05/10NOTARIZED: | | ACCESSION NBR:9305180328 DOC.DATE: 93/05/10 NOTARIZED: NO DOCKET ¹ FACIL:50-335 St. Lucie Plant, Unit 1, Florida Power & Light Co. 05000335 AUTH. NAME AUTHOR AFFILIATION YOUNG,R.J. Florida Power & Light Co. |
| NOFACIL:50-335 St.LuciePlant,Unit1,FloridaPower&LightCo.AUTH.NAMEAUTHORAFFILIATION YOUNG,R.J.
| | SAGER,D.A. Florida Power & Light Co. |
| FloridaPower&LightCo.SAGER,D.A.
| | RECIP.NAME RECIPIENT AFFILIATION |
| FloridaPower&LightCo.RECIP.NAME RECIPIENT AFFILIATION DOCKET¹05000335
| |
|
| |
|
| ==SUBJECT:== | | ==SUBJECT:== |
| LER93-004-00:on 930409,typo discovered inreptusedtodetermine RPSlowRCSflowtripsetpoint.Error existedsinceAug1988.Caused bydesigncontrolinadequacy.
| | LER 93-004-00:on 930409,typo discovered in rept used to determine RPS low RCS flow trip setpoint.Error existed since D Aug 1988.Caused by design control inadequacy. Engineering package developed to correct calculations.W/930510 ltr. |
| Engineering packagedeveloped tocorrectcalculations.W/930510 ltr.DZSTRZSUTZON CODE:IE22TCOPIESRECEIVED:LTR IENCL/SIZE:TITIE:50.73/50.9 LicenseeEventReport(LER),IncidentRpt,etc.NOTES:DRECIPIENT IDCODE/NAME PD2-2LANORRISgJINTERNAL: | | DZSTRZSUTZON CODE: IE22T COPIES RECEIVED:LTR I ENCL / SIZE: |
| ACNWAEOD/DOAAEOD/ROAB/DSP NRR/DE/EMEB NRR/DRCH/HHFB NRR/DRCH/HOLB NRR/DRSS/PRPB NRR/DSSA/SRXB RES/DSIR/EIB EXTERNAL:
| | TITIE: 50.73/50.9 Licensee Event Report (LER), Incident Rpt, etc. |
| EG&GBRYCEPJ.H NRCPDRNSICPOOREPW.COPIESLTTRENCL1111221122111111221111221111RECIPIENT IDCODE/NAME PD2-2PDACRSAEOD/DSP/TPAB NRR/DE/EELB NRR/DORS/OEAB NRR/DRCH/HICB NRR/DRIL/RPEB NRR.DSSA/SPLB 02RGN2FILE01LSTLOBBYWARDNSICMURPHY,G.A NUDOCSFULLTXTCOPIESLTTRENCL11221111111,111111111111.111DDDDNOTETOALL"RIDS"RECIPIENTS: | | NOTES: |
| PLEASEHELPUSTOREDUCEWASTE!CONTACTTHEDOCUMENTCONTROLDESK,ROOMPl-37(EXT.504-2065)
| | RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL D PD2-2 LA 1 1 PD2-2 PD 1 1 NORRISgJ 1 1 D INTERNAL: ACNW 2 2 ACRS 2 2 AEOD/DOA 1 1 AEOD/DSP/TPAB 1 1 AEOD/ROAB/DSP 2 2 NRR/DE/EELB 1 1 NRR/DE/EMEB 1 1 NRR/DORS/OEAB 1 1 NRR/DRCH/HHFB 1 1 NRR/DRCH/HICB 1, 1 NRR/DRCH/HOLB 1 1 NRR/DRIL/RPEB 1 1 NRR/DRSS/PRPB 2 2 NRR .DSSA/SPLB 1 1 NRR/DSSA/SRXB 1 1 02 1 1 RES/DSIR/EIB 1 1 RGN2 FILE 01 1 1 EXTERNAL: EG&G BRYCEPJ.H 2 2 L ST LOBBY WARD 1 1 NRC PDR 1 1 NSIC MURPHY,G.A 1 . 1 NSIC POOREPW. 1 1 NUDOCS FULL TXT 1 1 D |
| TOELIMINATE YOURNAMEFROMDISTRIBUTION LISTSFORDOCUMENTS YOUDON'TNEED!DFULLTEXTCONVERSION REQUIREDTOTALNUMBEROFCOPIESREQUIRED:
| | D D |
| LTTR32ENCL32 PP'fMay10,1993L-93-12910CFR50.73U.S.NuclearRegulatory Commission Attn:DocumentControlDeskWashington, D.C.20555Re:.St.LucieUnit1DocketNo.50-335Reportable Event:93-004DateofEvent:April9,1993Incorrect RCSLowFlowTripSetpointduetoaDesinErrorTheattachedLicenseeEventReportisbeingsubmitted pursuanttotherequirements of10CFR50.73toprovidenotification ofthesubjectevent.Verytrulyyours,4A8a~D.A.gerVicersidentSt.LuePlantDAS/JWH/kw Attachment cc:StewartD.Ebneter,RegionalAdministrator, USNRCRegionIISeniorResidentInspector, USNRC,St.LuciePlantDAS/PSL8917-931700339305i80328 9305i0PDRADOCK05000335SPDRanFPLGroupcompany PPPFPLFEOElmloolNRCFormK6(M9)L.S.tEUCLEARREGULATORY COMMISSION LICENSEEEVENTREPORT(LER)APPROYOTONENCk0110010IENNPEE'NHNT EETPIATE0NAaENPENINEPCNTETOCEPNCYWITHTI00NfOIEAATlON CCATECSTINTINCEEET.>>0 HTESONWNaCONNENTESNONEPNOTAfaENEETTwIE ToTHEINOCla0ANTPEPONTENANAKINNTEAANCHTPANIAIANIANAENIPEIANATCNY~WATPNarol.
| | NOTE TO ALL"RIDS" RECIPIENTS: |
| OCIPHENaToTHEPPENWITTN SEOOCTONPNOECTo'110010PA CfSCEOfNAMOEIENT PIEIOAXNT.WASPNeOTCPC OCITNELFACILITYNAME(1)St.LucieUnit1DOCKETNUMBER(2)PAGE3050003351 04(4)Incorrect ReactorCoolantSystemLowFlowTripSetpointresultsinacondition prohibited byTechnical Specifications duetoaDesignControlInadequacy.
| | PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT. 504-2065) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED! |
| EVENTDATE(5)LERNUMBER(6)REPORTDATE(7)OTHERFACILITIES INVOLVED(8)MOMlHDAY0409OPERATING MODE(9)YEARYEAR9393SIAL004MONTHDAYYEAR00051093FACILITYNAMESN/AN/A20.402(b) 20.405(c) 50.73(a)(2)(iv)
| | FULL TEXT CONVERSION REQUIRED TOTAL NUMBER OF COPIES REQUIRED: LTTR 32 ENCL 32 |
| THISREPORTISSUBMITTED PURSUANTTOTHEREQUIREMENTS OF10CFR:Checkoneormoreofthefollowin(11)DOCKETNUMBER(S) 050000500073.71(b)POWERLEVEL(10)20.405(a)(1
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| )(i)20.405(a)(1
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| )(ii)20.405(a)(1)(iii) 20.405(a)(1)(iv) 20.405(a)(1)(v) 50.36(c)(1) 50.36(c)(2) 50.73(a)(2)(i) 50.73(a)(2)(ii) 50.73(a)(2)(iii) 50.73(a)(2)(v) 50.73(a)(2)(vii) 50.73(a)(2)(viii)(A) 50.73(a)(2)(viii)(B) 50.73(a)(2)(x) 73.71(c)OTHER(SpecifyinAbstractbelowandinTextNRCForm366A)NAMELICENSEECONTACTFORTHISLER12RobertJ.Young,ShiftTechnical AdvisorTELEPONENUMBERAREACODE407465.3550COMPLETEONELINEFOREACHCOMPONENT FAILUREDESCRIBED INTHISREPORT13CAUSESYSTEMCOMPONENT MANUFAG-REPORTABLE TURERTONPRDSCAUSESYSTEMCOMPONENT MANUFAC-REPORTABLE lURERTONPRDSSUPPLEMENTAL REPORTEXPECTED14IIIEXPECTEDMONIHDAYYEARSUBMISSION DATE(15)YES(Ifyes,completeEXPECTEDSUBMISSION DATE)ABSTRACT(Limitto1400spaces.ie.approximately fifteensingle-space typewritten lines)(16)OnApril9,1993,St.LucieUnit1wasinMode6whenatypographical errorwasdiscovered byFPLNuclearEngineering inareportusedtodetermine theReactorProtection System(RPS)lowReactorCoolantSystem(RCS)flowtripsetpoint.
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| Technical Specification 2.2.1,Table2.2-1statesthatthetripsetpointwillbegreaterthanorequalto95%ofdesignreactorcoolantflow.TheFPLNuclearEngineering report,whichdescribed theconversion ofpressuredropacrossthesteamgenerators totheRPSlowRCSflowtripsetpoint, contained anincorrect constant.
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| Thereportwassubsequently transmitted totheplantstaffandtheInstrument andControlDepartment adjustedtheRCSlowflowsetpoint.
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| ThiserrorcausedthesettingoftheRCSlowflowtripsetpointtoavalueapproximately 3%belowtheminimum95%ofdesignflow.ThissetpointerrorexistedsinceAugust1988.Therootcauseofthiseventwasadesigncontrolinadequacy.
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| Atypographical errorwasmadeinthereporttransmitted totheplantstaff.Theerrorwouldhavebeendiscovered ifthereviewprocessforthetransmitted reporthadundergone anindependent review.TheNuclearEngineering processcurrently inplacepreventsasimilareventfromoccurring byrequiring independent reviewoftransmitted setpoints.
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| Corrective actionsforthisevent:Anengineering evaluation wasperformed thatconcluded thattheoperation ofUnit1duringthistimeperiodwaswithintheboundsofthesafetyanalysis.
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| Areviewoftheprocedure usedtodetermine theUnit2lowRCSflowsetpointverifiedthatitdidnotcontainasimilarerror.Afterareviewofinternalrecords,NuclearEngineering verifiedthatnootherUnit1or2RPSsetpointchangesweretransmitted totheplantinerror.Anengineering packagewasdeveloped toprovidethecorrected calculations fordetermination oftheRPSreactorcoolantsystemlowflowtripsetpoint.
