|
|
| (4 intermediate revisions by the same user not shown) |
| Line 3: |
Line 3: |
| | issue date = 10/16/1987 | | | issue date = 10/16/1987 |
| | title = LER 87-006-00:on 870917,discovered That Test of Emergency Diesel Generator Automatic Load Sequence Relays Incomplete. Caused by Personnel Error.Personnel Immediately Performed Required Surveillance Test Per procedure.W/871016 Ltr | | | title = LER 87-006-00:on 870917,discovered That Test of Emergency Diesel Generator Automatic Load Sequence Relays Incomplete. Caused by Personnel Error.Personnel Immediately Performed Required Surveillance Test Per procedure.W/871016 Ltr |
| | author name = MENDOZA V N, WOODY C O | | | author name = Mendoza V, Woody C |
| | author affiliation = FLORIDA POWER & LIGHT CO. | | | author affiliation = FLORIDA POWER & LIGHT CO. |
| | addressee name = | | | addressee name = |
| Line 16: |
Line 16: |
|
| |
|
| =Text= | | =Text= |
| {{#Wiki_filter:REGULATINFORMATIONDISTRIBUTIOYSTEM<RIDS)ACCESSIONNBRFACIL:50-389AUTH.NAMEMENDOZAIV.N.WOODY'.O.RECIP.NAME8710220113DOC.DATE:87/10/ibNOTARIZED:NOSt.LuciePlantiUnit2iFloridaPoeerhLightCo.AUTHORAFFILIATIONFloridaPower5LightCo.FloridaPoeer5LightCo.RECIPIENT'AFFILIATIONDOCKET¹05000389 | | {{#Wiki_filter:REGULAT INFORMATION DISTRIBUTIO YSTEM <RIDS) |
| | ACCESSION NBR 8710220113 DOC. DATE: 87/10/ib NOTARIZED: NO DOCKET ¹ FAC IL: 50-389 St. Lucie Planti Unit 2i Florida Poeer h Light Co. 05000389 AUTH. NAME AUTHOR AFF ILIAT ION MEN DO Z A I V. N. Florida Power 5 Li ght Co. |
| | WOODY'. O. Florida Poeer 5 Light Co. |
| | RECIP. NAME RECIPIENT 'AFFILIATION |
|
| |
|
| ==SUBJECT:== | | ==SUBJECT:== |
| LER87-00b-00:on870917'estof2ASc2Bemergency'ieselgeneratorautomaticloadsequencerelaysincomplete.Causedbgpersonnelerror.Personnelimmed.iatelgperformedrequiredsurveillancetestinaccordanceUj/procedure.W/8710ibltr.DISTRIBUTIONCODE:IESRDCOPIESRECEIVED:LTRIENCLgSIZE:TITLE:50.73LicenseeEventReport<LER)iIncidentRptietc.NOTES:RECIPIENTIDCODE/NAMEPD2-2LATOURIGNYiEINTERNAL:ACRSMICHELSONAEOD/DOAAEOD/DSP/ROABARM/DCTS/DABNRR/DEST/ADSNRR/DEST/ELBNRR/DEST/MEBNRR/DEST/PSBNRR/DEST/SGBNRR/DLPG/GABNRR/DREP/RABSIB02RESTELFQRDIJRGN2FILE01EXTERNAL:EGLGGRQHiMLPDRNSICHARRISIJCOPIESLTTRENCL111111122111011111111111111111551111*RECIPIENTIDCODE/NAMEPD2-2PDACRSMOELLERAEQD/DSP/NASAEOD/DSP/TPAB.DEDRQNRR/DEST/CEBNRR/DEBT/ICSBNRR/DEST/MTBNRR/DEST/RSBNRR/DLPG/HFBNRR/DOEA/EABNRR/DREP/RPBNRR/PMAS/ILRBRESDEPYGIRES/DE/EIB'STLOBBYWARDNRC'PDRNSICMAYS.GCOPIESLTTRENCL1122111'111:111111111122"11.111'1111TOTALNUMBEROFCOPIESREQUIRED:LTTR45ENCL44 NRCForm344(403)LICENSEEEVENTREPORT(LER)V.S.NUCLEARREGULATORYCOMMISSIONAPPROVEDOMBNO.3150010CEXPIRES,'i3)i45FACILITYNAME(I)ST.LUCIEUNIT2DOCKE'TNUMBER12)PAGEI3i03891OF03''MISSEDSURVEILLANCEONTHE2AAND2BEMERGENCYDIESELGENERATORAUTOMATICLOADSEUENCERELAYSDUETOACOGNITIVEPERSONNELERROR.EVENTDATE(5)LERNUMBER(4)REPORTDATE(7)OTHERFACILITIESINVOLVED(SIMONTHOAYYEARYEARei>.;SEQUENTIALy'-NUMSERSrTNUMSERMONTHDAYR4Vt)KINYEARFACILITYNAMESN/ADOCKETNVMBERISI0500009178787060010168705000OPERATINOMOOK(~I~OWERL'EYEL1020402(4)20A04(e)Ill(0204444)Ii)I4I20A04(~l(1)(SI)2040441(11(lvl204044)llI(v)20404(el50.34IclI)I50.34(cl(1)X50.73(el(2)(II50.73(el(2)(4)50.73(el(2)((BILICENSEECONTACTFORTHISLER(12)50.73(~l(2)(wI50.73(~II2I(v)50.73(e)(2)(vnl50,73Ie)LT)4iil)(Al50.73(~I(2)Ivi)i~)I4I50.73I~)(2IIxlTHISREPORTISSUBMITTEDPURSUANTT0THKREQUIREMENTSOF10CFR(I;fCneceoneormoreOftnefollowing