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| | issue date = 08/14/1989 | | | issue date = 08/14/1989 |
| | title = LER 89-004-00:on 890715,discovered That Reactor Containment Fan Coolers Had Filter Media in Place During Power Operations.Caused by Inadequate Maint Instructions.Filters Removed & Maint Instructions revised.W/890814 Ltr | | | title = LER 89-004-00:on 890715,discovered That Reactor Containment Fan Coolers Had Filter Media in Place During Power Operations.Caused by Inadequate Maint Instructions.Filters Removed & Maint Instructions revised.W/890814 Ltr |
| | author name = SNYDER M J, WOODY C O | | | author name = Snyder M, Woody C |
| | author affiliation = FLORIDA POWER & LIGHT CO. | | | author affiliation = FLORIDA POWER & LIGHT CO. |
| | addressee name = | | | addressee name = |
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| {{#Wiki_filter:gcczlERATEDDISI+3UTIONDEMONSTRA'gNSYSTEMREGULATORYINFORMATIONDISTRIBUTIONSYSTEM(RIDS)ACCESSIONNBR:8908220121DOC.DATE:89/08/14NOTARIZED:NOFACIL:50-335St.LuciePlant,Unit1,FloridaPower&LightCo.AUTH.NAMEAUTHORAFFILIATIONSNYDER,M.J.FloridaPower&LightCo.WOODY,C.O.FloridaPower&LightCo.RECIP.NAMERECIPIENTAFFILIATIONDOCKET05000335R | | {{#Wiki_filter:gcczlERATED DISI+3UTION DEMONSTRA'gN SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS) |
| | ACCESSION NBR:8908220121 DOC.DATE: 89/08/14 NOTARIZED: NO DOCKET FACIL:50-335 St. Lucie Plant, Unit 1, Florida Power & Light Co. 05000335 AUTH. NAME AUTHOR AFFILIATION SNYDER,M.J. Florida Power & Light Co. |
| | WOODY,C.O. Florida Power & Light Co. |
| | RECIP.NAME RECIPIENT AFFILIATION R |
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| |
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| ==SUBJECT:== | | ==SUBJECT:== |
| LER89-004-00:on890715,containmentfancoolerfiltersleftinplaceduringunitpoweroperationduetoIP.W/8ltr.DISTRIBUTIONCODE:IE22TCOPIESRECEIVED:LTRENCL/SIZE:TITLE:50.73/50.9LicenseeEventReport(LER),ncidentRpt,etc.NOTES:RECIPIENTIDCODE/NAMEPD2-2LANORRIS,JINTERNAL:ACRSMICHELSONACRSWYLIEAEOD/DSP/TPABDEDRONRR/DEST/CEB8HNRR/DEST/ICSB7NRR/DEST/MTB9HNRR/DEST/RSB8ENRR/DLPQ/HFB10NRR/DOEA/EAB11NUDOCS-ABSTRACTRES/DSIR/EIBEXTERNALEG&GWILLIAMSESLSTLOBBYWARDNRCPDRNSICMURPHY,G.ACOPIESLTTRENCL111111111111111111111111111144111111RECIPIENTIDCODE/NAMEPD2-2PDACRSMOELLERAEOD/DOAAEOD/ROAB/DSPIRM/DCTS/DABNRR/DEST/ESB8DNRR/DEST/MEB9HNRR/DEST/PSB8DNRR/DEST/SGB8DNRR/DLPQ/PEB10PB10REGFILE02GN2ILE01FORDBLDGHOY,ALPDRNSICMAYS,GCOPIESLTTRENCL1122112211111111111.1221111111111hRID/hFULLTEXTCONVERSIONREQUIREDTOTALNUMBEROFCOPIESREQUIRED:LTTR40ENCL40 P.O.Box14000,JunoBeach,FL33408-0420@PLAUGUSTj14198gL-89'-299U.S.NuclearRegulatoryCommissionAttn:DocumentControlDeskWashington,D.C.20555Gentlemen:Re:St.LucieUnit1DocketNo.50-335ReportableEvent:89-04DateofEvent:July15,1989ContainmentFanCoolerFiltersLeftinPlaceDuringUnitPover0erationDuetoInadeateProceduresTheattachedvoluntaryLicenseeEventReportisbeingsubmittedtoprovidenotificationofthesubjectevent.Verytrulyyours,C.0.WoodyActingSeniorVicePresident-NuclearCOW/JRH/cm'ttachmentscc:StewartD.Ebneter,RegionalAdministrator,RegionII,USNRCSeniorResidentInspector,USNRC,St.LuciePlantan'f'r.Groupcompany NAC)erin$44195$1LICENSEEEVENTREPORTILER)U.S.NUCLEAAREGULATORYCOMMISSIONAPPAOVEOOMBNO2'1100104EXPIRES4-$1BSFACILITYNAME111DOCKETNUMBERIllPASt.Lucie,UnitOne0500033510FOCONTAINMENTFANCOOLERFILTERSLEFTINPLACEDURINGUNITPOVEROPERATIONDUETOINADEQUATEPROCEDURESEVENTDATEISILERNUMBER(41REPORTDATE171OTHERFACILITIE5INVOLVEDISIMONTHOAYYEARYEAR140Ij44TIAL4VM44IMOIIITHNIMofreOAYYEARiACII.ITYVAMESN/AOOCKFTNVMBERISI05000071589840008148N/A05000OPERATINOMODE(~)5POWERLEYEL000~i20.402(oi20405(~)Ill(il20.40541(I)iii120.405(~IllI(iiil20.405(~l(l)(ivl20,405(~1111(vI20.405(cl50.$4(cl(ll50.