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| {{#Wiki_filter:ACCELERATED DISIKBUTION DEMONSTRA.TION SYSTEMREGULATINFORMATION DISTRIBUTION+STEM (RIDE)ACCESSION NBR:8903220424 DOC.DATE: | | {{#Wiki_filter:ACCELERATED DISIKBUTION DEMONSTRA.TION SYSTEM REGULAT INFORMATION DISTRIBUTION+STEM (RIDE)ACCESSION NBR:8903220424 DOC.DATE: 89/03/14 NOTARIZED: |
| 89/03/14NOTARIZED: | | NO DOCKET FACIL:50-4lg Beaver Valley Power Station, Unit 2, Duquesne Light C 05000412 AUTH.NAME AUTHOR AFFILIATION NOONANFT.P. |
| NODOCKETFACIL:50-4lg BeaverValleyPowerStation,Unit2,DuquesneLightC05000412AUTH.NAMEAUTHORAFFILIATION NOONANFT.P.
| | Duquesne Light Co.RECIP.NAME RECIPIENT AFFILIATION |
| DuquesneLightCo.RECIP.NAME RECIPIENT AFFILIATION
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| ==SUBJECT:== | | ==SUBJECT:== |
| LER89-003-00:on 890212,reactor trippedduetomainfeedwater regulating valvefailure.W/890314 ltr.W/8DISTRIBUTION CODE:IE22DCOPIESRECEIVED:LTR tENCLISIZE:TITLE:50.73LicenseeEventReport(LER),IncidentRpt,etc.NOTES:LPDR 2cysTranscripts.
| | LER 89-003-00:on 890212,reactor tripped due to main feedwater regulating valve failure.W/890314 ltr.W/8 DISTRIBUTION CODE: IE22D COPIES RECEIVED:LTR t ENCL I SIZE: TITLE: 50.73 Licensee Event Report (LER), Incident Rpt, etc.NOTES:LPDR 2cys Transcripts. |
| LPDR2cysPDRDocuments.
| | LPDR 2cys PDR Documents. |
| Application forpermitrenewalfiled.05000412RECIPIENT IDCODE/NAME PDl-4LATAMFPINTERNAL: | | Application for permit renewal filed.05000412 RECIPIENT ID CODE/NAME PDl-4 LA TAMFP INTERNAL: ACRS MICHELSON ACRS WYLIE AEOD/DSP/TPAB ARM/DCTS/DAB NRR/DEST/ADE 8H NRR/DEST/CEB 8H NRR/DEST/ICSB 7 NRR/DEST/MTB 9H.NRR/DEST/RSB 8E NRR/DLPQ/HFB 10 NRR/DOEA/EAB 11 NRR/DREP/RPB 10 NUDOCS-ABSTRACT RES/DSIR/EIB RGN1 FILE 01 EXTERNAL: EGSG WILLIAMSFS H ST LOBBY WARD NRC PDR NSIC MURPHYFG.A NOTES: COPIES LTTR ENCL 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 2 2 1 1 1 1 1 1 4 4 1 1 1'1 1 2 2 RECIPIENT ID CODE/NAME PD1-4 PD ACRS MOELLER AEOD/DOA AEOD/ROAB/DSP DEDRO NRR/DEST/ADS 7E NRR/DEST/ESB 8D NRR/DEST/MEB 9H NRR/DEST/PSB 8D NRR/DEST/SGB 8D NRR/DLPQ/QAB 10 NRR/DREP/RAB 10 NRRJ3/SIB 9A REG Fjj 02 RES/DSR/FRAB FORD BLDG HOYFA LPDR NSIC MAYSFG COPIES LTTR ENCL 1 1 2 2 1 1 2 2 1 1 1 0 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 NOZE'IO ALL'RIDS" RICIPZEPIS: |
| ACRSMICHELSON ACRSWYLIEAEOD/DSP/TPAB ARM/DCTS/DAB NRR/DEST/ADE 8HNRR/DEST/CEB 8HNRR/DEST/ICSB 7NRR/DEST/MTB 9H.NRR/DEST/RSB 8ENRR/DLPQ/HFB 10NRR/DOEA/EAB 11NRR/DREP/RPB 10NUDOCS-ABSTRACT RES/DSIR/EIB RGN1FILE01EXTERNAL:
| | PIZASE HELP US IO IlEDUCE%ASTl CGKPACT IHE DCjCUNEÃZ CGÃIK)L DESKF ROC'l-37 (EXT.20079)%0 EIZKBRXS YOUR MHB HKH DISTBZBUTICN LIBTS FOR DOC(IMENIS YOU DQHFT NEED<TOTAL NUMBER OF COPIES REQUIRED: LTTR 47 ENCL 46 |
| EGSGWILLIAMSFS HSTLOBBYWARDNRCPDRNSICMURPHYFG.A NOTES:COPIESLTTRENCL111111111111111111111111112211111144111'1122RECIPIENT IDCODE/NAME PD1-4PDACRSMOELLERAEOD/DOAAEOD/ROAB/DSP DEDRONRR/DEST/ADS 7ENRR/DEST/ESB 8DNRR/DEST/MEB 9HNRR/DEST/PSB 8DNRR/DEST/SGB 8DNRR/DLPQ/QAB 10NRR/DREP/RAB 10NRRJ3/SIB9AREGFjj02RES/DSR/FRAB FORDBLDGHOYFALPDRNSICMAYSFGCOPIESLTTRENCL112211221110111111111111111111111111NOZE'IOALL'RIDS"RICIPZEPIS:
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| PIZASEHELPUSIOIlEDUCE%ASTlCGKPACTIHEDCjCUNEÃZ CGÃIK)LDESKFROC'l-37(EXT.20079)%0EIZKBRXSYOURMHBHKHDISTBZBUTICN LIBTSFORDOC(IMENIS YOUDQHFTNEED<TOTALNUMBEROFCOPIESREQUIRED:
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| LTTR47ENCL46