/(1173.71(4)73.71(~IOTHER(SpecifyinapstisctOelOwentrinTert,iVRCperm3544INAMEV.N.Mendoza,ShiftTechnicalAdvisorTELEPHONENUssBERAREACODE305465-:3550COMPLETEONELINKFOREACHCOMPONENTFAILUREDESCRIBEDINTHISREPORT(13)CAUSESYSTEM'COMPONENTNANANAMANUFAC.TVRERNANAc:)Prrrst2wgSYSTKMCOMPONENTMANUFAC.TVRERREPORTABLETONPRDSw'vSUPPLEMENTALREPORTEXPECTEDlle)YESfffyet,CemptetetXptCTEDSVSetfSSIOefOATtfNOABSTRACT(Limittotc00tpeces.f.e..epprosimeNryRfteentingie.specstvpewrNNnfinest(14)EXPECTEDSUBMISSIONDATE(15IMONTNDAYYEARNAAt1900onSeptember17,1987,itwasdeterminedthatthe12monthtestofthe2Aand2BEmergencyDieselGenerator(EDG)automaticloadsequencerelayswasincomplete.Areviewofthesurveillanceprocedure,performedonMay4,1987,indicatedthatonlythecomponentsonthe4160volt2A3and2B3busesweretestedandthatthetestdidnotincludethecomponentsonthe4160volt.2ABbusandthe480voltloadcenters(LC).Therootcauseoftheeventwasacognitivepersonnelerrorbyutilitypersonnelimplementingthemaintenancesurveillanceprocedureandthequalitycontrolpersonnelreviewingtheplantworkorderandthemaintenancesurveillanceprocedureforcompletenessandcompliancetothesurveillancerequirements.'Forcorrectiveactions,theelectricalmaintenancepersonnelimmediately-performedtherequiredsurveillancetestinaccordancewiththeapprovedprocedure.PlantManagementhasre-emphasizedtheimportanceofadequatereviewofplantworkordersandsurveillanceprocedures.Inaddition,thesurveillanceprocedurewasrevisedforclarity.8710@201138710~16389PDRADOCK050$NRCForm344iS43s NRt!Form3EEAO.831LICENSEEEVENTREPORT(LERITEXTCONTINUATIONU.S.NUCLEARRECULATORYCOMMISSIONAPPROUEOOMSNO.3(50-0(0<EXPIRES:8/31/88FACILITYNAME(I)ST.LUCIEUNIT2OOCKETNUMBER(2)YEARLERNUMSER(8)N).SEQUENTIALNUMBERREvrsroNNUMBERPACE(3)TEXT///moree/reooierequired,ueeeddr(r'orre/HRCForrrr3SSA'e/l)2)0500038987006-0'2OF03DESCRIPTIONOPTHEEVENTAtapproximately'1730onSeptember17;1987,operationspersonnel.werenotified~thatanFPLQualityAssuranceaudithaddeterminedthetwelvemonthtestofthe2Aand2Bemergencydieselgenerator(EDG)(EIISSEK)automaticloadsequencerelaysperformedonMay4,1987wasincomplete.Thisprocedurerequiredthatallcomponentsonthethe4160Vbusesandthe480Vloadcenters(LC)betestedforproperloadsequencerelaytiming.Duringthereview,itwasdiscoveredthatonlythecomponentsonthe4160volt2A3and2B3busesweretested.At1900onSeptember17,1987,effortswerestarted"toperformtherequiredsurveillanceteststocomplywiththeTechnicalSpecificationrequirements.By0600onSeptember18,1987,allthecomponentsonthe2AEDG(Train"A")weresatisfactorilytestedandby1453onSeptember18,1987,allofthe2Aand,2BEDGcomponentsweresatisfactorilytested.AlltherelaystestedwerefoundtobewithinthetolerancerequirementsoftheTechnicalSpecifications.St.LucieUnit82remainedatMode1,100%power,throughoutthistimeperiod.rCAUSEOPTHEEVENTTherootcauseoftheeventwasacognitivepersonnelerrorbyutilitymaintenanceandqualitycontrolpersonnelresponsibleforreviewingtheplantworkorder(PWO)toensurecompleteimplementationandcompliancewiththerequirementsofthesurveillanceprocedures.Thecopyoftheprocedureusedbythejourneymanhadhandwrittendirectionsonthe'tepsof,the.procedure.indicatingwheretostart,andwheretostop.'heseinstructionsonlycoveredthe4160volt2A3and2B3components.Consequently,'160volt2ABbusandthe480VLCportionsoftheprocedurewereneverperformed.Thereviewof.thePWOdidnotrevealthisomission.ANALYSISOPTHEEVENTTechnicalSpecifications4.8.1.1.2.drequiresthatwhileoperatinginModes1,2,3,and4eachdieselgeneratorshallbedemonstratedoperablebyverifyingthatatleastonceper12monthstheautomaticloadsequencetimersareoperablewiththeintervalbetweeneachloadblockwithinplus/minusonesecondofitsdesigninterval.SincetheSt.LucieUnitN2wasoperatinginMode'1whentheeventwasdiscovered,thisreportisbeingsubmittedunder10CFR50.73(a)(2)(i)(B),anyoperationorconditionprohibitedbytechnicalspecificat'ionsasdefinedingenericletter87-09.Thelast'urveillancefortheEDG.12-monthtest'ftheautomaticloadsequencerelayswassatisfactorilyperformedinMay1986.ThissurveillanceprocedurewascompletedonSeptember18,1987,approximately18.5dayspastthemaximumallowableextensionof25%ofthetestingintervalafterthesurveillancewas'dueandapproximately22hoursafterthediscoveryofthecondition.Allcomponentstestedsatisfactorily,thusthehealthandsafetyofthegeneralpublicwerenotaffectedbythisevent.NRCFORM3BBA(94)3)
| | LER 87-00b-00: on 870917'est of 2A 2B emergency'iesel Sc generator automatic load sequence relays incomplete. Caused bg personnel error. Personnel immed.iatelg perf ormed required surveillance test in accordance Uj/procedure. W/8710ib ltr. |
| NRCFoehn3ddA(94)3ILICENSEEEVENTREPORT(LER)TEXTCONTINUATIONU.S.NUCLEARREGULATORYCOMMISSIONAPPROVEOOMBNO.3)9)W)04EXPIRES:8/31/88FACILITYNAME(I)DOCKETNUMBERl3)YEARLERNUMBER(8)SEOVENTIALNVMSSAK'IKIOAEV/SIONNVMSSAPAGE(3IST.LUCIEUNIT2TEXTIII///o/osPscois/odw'red,//sosddio'o/MIHRC%%d////3dSA'4/(17)osooo38987006003OF03CORRECTIVEACTIONS1.AfterOperationspersonnelwerenotifiedofthemissedsurveillancecondition,therequiredsurveillancewasimmediatelyperformedandwasdeemedsatisfactory.2.PlantManagementhasre-emphasizedtoplantpersonneltheimportanceofcompletingalltechnicalspecificationsurveillancesinatimelymannerasrequired.3.TheplantTxainingDepartmentwillevaluatethisitemtodetermineappropriatetrainingrequirementsandmethods..4.ThepersonnelresponsibleforpreparationandreviewoftheabovePWOhave*beencounselledontheimportanceofattentiontodetailinensuringTechnicalSpecificationsurveillancerequirementsaremet.5.Thesurveillanceprocedurewasrevisedforclarity.ADDITIONALINFORMATIONFailedcomponentinformation:Nocomponentorsystemfailuresoccuredduringthisevent.Previous.similarevent:ThemostrecentsimilareventonUnitII2wasamissedsurveillancesubmi.ttedunderLER$389-86-014.N/ICFORMSddA(94)3)
| | DISTRIBUTION CODE: IESRD COPIES RECEIVED: LTR TITLE: 50. 73 Licensee Event Report <LER)i I ENCL g Incident Rpti etc. |
| P.OX14000,JUNOBEAC<.,k.C;.gQ<0~pe.iOBcRi(,1~8(L<7OI7-IOCFR50.73U.S.NuclearRegulatoryCommissionAttn:DocumentControIDeskWashington,D.C.20555GentIemen:Re:St.LucieUnit2DocketNo.50-389ReportableEvent:87-06DateofEvent:Septemberl7,l987MissedSurveillanceonEmergencyDieselGeneratorAutoLoadSeuenceRelasTheattachedLicenseeEventReportisbeingsubmittedpursuanttotherequirmentsofIOCFR50.73.a.toprovidenotificationonthesubjectevent.Verytrulyyours,iI'p,i;o,E~C.0.Wo'odyGroupVicePresidentNuclearEnergyCOW/GRM/gpAttachmentcc:J.NelsonGrace,RegionalAdministrator,RegionII,USNRCSeniorResidentInspector,USNRC,St.LuciePlantGRMI/030/IanFPLGroupcompany}} | | SIZE: |
| | NOTES: |
| | RECIPIENT COPIES |
| | * REC IP IENT COP IES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD2-2 LA 1 PD2-2 PD 1 1 TOURIGNYi E 1 1 INTERNAL: ACRS MICHELSON 1 1 ACRS MOELLER 2 2 AEOD/DOA 1 1 AEQD/DSP/NAS 1 1 AEOD/DSP/ROAB 2 2 AEOD/DSP/TPAB . 1' ARM/DCTS/DAB DEDRQ NRR/DEST/ADS NRR/DEST/ELB 1 |
| | 1 1 |
| | 1 0 |
| | 1 NRR/DEST/CEB NRR/DEBT/ I CSB 1: |
| | 1 1 1 |