$4(el(2)50.7$(eI(2)Ii)50.7$(~l(ll(iilS0.7l(el(2)(iiilLICENSEECONTACTFORTHISLER(12)50.7l(~I(2l(ivi50.72(~)(21(vI50,77(4)(21(riiI507$N)(ll(niil(AI50.7$(~l(21(riillIBIS0.7l(~I(2)(e)THISREPORTISSUBMITTEDPURSUANTT0tHEREOUIREMENTSof10cfA():IcnrceonroirnrNroImrIoooiiinpl(117$.71(4)7$.7)(c)DTHEAlsorcirrinAorrrectoiio>>rod.nTerr.rVIICfor<<<<$54AIVoluntary4AMEMichaelJ.Snyder,ShiftTechnicalAdvisorTELEPIrONE4VMBERAREACODE407465"3550COMPLE'TfONfLINEfOAEACHCOMPONENTFAILUREDESCRIBEDINTHISREPORT1121CAUSESYSTEMCOMPO454TMANLPAC.Ti,'AfREPOA-ABLETO4PRDSCAVSESYSTEMCOMPONENT4IANVFAC.TVREREPORTABLfTOherrDSSUPPLEMENTALAEPOATEXPECTED(141EXPECTEDSV5MISSIONDATE(151MO47viDAYvfARYESII'nCOMP~rrEXPECTEDSVSMrSSiOiVOATEI4OAssTRAcTILinvrrorepCroicrrir,roorov.i<<rrrII'Irri<<e<<prrroke~trorn<<rrinI.<<nl1141On15July,1989,whileSt.LucieUnitOnewasshutdown,itwasdiscoveredthattheReactorContainmentFanCoolers(RCFC)hadfiltermediainplaceduringpoweroperations.TheRCFCfiltersreducefoulingofthesystem'scoolingcoilswhentheunitisshutdown.FilterswereinstalledduringtheFebruary1987refuelingoutage,werereplacedduringtheJuly1988refuelingoutageandleftinstalleduntilJuly,1989.Thecauseofthiseventwasduetoinadequatemaintenanceinstructions.Thefilterswereremoved,andanEngineeringevaluationisbeingpreparedtoverifyfilterperformanceunderaccidentconditions.St.LucieUnitTwoRCFCwereverifiedtohavefiltersremoved,maintenanceinstructionswillberevised,andothersafetyrelatedcomponentswerecheckedforimproperlyinstalledfilters.Thiseventwasdeterminednottobereportableunder10CFR50.72or50.73andisbeingsubmittedforinformationalpurposes.NACperi<<$44195$1 NRCfeIAI388AWQI~LICENSEEEVE:TREPORT(LER)TEXTCONTINUATIU.S.NUCLEARREGULATORYCOMMISSIONAPPROVEOOM8NO.3150WI04EXPIRES:8/31/NlfACILITYNAMEIlIOOCKETNUMSER121YEARLERNUMSER18)+SI55OVENTIALr@INVM58AEVI5IONNVM5APAGELSISt.Lucie,UnitOneTOIT/8'AMleNMCP8/59VIREV5444RRMA4/H/IChem3/5348/(Itl0500033502OFDESCRIPTIONOFEVENT:On15July,1989,whileSt.LucieUnitOne(PSLl)wasshutdownforaSteamGenerator(EIISIAB)tubeplugreplacementoutage,aninspectionoftheReactorContainmentFanCoolers(EIISIBK)(RCFC)showedthattheprefiltermediaforthesecoolerswasexcessivelydiscolored.ThesystemTechnicalManualfortheRCFCimpliesthattheprefiltermediashouldonlybeusedduringshutdownmodesofoperationtoreducefoulingofthecoolingcoilsduringconstructionormaintenance.TheprefilterswereinstalledduringtheFebruary1987refueling.outageandremainedinplaceuntilthenextrefuelingoutageofJuly,1988.NewfiltersinstalledduringtheJuly1988outagewereleftinplaceuntilJuly1989.Thelengthoftimethesefilterswereinstalledpromptedutilitypersonneltoinitiateanoperabilityassessmentonpastsystemperformance.CAUSEOFTHEEVENT:Thecauseofallowingprefiltermediatoremaininplaceduringpoweroperationwasduetomaintenanceinstructionsnotstatingthatthefiltershouldbeusedonlyduringoutageperiods.ANALYSISOFEVENT:Technical,Specification3/4.6.2.3addressesthesurveillancerequirementsandthebasesforthecontainmentcoolingsystem.TheoperabilityoftheRCFCensuresthat1)thecontainmentairtemperaturewillbemaintainedwithinlimitsduringnormaloperation,and2)adequateheatremovalcapacityisavailablewhenoperatedinconjunctionwiththeContainmentSpraySystemsduringpostulatedlossofcoolantaccidentconditions.ThesurveillancerequirementsfortheRCFCweremetunderpastsystemperformance.Thebasesofsystemoperationweresatisfiedasfollows:1)NormalcontainmentairtemperaturewasmaintainedwithinthelimitssetbyPSL1TechnicalSpecification3/4.6.1.5.Also,theRCFCmanufacturer,Westinghouse,analyzedtheresultsofdifferentialpressure(dp)measurementstakenoneachofthefourcoolingfansanddeterminedthattheasfoundfilterresistancewasnotaproblemduringnormalandpostulatedaccidentmodeoperation.Themeasureddpwaslessthanthemaximumdpfortherecommendedfilters.Therefore,theminimum"airflowrequirementfortheRCFCwasneverviolatedunderpastsystemperformance.NRCPOAM545Ar4USGPOII9880824538/455 