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| NRCForm388(9.83)I(LICENSEEEVENTREPORTILER)U.S.NUCLEARREGULATORY COMMISSION APPROVEOOMBNO.31504104EXPIRES:8/31/88FACILITYNAMEIIITITLE(4)ReactorTripDuetoMainFeedwater Regulating ValveFailureDOCKETNUMBER(2)05000PAGE3/1OF0FVENTDATE(5)LERNUMBER(5)REPORTDATEI7)OTHERFACILI'TIFS INVOLVED(8)MONTHOAYYEARYEARSEGVENTIAL NVMSEAyh'.REVISION'AiNUMBERMONTHOAYYEARFACILITYNAMESDOCKETNUMBER(s) 0500021289890030003489N/A05000OPERATING MODE(SIPOWERLEYELP55(10)5?'PNryr'Q?y r'rc'yvynHXrg?e"@.gp.'0.402(bl 20.405(el(I i(i)20.405(el(1)(ii)20.405(eI)II(ii))20.405(~l(l)IIv)20.405(~l(1)(vl20A05(cl50.35(cl(II 50.35IcI(2)5073(el(2)li)d0.73(~l(2)(i/I50.73(e)(2I(iii)LICENSEECONTACTFORTHISLER(12)50.73(e)(2)(iv)50.73(~)(2)(v)50,73(~)(21(viil50.73(~)(2)(wii)IAI 50.73(~)12)(wii)IBI 50.73(~)(2)(rrl0THEREOUIREMENTS OF10CFR(I:/CheckoneormorcOItncIoliowrnP/
| | NRC Form 388 (9.83)I(LICENSEE EVENT REPORT ILER)U.S.NUCLEAR REGULATORY COMMISSION APPROVEO OMB NO.31504104 EXPIRES: 8/31/88 F AC I LIT Y N A ME I I I TITLE (4)Reactor Trip Due to Main Feedwater Regulating Valve Failure DOCKET NUMBER (2)0 5 0 0 0 PAGE 3/1 OF 0 FVENT DATE (5)LER NUMBER (5)REPORT DATE I7)OTHER FACILI'TIFS INVOLVED (8)MONTH OAY YEAR YEAR SEGVENTIAL NVMSEA yh'.REVISION'Ai NUMBER MONTH OAY YEAR FACILITY NAMES DOCKET NUMBER(s)0 5 0 0 0 212 89 89 003 0 0 03 4 89 N/A 0 5 0 0 0 OPERATING MODE (SI POWE R LEYEL P 5 5 (10)5?'PNryr'Q?y r'rc'yvynHX rg?e"@.gp.'0.402(bl 20.405(el(I i(i)20.405(e l(1)(ii)20.405(e I)I I (ii))20.405(~l(l)I Iv)20.405(~l(1)(vl 20A05(cl 50.35(cl(II 50.35 Ic I (2)50 73(el(2)li)d0.73(~l(2)(i/I 50.73(e)(2 I (iii)LICENSEE CONTACT FOR THIS LER (12)50.73(e)(2)(iv)50.73(~)(2)(v)50,73(~)(21(viil 50.73(~)(2)(wii)IAI 50.73(~)12)(wii)IBI 50.73(~)(2)(rrl 0 THE REOUIREMENTS OF 10 CFR (I:/Check one or morc OI tnc IoliowrnP/ |
| (11)THISREPORTISSUBMITTED PURSUANTT73.71(b)73.71IclOTHER/SpetiryInAprrreCtoe/owenriinTert,NIICForm366AINAMEMr.ThomasP.Noonan,PlantManagerTELEPHONE NUMBERAREACODE412643-125COMPLETEONELINEFOREACHCOMPONENT FAILUREOESCRIBEO INTHISREPORT(13)CAUSESYSTEMCOMPONENT MANUFAC.TURERREPORTABLE pCAUSESYSTEMCOMPONENT MANVFAC.TVRERXJBFCVC635Y$P:,"'''.'SVPPLEMEN1'AL REPORTEXPECTFD(14)YES//Iycr,comp/etcEXPECTEDSU84IISSIOIY DATE/ABSTRACTILimrtto/400rpeccr./c,,epprovimeteiy | | (11)THIS REPORT IS SUBMITTED PURSUANT T 73.71(b)73.71Icl OTHER/Spetiry In AprrreCt oe/ow enriin Tert, NIIC Form 366AI NAME Mr.Thomas P.Noonan, Plant Manager TELEPHONE NUMBER AREA CODE 41 264 3-1 25 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE OESCRIBEO IN THIS REPORT (13)CAUSE SYSTEM COMPONENT MANUFAC.TURER REPORTABLE p CAUSE SYSTEM COMPONENT MANVFAC.TVRER X JB FCV C63 5 Y$P:,"'''.'SVPPLEMEN1'AL REPORT EXPECTFD (14)YES//I ycr, comp/etc EXPECTED SU84IISSIOIY DATE/ABSTRACT ILimrt to/400 rpeccr./c,, epprovimeteiy |
| /i/teenr/npletortetyPcwrinen | | /i/teen r/nple torte tyPcwrinen |
| /inn/l(d)EXPECTEDSU8MISSI0NDATE(15IMONTHOAYYEARNRCForm358(983)On2/12/89,withtheUnitinPowerOperation, apowerreduction from904reactorpowerto50%reactorpowerwasinprogressaspartofEndofCoreLifeprograms. | | /inn/l(d)EXPECTED SU 8 M I SS I 0 N DATE (15I MONTH OAY YEAR NRC Form 358 (9 83)On 2/12/89, with the Unit in Power Operation, a power reduction from 904 reactor power to 50%reactor power was in progress as part of End of Core Life programs.At 0048 hours, operators noticed erratic operation of the"C" Main Feedwater Regulating Valve (MFRV).The operators placed the"C" MFRV in manual to control steam generator level.At 0108 hours at approximately 55~reactor power, the"A" Main Feedwater Pump was shutdown to reduce the pressure differential across the valve allowing easier valve movement and control.At 0120 hours, a turbine trip/reactor trip occurred due to a high water level in the"C" steam generator. |
| At0048hours,operators noticederraticoperation ofthe"C"MainFeedwater Regulating Valve(MFRV).Theoperators placedthe"C"MFRVinmanualtocontrolsteamgenerator level.At0108hoursatapproximately 55~reactorpower,the"A"MainFeedwater Pumpwasshutdowntoreducethepressuredifferential acrossthevalveallowingeasiervalvemovementandcontrol.At0120hours,aturbinetrip/reactor tripoccurredduetoahighwaterlevelinthe"C"steamgenerator.