| | 1 NRR/DEST/MEB 1 1 NRR/DEST/MTB 1 1 NRR/DEST/PSB 1 1 NRR/DEST/RSB 1 1 NRR/DEST/SGB 1 1 NRR/DLPG/HFB 1 1 NRR/DLPG/GAB 1 NRR/DOEA/EAB NRR/DREP/RAB 1 1 |
| | 1 NRR/DREP/RPB 1 |
| | 2 2" 1 |
| | SIB 1 1 NRR/PMAS/ ILRB 1 1. |
| | 02 1 RES DEPY GI 1 1 RES TELFQRDI J 1 RES/DE/EIB 1' RGN2 FILE 01 1 EXTERNAL: EGLG GRQHi M 5 5 ST LOBBY WARD 1 LPDR 1 1 NRC'PDR 1 1 NSIC HARRISI J 1 1 NSIC MAYS. G 1 TOTAL NUMBER OF COPIES REQUIRED: LTTR 45 ENCL 44 |
| | |
| | NRC Form 344 V.S. NUCLEAR REGULATORY COMMISSION (403) |
| | APPROVED OMB NO. 3150010C EXPIRES,' i 3) i45 LICENSEE EVENT REPORT (LER) |
| | FACILITY NAME (I) DOCKE'T NUMBER 12) PAGE I3i 389 1OF03 |
| | ''ST.MISSED LUCIE UNIT 2 0 SURVEILLANCE ON THE 2A AND 2B EMERGENCY DIESEL GENERATOR AUTOMATIC LOAD SE UENCE RELAYS DUE TO A COGNITIVE PERSONNEL ERROR. |
| | EVENT DATE (5) LER NUMBER (4) REPORT DATE (7) OTHER FACILITIES INVOLVED (SI MONTH YEAR ei>.; SEQUENTIAL R 4 Vt)KIN MONTH DAY YEAR FACILITY NAMES DOCKET NVMBERISI OAY YEAR y' - |
| | NUMSER SrT NUMSER N/A 0 5 0 0 0 0 9 1 7 8 7 8 7 0Ill(0 6 0010 1 6 8 7 i)i 0 5 0 0 0 THIS REPORT IS SUBMITTED PURSUANT T 0 THK REQUIREMENTS OF 10 CFR (I; fCnece one or more Of tne following/ (11 OPERATINO MOOK (~ I 20402(4) 20404(el 50.73( ~ l(2)(wI 73.71(4) |
| | ~ OWER L'EY EL 20A04(e) 50.34 Icl I)I 50.73 ( ~ II 2 I( v) 73.71( ~ I 1 0 20 4444) Ii) I 4 I 50.34(cl(1) 50.73(e) (2)(vnl OTHER (Specify in apstisct OelOw entr in Tert, iVRC perm 20A04( ~ l(1)(SI) X 50.73(el(2)(II 50,7 3 Ie) LT)4iil)(Al 3544I 2040441(11(lvl 50.73(el(2)(4) 50.7 3( ~ I (2) Iv ) I4 I 204044) llI (v) 50.7 3(e l(2)((BI 50.73I ~ )(2IIxl LICENSEE CONTACT FOR THIS LER (12) |
| | NAME TELEPHONE NUssBER AREA CODE V. N. Mendoza, Shift Technical Advisor 3 054 65-: 3550 COMPLETE ONE LINK FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13) |
| | MANUFAC. MANUFAC. REPORTABLE CAUSE SYSTEM 'COMPONENT SYSTKM COMPONENT TVRER TVRER TO NPRDS c:)Prrrst 2 wg w'v NA NA NA NA NA SUPPLEMENTAL REPORT EXPECTED lle) MONTN DAY YEAR EXPECTED SUBMISSION DATE (15I YES fff yet, Cemptete tXptCTED SVSetfSSIOef OATtf NO N A ABSTRACT (Limit to tc00 tpeces. f.e.. epprosimeNry Rfteen tingie.specs tvpewrNNn finest (14) |
| | At 1900 on September 17, 1987, it was determined that the 12 month test of the 2A and 2B Emergency Diesel Generator (EDG) automatic load sequence relays was incomplete. A review of the surveillance procedure, performed on May 4, 1987, indicated that only the components on the 4160 volt 2A3 and 2B3 buses were tested and that the test did not include the components on the 4160 volt . 2AB bus and the 480 volt load centers (LC). |
| | The root cause of the event was a cognitive personnel error by utility personnel implementing the maintenance surveillance procedure and the quality control personnel reviewing the plant work order and the maintenance surveillance procedure for completeness and compliance to the surveillance requirements. |
| | 'For corrective actions, the electrical maintenance personnel immediately |
| | -performed the required surveillance test in accordance with the approved procedure. Plant Management has re-emphasized the importance of adequate review of plant work orders and surveillance procedures. In addition, the surveillance procedure was revised for clarity. |
| | 8710@20113 8710~16389 050 PDR ADOCK NRC Form 344 iS 43s |
| | |
| | U.S. NUCLEAR RECULATORY COMMISSION NRt! Form 3EEA O.831 LICENSEE EVENT REPORT (LERI TEXT CONTINUATION APPROUEO OMS NO. 3(50-0(0< |