NRCform388A(Q4)3)LICENSEEEVEREPORT{LER)TEXTCONTINUATIO)U.S.NUCLEARREOULATORYCOMMISSIONAPPROVEOOMSNO.3150-0104EXPIRES:8/3'I/88FACILITYNAMEII)DOCKETNUMBERll)LERNUMBERIS)PACE(3)St.Lucie,UnitOneTEitT/SRSNoCfoco/4oqulor/Uoo/aP/N/one////)C%%dnR38SA'4)IIT)05000335YEARrPPv.SEOUENTIALNUMSERREVISIONNUMSER03OF2)Section6.2ofthePSL1FUSARdescribesthedesignbasesandminimumrequirementsforcontainmentheatremovalsystems.Anyoneofthefollowingthreesubsystemswillprovideatleastminimumheatremovalcapabilitynecessarytolimitandreducethepostaccidentcontainmentpressureandtemperature:allfourcontainmentfancoolers(100percentcapacity),eitherofthetwocontainmentspraytrains(EIISIBE)(100percentcapacityforeachsubsystem).Evenassumingtheworstcase,noRCFCavailableandasingleactivefailureinoneofthetwocontainmentspraytrains,thesafetyfunctionofcontainmentheatremovalwouldhavebeenmetwiththeremainingoperablecontainmentspraysubsystem.Basedontheabove,itcanbeconcludedthatthehealthandsafetyofthepublicwerenotaffectedatanytimewiththecontinuousinstallationofprefiltersintheRCFC.Thiseventisnotdeemedreportableaspertherequirementsof10CFR50.73,orofanyoperationorconditionprohibitedbySt.LuciePlant'sTechnicalSpecifications.However,thisreportisbeingsubmittedforinformationalpurposes.CORRECTIVEACTIONS:1.St.LucieUnitTwo'sRCFCsystemTechnicalManualexplicitlystatesthattheprefiltermediashouldberemovedpriortopoweroperation.AninspectionofUnitTwo'sRCFCon15JulyconfirmedthatalloftheRCFCprefiltermediawasremovedbeforetheunitbeganpoweroperations.2.TestswereruntomeasurethedpacrosseachfilterandcoolingunitforPSL1.Thesetestrunsweremadetoaddresspossibleoperabilityconcernsoverapotentiallyhighfilterdp.ApreliminaryEngineeringevaluationdeter'minedthattheRCFCwereoperablewithprefiltersinstalledduringpoweroperation.3.TheprefilterswereremovedfromthePSLlRCFCandwillnotbeusedduringpoweroperations.r4.AnEngineeringsafetyevaluationisbeingperformedto,determinetheenvironmentalqualificationofthefiltermediaandtheperformanceofthesefiltersunderpostulatedaccidentconditions.ContactwithWestinghouse,FloridaFilters(supplierofthefiltermedialastused),andothermaterialmanufacturershasbeenestablishedinordertoassesspastperformancecapabilitiesoftheRCFC.NRCCORM344A)8831oU.S.GPO:I9880.824538/~55 kllCPocMS44AIbbb>LICENSEETREPORT(LER)TEXTCONTINUAV$IIVCLEAIIAEGVLATOIIYCOMMIS'PPIIOVEOOMbIIOSISO&104EXPIIIE$.b/SIIEEIPACILITYNAMEillSt.Lucie,UnitOneTEXT(/vere4S444b14EMPSKE444~iVIICAsmJXA'4)(17lOOCKETIIUMSESI(SS05000335YSAALEllRUMSEAlblSSGVCHT<AL~NUMSAASM+IQHMMM4ApPAGEulpgOF5,PSL1'sTechnicalManualonRCFCwillbechangedtoexplicitlyprohibitleavingfiltermediaonthefansduringpoweroperation.6.Othersafety-relatedcomponentswerecheckedtoverifythatnoothercomponentshaveunanalyzedfiltersinstalled.ADDITIONALINFORMATION:COMPONENTFAILURESNonePREVIOUSSIMILAREVENTSNoneMACSOAM444A4U$GPOlbbb'062~'Sbb~}}
| | LER 89-004-00:on 890715,containment fan cooler filters left in place during unit power operation due to IP. |
| | W/8 ltr. |
| | DISTRIBUTION CODE: IE22T COPIES RECEIVED:LTR ENCL / SIZE: |
| | TITLE: 50.73/50.9 Licensee Event Report (LER), ncident Rpt, etc. |
| | NOTES: |
| | RECIPIENT COPIES RECIPIENT COPIES h ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD2-2 LA 1 1 PD2-2 PD 1 1 NORRIS,J 1 1 INTERNAL: ACRS MICHELSON 1 1 ACRS MOELLER 2 2 ACRS WYLIE 1 1 AEOD/DOA 1 1 AEOD/DS P/TPAB 1 1 AEOD/ROAB/DSP 2 2 DEDRO 1 1 IRM/DCTS/DAB 1 1 NRR/DEST/CEB 8H 1 1 NRR/DEST/ESB 8D 1 1 NRR/DEST/ICSB 7 1 1 NRR/DEST/MEB 9H 1 1 NRR/DEST/MTB 9H 1 1 NRR/DEST/PSB 8D 1 1 NRR/DEST/RSB 8E 1 1 NRR/DEST/SGB 8D 1 1 NRR/DLPQ/HFB 10 1 1 NRR/DLPQ/PEB 10 1 . 1 NRR/DOEA/EAB 11 1 1 PB 10 2 2 NUDOCS-ABSTRACT 1 1 REG FILE 02 1 1 RES/DSIR/EIB 1 1 GN2 ILE 01 1 1 EXTERNAL EG&G WILLIAMS SE 4 4 FORD BLDG HOY,A 1 1 L ST LOBBY WARD 1 1 LPDR 1 1 R NRC PDR 1 1 NSIC MAYS,G 1 1 NSIC MURPHY,G.A 1 1 I D |
| | / |
| | h FULL TEXT CONVERSION REQUIRED TOTAL NUMBER OF COPIES REQUIRED: LTTR 40 ENCL 40 |
| | |
| | P.O. Box14000, Juno Beach, FL 33408-0420 |