| | The operators stabilized the plant in Hot Shutdown utilizing the Emergency Operating Procedures. |
| Theoperators stabilized theplantinHotShutdownutilizing theEmergency Operating Procedures.
| | The HC" MFRV was found to have sheared anti-rotation pins and the stem detached from the valve plug.The cause for the valve failure was attributed to hydraulic forces and vibration acting over time.The MFRVs were all disassembled, inspected and repaired as necessary. |
| TheHC"MFRVwasfoundtohaveshearedanti-rotation pinsandthestemdetachedfromthevalveplug.Thecauseforthevalvefailurewasattributed tohydraulic forcesandvibration actingovertime.TheMFRVswerealldisassembled, inspected andrepairedasnecessary.
| | This event was reported to the Nuclear Regulatory Commission at 0300 hours, in accordance with 10CFR50.72.b.2.ii. |
| ThiseventwasreportedtotheNuclearRegulatory Commission at0300hours,inaccordance with10CFR50.72.b.2.ii.
| | There were no safety implications to the public as a result of this event.This type of event has previously been analyzed as stated in the Updated Final Safety Analysis Report, Section 15.1.2,"Feedwater System Malfunctions Causing an Increase In Feedwater Flow".8903220424 8903i4$)PDR ADOCK 05000412 S PNU |
| Therewerenosafetyimplications tothepublicasaresultofthisevent.Thistypeofeventhaspreviously beenanalyzedasstatedintheUpdatedFinalSafetyAnalysisReport,Section15.1.2,"Feedwater SystemMalfunctions CausinganIncreaseInFeedwater Flow".8903220424 8903i4$)PDRADOCK05000412SPNU
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| NRCForm3SSA(943)LICENSEEEENTREPORTILER)TEXTCONTINUATION U.S.NUCLEARRFOULATORY COMMISSION APPROVEDOMBNO.3150-CI04 EXPIRES:8/3)/88FACILITYNAME<<IDOCKETNUMBER)2ILERNUMBER)8)i+:SEQUENTIAL SFINUMS8rrRFVISIONNUMBERPAGE)3)BeaverValleyPowerStation,Unit2ppppp412TEXT///rrroro H>>co/rroqo/rod.
| | NRC Form 3SSA (943)LICENSEE E ENT REPORT ILER)TEXT CONTINUATION U.S.NUCLEAR RFOULATORY COMMISSION APPROVED OMB NO.3150-CI04 EXPIRES: 8/3)/88 FACILITY NAME<<I DOCKET NUMBER)2I LER NUMBER)8)i+: SEQUENTIAL SFI NUMS 8 rr RFVISION NUMBER PAGE)3)Beaver Valley Power Station, Unit 2 p p p p p 4 1 2 TEXT///rrroro H>>co/r roqo/rod.o>>odd/I/orM/HRC Form36548l |
| o>>odd/I/orM/HRC Form36548l | | <<7) 8 9 0 0 3 00 02 QF 0 4 DESCRIPTION On 2/12/89, with the Unit in Power Operation (Operating Mode 1), Operations personnel were reducing reactor power from 90% to 50< as part of End of Core Life programs. Prior to the Operating crew assuming the shift at 2300 hours on 2/11/89, the<<B<< Main Feedwater Regulating Valve (MFRV) had previously exhibited erratic valve control for steam generator water level.The<<B<< MFRV was in the automatic mode, however, the valve was not controlling smoothly. At 0048 hours, operators noticed erratic operation of the<<C<<MFRV. At 0108 hours, at approximately 554 power, the<<A<< Main Feedwater Pump was shutdown. At 0120 hours, the water level in the<<C<< steam generator increased to the high-high level setpoint (75%)causing. a turbine trip and feedwater isolation signal. The turbine trip caused a reactor trip, since reactor power was above the trip permissive of 49'. The feedwater isolation signal caused the following actions to occur: 1) trip of the running main feedwater pump, 2)auto-start of the auxiliary feedwater pumps, and 3) closure of the main feedwater regulating valves and bypass valves.Following the reactor trip, the operators utilized the Emergency Operating Procedures (E-0" Reactor Trip or Safety Injection<< |
| <<7)890030002QF04DESCRIPTION On2/12/89,withtheUnitinPowerOperation (Operating Mode1),Operations personnel werereducingreactorpowerfrom90%to50<aspartofEndofCoreLifeprograms. | | and ES-0.1"Reactor Trip Response")to stabilize the plant in Hot Standby (Operating Mode 3).APPARENT CAUSE OF THE EVENT The cause for this event was attributed to the failure of the<<C<<Main.Feedwater Regulating Valve (2FHS*FCV498). |
| PriortotheOperating crewassumingtheshiftat2300hourson2/11/89,the<<B<<MainFeedwater Regulating Valve(MFRV)hadpreviously exhibited erraticvalvecontrolforsteamgenerator waterlevel.The<<B<<MFRVwasintheautomatic mode,however,thevalvewasnotcontrolling smoothly.