| | EXPIRES: 8/31/88 FACILITY NAME (I) OOCKET NUMBER (2) LER NUMSER (8) PACE (3) |
| | YEAR N). SEQUENTIAL REvrsroN NUMBER NUMBER ST. LUCIE UNIT 2 0 5 0 0 0 3 898 7 006 0' 2 OF 0 3 TEXT /// more e/reoo ie required, uee eddr(r'orre/ HRC Forrrr 3SSA'e/ l)2) |
| | DESCRIPTION OP THE EVENT At approximately '1730 on September 17; 1987, operations personnel. were notified that an FPL Quality |
| | ~ Assurance audit had determined the twelve month test of the 2A and 2B emergency diesel generator (EDG) (EIISSEK) automatic load sequence relays performed on May 4, 1987 was incomplete. This procedure required that all components on the the 4160 V buses and the 480 V load centers (LC) be tested for proper load sequence relay timing. During the review, it was discovered that only the components on the 4160 efforts volt 2A3 were and 2B3 buses were tested. At 1900 on September 17, 1987, started to perform the required surveillance tests to comply with the Technical Specification requirements. By 0600 on September 18, 1987, all the components on the 2A EDG (Train "A") were satisfactorily tested and by 1453 on September 18, 1987, all of the 2A and, 2B EDG components were satisfactorily tested. All the relays tested were found to be within the tolerance requirements of the Technical Specifications. St. Lucie Unit 82 remained at Mode 1, 100% power, throughout this time period. |
| | r CAUSE OP THE EVENT The root cause of the event was a cognitive personnel error by utility maintenance and quality control personnel responsible for reviewing the plant work order (PWO) to ensure complete implementation and compliance with the requirements of the surveillance procedures. The copy of the procedure used by the journeyman had handwritten directions on the'teps of, the .procedure .indicating where to start, and where to stop.'hese instructions only covered the 4160 volt 2A3 and 2B3 components. Consequently,'160 volt 2AB bus and the 480 V LC portions of the procedure were never performed. The review of. the PWO did not reveal this omission. |
| | ANALYSIS OP THE EVENT Technical Specifications 4.8.1.1.2.d requires that while operating in Modes 1,2,3,and 4 each diesel generator shall be demonstrated operable by verifying that at least once per 12 months the automatic load sequence timers are operable with the interval between each load block within plus/minus one second of its design interval. Since the St. Lucie Unit N2 was operating in Mode'1 when the event was discovered, this report is being submitted under 10 CFR 50.73(a) |
| | (2)(i)(B), any operation or condition prohibited by technical specificat'ions as defined in generic letter 87-09. The last'urveillance for the EDG .12-month test'f the automatic load sequence relays was satisfactorily performed in May 1986. This surveillance procedure was completed on September 18, 1987, approximately 18.5 days past the maximum allowable extension of 25% of the testing interval after the surveillance was'due and approximately 22 hours after the discovery of the condition. All components tested satisfactorily, thus the health and safety of the general public were not affected by this event. |
| | NRC FORM 3BBA (94)3) |
| | |
| | NRC Foehn 3ddA U.S. NUCLEAR REGULATORY COMMISSION (94)3 I LICENSEE EVENT REPORT (LER) TEXT CONTINUATION APPROVEO OMB NO. 3)9)W)04 EXPIRES: 8/31/88 FACILITY NAME (I) DOCKET NUMBER l3) LER NUMBER (8) PAGE (3I SEOVENTIAL K |