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| Instrumentation andControlpersonnel willreviseappropriate procedures andinstallthecorrecttripsetpointintheUnit1RPSpriortoenteringmode2.Priortodiscovery ofthisevent,Engineering adoptedaprocessrequiring independent reviewofsetpoints beforetransmittal totheplantstaff.FPLFacsimile ofNRGForm366(6-89)
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| FPLFsaslnilsof NRCFormSEI(&89)U.S.NUCLEARREGULATORY COMMISSION LICENSEEEVENTREPORT(LER)TEXTCONTINUATION Asswosf0oeIxsssssCIssfxssus'ass sfSTAIATf0OATCENsfilINSAONsfToCOINETWITHsissSfCWNATTCNCasEfCOONIfoUECTIsfsIsxsssxswNecoNNENTsIKOANowoEssesNfsoNATEToTIOINcsxsssNeISAONTSNANACEsfNTfssANCHTASTCEuaNXXENTIuauATEXTT
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| ~wAEINeTON.OossssfNeToTIOSNEIIwowIsoucwoNTwofcsETIsseIsssasrscfosswNACEISNT NeTseofs.WANNesfsf ocssexsFACILITYNAME(1)St.LucieUnit1DOCKETNUMBER(2)YEARLERNUMBER(6)gEQUENTIAL NUMBERREVISIONNUMBERPAGE(3)0500033593TEXT(lfmorespaceisrequired, useadditional NRCForm366A's)(1/)004000204OnApril9,1993,withUnit1inMode6,FPLNuclearEngineering performed areviewofthecalculations thatarecontained intheSt.LucieUnit1LowFlowTripSetpointCalibration Guidelines.
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| Thereviewwasbeingperformed tosupportaproposedchangetothesteamgenerator tubepluggingcriteria.
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| Duringthisreview,atypographical errorinareportthatdescribed conversion ofpressuredropacrosstheSteamGenerators (EIIS:AB) totheReactorProtection System(RPS)(EIIS:JC)ReactorCoolantSystem(RCS)lowflowtripsetpointwasfound.Theerrorresultedinthecalculation ofanon-conservative setpointwithwhichtheRPScreatesanautomatic reactortriptoprotectagainstalossofRCSflow.ThiserrorcausedtheRPSlowRCSflowtripsetpointtobeapproximately 3percentbelowtheTechnical Specification minimumof95percentofdesignflow.In1987thereportcontaining theincorrect information wassenttotheplantstafftosupportamodification totheRPS.InAugust1988,thereportwasreferenced whenthemodification totheRPSwasimplemented andwasusedtomodifyplantprocedures fortheinitialsettingandsubsequent monthlychecksofthisRPSlowflowtripsetpoint.
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| Thiscondition wasdiscovered inAprilof1993.Therootcauseofthiseventwasadesigncontrolinadequacy.
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| Atypographical errorwasmadebyFPLNuclearEngineering inthetransmittal ofacalculated setpointtotheplantstaff.Duringatransferofinformation fromanindependently verifiedengineering calculation toareport,atranscription errorcausedaconstantthatconvertspressuredropacrosstheSteamGenerators tothelowRCSflowtripsetpointtobenon-conservative.
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| Theincorrect reportwouldhavebeendiscovered andcorrected hadthetransmitted reporttotheplantstaffreceivedthesameindependent reviewthattheoriginalcalculation hadreceived.
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| Priortothediscovery ofthisevent,FPLNuclearEngineering adoptedtheprocessforrequiring independent reviewofallsetpoints beforetransmittal totheplantstaff.Thiseventisreportable under10CFR50.73(a)(2)(i)(B),
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| as"Anyoperation orcondition prohibited bytheplant'sTechnical Specifications."
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| Technical Specification 2.2.1requiresthattheRPStripsetpointforRCSlowflowbesetatorabove95percentofdesignflow(370,000gpm).Forcycles9,10and11ofUnit1operation, theRCSlowflowtripwaserroneously setatslightlyhigherthan92percentofdesignflow.TheRCSlowflowtripsetpointensuresthatforadegradation ofRCSflowresulting fromanalyzedtransients, areactortripoccurstopreventdeparture fromnucleateboilingratio(DNBR)safetylimits.Theprocesssignalforthisfunctionisdeveloped fromfourindependent differential pressurechannelswhichmeasurethepressuredropacrosstheprimarysideofbothSteamGenerators.
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| ThetotalSteamGenerator pressuredropiscomparedwiththelowRCSflowtripsetpoint.
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| Iftwochannelsindicateaflowwhichislessthanthetripsetpoint, anRPStripsignalisinitiated.
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| FPLFacsimile ofNRCForm366(6-89)
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| FPLFacstmloolNRCFormS66($89)U.S.NUCLEARREGULATORY COMMrSSIONUCENSEEEVENTREPORT(LER)TEXTCONTINUATION
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| ,AAINorrocooNI$
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| $$$oerorcofrfoarrfoeooeTAIATToofvcrNITNIoefcfocToccoe$vTATNoooofrfvAACON couococNIacracTl$04IeoafoNwrfoccrrrNTofccfrlooro IAATIENoeoNATcToTtoIocofoowo$fafomoNANACT$CNTONANCNreeTCAuaNOCITANIN$$AATONv~wANNIOTCN, oc$0$$aANITollofATNAwrovr IacucocNffvoacI$$$Ioeror$cffICEofIIANAccoaNT Afo$$$$ccr,wANNrcrcfo ocToooaFACILITYNAME(1)St.LucieUnit1DOCKETNUMBER(2)YEARLERNUMBER(6)EQUENTIAL
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| -rREVISIONNUMBER4NUMBERPAGE(3)0500033593 TEXT(Ifmorespaceisrequired, useadditional NRCForm366A's)(17)004000304Anevaluation (JPN-PSL1-SEFJ-93-006) wasperformed byFPLEngineering todetermine theavailable safetyanalysismarginforthemostlimitingtransients (lossofoffsitepowerandlossofRCSflow)forwhichprotection isprovidedbytheRCSlowflowtrip.Theresultsshowthattheapproximate 3percentsetpointerrorissufficiently offsetbyavailable flowmargin.Thus,violation oftheDNBRlimitforalossofoffsitepoweroralossofRCSfloweventwouldnothaveoccurrediftherehadbeenadegradation ofRCSfloweventduringthetimeperiodthatthesetpointerrorwasinplace.(AreviewofUnit1reactortripsshowedthattheRCSlowflowtripfunctionwasnotchallenged duringcycles9,10and11.Anadditional reviewofactualoperating conditions duringcycles9,10,and11wasperformed toensurethatnoothercondition existedthatwouldfurtheraggravate thecondition described inthisLER).TheReactorCoolantPump(RCP)(EIIS:P) seizedrotoreventhasbeenreanalyzed bythefuelvendorfora4percentreduction indesignflowandthecorresponding 4percentreduction intheRCSlowflowtripsetpoint.
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| Theanalysisshowsthattheacceptance criteriaforthepostulated RCPseizedrotoreventwasnotviolated.
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| Therefore, thehealthandsafetyofthepublicwasnotaffectedbythiscondition.
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| 1.Priortothediscovery ofthisevent,NuclearEngineering proceduralized areviewprocesstoensuretheaccuracyofsetpoints andplantchanges.Thisprocessrequiresanindependent verification ofsetpoints andplantchangesbeforetransmittal totheplantstaff,andwouldhavedetectedtheerrordescribed inthisreport.2.NuclearEngineering preparedanengineering evaluation anddetermined thatoperation ofUnit1wasboundedbythesafetyanalysesforCycles9,10,and11.3.NuclearEngineering reviewedinternalrecordsandverifiedthatnootherUnit1or2RPSsetpointchangesweretransmitted totheplantstaffinerror.4.NuclearEngineering reviewedtheUnit2RCSLowFlowTripSetpointDetermination procedure andverifiedthatitdidnotuseerroneous data.5.AFPLengineering packagewasdeveloped todocumentandtransmitthecorrected calculation fortheUnit1RPSIowRCSflowtripsetpoint.
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| 6.TheI&CDepartment willreviseprocedures 1-0120050 and1-1400050
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| ~toreflectthecorrectRCSlowflowtripsetpoints priortoUnit1enteringMode2.7.TheI&CDepartment willmaketheRPSlowRCSflowtripsetpointchangespriortoUnit1enteringMode2.FPLFacsimile ofNRCForm366(6-89)
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| FPLF55cslrrllo olNRCFormS6BU.S.NUCLEARREGULATORY COMMrSSION
| | May 10, 1993 PP'f L-93-129 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: 93-004 Date of Event: April 9, 1993 Incorrect RCS Low Flow Trip Setpoint due to a Desi n 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. |
| ~LICENSEEEVENTREPORT(LER)TEXTCONTINUATION APAN5TITO CAONCI$1500505fAASNS:IO00550TWATToTAANNN05IIINSAONICTOGTANAYWoilTIIS005$0AAOONCOTITCOONISISNST:500ITISICAINNoOONNANT0NTOAIIONO TAAoCNTSTYAATSloTININGTAYISAIAIINICNTSNANAGSISNTSNANCHTNINa IASIANATAIIINGAAATGNY | | Very truly yours, 4A8a ~ |
| ~WANNNTTGN.OG505$ | | D. A. ger Vice r sident St. Lu e Plant DAS/JWH/kw Attachment cc: Stewart D. Ebneter, Regional Administrator, USNRC Region Senior Resident Inspector, USNRC, St. Lucie Plant II DAS/PSL 8917-93 170033 9305i80328 9305i0 PDR ADOCK 05000335 S PDR an FPL Group company |
| 5N05TOONAAIYNWCa<ISTACTTGNTNOXGTTITIOSTINTTYNCS TNINNAGSINNT AI05TAOGCT,WAONKITTYA OO5050$.FACILITYNAME(1)DOCKETNUMBER(2)LERNUMBER(6)PAGE(3)St.LucieUnit1YEAR':0500033593EQUENTIAL NUMBER004.REVISIONUMBER000404TEXT(Ifmorespaceisrequired, useadditional NRCForm366A's)(1/)NoneAprevioussimilarLERatSt.Lucieinvolving adesignerrorfortheRPSwas:LER335-79-30 SteamGenerator LowLevelRPStripsetpoints lessthanTechnical Specifications duetoadesignermr.FPLFacsimile ofNRCForm366(6-89)}}
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| | ~ |
| | PPP FPL FEOElmlo ol L.S. tEUCLEAR REGULATORY COMMISSION APPROYOT ONE NCk 01 10 010I ENNPEE'NHNT NRC Form K6 EET PIATE 0 NAaE N PEN INEPCNTE TO CEPNCY WITH TI00 NfOIEAATlONCCATEC STINT (M9) |
| | LICENSEE EVENT REPORT (LER) INCEEET.>>0 HTE SONWNa CONNENTE SNONEPNO TAfaENEETTwIE To THE INOCla0 ANT PE PONTE NANAKINNT EAANCHTPANIAIANIANAENIPE IANATCNY WATPNarol. OC IPHE Na To THE PPENWITTN SEOOC TON PNOECT o'110010PA Cf SCE Of NAMOEIENTPIEI OAXNT.WASPNeOTCPC OC ITNEL FACILITYNAME (1) DOCKET NUMBER (2) PAGE 3 St. Lucie Unit 1 050003351 0 4 (4) Incorrect Reactor Coolant System Low Flow Trip Setpoint results in a condition prohibited by Technical Specifications due to a Design Control Inadequacy. |
| | EVENT DATE (5) LER NUMBER (6) REPORT DATE (7) OTHER FACILITIES INVOLVED(8) |