| | This valve is a Copes-Vulcan, Model No.D-100-160, Part No.16-FA37RG. |
| At0048hours,operators noticederraticoperation ofthe<<C<<MFRV. At0108hours, atapproximately 554power,the<<A<< MainFeedwater Pumpwasshutdown. | | The valve failure was attributed to the hydraulic forces and vibration, which over time, mechanically excite the valve, damaging the anti-rotation cage slots, plug guides, retaining pins and valve stem.The<<B<<Main Feedwater Regulating Valve was found to have damaged anti-rotation pins.Nr)C FORM 300A IS 83)'U.S~CPCI)988-33<')09 000)0 |
| At0120hours,thewaterlevelinthe<<C<<steamgenerator increased tothehigh-high levelsetpoint(75%)causing.aturbinetripandfeedwater isolation signal.Theturbinetripcausedareactortrip,sincereactorpowerwasabovethetrippermissive of49'.Thefeedwater isolation signalcausedthefollowing actionstooccur:1)tripoftherunningmainfeedwater pump,2)auto-start oftheauxiliary feedwater pumps,and3)closureofthemainfeedwater regulating valvesandbypassvalves.Following thereactortrip,theoperators utilizedtheEmergency Operating Procedures (E-0"ReactorTriporSafetyInjection<<
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| andES-0.1"ReactorTripResponse"
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| )tostabilize theplantinHotStandby(Operating Mode3).APPARENTCAUSEOFTHEEVENTThecauseforthiseventwasattributed tothefailureofthe<<C<<Main.Feedwater Regulating Valve(2FHS*FCV498). | |
| ThisvalveisaCopes-Vulcan, ModelNo.D-100-160, PartNo.16-FA37RG.
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| Thevalvefailurewasattributed tothehydraulic forcesandvibration, whichovertime,mechanically excitethevalve,damagingtheanti-rotation cageslots,plugguides,retaining pinsandvalvestem.The<<B<<MainFeedwater Regulating Valvewasfoundtohavedamagedanti-rotation pins.Nr)CFORM300AIS83)'U.S~CPCI)988-33<'
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| NRCForm366A194)3)LICENSEEENTREPORT(LERITEXTCONTINUAONU.S.NUCLEARREGULATORY COMMISSION APPROVEDOMBNO.3160&)04EXPIRES:8/31/88FACILITYNAME(1)DOCKETNUMBER(2)YEARLERNUMBER(6)SEQUENTIAL
| | NRC Form 366A 194)3)LICENSEE ENT REPORT (LERI TEXT CONTINUA ON U.S.NUCLEAR REGULATORY COMMISSION APPROVED OMB NO.3160&)04 EXPIRES: 8/31/88 FACILITY NAME (1)DOCKET NUMBER (2)YEAR LER NUMBER (6)SEQUENTIAL |
| +"'2REVISIONNVM8ER):.1NUMSSRPAGE(3)BeaverValleyPowerStation,Unit2osooo41289TEXT/lfmorospinto/4rtr)o/rod, ototddr)/ono/IVRC Form3664'4/OS)0030003oF04CORRECTIVE ACTIONSThefollowing corrective actionsweretakenasaresultofthisevent:Immediate: | | +"'2 REVISION NVM8ER):.1 NUMSSR PAGE (3)Beaver Valley Power Station, Unit 2 o s o o o 4 1 2 8 9 TEXT/lf moro spinto/4 rtr)o/rod, oto tddr)/ono/IVRC Form 3664'4/OS)0 0 3 0 0 03oF 0 4 CORRECTIVE ACTIONS The following corrective actions were taken as a result of this event: Immediate: |
| 1).Operations personnel utilizedtheEmergency Operating Procedures tostabilize theplantinHotStandby.2).Themainfeedwater regulating valvesweredisassembled andinspected. | | 1).Operations personnel utilized the Emergency Operating Procedures to stabilize the plant in Hot Standby.2).The main feedwater regulating valves were disassembled and inspected. |
| Theanti-rotation pinswerereplacedonallmainfeedwater regulating valves.Long-term:
| | The anti-rotation pins were replaced on all main feedwater regulating valves.Long-term: |
| AnEngineering Memorandum hasbeengenerated requesting Engineering toidentifyanactuatorandvalvedesignwhichwilleliminate themainfeedwater regulating valveproblemsduetothehydraulic forcesandvibration whichovertime,progressively damagethevalves.2).Allthreesteamgenerators willbeinspected duringtheFirstRefueling Outageforpotent'ial looseobjects.SAFETYIMPLICATIONS Therewerenosafetyimplications tothepublicasaresultofthisevent.Thistypeofeventhaspreviously beenanalyzedasstatedintheUpdatedFinalSafetyAnalysisReport(UFSAR),Section15.1.2,"Feedwater SystemMalfunctions CausinganIncreaseinFeedwater Flow".Additionally, alltherequiredEngineered SafetyFeatures(ESF)systemcomponents actuatedasfollowsasaresultofthesteamgenerator high-high waterlevelcondition 1).Turbinetrip,causingareactortripbecausereactorpowerwasgreaterthantheP-9trippermissive, 2).Feedwater following:
| | An Engineering Memorandum has been generated requesting Engineering to identify an actuator and valve design which will eliminate the main feedwater regulating valve problems due to the hydraulic forces and vibration which over time, progressively damage the valves.2).All three steam generators will be inspected during the First Refueling Outage for potent'ial loose objects.SAFETY IMPLICATIONS There were no safety implications to the public as a result of this event.This type of event has previously been analyzed as stated in the Updated Final Safety Analysis Report (UFSAR), Section 15.1.2,"Feedwater System Malfunctions Causing an Increase in Feedwater Flow".Additionally, all the required Engineered Safety Features (ESF)system components actuated as follows as a result of the steam generator high-high water level condition 1).Turbine trip, causing a reactor trip because reactor power was greater than the P-9 trip permissive, 2).Feedwater following: |