| | 'I AEV/SION YEAR NVMSSA KIO NVMSSA ST. LUCIE UNIT 2 o s o o o 38 987 006 0 0 3 OF 03 TEXT III///o/o sPsco is /odw'red, //so sddio'o/MIHRC %%d////3dSA'4/ (17) |
| | CORRECTIVE ACTIONS |
| | : 1. After Operations personnel were notified of the missed surveillance condition, the required surveillance was immediately performed and was deemed satisfactory. |
| | : 2. Plant Management has re-emphasized to plant personnel the importance of completing all technical specification surveillances in a timely manner as required. |
| | : 3. The plant Txaining Department will evaluate this item to determine appropriate training requirements and methods.. |
| | : 4. The personnel responsible for preparation and review of the above PWO have been counselled on the importance of attention to detail in ensuring Technical Specification surveillance requirements are met. |
| | : 5. The surveillance procedure was revised for clarity. |
| | ADDITIONAL INFORMATION Failed component information: |
| | No component or system failures occured during this event. |
| | Previous .similar event: |
| | The most recent similar event on Unit II2 was a missed surveillance submi.tted under LER $ 389-86-014. |
| | N/IC FORM SddA (94)3) |
| | |
| | P. OX 14000, JUNO BEAC<., k . |
| | C; |
| | .gQ |
| | <0 |
| | ~pe iOBcR i (, 1~8( |
| | L<7 OI7-IO CFR 50.73 U.S. Nuclear Regulatory Commission A t tn: Doc umen t Contr o I Desk Washington, D. C. 20555 Gen t I emen: |
| | Re: St. Lucie Unit 2 Docket No. 50-389 Reportable Event: 87-06 Date of Event: September l7, l 987 Missed Surveillance on Emergency Diesel Generator Auto Load Se uence Rela s The attached Licensee Event Report is being submitted pursuant to the requirments of IO CFR 50.73.a. to provide notification on the subject event. |
| | Very truly yours, iI'p,i;o,E~ |
| | C. 0. Wo'ody Group Vice President Nuclear Energy COW/GRM/gp Attachment cc: J. Nelson Grace, Regional Administrator, Region II, USNRC Senior Resident Inspector, USNRC, St. Lucie Plant GRM I /030/I an FPL Group company}} |
|
|---|
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
REGULAT INFORMATION DISTRIBUTIO YSTEM <RIDS)
ACCESSION NBR 8710220113 DOC. DATE: 87/10/ib NOTARIZED: NO DOCKET ¹ FAC IL: 50-389 St. Lucie Planti Unit 2i Florida Poeer h Light Co. 05000389 AUTH. NAME AUTHOR AFF ILIAT ION MEN DO Z A I V. N. Florida Power 5 Li ght Co.
WOODY'. O. Florida Poeer 5 Light Co.
RECIP. NAME RECIPIENT 'AFFILIATION
SUBJECT:
LER 87-00b-00: on 870917'est of 2A 2B emergency'iesel Sc generator automatic load sequence relays incomplete. Caused bg personnel error. Personnel immed.iatelg perf ormed required surveillance test in accordance Uj/procedure. W/8710ib ltr.
DISTRIBUTION CODE: IESRD COPIES RECEIVED: LTR TITLE: 50. 73 Licensee Event Report <LER)i I ENCL g Incident Rpti etc.
SIZE:
NOTES:
RECIPIENT COPIES
- REC IP IENT COP IES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD2-2 LA 1 PD2-2 PD 1 1 TOURIGNYi E 1 1 INTERNAL: ACRS MICHELSON 1 1 ACRS MOELLER 2 2 AEOD/DOA 1 1 AEQD/DSP/NAS 1 1 AEOD/DSP/ROAB 2 2 AEOD/DSP/TPAB . 1' ARM/DCTS/DAB DEDRQ NRR/DEST/ADS NRR/DEST/ELB 1
1 1
1 0
1 NRR/DEST/CEB NRR/DEBT/ I CSB 1:
1 1 1
1 NRR/DEST/MEB 1 1 NRR/DEST/MTB 1 1 NRR/DEST/PSB 1 1 NRR/DEST/RSB 1 1 NRR/DEST/SGB 1 1 NRR/DLPG/HFB 1 1 NRR/DLPG/GAB 1 NRR/DOEA/EAB NRR/DREP/RAB 1 1
1 NRR/DREP/RPB 1
2 2" 1
SIB 1 1 NRR/PMAS/ ILRB 1 1.