| | @PL AUGUSTj 14 198g L-89'-299 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. C. 20555 Gentlemen: |
| | Re: St. Lucie Unit 1 Docket No. 50-335 Reportable Event: 89-04 Date of Event: July 15, 1989 Containment Fan Cooler Filters Left in Place During Unit Pover 0 eration Due to Inade ate Procedures The attached voluntary Licensee Event Report is being submitted to provide notification of the subject event. |
| | Very truly yours, C. 0. Woody Acting Senior Vice President Nuclear COW/JRH/cm |
| | 'ttachments cc: Stewart D. Ebneter, Regional Administrator, Region Senior Resident Inspector, USNRC, St. Lucie Plant II, USNRC an 'f'r. Group company |
| | |
| | NAC )erin $ 44 U.S. NUCLEAA REGULATORY COMMISSION 19 5$ 1 APPAOVEO OMB NO 2'1100104 EXPIRES 4-$ 1 BS LICENSEE EVENT REPORT ILER) |
| | DOCKET NUMBER Ill PA FACILITY NAME 111 St. Lucie, Unit One 0500033510FO CONTAINMENT FAN COOLER FILTERS LEFT IN PLACE DURING UNIT POVER OPERATION DUE TO INADEQUATE PROCEDURES EVENT DATE ISI LER NUMBER (41 REPORT DATE 171 OTHER F ACILITIE5 INVOLVED ISI 1 4 0 Ij4 4 T I A L iACII.ITYVAMES OOCKF T NVMBERISI MONTH OAY YEAR YEAR 4VM44 I NI Mof re MOIIITH OAY YEAR N/A 0 5 0 0 0 0 7 1 5 8 9 8 4 0 00 8148 N/A 0 5 0 0 0 OPERATINO THIS REPORT IS SUBMITTED PURSUANT T 0 tHE REOUIREMENTS of 10 cf A (): Icnrce onr oi rnrNr oI mr Ioooiiinpl (11 MODE ( ~ ) 7$ .71(4) 5 20.402(oi 20.405(cl 50.7l( ~ I(2 l(ivi POWER 20 405( ~ ) Ill(il 50.$ 4(cl(ll 50.7 2( ~ ) (21( v I 7$ .7)(c) |
| | LEYEL DTHEA lsorcirr in Aorrrect 0 0 0 20. 405 4 1 (I) iii1 50.$ 4(el(2) 50,7 7 (4) (21( riiI oiio>> rod.n Terr. rVIIC for<<<< |
| | 20.405( ~ I llI (iiil 50.7 $ (e I (2) I i) 50 7$ N)(ll(niil(AI $ 54AI |
| | ~ i 20.405( ~ l(l)(ivl 50.7$ ( ~ l(ll(iil 50.7$ ( ~ l(21(riillIBI 20,405( ~ 1111(v I S0.7 l(el(2)(iiil S0.7l( ~ I(2)(e) |
| | Voluntary LICENSEE CONTACT FOR THIS LER (12) 4AME TELEPIrONE 4VMBER AREA CODE Michael J. Snyder, Shift Technical Advisor 407 465" 3550 COMPLE'Tf ONf LINE fOA EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT 1121 MANLPAC. EPOA-ABLE 4IANVFAC. EPORTABLf CAUSE SYSTE M COMPO454T Ti,'AfR TO 4PRDS CAVSE SYSTEM COMPONENT TVRER TO herrDS SUPPLEMENTAL AEPOAT EXPECTED (141 MO47vi DAY vf AR EXPECTED SV 5 M I SS ION DATE (151 YES II'n COMP ~ rr EXPECTED SVSMrSSiOiV OATEI 4O AssTRAcT ILinvr ro repC roicrri r, roorov.i<<rrr I I'Irri<<e <<prr roke ~ trorn<<rrin I.<<nl 1141 On 15 July, 1989, while St. Lucie Unit One was shutdown, it was discovered that the Reactor Containment Fan Coolers (RCFC) had filter media in place during power operations. The RCFC filters reduce fouling of the system's cooling coils when the unit is shutdown. Filters were installed during the February 1987 refueling outage, were replaced during the July 1988 refueling outage and left installed until July, 1989. The cause of this event was due to inadequate maintenance instructions. The filters were removed, and an Engineering evaluation is being prepared to verify filter performance under accident conditions. St. Lucie Unit Two RCFC were verified to have filters removed, maintenance instructions will be revised, and other safety related components were checked for improperly installed filters. This event was determined not to be reportable under 10CFR50.72 or 50.73 and is being submitted for informational purposes. |
| | NAC peri<< $44 19 5$ 1 |
| | |
| | NRC feIAI 388A U.S. NUCLEAR REGULATORY COMMISSION WQ I ~ |
| | LICENSEE EVE: T REPORT (LER) TEXT CONTINUATI APPROVEO OM8 NO. 3150WI04 EXPIRES: 8/31/Nl fACILITYNAME IlI OOCKET NUMSER 121 LER NUMSER 18) PAGE LSI YEAR +SI 55OVENTIAL AEVI5ION r@I NVM 58 NVM 5A St. Lucie, Unit TOIT /8'AMle NMCP 8 /59VIRE One V54 44RRMA4/H/IC hem 3/5348/ (Itl 05000335 0 2 OF DESCRIPTION OF EVENT: |