| Isolation (FWI)signal,causingtheNRCFORM34OA(94)3)A).Tripoftherunningmainfeedwater pump,B).Automatic startoftheauxiliary feedwater pumps2FWE*P22, 23Aand23B),C).Closureofthemainfeedwater regulating valvesandbypassvalves.~V.S.CPOI)988-920-889 | | Isolation (FWI)signal, causing the NRC FORM 34OA (94)3)A).Trip of the running main feedwater pump, B).Automatic start of the auxiliary feedwater pumps 2FWE*P22, 23A and 23B), C).Closure of the main feedwater regulating valves and bypass valves.~V.S.CPOI)988-920-889 |
| ~OOOTO | | ~OOOTO |
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| NRCForm388A(94)3)LICENSEEENTREPORTILER)TEXTCONTINUAONV.S.NUCLEARREGULATORY COMMISSION APPROVEDOMBNO.3)50&)04EXPIRES:8/31/88FACILITYNAME(I)DOCKETNUMBER(2)LERNUMBER(8)YEARggSEOUENTIAL PP?rNUMBER.Rrr.REvrsKINNUMBERPAGE(3)8eavergallePowerStation,Unit2osooo412TEXTIIImoroZ>>oo/4re/rr/rod, IrooEdcNane/HRC
| | NRC Form 388A (94)3)LICENSEE ENT REPORT ILER)TEXT CONTINUA ON V.S.NUCLEAR REGULATORY COMMISSION APPROVED OMB NO.3)50&)04 EXPIRES: 8/31/88 FACILITY NAME (I)DOCKET NUMBER (2)LER NUMBER (8)YEAR gg SEOUENTIAL PP?r NUMBER.Rrr.REvrsKIN NUMBER PAGE (3)8eaver gal le Power Station, Unit 2 o s o o o 4 1 2 TEXT III moro Z>>oo/4 re/rr/rod, Iroo EdcNane/HRC |
| %%dmr36849/lll)890030004OF04Inaddition, theNuclearSteamSystemSupplier(NSSS)hasevaluated theutility's engineering interpretation oftheSteamGenerator Parametric LooseObjectLicensing Report(WCAP-12101), | | %%dmr 3684 9/lll)8 9 003 0 0 0 4 OF 0 4 In addition, the Nuclear Steam System Supplier (NSSS)has evaluated the utility's engineering interpretation of the Steam Generator Parametric Loose Object Licensing Report (WCAP-12101), which addressed the safety significance of the potential loose part (anti-rotation pin from 2FWS*FCV498) which could be trapped in the"C" steam generator tubesheet annulus.It was concluded that the estimated time required for the loose object to wear into a tube to the minimum allowable wall thickness, is 2.4 years.The NSSS concurred with this safety evaluation justifying continued operation of the remaining operating cycle.REPORTABI LITY This event was reported to the Nuclear Regulatory Commission at 0300 hours in accordance with 10CFR50.72.b.2.ii. |
| whichaddressed thesafetysignificance ofthepotential loosepart(anti-rotation pinfrom2FWS*FCV498) whichcouldbetrappedinthe"C"steamgenerator tubesheet annulus.Itwasconcluded thattheestimated timerequiredforthelooseobjecttowearintoatubetotheminimumallowable wallthickness, is2.4years.TheNSSSconcurred withthissafetyevaluation justifying continued operation oftheremaining operating cycle.REPORTABI LITYThiseventwasreportedtotheNuclearRegulatory Commission at0300hoursinaccordance with10CFR50.72.b.2.ii.
| | This written report is being provided in accordance with 10CFR50.73.a.2.iv, as an event involving a reactor protection system (RPS)or engineered safety fea'tures (ESF)system actuation. |
| Thiswrittenreportisbeingprovidedinaccordance with10CFR50.73.a.2.iv, asaneventinvolving areactorprotection system(RPS)orengineered safetyfea'tures (ESF)systemactuation.
| | PREVIOUS OCCURRENCES There have been no previous Licensee Event Reports issued on this type of event/equipment failure at Beaver Valley Power Station Unit 2.NRC FORM 388A l94)3)AU.S.GPOr IOSS SSB SSP I)0r)10 |
| PREVIOUSOCCURRENCES TherehavebeennopreviousLicenseeEventReportsissuedonthistypeofevent/equipment failureatBeaverValleyPowerStationUnit2.NRCFORM388Al94)3)AU.S.GPOrIOSSSSBSSPI)0r)10
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| gled~DuquesneltNuclearGroupP,O,Box4Shippingporh PA15077~TelephOne (412)393-6000March14,1989ND3SPM:0422 BeaverValleyPowerStation,UnitNo.2DocketNo.50-412,LicenseNo.NPF-73LER89-003-00 UnitedStatesNuclearRegulatory Commission DocumentControlDeskWashington, DC20555Gentlemen: | | gled~Duquesne lt Nuclear Group P,O, Box 4 Shippingporh PA 15077~TelephOne (412)393-6000 March 14, 1989 ND3SPM:0422 Beaver Valley Power Station, Unit No.2 Docket No.50-412, License No.NPF-73 LER 89-003-00 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen: |
| Inaccordance withAppendixA,BeaverValleyTechnical Specifications, thefollowing LicenseeEventReportissubmitted:
| | In accordance with Appendix A, Beaver Valley Technical Specifications, the following Licensee Event Report is submitted: |
| LER89-003-00, 10CFR50.73a.2.iv,"ReactorTripDuetoMainFeedwater Regulating ValveFailure".