| | MOMlH DAY YEAR YEAR S IAL MONTH DAY YEAR FACILITYNAMES DOCKET NUMBER(S) |
| | N/A 05 000 0 4 09 9 3 9 3 0 0 4 00051093 THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR: |
| | N/A 05000 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) 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 and in Text 20.405(a)(1)(iv) 50.73(a)(2)(viii)(B) NRC Form 366A) 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 NAME TELEP ONE NUMBER AREA CODE Robert J. Young, Shift Technical Advisor 4 0 7 465.3550 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT 13 MANUFAG- REPORTABLE MANUFAC- REPORTABLE CAUSE SYSTEM COMPONENT TURER TO NPRDS CAUSE SYSTEM COMPONENT lURER TO NPRDS I I I SUPPLEMENTAL REPORT EXPECTED 14 EXPECTED MONIH DAY YEAR SUBMISSION YES (Ifyes, complete EXPECTED SUBMISSION DATE) DATE (15) |
| | ABSTRACT (Limit to 1400 spaces. i e. approximately fifteen single-space typewritten lines) (1 6) |
| | On April 9, 1993, St. Lucie Unit 1 was in Mode 6 when a typographical error was discovered by FPL Nuclear Engineering in a report used to determine the Reactor Protection System (RPS) low Reactor Coolant System (RCS) flow trip setpoint. Technical Specification 2.2.1, Table 2.2-1 states that the trip setpoint will be greater than or equal to 95% of design reactor coolant flow. The FPL Nuclear Engineering report, which described the conversion of pressure drop across the steam generators to the RPS low RCS flow trip setpoint, contained an incorrect constant. The report was subsequently transmitted to the plant staff and the Instrument and Control Department adjusted the RCS low flow setpoint. This error caused the setting of the RCS low flow trip setpoint to a value approximately 3% below the minimum 95% of design flow. This setpoint error existed since August 1988. |
| | The root cause of this event was a design control inadequacy. A typographical error was made in the report transmitted to the plant staff. The error would have been discovered if the review process for the transmitted report had undergone an independent review. The Nuclear Engineering process currently in place prevents a similar event from occurring by requiring independent review of transmitted setpoints. |
| | Corrective actions for this event: An engineering evaluation was performed that concluded that the operation of Unit 1 during this time period was within the bounds of the safety analysis. A review of the procedure used to determine the Unit 2 low RCS flow setpoint verified that it did not contain a similar error. After a review of internal records, Nuclear Engineering verified that no other Unit 1 or 2 RPS setpoint changes were transmitted to the plant in error. An engineering package was developed to provide the corrected calculations for determination of the RPS reactor coolant system low flow trip setpoint. Instrumentation and Control personnel will revise appropriate procedures and install the correct trip setpoint in the Unit 1 RPS prior to entering mode 2. Prior to discovery of this event, Engineering adopted a process requiring independent review of setpoints before transmittal to the plant staff. |
| | FPL Facsimile of NRG Form 366 (6-89) |
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| | ~ |
| | FPL Fsaslnilsof U.S. NUCLEAR REGULATORY COMMISSION Asswosf 0 oe Ixs ss ss C I ss NRC Form SEI |
| | (&89) fxssus'ass s LICENSEE EVENT REPORT (LER) fSTAIATf0 OATCE N sf ilINSAONsf To COINET WITH siss SfCWNATTCN Cas EfCOON IfoUECTIsfs Isxs ssxswNe coNNENTs IKOANowoEsses N fsoNATE To TIO INcsxsss TEXT CONTINUATION Ne ISAONTS NANACEsf NT fssANCH TASTCE ua NXXENTIuauATEXTT wAEINeTON. Oo ssssf Ne To TIO SNEIIwow IsoucwoN Twofcs ETI sseIsss asrscf os swNACEISNT Ne Tseofs. WANNesfsf oc ssexs FACILITYNAME (1) DOCKET NUMBER (2) LER NUMBER (6) PAGE (3) |
| | YEAR g EQUENTIAL REVISION St. Lucie Unit1 NUMBER NUMBER 0 500 0335 9 3 0 0 4 0 0 0 2 0 4 TEXT (lfmore spaceis required, use additional NRC Form 366A's) (1/) |
| | On April 9, 1993, with Unit 1 in Mode 6, FPL Nuclear Engineering performed a review of the calculations that are contained in the St. Lucie Unit 1 Low Flow Trip Setpoint Calibration Guidelines. |
| | The review was being performed to support a proposed change to the steam generator tube plugging criteria. During this review, a typographical error in a report that described conversion of pressure drop across the Steam Generators (EIIS:AB) to the Reactor Protection System (RPS) (EIIS: |
| | JC) Reactor Coolant System (RCS) low flow trip setpoint was found. The error resulted in the calculation of a non-conservative setpoint with which the RPS creates an automatic reactor trip to protect against a loss of RCS flow. This error caused the RPS low RCS flow trip setpoint to be approximately 3 percent below the Technical Specification minimum of 95 percent of design flow. |
| | In 1987 the report containing the incorrect information was sent to the plant staff to support a modification to the RPS. In August 1988, the report was referenced when the modification to the RPS was implemented and was used to modify plant procedures for the initial setting and subsequent monthly checks of this RPS low flow trip setpoint. This condition was discovered in April of 1993. |
| | The root cause of this event was a design control inadequacy. A typographical error was made by FPL Nuclear Engineering in the transmittal of a calculated setpoint to the plant staff. During a transfer of information from an independently verified engineering calculation to a report, a transcription error caused a constant that converts pressure drop across the Steam Generators to the low RCS flow trip setpoint to be non-conservative. The incorrect report would have been discovered and corrected had the transmitted report to the plant staff received the same independent review that the original calculation had received. Prior to the discovery of this event, FPL Nuclear Engineering adopted the process for requiring independent review of all setpoints before transmittal to the plant staff. |
| | This event is reportable under 10CFR50.73(a)(2)(i)(B), as "Any operation or condition prohibited by the plant's Technical Specifications." Technical Specification 2.2.1 requires that the RPS trip setpoint for RCS low flow be set at or above 95 percent of design flow (370,000 gpm). For cycles 9, 10 and 11 of Unit 1 operation, the RCS low flow trip was erroneously set at slightly higher than 92 percent of design flow. |
| | The RCS low flow trip setpoint ensures that for a degradation of RCS flow resulting from analyzed transients, a reactor trip occurs to prevent departure from nucleate boiling ratio (DNBR) safety limits. |
| | The process signal for this function is developed from four independent differential pressure channels which measure the pressure drop across the primary side of both Steam Generators. The total Steam Generator pressure drop is compared with the low RCS flow trip setpoint. If two channels indicate a flow which is less than the trip setpoint, an RPS trip signal is initiated. |
| | FPL Facsimile of NRC Form 366 (6-89) |
| | |
| | ~ |
| | FPL Facstmlo ol U.S. NUCLEAR REGULATORY COMMrSS ION , AAINorrocooNI$ $ $ $ oeror NRC Form S66 cofrfoa rrfoeo |
| | ($ 89) oe TAIATTo ofvcrN ITN Ioefcfoc To ccoe$ v TATNooo ofrfvAACONcouococN UCENSEE EVENT REPORT (LER) Iacra cTl $ 0 4 Ieoa foNwrfoccrrrNT o fccfrlooro IAATIENoeoNATc To Tto Iocofoo wo$ fafomo NANACT$C NT ONANCN reeTCA ua NOCIT AN IN$$ AATONv TEXT CONTINUATION wANNIOTCN,oc $ 0$ $ a ANITo llo f I ATNAwrovrIacucocN ffvoac $ $ $ Ioe ror$ cffICE of IIANAccoaNTAfo $ $$ $ ccr,wANNrcrcfo oc Toooa FACILITYNAME (1) DOCKET NUMBER (2) LER NUMBER (6) PAGE (3) |
| | YEAR EQUENTIAL -r REVISION St. Lucie Unit 1 NUMBER 4 NUMBER 0500033593 0 0 4 0 0 0 3 0 4 TEXT (Ifmore spaceis required, use additional NRC Form 366A's) (17) |
| | An evaluation (JPN-PSL1-SEFJ-93-006) was performed by FPL Engineering to determine the available safety analysis margin for the most limiting transients (loss of offsite power and loss of RCS flow) for which protection is provided by the RCS low flow trip. The results show that the approximate 3 percent setpoint error is sufficiently offset by available flow margin. Thus, violation of the DNBR limit for a loss of offsite power or a loss of RCS flow event would not have occurred if there hadbeen a degradation of RCS flow event during the time period that the setpoint error was in place. (A review of Unit 1 reactor trips showed that the RCS low flow trip function was not challenged during cycles 9,10 and 11. An additional review of actual operating conditions during cycles 9, 10, and 11 was performed to ensure that no other condition existed that would further aggravate the condition described in this LER). |
| | The Reactor Coolant Pump (RCP)(EIIS:P) seized rotor event has been reanalyzed by the fuel vendor for a 4 percent reduction in design flow and the corresponding 4 percent reduction in the RCS low flow trip setpoint. The analysis shows that the acceptance criteria for the postulated RCP seized rotor event was not violated. Therefore, the health and safety of the public was not affected by this condition. |
| | : 1. Prior to the discovery of this event, Nuclear Engineering proceduralized a review process to ensure the accuracy of setpoints and plant changes. This process requires an independent verification of setpoints and plant changes before transmittal to the plant staff, and would have detected the error described in this report. |
| | : 2. Nuclear Engineering prepared an engineering evaluation and determined that operation of Unit 1 was bounded by the safety analyses for Cycles 9, 10, and 11. |
| | : 3. Nuclear Engineering reviewed internal records and verified that no other Unit 1 or 2 RPS setpoint changes were transmitted to the plant staff in error. |