| | On 15 July, 1989, while St. Lucie Unit One (PSLl) was shutdown for a Steam Generator (EIISIAB) tube plug replacement outage, an inspection of the Reactor Containment Fan Coolers (EIISIBK) (RCFC) showed that the prefilter media for these coolers was excessively discolored. The system Technical Manual for the RCFC implies that the prefilter media should only be used during shutdown modes of operation to reduce fouling of the cooling coils during construction or maintenance. |
| | The prefilters were installed during the February 1987 refueling .outage and remained in place until the next refueling outage of July, 1988. |
| | New filters installed during the July 1988 outage were left in place until July 1989. The length of time these filters were installed prompted utility personnel to initiate an operability assessment on past system performance. |
| | CAUSE OF THE EVENT: |
| | The cause of allowing prefilter media to remain in place during power operation was due to maintenance instructions not stating that the filter should be used only during outage periods. |
| | ANALYSIS OF EVENT: |
| | Technical, Specification 3/4.6.2.3 addresses the surveillance requirements and the bases for the containment cooling system. The operability of the RCFC ensures that 1) the containment air temperature will be maintained within limits during normal operation, and 2) adequate heat removal capacity is available when operated in conjunction with the Containment Spray Systems during postulated loss of coolant accident conditions. The surveillance requirements for the RCFC were met under past system performance. The bases of system operation were satisfied as follows: |
| | : 1) Normal containment air temperature was maintained within the limits set by PSL1 Technical Specification 3/4.6.1.5. Also, the RCFC manufacturer, Westinghouse, analyzed the results of differential pressure (dp) measurements taken on each of the four cooling fans and determined that the as found filter resistance was not a problem during normal and postulated accident mode operation. The measured dp was less than the maximum dp for the recommended filters. |
| | Therefore, the minimum airflow requirement for the RCFC was never violated under past system performance. |
| | NRC POAM 545A 4 U S GPOI I 988 0 824 538/455 r |
| | |
| | NRC form 388A U.S. NUCLEAR REOULATORY COMMISSION (Q4)3) |
| | LICENSEE EVE REPORT {LER) TEXT CONTINUATIO) APPROVEO OMS NO. 3150-0104 EXPIRES: 8/3'I/88 FACILITY NAME II) DOCKET NUMBER ll) LER NUMBER IS) PACE (3) |
| | YEAR SEOUENTIAL REVISION rPPv. NUMSER NUMSER St. Lucie, Unit One TEitT /SRSNo Cfoco/4 oqulor/ Uoo/aP/N/one////)C %%dnR 38SA'4) I IT) 0 5 0 0 0 335 0 3 OF |
| | : 2) Section 6.2 of the PSL1 FUSAR describes the design bases and minimum requirements for containment heat removal systems. Any one of the following three subsystems will provide at least minimum heat removal capability necessary to limit and reduce the post accident containment pressure and temperature: all four containment fan coolers (100 percent capacity), either of the two containment spray trains (EIISIBE) |
| | (100 percent capacity for each subsystem). Even assuming the worst case, no RCFC available and a single active failure in one of the two containment spray trains, the safety function of containment heat removal would have been met with the remaining operable containment spray subsystem. |
| | Based on the above, it can be concluded that the health and safety of the public were not affected at any time with the continuous installation of prefilters in the RCFC. |
| | This event is not deemed reportable as per the requirements of 10 CFR 50.73, or of any operation or condition prohibited by St. Lucie Plant's Technical Specifications. However, this report is being submitted for informational purposes. |
| | CORRECTIVE ACTIONS: |