02 1 RES DEPY GI 1 1 RES TELFQRDI J 1 RES/DE/EIB 1' RGN2 FILE 01 1 EXTERNAL: EGLG GRQHi M 5 5 ST LOBBY WARD 1 LPDR 1 1 NRC'PDR 1 1 NSIC HARRISI J 1 1 NSIC MAYS. G 1 TOTAL NUMBER OF COPIES REQUIRED: LTTR 45 ENCL 44
NRC Form 344 V.S. NUCLEAR REGULATORY COMMISSION (403)
APPROVED OMB NO. 3150010C EXPIRES,' i 3) i45 LICENSEE EVENT REPORT (LER)
FACILITY NAME (I) DOCKE'T NUMBER 12) PAGE I3i 389 1OF03
ST.MISSED LUCIE UNIT 2 0 SURVEILLANCE ON THE 2A AND 2B EMERGENCY DIESEL GENERATOR AUTOMATIC LOAD SE UENCE RELAYS DUE TO A COGNITIVE PERSONNEL ERROR.
EVENT DATE (5) LER NUMBER (4) REPORT DATE (7) OTHER FACILITIES INVOLVED (SI MONTH YEAR ei>.; SEQUENTIAL R 4 Vt)KIN MONTH DAY YEAR FACILITY NAMES DOCKET NVMBERISI OAY YEAR y' -
NUMSER SrT NUMSER N/A 0 5 0 0 0 0 9 1 7 8 7 8 7 0Ill(0 6 0010 1 6 8 7 i)i 0 5 0 0 0 THIS REPORT IS SUBMITTED PURSUANT T 0 THK REQUIREMENTS OF 10 CFR (I; fCnece one or more Of tne following/ (11 OPERATINO MOOK (~ I 20402(4) 20404(el 50.73( ~ l(2)(wI 73.71(4)
~ OWER L'EY EL 20A04(e) 50.34 Icl I)I 50.73 ( ~ II 2 I( v) 73.71( ~ I 1 0 20 4444) Ii) I 4 I 50.34(cl(1) 50.73(e) (2)(vnl OTHER (Specify in apstisct OelOw entr in Tert, iVRC perm 20A04( ~ l(1)(SI) X 50.73(el(2)(II 50,7 3 Ie) LT)4iil)(Al 3544I 2040441(11(lvl 50.73(el(2)(4) 50.7 3( ~ I (2) Iv ) I4 I 204044) llI (v) 50.7 3(e l(2)((BI 50.73I ~ )(2IIxl LICENSEE CONTACT FOR THIS LER (12)
NAME TELEPHONE NUssBER AREA CODE V. N. Mendoza, Shift Technical Advisor 3 054 65-: 3550 COMPLETE ONE LINK FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13)
MANUFAC. MANUFAC. REPORTABLE CAUSE SYSTEM 'COMPONENT SYSTKM COMPONENT TVRER TVRER TO NPRDS c:)Prrrst 2 wg w'v NA NA NA NA NA SUPPLEMENTAL REPORT EXPECTED lle) MONTN DAY YEAR EXPECTED SUBMISSION DATE (15I YES fff yet, Cemptete tXptCTED SVSetfSSIOef OATtf NO N A ABSTRACT (Limit to tc00 tpeces. f.e.. epprosimeNry Rfteen tingie.specs tvpewrNNn finest (14)
At 1900 on September 17, 1987, it was determined that the 12 month test of the 2A and 2B Emergency Diesel Generator (EDG) automatic load sequence relays was incomplete. A review of the surveillance procedure, performed on May 4, 1987, indicated that only the components on the 4160 volt 2A3 and 2B3 buses were tested and that the test did not include the components on the 4160 volt . 2AB bus and the 480 volt load centers (LC).
The root cause of the event was a cognitive personnel error by utility personnel implementing the maintenance surveillance procedure and the quality control personnel reviewing the plant work order and the maintenance surveillance procedure for completeness and compliance to the surveillance requirements.
'For corrective actions, the electrical maintenance personnel immediately
-performed the required surveillance test in accordance with the approved procedure. Plant Management has re-emphasized the importance of adequate review of plant work orders and surveillance procedures. In addition, the surveillance procedure was revised for clarity.
8710@20113 8710~16389 050 PDR ADOCK NRC Form 344 iS 43s
U.S. NUCLEAR RECULATORY COMMISSION NRt! Form 3EEA O.831 LICENSEE EVENT REPORT (LERI TEXT CONTINUATION APPROUEO OMS NO. 3(50-0(0<
EXPIRES: 8/31/88 FACILITY NAME (I) OOCKET NUMBER (2) LER NUMSER (8) PACE (3)
YEAR N). SEQUENTIAL REvrsroN NUMBER NUMBER ST. LUCIE UNIT 2 0 5 0 0 0 3 898 7 006 0' 2 OF 0 3 TEXT /// more e/reoo ie required, uee eddr(r'orre/ HRC Forrrr 3SSA'e/ l)2)
DESCRIPTION OP THE EVENT At approximately '1730 on September 17; 1987, operations personnel. were notified that an FPL Quality
~ Assurance audit had determined the twelve month test of the 2A and 2B emergency diesel generator (EDG) (EIISSEK) automatic load sequence relays performed on May 4, 1987 was incomplete. This procedure required that all components on the the 4160 V buses and the 480 V load centers (LC) be tested for proper load sequence relay timing. During the review, it was discovered that only the components on the 4160 efforts volt 2A3 were and 2B3 buses were tested. At 1900 on September 17, 1987, started to perform the required surveillance tests to comply with the Technical Specification requirements. By 0600 on September 18, 1987, all the components on the 2A EDG (Train "A") were satisfactorily tested and by 1453 on September 18, 1987, all of the 2A and, 2B EDG components were satisfactorily tested. All the relays tested were found to be within the tolerance requirements of the Technical Specifications. St. Lucie Unit 82 remained at Mode 1, 100% power, throughout this time period.