| | : 4. Nuclear Engineering reviewed the Unit 2 RCS Low Flow Trip Setpoint Determination procedure and verified that it did not use erroneous data. |
| | : 5. A FPL engineering package was developed to document and transmit the corrected calculation for the Unit 1 RPS Iow RCS flow trip setpoint. |
| | : 6. The I&C Department will revise procedures 1-0120050 |
| | ~ and 1-1400050 to reflect the correct RCS low flow trip setpoints prior to Unit 1 entering Mode 2. |
| | : 7. The I&C Department will make the RPS low RCS flow trip setpoint changes prior to Unit 1 entering Mode 2. |
| | FPL Facsimile of NRC Form 366 (6-89) |
| | |
| | ~ |
| | FPL F55cslrrllo ol U.S. NUCLEAR REGULATORY COMMrSSION APAN5TITOCAO NCI $ 1 50 0505 NRC Form S6B fAASNS: IO005 LICENSEE EVENT REPORT (LER) 5 0TWAT To TAANNN05 II INSAONIC TO GTANAYW oil TIIS 005$ 0AAOON COTITCOON ISISN ST: 500 ITIS ICAINNo OONNANT0 NTOAIIONOTAAoCNTSTYAATS lo TIN INGTAYIS |
| | ~ |
| | AIAIINICNTSNANAGSISNTSNANCHTNINaIAS IANATAIIINGAAATGNY TEXT CONTINUATION WANNNTTGN.OG505$5 N05TOON AAIYNWCa<ISTACTTGNTNOXGTTITIOSTINTTYNCS TN INNAGSINNTAI05 TAOGCT, WAONKITTYAOO 5050$ . |
| | FACILITYNAME (1) DOCKET NUMBER (2) LER NUMBER (6) PAGE (3) |
| | YEAR ': EQUENTIAL NUMBER |
| | . REVISIO NUMBER St. Lucie Unit 1 0 500 0335 9 3 0 0 4 0 0 0 4 0 4 TEXT (Ifmore spaceis required, use additional NRC Form 366A's) (1/) |
| | None A previous similar LER at St. Lucie involving a design error for the RPS was: |
| | LER 335-79-30 Steam Generator Low Level RPS trip setpoints less than Technical Specifications due to a design ermr. |
| | FPL Facsimile of NRC Form 366 (6-89)}} |
|
|---|
Category:LICENSEE EVENT REPORT (SEE ALSO AO
MONTHYEARML17241A4891999-10-0707 October 1999
LER 99-004-00:on 990912,noted That MSSV Surveillance Was Outside of TS Requirements.Caused by Setpoint Drift.Subject MSSVs Are Being Refurbished & Retested Prior to Unit Startup from SL1-16 Refueling Outage.With 991007 Ltr
ML17241A4111999-07-16016 July 1999
LER 99-007-00:on 990610,unplanned Cooldown Transient Occurred Due to Personnel Error.Trained & Briefed Personnel & Revised Procedures.With 990716 Ltr
ML17241A4031999-07-0606 July 1999
LER 99-006-00:on 990605,sub-critical Reactor Trip Occurred Due to Inadvertent MSIV Opening.Caused by Personnel Error. Provided Operation Supervision Instruction to Operating Crews,Stand Down Meetings & Operator Aids.With 990706 Ltr
ML17241A4041999-07-0606 July 1999
LER 99-005-00:on 990604,CEA Drop Resulted in Manual Reactor Trip.Caused by Procedural Inadequacies.Procedure Changes Are Planned to Correct Lack of Procedural Guidance for CEA Subgroup Power Switch Replacement.With 990706 Ltr
ML17241A3941999-06-30030 June 1999
LER 99-004-01:on 990415,as Found Cycle 10 Psv Setpoints Were Outside TS Limits.Caused by Manufacturing Process Defect. All Three Psvs Were Replaced with pre-tested Valves During Cycle 11 Refueling Outage.With 990630 Ltr
ML17241A3551999-06-0404 June 1999
LER 99-002-00:on 990505,both Trains of Safety Injection Actuation Were Blocked During Surveillance.Caused by Procedure Error.Procedure Revised.With 990604 Ltr
ML17241A3321999-05-17017 May 1999
LER 99-004-00:on 990415,determined That as Found Cycle 10 Psv Setpoints Outside TS Limits.Root Cause Under Investigation.Psvs Replaced with pe-tested Valves During Cycle 11
ML17241A3271999-05-0606 May 1999
LER 99-003-00:on 990406,ECCS Suction Header Leak Resulted in Both ECCS Trains Being Inoperable & Entry Into TS 3.0.3. Caused by Chloride Induced OD Stress Corrosion Cracking of Piping.Made Code Repairs & Coated Piping.With 990506 Ltr
ML17229B0791999-04-0707 April 1999
LER 99-001-00:on 990309,discovered Inadequate Design & IST SRs for Iodine Removal Sys (Irs).Caused by Original Design Inadequacies & Personnel Error.Naoh Tank Vent Valve V07233 Was Tagged Open.With 990407 Ltr
ML17229B0801999-04-0707 April 1999
LER 99-002-00:on 990311,SG ECT Error Caused Operation with Condition Prohibited by Ts.Caused by Deficiencies in Data Analysis Guideline Instructions.Licensee Will Change Data Analysis Guidelines for Lead Analysts.With 990407 Ltr
ML17229B0541999-03-10010 March 1999
LER 99-001-00:on 990211,inadequate TS SRs for SIT & SDC Isolation Valves Were Noted.Caused by Failure to Correctly Implement TS Srs.Submitted LAR to Align Required TS SR with Design Bases Requirements Being Verified.With 990310 Ltr
ML17229A9901999-01-20020 January 1999
LER 98-009-00:on 981223,noted That Facility Operated Outside of Design Basis.Caused by non-conservative MSLB Analysis Inputs.Will Review SR Component Differences Between Units & Will re-baseline LTOP Analysis.With 990120 Ltr
ML17229A9821999-01-0404 January 1999
LER 98-010-00:on 981207,RCS Boron Sample Frequency Required by Ts,Was Exceeded by Twelve Minutes.Caused by Personnel Error.Equipment Clearance Order Was Lifted to Draw Required Sample & Operations Procedure Was Changed.With 990104 Ltr
ML17229A9611998-12-22022 December 1998
LER 97-002-01:on 981204,containment Sump Debris Screen Was Not IAW Design.Caused by Inadequate C/As for Sump Screen Anamolies.All Identified Sump Screen Deficiencies Were Dispositioned &/Or Repaired.With 981222 Ltr
ML17229A9561998-12-15015 December 1998
LER 98-008-00:on 981118,missed TS SG U Tube Insp.Caused by Encoding Errors While Using Remote Positioning Fixtures.All SG Tube Surveyed.With 981215 Ltr
ML17229A9301998-11-25025 November 1998
LER 98-005-01:on 980807,discovered That New MOV Methodology Caused Past PORV Block Valve Operability Problem.Caused by Inadequacies in Original Vendor MOV Methodology.Planned Valve Mods Will Be Implemented During Cycle 11 1998 Outage
ML17229A9021998-11-0404 November 1998
LER 98-008-00:on 981008,inadequate Reactor Protection Sys Trip Bypass TS Was Noted.Caused by Poorly Worded Ts. Submitted LAR to Clarify Power Requirements for High Rate of Power Trips.With 981104 Ltr
ML17229A8771998-10-14014 October 1998
LER 98-006-00:on 980918,inadvertent Afas Actuation Was Noted.Caused by Degradation of Multiple Afas Power Supplies. Replaced Afas Power Supplies & Revised Procedures.With 981014 Ltr
ML17229A8761998-10-14014 October 1998
LER 98-007-00:on 980918,identified Discrepancies Between Fire Protection Design Requirements & Field Conditions. Caused by Inadequate Translation & Implementation of Fire Protection Requirements.Procedures Revised.With 981014 Ltr
ML17229A8511998-09-0202 September 1998
LER 98-005-00:on 980807,discovered That PORV Margins Were Insufficient to Accommodate Addl Conservatism.Caused by Inadequacies in Original Vendor MOV Methodology.Will Implement Planned Valve Actuator mods.W/980902 Ltr
ML17229A8201998-07-29029 July 1998
LER 98-007-00:on 980630,inadequate Procedure May Have Resulted in SBO Recovery Complications.Caused by Inadequate Procedures.Attached Caution Tags to Appropriate Control switches.W/980729 Ltr
ML17229A7411998-05-28028 May 1998
LER 98-004-00:on 980430,discovered Waste Gas Decay Tank Operation W/O Available Oxygen Analyzers,Which Is Prohibited by Ts.Caused by Inadequate Licensee Review of License Amend. Oxygen Analyzer recalibrated.W/980528 Ltr
ML17229A7381998-05-21021 May 1998
LER 98-006-00:on 980421,missed EDG Fuel Oil Sample Surveillance Was Noted.Caused by Personnel Error.Revised Fuel Oil Sampling Service Purchase Order & Revised Site procedure.W/980521 Ltr
ML17229A7011998-04-27027 April 1998
LER 98-003-00:on 980326,discovered Containment Pressure Instrumentation Design Single Failure Vulnerability.Caused by Inadequate Design by Personnel Error.Removed RPS & ESFAS Containment Pressure Bypass Keys immediately.W/980427 Ltr
ML17229A6761998-04-0202 April 1998
LER 98-005-00:on 980305,identified Two Conditions That Were Outside App R Design Bases.Caused by Design Oversight During Development of Original App R Safe SD Design.Established 30 Minute Roving Fire Watches & Provided training.W/980402 Ltr
ML17229A6731998-03-26026 March 1998
LER 98-002-00:on 980224,radiation Monitor Surveillance Inadequacies Led to Operating of Facility Prohibited by Tss. Caused by Congnitive Personnel Error.Permanent Procedure Changes Were implemented.W/980326 Ltr
ML17229A6551998-03-0505 March 1998
LER 98-001-00:on 980206,high/low Pressure Shutdown Cooling Interface Was Noted Outside App R Design Bases.Caused by Personnel Error.Addl Guidance Was Provided to Engineering Dept personnel.W/980305 Ltr
ML17229A6281998-02-19019 February 1998
LER 98-004-00:on 980121,emergency Lighting Outside App R Design Bases Occurred.Caused by Congnitive Personnel Error During Translation of App R Section Iii.Procedures Onop 1 & 2 ONP-100.01 Were Issued for Use on 980206.W/980219 Ltr
ML17229A6211998-02-0909 February 1998
LER 98-003-00:on 980110,manual Rt Due to DEH Leak at Turbine Test Block Was Noted.Caused by o-ring Extrusion.Shortened Bolts by About 0.125 & Reinstalled at Correct Torque values.W/980209 Ltr
ML17229A6191998-02-0404 February 1998
LER 98-002-00:on 980105,CIS Bistable in Bypass Resulted in Condition Prohibited by Tss.Caused by Personnel Error. Radiation Monitor Was Restored to service.W/980204 Ltr
ML17229A6161998-02-0303 February 1998
LER 98-001-00:on 980104,inadvertent RPS Actuation Occurred Due to Personnel Error.Caused by Procedural Inadequacies & Inadequate self-checking by Licensed Utility Personnel. Placards Have Been Placed in CRs.W/980203 Ltr
ML17229A6051998-01-27027 January 1998
LER 97-010-01:on 971027,inadvertent Core Alteration Prohibited by TSs Were Noted Due to Stuck Cea.Caused by Personnel Error.Cea #24 Was Dislodged & Transferred to Spent Pool for insp.W/980127 Ltr
ML17229A5501997-12-0505 December 1997
LER 97-008-00:on 971107,inadequate CR Ventilation Surveillance Resulted in Condition Prohibited by Ts.Caused by non-cognitive Personnel Error.Operating Procedure 2-1900050 Was revised.W/971205 Ltr