| | : 1. St. Lucie Unit Two's RCFC system Technical Manual explicitly states that the prefilter media should be removed prior to power operation. |
| | An inspection of Unit Two's RCFC on 15 July confirmed that all of the RCFC prefilter media was removed before the unit began power operations. |
| | : 2. Tests were run to measure the dp across each filter and cooling unit for PSL1. These test runs were made to address possible operability concerns over a potentially high filter dp. A preliminary Engineering evaluation deter'mined that the RCFC were operable with prefilters installed during power operation. |
| | : 3. The prefilters were removed from the PSLl RCFC and will not be used during power operations. r |
| | : 4. An Engineering safety evaluation is being performed to ,determine the environmental qualification of the filter media and the performance of these filters under postulated accident conditions. Contact with Westinghouse, Florida Filters (supplier of the filter media last used), and other material manufacturers has been established in order to assess past performance capabilities of the RCFC. |
| | NRC CORM 344A o U.S.GPO: I 988 0.824 538/ ~ 55 |
| | )8831 |
| | |
| | kllC PocM S44A V $ IIVCLEAIIAEGVLATOIIY Ibbb> |
| | T REPORT (LER) TEXT CONTINUA COMMIS'PPIIOVEO LICENSEE OMb IIO SISO&104 EXPIIIE$ . b/SIIEEI PACILITY NAME ill OOCKET IIUMSESI (SS LEll RUMSEA lbl PAGE ul YSAA SSGVCHT<AL ASM+IQH |
| | ~ NUM SA MMM 4A St. Lucie, Unit TEXT (/vere 4S444 b 14EMPSKE 444 ~ One iVIIC Asm JXA'4) (17l 0 5 0 0 0 3 3 5 p p g OF 5, PSL 1's Technical Manual on RCFC will be changed to explicitly prohibit leaving filter media on the fans during power operation. |
| | : 6. Other safety-related components were checked to verify that no other components have unanalyzed filters installed. |
| | ADDITIONAL INFORMATION: |
| | COMPONENT FAILURES None PREVIOUS SIMILAR EVENTS None MAC SOAM 444A 4 U $ GPO lbbb'0 62 ~ 'Sbb ~}} |
|
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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
gcczlERATED DISI+3UTION DEMONSTRA'gN SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR:8908220121 DOC.DATE: 89/08/14 NOTARIZED: NO DOCKET FACIL:50-335 St. Lucie Plant, Unit 1, Florida Power & Light Co. 05000335 AUTH. NAME AUTHOR AFFILIATION SNYDER,M.J. Florida Power & Light Co.
WOODY,C.O. Florida Power & Light Co.
RECIP.NAME RECIPIENT AFFILIATION R
SUBJECT:
LER 89-004-00:on 890715,containment fan cooler filters left in place during unit power operation due to IP.
W/8 ltr.
DISTRIBUTION CODE: IE22T COPIES RECEIVED:LTR ENCL / SIZE:
TITLE: 50.73/50.9 Licensee Event Report (LER), ncident Rpt, etc.
NOTES:
RECIPIENT COPIES RECIPIENT COPIES h ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD2-2 LA 1 1 PD2-2 PD 1 1 NORRIS,J 1 1 INTERNAL: ACRS MICHELSON 1 1 ACRS MOELLER 2 2 ACRS WYLIE 1 1 AEOD/DOA 1 1 AEOD/DS P/TPAB 1 1 AEOD/ROAB/DSP 2 2 DEDRO 1 1 IRM/DCTS/DAB 1 1 NRR/DEST/CEB 8H 1 1 NRR/DEST/ESB 8D 1 1 NRR/DEST/ICSB 7 1 1 NRR/DEST/MEB 9H 1 1 NRR/DEST/MTB 9H 1 1 NRR/DEST/PSB 8D 1 1 NRR/DEST/RSB 8E 1 1 NRR/DEST/SGB 8D 1 1 NRR/DLPQ/HFB 10 1 1 NRR/DLPQ/PEB 10 1 . 1 NRR/DOEA/EAB 11 1 1 PB 10 2 2 NUDOCS-ABSTRACT 1 1 REG FILE 02 1 1 RES/DSIR/EIB 1 1 GN2 ILE 01 1 1 EXTERNAL EG&G WILLIAMS SE 4 4 FORD BLDG HOY,A 1 1 L ST LOBBY WARD 1 1 LPDR 1 1 R NRC PDR 1 1 NSIC MAYS,G 1 1 NSIC MURPHY,G.A 1 1 I D
/
h FULL TEXT CONVERSION REQUIRED TOTAL NUMBER OF COPIES REQUIRED: LTTR 40 ENCL 40
P.O. Box14000, Juno Beach, FL 33408-0420
@PL AUGUSTj 14 198g L-89'-299 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. C. 20555 Gentlemen:
Re: St. Lucie Unit 1 Docket No. 50-335 Reportable Event: 89-04 Date of Event: July 15, 1989 Containment Fan Cooler Filters Left in Place During Unit Pover 0 eration Due to Inade ate Procedures The attached voluntary Licensee Event Report is being submitted to provide notification of the subject event.