| | LER 89-003-00, 10 CFR 50.73 a.2.iv,"Reactor Trip Due to Main Feedwater Regulating Valve Failure".Very truly yours, T.P.Noonan Plant Manager vhy Attachment |
| Verytrulyyours,T.P.NoonanPlantManagervhyAttachment
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| March14,1989ND3SPM'0422 PagetwoCC:Mr.WilliamT.RussellRegionalAdministrator UnitedStatesNuclearRegulatory Commission Region1475Allendale Rd.KingofPrussia,PA19406C.A.Roteck,OhioEdisonMr.PeterTam,BVPSLicensing ProjectManagerUnitedStatesNuclearRegulatory Commission Washington, DC20555J.Beall,NuclearRegulatory Commission, BVPSSeniorResidentInspector Mr.AlexTimme,CAPCONuclearProjectsCoordinator ToledoEdisonINPORecordsCenterSuite15001100Circle75ParkwayAtlanta,GA30339G.E.Muckle,FactoryMutualEngineering, Pittsburgh Mr.J.N.Steinmetz, Operating PlantProjectsManagerMidAtlanticAreaWestinghouse ElectricCorporation EnergySystemsServiceDivisionBox355Pittsburgh, PA15230AmericanNuclearInsurersc/oDottieSherman,ANILibraryTheExchangeSuite245270Farmington AvenueFarmington, CT06032Mr.RichardJanatiDepartment ofEnvironmental Resources P.O.Box206316thFloor,FultonBuilding*Harrisburg, PA17120Director, SafetyEvaluation
| | March 14, 1989 ND3SPM'0422 Page two CC: Mr.William T.Russell Regional Administrator United States Nuclear Regulatory Commission Region 1 475 Allendale Rd.King of Prussia, PA 19406 C.A.Roteck, Ohio Edison Mr.Peter Tam, BVPS Licensing Project Manager United States Nuclear Regulatory Commission Washington, DC 20555 J.Beall, Nuclear Regulatory Commission, BVPS Senior Resident Inspector Mr.Alex Timme, CAPCO Nuclear Projects Coordinator Toledo Edison INPO Records Center Suite 1500 1100 Circle 75 Parkway Atlanta, GA 30339 G.E.Muckle, Factory Mutual Engineering, Pittsburgh Mr.J.N.Steinmetz, Operating Plant Projects Manager Mid Atlantic Area Westinghouse Electric Corporation Energy Systems Service Division Box 355 Pittsburgh, PA 15230 American Nuclear Insurers c/o Dottie Sherman, ANI Library The Exchange Suite 245 270 Farmington Avenue Farmington, CT 06032 Mr.Richard Janati Department of Environmental Resources P.O.Box 2063 16th Floor, Fulton Building*Harrisburg, PA 17120 Director, Safety Evaluation |
| &ControlVirginiaElectric6PowerCo.P.O.Box26666OneJamesRiverPlazaRichmond, VA23261 | | &Control Virginia Electric 6 Power Co.P.O.Box 26666 One James River Plaza Richmond, VA 23261 |
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Category:LICENSEE EVENT REPORT (SEE ALSO AO
MONTHYEARML20029D6571994-05-0606 May 1994
LER 94-005-00:on 940407,chain Locking Mechanism on CP Suction Isolation Valve,Was Found Broken.Caused by Personnel Error.Corrective Action:New Chain Placed on Valve Handwheel & Chain Locking Mechanism intacted.W/940506 Ltr
ML20029D8031994-05-0404 May 1994
LER 94-003-00:on 940404,two Flow Orifices Were Improperly Installed.Caused by Improper Installation of All Accessible Flow Orifices.Personnel Performed Procedure Ost 1.6.4 Correcting Improperly Installed orifices.W/940504 Ltr
ML20046B5481993-07-30030 July 1993
LER 93-012-00:on 930702,discovered That Hydrogen Analyzer Inoperable During Quarterly Performance of Calibration Procedure.Test Personnel Contributed to Cause of Event.Test & Calibration Procedures Will Be revised.W/930730 Ltr
ML20045J1201993-07-19019 July 1993
LER 93-011-00:on 930619,ESF Actuation Letdown Isolation Occurred While Synchronizing Main Unit Generator.Caused by Cooldown of RCS Due to Steam Demand.Plant Stabilized within Three Minutes & Pressurizer Level restored.W/930719 Ltr
ML20045G4591993-07-0808 July 1993
LER 93-010-00:on 930614,determined That TS Surveillance on SI Accumulator Samples Missed Due to Draining & Refilling Accumulators Several Times During Outage.Accumulators a & C Immediately sampled.W/930708 Ltr
ML20045F4711993-07-0202 July 1993
LER 93-009-00:on 930607,high Radiation Area Barrier Was Unlocked Due to Personnel Error.Comprehensive Confirmation Survey Performed,Personnel Interviewed & Task Force Formed. W/930702 Ltr
ML20044F1541993-05-21021 May 1993
LER 93-007-00:on 930423,discoverd That Original Piping Did Not Conform to Design Code Requirement.Caused by Design Deficiency.Headers Fitted W/Code Approved End Caps & Tested & Now Conform to Design requirements.W/930521 Ltr
ML20044F1521993-05-21021 May 1993
LER 93-008-00:on 930423,leakage Detected Through Two Check Valves in Chlorine Injection Line.Caused by Failure to Include Valves in ASME Section XI Testing Program.Check Valves Added to ASME Testing program.W/930521 Ltr
ML20044D5251993-05-14014 May 1993
LER 93-006-00:on 930415,two Operators Entered Posted Area W/O Radiation Monitoring Device & Entered Locked High Radiation Area & Left Barrier Open.Caused by Personnel Error in Judgement.Operators counseled.W/930514 Ltr
ML20024H1191991-05-15015 May 1991
LER 91-012-00:on 910415,excessive Max Operating Pressure Differential for Selected Solenoid Operated Valves Noted. Caused by Design Deficiencies.Equipment Mod Initiated to Replace Solenoid valve.W/910515 Ltr
ML20029B2541991-03-0404 March 1991
LER 91-005-00:on 910131,steam Leakage in Auxiliary Feedwater Pumproom Caused ESF Actuation.Caused by Personnel Error. Control Room Operator Closed Steam Supply Isolation Valve to Stop Steam Leaking & Event Will Be reviewed.W/910304 Ltr
ML17286B2651991-02-14014 February 1991