ML17309A9091997-12-0202 December 1997
LER 97-011-00:on 971102,non-conservative RAS Set Point Resulted in Operation Prohibited by Ts.Caused by Inadequate Set Point & Instrument Loop Scaling Process.Revised ESFAS Functional Tp W/Proper Set point.W/971202 Ltr
ML17229A5391997-11-26026 November 1997
LER 97-010-00:on 971027,inadvertant Core Alteration Prohibited by TS Occurred.Caused by CEA Failure to Detach from Ugs.Safety Evaluation Was Performed & Procedural Rev Made to Continue Upper Guide Structure move.W/971126 Ltr
ML17229A5151997-11-0707 November 1997
LER 97-007-00:on 971008,inoperable Containment Cooling Fan Resulted in Operation of Facility Outside Design Basis. Caused by non-cognitive Personnel Error.Ccs Operation Was Revised & Issued on 971013.W/971107 Ltr
ML17229A4991997-10-17017 October 1997
LER 97-009-00:on 970917,inoperable PORV Block Valve Resulted in Operation Prohibited by Tech Specs Occurred.Caused by Plant GL 89-10 Program Plan to Review Plant Manager Action Item Sys.Porv Block Valve V-1403 restored.W/971017 Ltr
ML17309A9011997-08-27027 August 1997
LER 97-008-00:on 970728,mechanical Fire Penetrations Were Inoperable & Outside App R Design Bases.Caused by Seal Mfg Not Providing Formal Documentation for Installed Seals. Modified Inoperable Fire penetrations.W/970827 Ltr
ML17229A4311997-07-29029 July 1997
LER 97-006-00:on 970630,discovered Inadequate Testing of Engineered Safety Features Subgroup Relays.Caused by Inadequacy in Implementing TS Requirements in Surveillance Procedures.Revised Surveillance procedures.W/970729 Ltr
ML17229A4241997-07-25025 July 1997
LER 97-005-00:on 970625,discovered That Hot Shutdown Control Panel Shutdown Cooling Flow indicator,FI-3306 Inoperable. Caused by Weakness in Work Order & Procedure Used to Repair FI-3306.Section Meeting W/I&C Planners held.W/970725 Ltr
ML17229A3971997-07-11011 July 1997
LER 97-004-00:on 970611,discovered Incorrect Original Cable Tray Fire Stop Assembly Installation Was Outside App R Design Basis.Caused by Personnel Error.Hourly Fire Watch Patrols Will Be posted.W/970711 Ltr
ML17229A3871997-06-19019 June 1997
LER 97-003-00:on 970521,determined Required Post Maint Open Stroke Test for Valve V3245,2B2 SIT Discharge Check Valve, Had Not Been Performed.Caused by Personnel Error.Procedure revised.W/970619 Ltr
ML17229A3841997-06-17017 June 1997
LER 97-002-00:on 970518,containment Sump Debris Screen Was Not IAW Design Due to Gaps in Screen Encl.Performed SER to Document Containment Sump Design requirements.W/970617 Ltr
ML17229A3751997-06-0202 June 1997
LER 97-006-00:on 970501,operation Was Prohibited by TS Due to Inadequately Tested Degraded Voltage Sys.Revised Unit 1 ESFAS Surveillance Test procedure.W/970602 Ltr
ML17229A3611997-05-29029 May 1997
LER 97-007-00:on 970502,reactor Coolant Pump Oil Collection Sys Was Outside App R Design Bases.Identified Leak Sites Were Repaired & Mods to RCP Oil Collection Sys to Capture Any Future Leakage from areas.W/970529 Ltr
ML17229A3491997-05-21021 May 1997
LER 97-001-00:on 970423,containment Isolation Actuation Occurred.Caused by Increased Radiation Levels During Removal of Upper Guide Structure.Proper Actuation of Containment Isolation Components Was verified.W/970521 Ltr
ML17229A3441997-05-13013 May 1997
LER 97-005-00:on 970419,reactor Was Shutdown Due to Reactor Coolant Pressure Boundary Leakage.Hot Cracking Was Caused by Weld Contamination.Repairs to RCPB Were Completed & 1A SDC Train Was Restored to Svc
ML17229A3141997-04-30030 April 1997
LER 97-004-00:on 970402,refueling Machine Was Operating in Manner Prohibited by TS Due to Original Design of Refueling Machine Bypass Feature Conflicting W/Ts Requirements. Eliminated Overload Cut Off Limit bypass.W/970430 Ltr
ML17229A2951997-03-31031 March 1997
LER 97-003-00:on 970304,automatic Rt Resulted from Loss of Electrical Power to 1A2 Rc Pump.Rcp Breaker Was Replaced & Pump Was Returned to svc.W/970331 Ltr
ML17229A2721997-03-21021 March 1997
LER 97-002-00:on 970221,operation in Excess of Max Rated Thermal Power Occurred Due to Digital Data Processing Sys (Ddps) Calorimetric Error.Verified Acceptable Performance of Ddps Functions & Reviewed Software mods.W/970321 Ltr
1999-07-06
[Table view]
Category:RO)
MONTHYEARML17241A4891999-10-0707 October 1999
LER 99-004-00:on 990912,noted That MSSV Surveillance Was Outside of TS Requirements.Caused by Setpoint Drift.Subject MSSVs Are Being Refurbished & Retested Prior to Unit Startup from SL1-16 Refueling Outage.With 991007 Ltr
ML17241A4111999-07-16016 July 1999
LER 99-007-00:on 990610,unplanned Cooldown Transient Occurred Due to Personnel Error.Trained & Briefed Personnel & Revised Procedures.With 990716 Ltr
ML17241A4031999-07-0606 July 1999
LER 99-006-00:on 990605,sub-critical Reactor Trip Occurred Due to Inadvertent MSIV Opening.Caused by Personnel Error. Provided Operation Supervision Instruction to Operating Crews,Stand Down Meetings & Operator Aids.With 990706 Ltr
ML17241A4041999-07-0606 July 1999
LER 99-005-00:on 990604,CEA Drop Resulted in Manual Reactor Trip.Caused by Procedural Inadequacies.Procedure Changes Are Planned to Correct Lack of Procedural Guidance for CEA Subgroup Power Switch Replacement.With 990706 Ltr
ML17241A3941999-06-30030 June 1999
LER 99-004-01:on 990415,as Found Cycle 10 Psv Setpoints Were Outside TS Limits.Caused by Manufacturing Process Defect. All Three Psvs Were Replaced with pre-tested Valves During Cycle 11 Refueling Outage.With 990630 Ltr
ML17241A3551999-06-0404 June 1999
LER 99-002-00:on 990505,both Trains of Safety Injection Actuation Were Blocked During Surveillance.Caused by Procedure Error.Procedure Revised.With 990604 Ltr
ML17241A3321999-05-17017 May 1999
LER 99-004-00:on 990415,determined That as Found Cycle 10 Psv Setpoints Outside TS Limits.Root Cause Under Investigation.Psvs Replaced with pe-tested Valves During Cycle 11
ML17241A3271999-05-0606 May 1999
LER 99-003-00:on 990406,ECCS Suction Header Leak Resulted in Both ECCS Trains Being Inoperable & Entry Into TS 3.0.3. Caused by Chloride Induced OD Stress Corrosion Cracking of Piping.Made Code Repairs & Coated Piping.With 990506 Ltr
ML17229B0791999-04-0707 April 1999
LER 99-001-00:on 990309,discovered Inadequate Design & IST SRs for Iodine Removal Sys (Irs).Caused by Original Design Inadequacies & Personnel Error.Naoh Tank Vent Valve V07233 Was Tagged Open.With 990407 Ltr
ML17229B0801999-04-0707 April 1999
LER 99-002-00:on 990311,SG ECT Error Caused Operation with Condition Prohibited by Ts.Caused by Deficiencies in Data Analysis Guideline Instructions.Licensee Will Change Data Analysis Guidelines for Lead Analysts.With 990407 Ltr
ML17229B0541999-03-10010 March 1999
LER 99-001-00:on 990211,inadequate TS SRs for SIT & SDC Isolation Valves Were Noted.Caused by Failure to Correctly Implement TS Srs.Submitted LAR to Align Required TS SR with Design Bases Requirements Being Verified.With 990310 Ltr
ML17229A9901999-01-20020 January 1999
LER 98-009-00:on 981223,noted That Facility Operated Outside of Design Basis.Caused by non-conservative MSLB Analysis Inputs.Will Review SR Component Differences Between Units & Will re-baseline LTOP Analysis.With 990120 Ltr
ML17229A9821999-01-0404 January 1999
LER 98-010-00:on 981207,RCS Boron Sample Frequency Required by Ts,Was Exceeded by Twelve Minutes.Caused by Personnel Error.Equipment Clearance Order Was Lifted to Draw Required Sample & Operations Procedure Was Changed.With 990104 Ltr
ML17229A9611998-12-22022 December 1998
LER 97-002-01:on 981204,containment Sump Debris Screen Was Not IAW Design.Caused by Inadequate C/As for Sump Screen Anamolies.All Identified Sump Screen Deficiencies Were Dispositioned &/Or Repaired.With 981222 Ltr
ML17229A9561998-12-15015 December 1998
LER 98-008-00:on 981118,missed TS SG U Tube Insp.Caused by Encoding Errors While Using Remote Positioning Fixtures.All SG Tube Surveyed.With 981215 Ltr
ML17229A9301998-11-25025 November 1998
LER 98-005-01:on 980807,discovered That New MOV Methodology Caused Past PORV Block Valve Operability Problem.Caused by Inadequacies in Original Vendor MOV Methodology.Planned Valve Mods Will Be Implemented During Cycle 11 1998 Outage
ML17229A9021998-11-0404 November 1998
LER 98-008-00:on 981008,inadequate Reactor Protection Sys Trip Bypass TS Was Noted.Caused by Poorly Worded Ts. Submitted LAR to Clarify Power Requirements for High Rate of Power Trips.With 981104 Ltr
ML17229A8771998-10-14014 October 1998
LER 98-006-00:on 980918,inadvertent Afas Actuation Was Noted.Caused by Degradation of Multiple Afas Power Supplies. Replaced Afas Power Supplies & Revised Procedures.With 981014 Ltr
ML17229A8761998-10-14014 October 1998
LER 98-007-00:on 980918,identified Discrepancies Between Fire Protection Design Requirements & Field Conditions. Caused by Inadequate Translation & Implementation of Fire Protection Requirements.Procedures Revised.With 981014 Ltr
ML17229A8511998-09-0202 September 1998
LER 98-005-00:on 980807,discovered That PORV Margins Were Insufficient to Accommodate Addl Conservatism.Caused by Inadequacies in Original Vendor MOV Methodology.Will Implement Planned Valve Actuator mods.W/980902 Ltr
ML17229A8201998-07-29029 July 1998
LER 98-007-00:on 980630,inadequate Procedure May Have Resulted in SBO Recovery Complications.Caused by Inadequate Procedures.Attached Caution Tags to Appropriate Control switches.W/980729 Ltr
ML17229A7411998-05-28028 May 1998
LER 98-004-00:on 980430,discovered Waste Gas Decay Tank Operation W/O Available Oxygen Analyzers,Which Is Prohibited by Ts.Caused by Inadequate Licensee Review of License Amend. Oxygen Analyzer recalibrated.W/980528 Ltr
ML17229A7381998-05-21021 May 1998
LER 98-006-00:on 980421,missed EDG Fuel Oil Sample Surveillance Was Noted.Caused by Personnel Error.Revised Fuel Oil Sampling Service Purchase Order & Revised Site procedure.W/980521 Ltr