Very truly yours, C. 0. Woody Acting Senior Vice President Nuclear COW/JRH/cm
'ttachments cc: Stewart D. Ebneter, Regional Administrator, Region Senior Resident Inspector, USNRC, St. Lucie Plant II, USNRC an 'f'r. Group company
NAC )erin $ 44 U.S. NUCLEAA REGULATORY COMMISSION 19 5$ 1 APPAOVEO OMB NO 2'1100104 EXPIRES 4-$ 1 BS LICENSEE EVENT REPORT ILER)
DOCKET NUMBER Ill PA FACILITY NAME 111 St. Lucie, Unit One 0500033510FO CONTAINMENT FAN COOLER FILTERS LEFT IN PLACE DURING UNIT POVER OPERATION DUE TO INADEQUATE PROCEDURES EVENT DATE ISI LER NUMBER (41 REPORT DATE 171 OTHER F ACILITIE5 INVOLVED ISI 1 4 0 Ij4 4 T I A L iACII.ITYVAMES OOCKF T NVMBERISI MONTH OAY YEAR YEAR 4VM44 I NI Mof re MOIIITH OAY YEAR N/A 0 5 0 0 0 0 7 1 5 8 9 8 4 0 00 8148 N/A 0 5 0 0 0 OPERATINO THIS REPORT IS SUBMITTED PURSUANT T 0 tHE REOUIREMENTS of 10 cf A (): Icnrce onr oi rnrNr oI mr Ioooiiinpl (11 MODE ( ~ ) 7$ .71(4) 5 20.402(oi 20.405(cl 50.7l( ~ I(2 l(ivi POWER 20 405( ~ ) Ill(il 50.$ 4(cl(ll 50.7 2( ~ ) (21( v I 7$ .7)(c)
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Voluntary LICENSEE CONTACT FOR THIS LER (12) 4AME TELEPIrONE 4VMBER AREA CODE Michael J. Snyder, Shift Technical Advisor 407 465" 3550 COMPLE'Tf ONf LINE fOA EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT 1121 MANLPAC. EPOA-ABLE 4IANVFAC. EPORTABLf CAUSE SYSTE M COMPO454T Ti,'AfR TO 4PRDS CAVSE SYSTEM COMPONENT TVRER TO herrDS SUPPLEMENTAL AEPOAT EXPECTED (141 MO47vi DAY vf AR EXPECTED SV 5 M I SS ION DATE (151 YES II'n COMP ~ rr EXPECTED SVSMrSSiOiV OATEI 4O AssTRAcT ILinvr ro repC roicrri r, roorov.i<<rrr I I'Irri<<e <<prr roke ~ trorn<<rrin I.<<nl 1141 On 15 July, 1989, while St. Lucie Unit One was shutdown, it was discovered that the Reactor Containment Fan Coolers (RCFC) had filter media in place during power operations. The RCFC filters reduce fouling of the system's cooling coils when the unit is shutdown. Filters were installed during the February 1987 refueling outage, were replaced during the July 1988 refueling outage and left installed until July, 1989. The cause of this event was due to inadequate maintenance instructions. The filters were removed, and an Engineering evaluation is being prepared to verify filter performance under accident conditions. St. Lucie Unit Two RCFC were verified to have filters removed, maintenance instructions will be revised, and other safety related components were checked for improperly installed filters. This event was determined not to be reportable under 10CFR50.72 or 50.73 and is being submitted for informational purposes.
NAC peri<< $44 19 5$ 1
NRC feIAI 388A U.S. NUCLEAR REGULATORY COMMISSION WQ I ~
LICENSEE EVE: T REPORT (LER) TEXT CONTINUATI APPROVEO OM8 NO. 3150WI04 EXPIRES: 8/31/Nl fACILITYNAME IlI OOCKET NUMSER 121 LER NUMSER 18) PAGE LSI YEAR +SI 55OVENTIAL AEVI5ION r@I NVM 58 NVM 5A St. Lucie, Unit TOIT /8'AMle NMCP 8 /59VIRE One V54 44RRMA4/H/IC hem 3/5348/ (Itl 05000335 0 2 OF DESCRIPTION OF EVENT:
On 15 July, 1989, while St. Lucie Unit One (PSLl) was shutdown for a Steam Generator (EIISIAB) tube plug replacement outage, an inspection of the Reactor Containment Fan Coolers (EIISIBK) (RCFC) showed that the prefilter media for these coolers was excessively discolored. The system Technical Manual for the RCFC implies that the prefilter media should only be used during shutdown modes of operation to reduce fouling of the cooling coils during construction or maintenance.