LER 90-006-01:on 900605,containment Isolation Valves Exceeded Stroke Time Limit,Per Tech Spec 3.6.3.1.Caused by Deficient Surveillance Program.Surveillance Procedures Revised to Include Stroke Time requirements.W/910214 Ltr
ML20028H7391991-01-23023 January 1991
LER 90-007-01:on 900622,containment Entry Performed to Determine If Flanges Installed,Per Info Notice 90-019. Flanges Immediately Removed.Caused by Procedural Deficiency. Transfer Canal Draining Procedures revised.W/910123 Ltr
ML20024F7441990-12-14014 December 1990
LER 90-021-00:on 901113,ESF Actuation & Feedwater Isolation Occurred During MSIV Stroke Testing.Caused by Operator Error.Feedwater Isolation Signal Reset & Isolation Valves reopened.W/901214 Ltr
ML20024F7431990-12-14014 December 1990
LER 90-023-00:on 901114,ESF Actuation & Feedwater Isolation Occurred in Response to Opening Condenser Steam Dump Valve. Caused by Operation of Steam Dump Sys in Steam Pressure Control Mode.Signal reset.W/901214 Ltr
ML17285B4731990-07-18018 July 1990
LER 90-007-00:on 900622,refueling Cavity Drain Flanges Found to Be Installed During Operation.Caused by Deficiency in Transfer Canal Draining Procedure.Procedure Revised to Verify Removal of Flanges After Canal drained.W/900717 Ltr
ML20043G5771990-06-15015 June 1990
LER 89-017-02:on 891218,atmospheric Steam Relief Valve C Opened to Lower MSIV C.Caused by Swell Phenomena Experienced After Opening MSIV C.Feedwater Isolation Signal Reset. W/900615 Ltr
ML20043B5171990-05-23023 May 1990
LER 90-004-00:on 900423,inadvertent ESF Actuation Occurred During Safeguards Protection Sys Testing.Caused by Personnel Closing Breaker Before Resetting Safety Injection Sys Signal.Signal reset.W/900523 Ltr
ML20043B5201990-05-23023 May 1990
LER 90-005-00:on 900423,inadvertent ESF Actuation Occurred During Quench Spray Flow Switch Calibr.Caused by Error in Procedure Resulting in Installation of Two Leads on Same Terminal.Discharge Valves opened.W/900523 Ltr
ML20043A4991990-05-16016 May 1990
LER 88-005-01:on 880219,startup Feedwater Pump Started, Causing Current Surge That Actuated Overcurrent Relay for Emergency Response Facility Transformer 3B.Caused by Faulty Transformer Relay.Relay replaced.W/900516 Ltr
ML20012E6681990-03-29029 March 1990
LER 90-006-00:on 900227,plant Operation in Excess of Licensing Basis.Caused by Failure of Computer to Synchronize File Addresses in Task 3D.Heat Balance Calculations Reverified Using Data from Plant Variable Computer
ML20012C4141990-03-14014 March 1990
LER 90-002-00:on 900117,steam Generator B Channel 3 Pressure Transmitter Failed Low & Declared Inoperable.On 900119, Discovered That Channel Returned to Svc W/O Completing Required Time Response Testing on transmitter.W/900314 Ltr
ML20012C7271990-03-14014 March 1990
LER 90-002-00:on 900217,steam Generator B Channel 3 Pressure Transmitter Failed Low & Declared Inoperable.Caused by Failure to Complete Tech Spec Required post-maint Test. Post-maint Test Procedure revised.W/900314 Ltr
ML20012C0631990-03-0808 March 1990
LER 90-005-01:on 900209,defect Found in Casing of Limitorque Model HBC-1 Gear Operators,Causing Valve Motion to Cease Prematurely in Open Direction.Caused by Excess Matl on Housings.Also Reported Per Part 21.W/900308 Ltr
ML20012C0651990-03-0808 March 1990
LER 90-003-01:on 900110,determined That Recirculation Spray HX River Water Radiation Monitor Sample Line Lacked Automatic,Remote Manual or Locked Shut Containment Isolation Valve.Request for Exemption Submitted to NRC.W/900308 Ltr
ML20011F2761990-02-23023 February 1990
LER 90-004-00:on 900124:discovered That Control Rod Positions Not Recorded on Operator Logs on 890425 When Control Rod Insertion Limit Monitor & Deviation Alarm Out of Svc.Cause Not Stated.Personnel counseled.W/900223 Ltr
ML20006F2041990-02-20020 February 1990
LER 90-002-00:on 900114,120-volt Ac Inverter for Vital Bus 3 Experienced Blown Dc Input Fuse When Inverter Bypassed & Aligned to 480-volt Ac Emergency Power.Caused by Mgt Action. Administrative Guidance issued.W/900220 Ltr
ML20011E6341990-02-14014 February 1990
LER 90-005-00:on 900209,six Limitorque Corp Gear Operators, Model HBC-1,found to Contain Defect in Casting of Limit Stop Housing.Housings Machined to Remove Excess Matl.Item Reportable Per Part 21.W/900214 Ltr
ML17223A7461990-02-0909 February 1990
LER 90-003-00:on 900110,determined That Recirculation Spray HX River Water Radiation Monitor Sample Lines Lacked Automatic,Remote Manual or Locked Shut Isolation Valve. Exemption Request from GDC 57 initiated.W/900209 Ltr
ML20011E2501990-02-0606 February 1990
LER 90-001-00:on 900107,high Radiation Alarm Received on Steam Generator Blowdown (SGBD) Sample Radiation Monitor, Causing SGBD Sys Isolation.Caused by Crud Particles Swept Into Monitor.Monitor Purged & Returned to svc.W/890206 Ltr
ML20006B4031990-01-26026 January 1990
LER 89-018-01:on 891227,reactor Trip Occurred Following Initial Startup from Refueling Outage.Caused by Trip of 480 Volt Ac Feeder Breaker to Rod Drive Motor Generator Sets. Installed Spare Breaker tested.W/900126 Ltr
ML20006A8711990-01-23023 January 1990
LER 89-019-00:on 891227,discovered That Manual Reactor Trip Operating Surveillance Test Not Performed within Required Frequency Prior to Previous Reactor start-up on 891224. Caused by Inadequate start-up procedures.W/900123 Ltr
ML20006A8901990-01-23023 January 1990