ML17229A7011998-04-27027 April 1998
LER 98-003-00:on 980326,discovered Containment Pressure Instrumentation Design Single Failure Vulnerability.Caused by Inadequate Design by Personnel Error.Removed RPS & ESFAS Containment Pressure Bypass Keys immediately.W/980427 Ltr
ML17229A6761998-04-0202 April 1998
LER 98-005-00:on 980305,identified Two Conditions That Were Outside App R Design Bases.Caused by Design Oversight During Development of Original App R Safe SD Design.Established 30 Minute Roving Fire Watches & Provided training.W/980402 Ltr
ML17229A6731998-03-26026 March 1998
LER 98-002-00:on 980224,radiation Monitor Surveillance Inadequacies Led to Operating of Facility Prohibited by Tss. Caused by Congnitive Personnel Error.Permanent Procedure Changes Were implemented.W/980326 Ltr
ML17229A6551998-03-0505 March 1998
LER 98-001-00:on 980206,high/low Pressure Shutdown Cooling Interface Was Noted Outside App R Design Bases.Caused by Personnel Error.Addl Guidance Was Provided to Engineering Dept personnel.W/980305 Ltr
ML17229A6281998-02-19019 February 1998
LER 98-004-00:on 980121,emergency Lighting Outside App R Design Bases Occurred.Caused by Congnitive Personnel Error During Translation of App R Section Iii.Procedures Onop 1 & 2 ONP-100.01 Were Issued for Use on 980206.W/980219 Ltr
ML17229A6211998-02-0909 February 1998
LER 98-003-00:on 980110,manual Rt Due to DEH Leak at Turbine Test Block Was Noted.Caused by o-ring Extrusion.Shortened Bolts by About 0.125 & Reinstalled at Correct Torque values.W/980209 Ltr
ML17229A6191998-02-0404 February 1998
LER 98-002-00:on 980105,CIS Bistable in Bypass Resulted in Condition Prohibited by Tss.Caused by Personnel Error. Radiation Monitor Was Restored to service.W/980204 Ltr
ML17229A6161998-02-0303 February 1998
LER 98-001-00:on 980104,inadvertent RPS Actuation Occurred Due to Personnel Error.Caused by Procedural Inadequacies & Inadequate self-checking by Licensed Utility Personnel. Placards Have Been Placed in CRs.W/980203 Ltr
ML17229A6051998-01-27027 January 1998
LER 97-010-01:on 971027,inadvertent Core Alteration Prohibited by TSs Were Noted Due to Stuck Cea.Caused by Personnel Error.Cea #24 Was Dislodged & Transferred to Spent Pool for insp.W/980127 Ltr
ML17229A5501997-12-0505 December 1997
LER 97-008-00:on 971107,inadequate CR Ventilation Surveillance Resulted in Condition Prohibited by Ts.Caused by non-cognitive Personnel Error.Operating Procedure 2-1900050 Was revised.W/971205 Ltr
ML17309A9091997-12-0202 December 1997
LER 97-011-00:on 971102,non-conservative RAS Set Point Resulted in Operation Prohibited by Ts.Caused by Inadequate Set Point & Instrument Loop Scaling Process.Revised ESFAS Functional Tp W/Proper Set point.W/971202 Ltr
ML17229A5391997-11-26026 November 1997
LER 97-010-00:on 971027,inadvertant Core Alteration Prohibited by TS Occurred.Caused by CEA Failure to Detach from Ugs.Safety Evaluation Was Performed & Procedural Rev Made to Continue Upper Guide Structure move.W/971126 Ltr
ML17229A5151997-11-0707 November 1997
LER 97-007-00:on 971008,inoperable Containment Cooling Fan Resulted in Operation of Facility Outside Design Basis. Caused by non-cognitive Personnel Error.Ccs Operation Was Revised & Issued on 971013.W/971107 Ltr
ML17229A4991997-10-17017 October 1997
LER 97-009-00:on 970917,inoperable PORV Block Valve Resulted in Operation Prohibited by Tech Specs Occurred.Caused by Plant GL 89-10 Program Plan to Review Plant Manager Action Item Sys.Porv Block Valve V-1403 restored.W/971017 Ltr
ML17309A9011997-08-27027 August 1997
LER 97-008-00:on 970728,mechanical Fire Penetrations Were Inoperable & Outside App R Design Bases.Caused by Seal Mfg Not Providing Formal Documentation for Installed Seals. Modified Inoperable Fire penetrations.W/970827 Ltr
ML17229A4311997-07-29029 July 1997
LER 97-006-00:on 970630,discovered Inadequate Testing of Engineered Safety Features Subgroup Relays.Caused by Inadequacy in Implementing TS Requirements in Surveillance Procedures.Revised Surveillance procedures.W/970729 Ltr
ML17229A4241997-07-25025 July 1997
LER 97-005-00:on 970625,discovered That Hot Shutdown Control Panel Shutdown Cooling Flow indicator,FI-3306 Inoperable. Caused by Weakness in Work Order & Procedure Used to Repair FI-3306.Section Meeting W/I&C Planners held.W/970725 Ltr
ML17229A3971997-07-11011 July 1997
LER 97-004-00:on 970611,discovered Incorrect Original Cable Tray Fire Stop Assembly Installation Was Outside App R Design Basis.Caused by Personnel Error.Hourly Fire Watch Patrols Will Be posted.W/970711 Ltr
ML17229A3871997-06-19019 June 1997
LER 97-003-00:on 970521,determined Required Post Maint Open Stroke Test for Valve V3245,2B2 SIT Discharge Check Valve, Had Not Been Performed.Caused by Personnel Error.Procedure revised.W/970619 Ltr
ML17229A3841997-06-17017 June 1997
LER 97-002-00:on 970518,containment Sump Debris Screen Was Not IAW Design Due to Gaps in Screen Encl.Performed SER to Document Containment Sump Design requirements.W/970617 Ltr
ML17229A3751997-06-0202 June 1997
LER 97-006-00:on 970501,operation Was Prohibited by TS Due to Inadequately Tested Degraded Voltage Sys.Revised Unit 1 ESFAS Surveillance Test procedure.W/970602 Ltr
ML17229A3611997-05-29029 May 1997
LER 97-007-00:on 970502,reactor Coolant Pump Oil Collection Sys Was Outside App R Design Bases.Identified Leak Sites Were Repaired & Mods to RCP Oil Collection Sys to Capture Any Future Leakage from areas.W/970529 Ltr
ML17229A3491997-05-21021 May 1997
LER 97-001-00:on 970423,containment Isolation Actuation Occurred.Caused by Increased Radiation Levels During Removal of Upper Guide Structure.Proper Actuation of Containment Isolation Components Was verified.W/970521 Ltr
ML17229A3441997-05-13013 May 1997
LER 97-005-00:on 970419,reactor Was Shutdown Due to Reactor Coolant Pressure Boundary Leakage.Hot Cracking Was Caused by Weld Contamination.Repairs to RCPB Were Completed & 1A SDC Train Was Restored to Svc
ML17229A3141997-04-30030 April 1997
LER 97-004-00:on 970402,refueling Machine Was Operating in Manner Prohibited by TS Due to Original Design of Refueling Machine Bypass Feature Conflicting W/Ts Requirements. Eliminated Overload Cut Off Limit bypass.W/970430 Ltr
ML17229A2951997-03-31031 March 1997
LER 97-003-00:on 970304,automatic Rt Resulted from Loss of Electrical Power to 1A2 Rc Pump.Rcp Breaker Was Replaced & Pump Was Returned to svc.W/970331 Ltr
ML17229A2721997-03-21021 March 1997
LER 97-002-00:on 970221,operation in Excess of Max Rated Thermal Power Occurred Due to Digital Data Processing Sys (Ddps) Calorimetric Error.Verified Acceptable Performance of Ddps Functions & Reviewed Software mods.W/970321 Ltr
1999-07-06
[Table view]
Category:TEXT-SAFETY REPORT
MONTHYEARML17241A4891999-10-0707 October 1999
LER 99-004-00:on 990912,noted That MSSV Surveillance Was Outside of TS Requirements.Caused by Setpoint Drift.Subject MSSVs Are Being Refurbished & Retested Prior to Unit Startup from SL1-16 Refueling Outage.With 991007 Ltr
ML17241A4951999-09-30030 September 1999
Monthly Operating Repts for Sept 1999 for St Lucie,Units 1 & 2.With 991014 Ltr
ML17241A4741999-08-31031 August 1999
Rev 1 to PCM 99016, St Lucie Unit 1,Cycle 16 Colr.
ML17241A4591999-08-31031 August 1999
Monthly Operating Repts for Aug 1999 for St Lucie,Units 1 & 2.With 990913 Ltr
ML17241A4301999-07-31031 July 1999
Monthly Operating Repts for Jul 1999 for St Lucie Units 1 & 2.With 990805 Ltr
ML17241A4111999-07-16016 July 1999
LER 99-007-00:on 990610,unplanned Cooldown Transient Occurred Due to Personnel Error.Trained & Briefed Personnel & Revised Procedures.With 990716 Ltr
ML17241A4031999-07-0606 July 1999
LER 99-006-00:on 990605,sub-critical Reactor Trip Occurred Due to Inadvertent MSIV Opening.Caused by Personnel Error. Provided Operation Supervision Instruction to Operating Crews,Stand Down Meetings & Operator Aids.With 990706 Ltr
ML17241A4041999-07-0606 July 1999
LER 99-005-00:on 990604,CEA Drop Resulted in Manual Reactor Trip.Caused by Procedural Inadequacies.Procedure Changes Are Planned to Correct Lack of Procedural Guidance for CEA Subgroup Power Switch Replacement.With 990706 Ltr
ML17241A4091999-06-30030 June 1999
Monthly Operating Repts for June 1999 for St Lucie,Units 1 & 2.With 990712 Ltr
ML17241A3941999-06-30030 June 1999
LER 99-004-01:on 990415,as Found Cycle 10 Psv Setpoints Were Outside TS Limits.Caused by Manufacturing Process Defect. All Three Psvs Were Replaced with pre-tested Valves During Cycle 11 Refueling Outage.With 990630 Ltr
ML17355A3681999-06-30030 June 1999
Revised Update to Topical QA Rept, Dtd June 1999
ML17241A3551999-06-0404 June 1999
LER 99-002-00:on 990505,both Trains of Safety Injection Actuation Were Blocked During Surveillance.Caused by Procedure Error.Procedure Revised.With 990604 Ltr
ML17241A3631999-05-31031 May 1999
Monthly Operating Repts for May 1999 for St Lucie Units 1 & 2.With 990610 Ltr
ML17241A3321999-05-17017 May 1999
LER 99-004-00:on 990415,determined That as Found Cycle 10 Psv Setpoints Outside TS Limits.Root Cause Under Investigation.Psvs Replaced with pe-tested Valves During Cycle 11
ML17241A3271999-05-0606 May 1999
LER 99-003-00:on 990406,ECCS Suction Header Leak Resulted in Both ECCS Trains Being Inoperable & Entry Into TS 3.0.3. Caused by Chloride Induced OD Stress Corrosion Cracking of Piping.Made Code Repairs & Coated Piping.With 990506 Ltr
ML17241A3331999-04-30030 April 1999
Monthly Operating Rept for Apr 1999 for St Lucie,Units 1 & 2.With 990517 Ltr
ML17229B0801999-04-0707 April 1999
LER 99-002-00:on 990311,SG ECT Error Caused Operation with Condition Prohibited by Ts.Caused by Deficiencies in Data Analysis Guideline Instructions.Licensee Will Change Data Analysis Guidelines for Lead Analysts.With 990407 Ltr
ML17229B0841999-04-0707 April 1999
Rev 2 to PSL-ENG-SEMS-98-102, Engineering Evaluation of ECCS Suction Lines.