The prefilters were installed during the February 1987 refueling .outage and remained in place until the next refueling outage of July, 1988.
New filters installed during the July 1988 outage were left in place until July 1989. The length of time these filters were installed prompted utility personnel to initiate an operability assessment on past system performance.
CAUSE OF THE EVENT:
The cause of allowing prefilter media to remain in place during power operation was due to maintenance instructions not stating that the filter should be used only during outage periods.
ANALYSIS OF EVENT:
Technical, Specification 3/4.6.2.3 addresses the surveillance requirements and the bases for the containment cooling system. The operability of the RCFC ensures that 1) the containment air temperature will be maintained within limits during normal operation, and 2) adequate heat removal capacity is available when operated in conjunction with the Containment Spray Systems during postulated loss of coolant accident conditions. The surveillance requirements for the RCFC were met under past system performance. The bases of system operation were satisfied as follows:
- 1) Normal containment air temperature was maintained within the limits set by PSL1 Technical Specification 3/4.6.1.5. Also, the RCFC manufacturer, Westinghouse, analyzed the results of differential pressure (dp) measurements taken on each of the four cooling fans and determined that the as found filter resistance was not a problem during normal and postulated accident mode operation. The measured dp was less than the maximum dp for the recommended filters.
Therefore, the minimum airflow requirement for the RCFC was never violated under past system performance.
NRC POAM 545A 4 U S GPOI I 988 0 824 538/455 r
NRC form 388A U.S. NUCLEAR REOULATORY COMMISSION (Q4)3)
LICENSEE EVE REPORT {LER) TEXT CONTINUATIO) APPROVEO OMS NO. 3150-0104 EXPIRES: 8/3'I/88 FACILITY NAME II) DOCKET NUMBER ll) LER NUMBER IS) PACE (3)
YEAR SEOUENTIAL REVISION rPPv. NUMSER NUMSER St. Lucie, Unit One TEitT /SRSNo Cfoco/4 oqulor/ Uoo/aP/N/one////)C %%dnR 38SA'4) I IT) 0 5 0 0 0 335 0 3 OF
- 2) Section 6.2 of the PSL1 FUSAR describes the design bases and minimum requirements for containment heat removal systems. Any one of the following three subsystems will provide at least minimum heat removal capability necessary to limit and reduce the post accident containment pressure and temperature: all four containment fan coolers (100 percent capacity), either of the two containment spray trains (EIISIBE)
(100 percent capacity for each subsystem). Even assuming the worst case, no RCFC available and a single active failure in one of the two containment spray trains, the safety function of containment heat removal would have been met with the remaining operable containment spray subsystem.
Based on the above, it can be concluded that the health and safety of the public were not affected at any time with the continuous installation of prefilters in the RCFC.
This event is not deemed reportable as per the requirements of 10 CFR 50.73, or of any operation or condition prohibited by St. Lucie Plant's Technical Specifications. However, this report is being submitted for informational purposes.
CORRECTIVE ACTIONS:
- 1. St. Lucie Unit Two's RCFC system Technical Manual explicitly states that the prefilter media should be removed prior to power operation.
An inspection of Unit Two's RCFC on 15 July confirmed that all of the RCFC prefilter media was removed before the unit began power operations.
- 2. Tests were run to measure the dp across each filter and cooling unit for PSL1. These test runs were made to address possible operability concerns over a potentially high filter dp. A preliminary Engineering evaluation deter'mined that the RCFC were operable with prefilters installed during power operation.
- 3. The prefilters were removed from the PSLl RCFC and will not be used during power operations. r
- 4. An Engineering safety evaluation is being performed to ,determine the environmental qualification of the filter media and the performance of these filters under postulated accident conditions. Contact with Westinghouse, Florida Filters (supplier of the filter media last used), and other material manufacturers has been established in order to assess past performance capabilities of the RCFC.
NRC CORM 344A o U.S.GPO: I 988 0.824 538/ ~ 55
)8831
kllC PocM S44A V $ IIVCLEAIIAEGVLATOIIY Ibbb>
T REPORT (LER) TEXT CONTINUA COMMIS'PPIIOVEO LICENSEE OMb IIO SISO&104 EXPIIIE$ . b/SIIEEI PACILITY NAME ill OOCKET IIUMSESI (SS LEll RUMSEA lbl PAGE ul YSAA SSGVCHT<AL ASM+IQH
~ NUM SA MMM 4A St. Lucie, Unit TEXT (/vere 4S444 b 14EMPSKE 444 ~ One iVIIC Asm JXA'4) (17l 0 5 0 0 0 3 3 5 p p g OF 5, PSL 1's Technical Manual on RCFC will be changed to explicitly prohibit leaving filter media on the fans during power operation.
- 6. Other safety-related components were checked to verify that no other components have unanalyzed filters installed.
ADDITIONAL INFORMATION:
COMPONENT FAILURES None PREVIOUS SIMILAR EVENTS None MAC SOAM 444A 4 U $ GPO lbbb'0 62 ~ 'Sbb ~