r CAUSE OP THE EVENT The root cause of the event was a cognitive personnel error by utility maintenance and quality control personnel responsible for reviewing the plant work order (PWO) to ensure complete implementation and compliance with the requirements of the surveillance procedures. The copy of the procedure used by the journeyman had handwritten directions on the'teps of, the .procedure .indicating where to start, and where to stop.'hese instructions only covered the 4160 volt 2A3 and 2B3 components. Consequently,'160 volt 2AB bus and the 480 V LC portions of the procedure were never performed. The review of. the PWO did not reveal this omission.
ANALYSIS OP THE EVENT Technical Specifications 4.8.1.1.2.d requires that while operating in Modes 1,2,3,and 4 each diesel generator shall be demonstrated operable by verifying that at least once per 12 months the automatic load sequence timers are operable with the interval between each load block within plus/minus one second of its design interval. Since the St. Lucie Unit N2 was operating in Mode'1 when the event was discovered, this report is being submitted under 10 CFR 50.73(a)
(2)(i)(B), any operation or condition prohibited by technical specificat'ions as defined in generic letter 87-09. The last'urveillance for the EDG .12-month test'f the automatic load sequence relays was satisfactorily performed in May 1986. This surveillance procedure was completed on September 18, 1987, approximately 18.5 days past the maximum allowable extension of 25% of the testing interval after the surveillance was'due and approximately 22 hours2.546296e-4 days <br />0.00611 hours <br />3.637566e-5 weeks <br />8.371e-6 months <br /> after the discovery of the condition. All components tested satisfactorily, thus the health and safety of the general public were not affected by this event.
NRC FORM 3BBA (94)3)
NRC Foehn 3ddA U.S. NUCLEAR REGULATORY COMMISSION (94)3 I LICENSEE EVENT REPORT (LER) TEXT CONTINUATION APPROVEO OMB NO. 3)9)W)04 EXPIRES: 8/31/88 FACILITY NAME (I) DOCKET NUMBER l3) LER NUMBER (8) PAGE (3I SEOVENTIAL K
'I AEV/SION YEAR NVMSSA KIO NVMSSA ST. LUCIE UNIT 2 o s o o o 38 987 006 0 0 3 OF 03 TEXT III///o/o sPsco is /odw'red, //so sddio'o/MIHRC %%d////3dSA'4/ (17)
CORRECTIVE ACTIONS
- 1. After Operations personnel were notified of the missed surveillance condition, the required surveillance was immediately performed and was deemed satisfactory.
- 2. Plant Management has re-emphasized to plant personnel the importance of completing all technical specification surveillances in a timely manner as required.
- 3. The plant Txaining Department will evaluate this item to determine appropriate training requirements and methods..
- 4. The personnel responsible for preparation and review of the above PWO have been counselled on the importance of attention to detail in ensuring Technical Specification surveillance requirements are met.
- 5. The surveillance procedure was revised for clarity.
ADDITIONAL INFORMATION Failed component information:
No component or system failures occured during this event.
Previous .similar event:
The most recent similar event on Unit II2 was a missed surveillance submi.tted under LER $ 389-86-014.
N/IC FORM SddA (94)3)
P. OX 14000, JUNO BEAC<., k .
C;
.gQ
<0
~pe iOBcR i (, 1~8(
L<7 OI7-IO CFR 50.73 U.S. Nuclear Regulatory Commission A t tn: Doc umen t Contr o I Desk Washington, D. C. 20555 Gen t I emen:
Re: St. Lucie Unit 2 Docket No. 50-389 Reportable Event: 87-06 Date of Event: September l7, l 987 Missed Surveillance on Emergency Diesel Generator Auto Load Se uence Rela s The attached Licensee Event Report is being submitted pursuant to the requirments of IO CFR 50.73.a. to provide notification on the subject event.
Very truly yours, iI'p,i;o,E~
C. 0. Wo'ody Group Vice President Nuclear Energy COW/GRM/gp Attachment cc: J. Nelson Grace, Regional Administrator, Region II, USNRC Senior Resident Inspector, USNRC, St. Lucie Plant GRM I /030/I an FPL Group company