ML17229B0791999-04-0707 April 1999
LER 99-001-00:on 990309,discovered Inadequate Design & IST SRs for Iodine Removal Sys (Irs).Caused by Original Design Inadequacies & Personnel Error.Naoh Tank Vent Valve V07233 Was Tagged Open.With 990407 Ltr
ML17229B0961999-03-31031 March 1999
Monthly Operating Repts for Mar 1999 for St Lucie,Units 1 & 2.With 990408 Ltr
ML17229B0541999-03-10010 March 1999
LER 99-001-00:on 990211,inadequate TS SRs for SIT & SDC Isolation Valves Were Noted.Caused by Failure to Correctly Implement TS Srs.Submitted LAR to Align Required TS SR with Design Bases Requirements Being Verified.With 990310 Ltr
ML17229B0461999-02-28028 February 1999
Monthly Operating Repts for Feb 1999 for St Lucie,Units 1 & 2.With 990310 Ltr
ML17229B0051999-01-31031 January 1999
Monthly Operating Repts for Jan 1999 for St Lucie,Units 1 & 2.With 990211 Ltr
ML17229A9901999-01-20020 January 1999
LER 98-009-00:on 981223,noted That Facility Operated Outside of Design Basis.Caused by non-conservative MSLB Analysis Inputs.Will Review SR Component Differences Between Units & Will re-baseline LTOP Analysis.With 990120 Ltr
ML17229A9961999-01-14014 January 1999
SG Tube Inservice Insp Special Rept.
ML17229A9821999-01-0404 January 1999
LER 98-010-00:on 981207,RCS Boron Sample Frequency Required by Ts,Was Exceeded by Twelve Minutes.Caused by Personnel Error.Equipment Clearance Order Was Lifted to Draw Required Sample & Operations Procedure Was Changed.With 990104 Ltr
ML17229A9831998-12-31031 December 1998
Monthly Operating Repts for Dec 1998 for St Lucie,Units 1 & 2.With 990111 Ltr
ML17229A9611998-12-22022 December 1998
LER 97-002-01:on 981204,containment Sump Debris Screen Was Not IAW Design.Caused by Inadequate C/As for Sump Screen Anamolies.All Identified Sump Screen Deficiencies Were Dispositioned &/Or Repaired.With 981222 Ltr
ML17229A9561998-12-15015 December 1998
LER 98-008-00:on 981118,missed TS SG U Tube Insp.Caused by Encoding Errors While Using Remote Positioning Fixtures.All SG Tube Surveyed.With 981215 Ltr
ML17241A3581998-12-0909 December 1998
Changes,Tests & Experiments Made as Allowed by 10CFR50.59 for Period of 970526-981209.
ML17229A9421998-11-30030 November 1998
Monthly Operating Repts for Nov 1998 for St Lucie,Units 1 & 2.With 981215 Ltr
ML17229A9301998-11-25025 November 1998
LER 98-005-01:on 980807,discovered That New MOV Methodology Caused Past PORV Block Valve Operability Problem.Caused by Inadequacies in Original Vendor MOV Methodology.Planned Valve Mods Will Be Implemented During Cycle 11 1998 Outage
ML17229A9021998-11-0404 November 1998
LER 98-008-00:on 981008,inadequate Reactor Protection Sys Trip Bypass TS Was Noted.Caused by Poorly Worded Ts. Submitted LAR to Clarify Power Requirements for High Rate of Power Trips.With 981104 Ltr
ML17241A4931998-11-0101 November 1998
Statement of Account for Period of 981101-990930 for Suntrust Bank,As Trustee for Florida Municipal Power Agency Nuclear Decommissioning Trust (St Lucie Project).
ML17229A9051998-10-31031 October 1998
Monthly Operating Repts for Oct 1998 for St Lucie,Units 1 & 2.With 981110 Ltr
ML17229A8871998-10-19019 October 1998
Part 21 Rept Re Potential Defect in Swagelok Stainless Steel Front Ferrule,Part Number SS-503-1 Which Was Machined with Improper Length.C/A Includes Insp Equipment That Will 100% Identify Short Length
ML17229A8781998-10-19019 October 1998
Part 21 Rept Re Potential Defect in Swagelok Stainless Steel Front Ferrule,Part Number SS-503-1,which Was Machined with Improper Length.Insp Equipment That Will 100% Identify Short Length
ML17229A8771998-10-14014 October 1998
LER 98-006-00:on 980918,inadvertent Afas Actuation Was Noted.Caused by Degradation of Multiple Afas Power Supplies. Replaced Afas Power Supplies & Revised Procedures.With 981014 Ltr
ML17229A8761998-10-14014 October 1998
LER 98-007-00:on 980918,identified Discrepancies Between Fire Protection Design Requirements & Field Conditions. Caused by Inadequate Translation & Implementation of Fire Protection Requirements.Procedures Revised.With 981014 Ltr
ML17229A8721998-09-30030 September 1998
Monthly Operating Repts for Sept 1998 for St Lucie Units 1 & 2.With 981009 Ltr
ML17229A8511998-09-0202 September 1998
LER 98-005-00:on 980807,discovered That PORV Margins Were Insufficient to Accommodate Addl Conservatism.Caused by Inadequacies in Original Vendor MOV Methodology.Will Implement Planned Valve Actuator mods.W/980902 Ltr
ML17229A8611998-08-31031 August 1998
Monthly Operating Repts for Aug 1998 for St Lucie,Units 1 & 2.With 980911 Ltr
ML18066A2771998-08-13013 August 1998
Part 21 Rept Re Deficiency in CE Current Screening Methodology for Determining Limiting Fuel Assembly for Detailed PWR thermal-hydraulic Sa.Evaluations Were Performed for Affected Plants to Determine Effect of Deficiency
ML17229A8481998-08-0707 August 1998
Rev 1 to PSL-ENG-SEFJ-98-013, St Lucie Unit 2,Cycle 10 Colr.
ML17229A9461998-08-0707 August 1998
Rev 0 to PCM 98016, St Lucie Unit 2,Cycle 11 Colr.
ML17229A8301998-07-31031 July 1998
Monthly Operating Repts for July 1998 for St Lucie,Units 1 & 2.W/980814 Ltr
ML17229A8201998-07-29029 July 1998
LER 98-007-00:on 980630,inadequate Procedure May Have Resulted in SBO Recovery Complications.Caused by Inadequate Procedures.Attached Caution Tags to Appropriate Control switches.W/980729 Ltr
ML17229A7981998-06-30030 June 1998
Monthly Operating Repts for June 1998 for St Lucie,Units 1 & 2.W/980713 Ltr
ML17229A7701998-05-31031 May 1998
Monthly Operating Repts for May 1998 for St Lucie,Units 1 & 2.W/980612 Ltr
ML17229A7411998-05-28028 May 1998
LER 98-004-00:on 980430,discovered Waste Gas Decay Tank Operation W/O Available Oxygen Analyzers,Which Is Prohibited by Ts.Caused by Inadequate Licensee Review of License Amend. Oxygen Analyzer recalibrated.W/980528 Ltr
1999-09-30
[Table view] |
Text
ACCELERANT DOCUMENT DISTRj: UTION SYSTEM REGULAT INFORMATION DISTRIBUTION STEM (RIDS)
ACCESSION NBR:9305180328 DOC.DATE: 93/05/10 NOTARIZED: NO DOCKET ¹ FACIL:50-335 St. Lucie Plant, Unit 1, Florida Power & Light Co. 05000335 AUTH. NAME AUTHOR AFFILIATION YOUNG,R.J. Florida Power & Light Co.
SAGER,D.A. Florida Power & Light Co.
RECIP.NAME RECIPIENT AFFILIATION
SUBJECT:
LER 93-004-00:on 930409,typo discovered in rept used to determine RPS low RCS flow trip setpoint.Error existed since D Aug 1988.Caused by design control inadequacy. Engineering package developed to correct calculations.W/930510 ltr.
DZSTRZSUTZON CODE: IE22T COPIES RECEIVED:LTR I ENCL / SIZE:
TITIE: 50.73/50.9 Licensee Event Report (LER), Incident Rpt, etc.
NOTES:
RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL D PD2-2 LA 1 1 PD2-2 PD 1 1 NORRISgJ 1 1 D INTERNAL: ACNW 2 2 ACRS 2 2 AEOD/DOA 1 1 AEOD/DSP/TPAB 1 1 AEOD/ROAB/DSP 2 2 NRR/DE/EELB 1 1 NRR/DE/EMEB 1 1 NRR/DORS/OEAB 1 1 NRR/DRCH/HHFB 1 1 NRR/DRCH/HICB 1, 1 NRR/DRCH/HOLB 1 1 NRR/DRIL/RPEB 1 1 NRR/DRSS/PRPB 2 2 NRR .DSSA/SPLB 1 1 NRR/DSSA/SRXB 1 1 02 1 1 RES/DSIR/EIB 1 1 RGN2 FILE 01 1 1 EXTERNAL: EG&G BRYCEPJ.H 2 2 L ST LOBBY WARD 1 1 NRC PDR 1 1 NSIC MURPHY,G.A 1 . 1 NSIC POOREPW. 1 1 NUDOCS FULL TXT 1 1 D
D D
NOTE TO ALL"RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT. 504-2065) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!
FULL TEXT CONVERSION REQUIRED TOTAL NUMBER OF COPIES REQUIRED: LTTR 32 ENCL 32
May 10, 1993 PP'f L-93-129 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: 93-004 Date of Event: April 9, 1993 Incorrect RCS Low Flow Trip Setpoint due to a Desi n 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.
Very truly yours, 4A8a ~
D. A. ger Vice r sident St. Lu e Plant DAS/JWH/kw Attachment cc: Stewart D. Ebneter, Regional Administrator, USNRC Region Senior Resident Inspector, USNRC, St. Lucie Plant II DAS/PSL 8917-93 170033 9305i80328 9305i0 PDR ADOCK 05000335 S PDR an FPL Group company
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PPP FPL FEOElmlo ol L.S. tEUCLEAR REGULATORY COMMISSION APPROYOT ONE NCk 01 10 010I ENNPEE'NHNT NRC Form K6 EET PIATE 0 NAaE N PEN INEPCNTE TO CEPNCY WITH TI00 NfOIEAATlONCCATEC STINT (M9)
LICENSEE EVENT REPORT (LER) INCEEET.>>0 HTE SONWNa CONNENTE SNONEPNO TAfaENEETTwIE To THE INOCla0 ANT PE PONTE NANAKINNT EAANCHTPANIAIANIANAENIPE IANATCNY WATPNarol. OC IPHE Na To THE PPENWITTN SEOOC TON PNOECT o'110010PA Cf SCE Of NAMOEIENTPIEI OAXNT.WASPNeOTCPC OC ITNEL FACILITYNAME (1) DOCKET NUMBER (2) PAGE 3 St. Lucie Unit 1 050003351 0 4 (4) Incorrect Reactor Coolant System Low Flow Trip Setpoint results in a condition prohibited by Technical Specifications due to a Design Control Inadequacy.
EVENT DATE (5) LER NUMBER (6) REPORT DATE (7) OTHER FACILITIES INVOLVED(8)
MOMlH DAY YEAR YEAR S IAL MONTH DAY YEAR FACILITYNAMES DOCKET NUMBER(S)
N/A 05 000 0 4 09 9 3 9 3 0 0 4 00051093 THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR:
N/A 05000 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) 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 and in Text 20.405(a)(1)(iv) 50.73(a)(2)(viii)(B) NRC Form 366A) 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 NAME TELEP ONE NUMBER AREA CODE Robert J. Young, Shift Technical Advisor 4 0 7 465.3550 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT 13 MANUFAG- REPORTABLE MANUFAC- REPORTABLE CAUSE SYSTEM COMPONENT TURER TO NPRDS CAUSE SYSTEM COMPONENT lURER TO NPRDS I I I SUPPLEMENTAL REPORT EXPECTED 14 EXPECTED MONIH DAY YEAR SUBMISSION YES (Ifyes, complete EXPECTED SUBMISSION DATE) DATE (15)
ABSTRACT (Limit to 1400 spaces. i e. approximately fifteen single-space typewritten lines) (1 6)
On April 9, 1993, St. Lucie Unit 1 was in Mode 6 when a typographical error was discovered by FPL Nuclear Engineering in a report used to determine the Reactor Protection System (RPS) low Reactor Coolant System (RCS) flow trip setpoint. Technical Specification 2.2.1, Table 2.2-1 states that the trip setpoint will be greater than or equal to 95% of design reactor coolant flow. The FPL Nuclear Engineering report, which described the conversion of pressure drop across the steam generators to the RPS low RCS flow trip setpoint, contained an incorrect constant. The report was subsequently transmitted to the plant staff and the Instrument and Control Department adjusted the RCS low flow setpoint. This error caused the setting of the RCS low flow trip setpoint to a value approximately 3% below the minimum 95% of design flow. This setpoint error existed since August 1988.
The root cause of this event was a design control inadequacy. A typographical error was made in the report transmitted to the plant staff. The error would have been discovered if the review process for the transmitted report had undergone an independent review. The Nuclear Engineering process currently in place prevents a similar event from occurring by requiring independent review of transmitted setpoints.
Corrective actions for this event: An engineering evaluation was performed that concluded that the operation of Unit 1 during this time period was within the bounds of the safety analysis. A review of the procedure used to determine the Unit 2 low RCS flow setpoint verified that it did not contain a similar error. After a review of internal records, Nuclear Engineering verified that no other Unit 1 or 2 RPS setpoint changes were transmitted to the plant in error. An engineering package was developed to provide the corrected calculations for determination of the RPS reactor coolant system low flow trip setpoint. Instrumentation and Control personnel will revise appropriate procedures and install the correct trip setpoint in the Unit 1 RPS prior to entering mode 2. Prior to discovery of this event, Engineering adopted a process requiring independent review of setpoints before transmittal to the plant staff.
FPL Facsimile of NRG Form 366 (6-89)
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FPL Fsaslnilsof U.S. NUCLEAR REGULATORY COMMISSION Asswosf 0 oe Ixs ss ss C I ss NRC Form SEI
(&89) fxssus'ass s LICENSEE EVENT REPORT (LER) fSTAIATf0 OATCE N sf ilINSAONsf To COINET WITH siss SfCWNATTCN Cas EfCOON IfoUECTIsfs Isxs ssxswNe coNNENTs IKOANowoEsses N fsoNATE To TIO INcsxsss TEXT CONTINUATION Ne ISAONTS NANACEsf NT fssANCH TASTCE ua NXXENTIuauATEXTT wAEINeTON. Oo ssssf Ne To TIO SNEIIwow IsoucwoN Twofcs ETI sseIsss asrscf os swNACEISNT Ne Tseofs. WANNesfsf oc ssexs FACILITYNAME (1) DOCKET NUMBER (2) LER NUMBER (6) PAGE (3)
YEAR g EQUENTIAL REVISION St. Lucie Unit1 NUMBER NUMBER 0 500 0335 9 3 0 0 4 0 0 0 2 0 4 TEXT (lfmore spaceis required, use additional NRC Form 366A's) (1/)
On April 9, 1993, with Unit 1 in Mode 6, FPL Nuclear Engineering performed a review of the calculations that are contained in the St. Lucie Unit 1 Low Flow Trip Setpoint Calibration Guidelines.
The review was being performed to support a proposed change to the steam generator tube plugging criteria. During this review, a typographical error in a report that described conversion of pressure drop across the Steam Generators (EIIS:AB) to the Reactor Protection System (RPS) (EIIS:
JC) Reactor Coolant System (RCS) low flow trip setpoint was found. The error resulted in the calculation of a non-conservative setpoint with which the RPS creates an automatic reactor trip to protect against a loss of RCS flow. This error caused the RPS low RCS flow trip setpoint to be approximately 3 percent below the Technical Specification minimum of 95 percent of design flow.
In 1987 the report containing the incorrect information was sent to the plant staff to support a modification to the RPS. In August 1988, the report was referenced when the modification to the RPS was implemented and was used to modify plant procedures for the initial setting and subsequent monthly checks of this RPS low flow trip setpoint. This condition was discovered in April of 1993.
The root cause of this event was a design control inadequacy. A typographical error was made by FPL Nuclear Engineering in the transmittal of a calculated setpoint to the plant staff. During a transfer of information from an independently verified engineering calculation to a report, a transcription error caused a constant that converts pressure drop across the Steam Generators to the low RCS flow trip setpoint to be non-conservative. The incorrect report would have been discovered and corrected had the transmitted report to the plant staff received the same independent review that the original calculation had received. Prior to the discovery of this event, FPL Nuclear Engineering adopted the process for requiring independent review of all setpoints before transmittal to the plant staff.
This event is reportable under 10CFR50.73(a)(2)(i)(B), as "Any operation or condition prohibited by the plant's Technical Specifications." Technical Specification 2.2.1 requires that the RPS trip setpoint for RCS low flow be set at or above 95 percent of design flow (370,000 gpm). For cycles 9, 10 and 11 of Unit 1 operation, the RCS low flow trip was erroneously set at slightly higher than 92 percent of design flow.
The RCS low flow trip setpoint ensures that for a degradation of RCS flow resulting from analyzed transients, a reactor trip occurs to prevent departure from nucleate boiling ratio (DNBR) safety limits.
The process signal for this function is developed from four independent differential pressure channels which measure the pressure drop across the primary side of both Steam Generators. The total Steam Generator pressure drop is compared with the low RCS flow trip setpoint. If two channels indicate a flow which is less than the trip setpoint, an RPS trip signal is initiated.
FPL Facsimile of NRC Form 366 (6-89)
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FPL Facstmlo ol U.S. NUCLEAR REGULATORY COMMrSS ION , AAINorrocooNI$ $ $ $ oeror NRC Form S66 cofrfoa rrfoeo
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YEAR EQUENTIAL -r REVISION St. Lucie Unit 1 NUMBER 4 NUMBER 0500033593 0 0 4 0 0 0 3 0 4 TEXT (Ifmore spaceis required, use additional NRC Form 366A's) (17)
An evaluation (JPN-PSL1-SEFJ-93-006) was performed by FPL Engineering to determine the available safety analysis margin for the most limiting transients (loss of offsite power and loss of RCS flow) for which protection is provided by the RCS low flow trip. The results show that the approximate 3 percent setpoint error is sufficiently offset by available flow margin. Thus, violation of the DNBR limit for a loss of offsite power or a loss of RCS flow event would not have occurred if there hadbeen a degradation of RCS flow event during the time period that the setpoint error was in place. (A review of Unit 1 reactor trips showed that the RCS low flow trip function was not challenged during cycles 9,10 and 11. An additional review of actual operating conditions during cycles 9, 10, and 11 was performed to ensure that no other condition existed that would further aggravate the condition described in this LER).
The Reactor Coolant Pump (RCP)(EIIS:P) seized rotor event has been reanalyzed by the fuel vendor for a 4 percent reduction in design flow and the corresponding 4 percent reduction in the RCS low flow trip setpoint. The analysis shows that the acceptance criteria for the postulated RCP seized rotor event was not violated. Therefore, the health and safety of the public was not affected by this condition.
- 1. Prior to the discovery of this event, Nuclear Engineering proceduralized a review process to ensure the accuracy of setpoints and plant changes. This process requires an independent verification of setpoints and plant changes before transmittal to the plant staff, and would have detected the error described in this report.
- 2. Nuclear Engineering prepared an engineering evaluation and determined that operation of Unit 1 was bounded by the safety analyses for Cycles 9, 10, and 11.
- 3. Nuclear Engineering reviewed internal records and verified that no other Unit 1 or 2 RPS setpoint changes were transmitted to the plant staff in error.
- 4. Nuclear Engineering reviewed the Unit 2 RCS Low Flow Trip Setpoint Determination procedure and verified that it did not use erroneous data.
- 5. A FPL engineering package was developed to document and transmit the corrected calculation for the Unit 1 RPS Iow RCS flow trip setpoint.
- 6. The I&C Department will revise procedures 1-0120050
~ and 1-1400050 to reflect the correct RCS low flow trip setpoints prior to Unit 1 entering Mode 2.
- 7. The I&C Department will make the RPS low RCS flow trip setpoint changes prior to Unit 1 entering Mode 2.
FPL Facsimile of NRC Form 366 (6-89)
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FACILITYNAME (1) DOCKET NUMBER (2) LER NUMBER (6) PAGE (3)
YEAR ': EQUENTIAL NUMBER
. REVISIO NUMBER St. Lucie Unit 1 0 500 0335 9 3 0 0 4 0 0 0 4 0 4 TEXT (Ifmore spaceis required, use additional NRC Form 366A's) (1/)
None A previous similar LER at St. Lucie involving a design error for the RPS was:
LER 335-79-30 Steam Generator Low Level RPS trip setpoints less than Technical Specifications due to a design ermr.
FPL Facsimile of NRC Form 366 (6-89)