LER 89-014-01:on 891101,routine Radiation Barrier Check Identified Faulty Door Locking Mechanism.Caused by Weld Latching Mechanism Plate Interfering W/Locking Action of Door.Mechanism Modified & Latch removed.W/900123 Ltr
ML20006A8721990-01-23023 January 1990
LER 89-009-01:on 890413,temporary Protection Covers Found on Five Temp Elements During Test of High Energy Line Break Temp Elements.Caused by Deficiency in Surveillance Program. Covers Immediately Removed from Temp elements.W/900123 Ltr
ML20006A8691990-01-23023 January 1990
LER 89-017-01:on 891218,feedwater Isolation ESF Actuation, Caused by Swell Phenomena Experienced After Opening of C Msiv.Feedwater Isolation Signal Reset & Restored to Prefeedwater Isolation conditions.W/900118 Ltr
ML19354E1551990-01-17017 January 1990
LER 89-017-00:on 891218,feedwater Isolation Occurred Due to Erroneous Level Transmitter Root Valve Position Indication. Operations Personnel Reset Feedwater Isolation Signal. W/900117 Ltr
ML19354E1071990-01-16016 January 1990
LER 89-016-00:on 891215 & 16,erratic Level Transmitter Behavior Caused Steam Generator B hi-hi Level Feedwater Isolation.Caused by Inner Plugs Remaining Partially Inserted After Valves Opened.Plugs Freed from seats.W/900116 Ltr
ML20005F8901990-01-12012 January 1990
LER 89-015-01:on 891213,operator Incorrectly Restored Solid State Protection Sys Generating Low Steamline Pressure Safety Injection Signal.Caused by Operator Error.Plant Restored to pre-safety Injection condition.W/900112 Ltr
ML19332F5051989-12-12012 December 1989
LER 89-013-00:on 891112,4 Kv Bus 1A Power Supply Breaker Tripped on Phase overcurrent,de-energizing Emergency Bus 1A. Caused by Incorrect Tap Setting on Overcurrrent Relay.Relay Taps Reset & Breaker replaced.W/891211 Ltr
ML20005D6631989-12-0606 December 1989
LER 89-027-00:on 891106,Train a Svc Water Pump Seal Water Supply Automatically Transferred to Backup Supply Due to Low Pressure.Caused by Seal Water Normal Supply Inadvertently Isolating While de-energizing.Manual revised.W/891206 Ltr
ML19332E4931989-12-0101 December 1989
LER 89-014-00:on 891108,routine Radiation Barrier Check Identified Faulty Door Locking Mechanism on North Door to East Valve Trench Area.Caused by Welded Latching Mechanism. Locking Mechanism modified.W/891201 Ltr
ML19332D2321989-11-20020 November 1989
LER 89-026-00:on 891020,automatic Start of Auxiliary Feedwater Pumps Caused Steam Generator Blowdown Isolation. Caused by Inadequate Communications & Radiation Monitor Setpoint.Setpoint adjusted.W/891120 Ltr
ML19325F1821989-11-0808 November 1989
LER 89-012-00:on 891010,in-core Instrumentation Guide Thimble Tubes Identified W/Degradation in Excess of 60% Wall Thickness.Caused by Mechanical Wear of Thimbles Against Reactor Vessel Internals.Tubes isolated.W/891108 Ltr
ML19327B8701989-10-31031 October 1989
LER 89-014-01:on 890506,supply Breaker to 480 Volt Essential Bus J Opened & Alternate Bus J Supply Breaker Did Not Close. Caused by Spurious Trip Due to Broken Circuit.Reset Button Returned to Normal Position & Breaker closed.W/891031 Ltr
ML19324C3741989-10-30030 October 1989
LER 88-002-01:on 880127,radiation Monitors for Control Room Deenergized,Resulting in Actuation of Control Room Emergency Bottled Air Pressurization Sys.Cause Not Determined.Pressure Transmitter to Be replaced.W/891030 Ltr
ML19327B1851989-10-20020 October 1989
LER 89-011-00:on 890920,engineering Determined That Rupture Restraint Gaps Were Opened to Greater than Original Design Analysis.Caused by Alignment Performed During Hot Functional Testing.Design Change Mod to Be performed.W/891020 Ltr
ML19325C6321989-10-10010 October 1989
LER 89-025-00:on 890910,high Temps on Steam Generators B & C Auxiliary Feedwater Lines Identified.Caused by Improper Seating of Auxiliary Feedwater Check Valves.Procedure Initiated to Verify & Correct condition.W/891010 Ltr
ML19325C8851989-09-0909 September 1989
LER 89-010-00:on 890907,UL Test Results Indicated That Horizontally Mounted Prototype Fire Dampers Failed to Comply W/Requirements of Ul Std 555-1968.Caused by Discrepancies Between as-fabricated & Required specs.W/891009 Ltr
ML18041A1891989-04-21021 April 1989
LER 89-005-00:on 890322,safety Injection Occurred Due to Low Pressurizer Pressure.Caused by Deficiencies in Safety Accumulator Check Valve Surveillance Test.Refueling Outage Calibr Procedures pre-reviewed by operators.W/890421 Ltr
ML18041A1881989-03-14014 March 1989
LER 89-003-00:on 890212,noticed Erratic Operation of Main Feedwater Regulating Valve C & Turbine Trip/Reactor Trip Occurred Due to High Water Level in Steam Generator C.Caused by Valve Vibration & Hydraulic forces.W/890314 Ltr
1994-05-06
[Table view]
Category:RO)
MONTHYEARML20029D6571994-05-0606 May 1994
LER 94-005-00:on 940407,chain Locking Mechanism on CP Suction Isolation Valve,Was Found Broken.Caused by Personnel Error.Corrective Action:New Chain Placed on Valve Handwheel & Chain Locking Mechanism intacted.W/940506 Ltr
ML20029D8031994-05-0404 May 1994
LER 94-003-00:on 940404,two Flow Orifices Were Improperly Installed.Caused by Improper Installation of All Accessible Flow Orifices.Personnel Performed Procedure Ost 1.6.4 Correcting Improperly Installed orifices.W/940504 Ltr
ML20046B5481993-07-30030 July 1993
LER 93-012-00:on 930702,discovered That Hydrogen Analyzer Inoperable During Quarterly Performance of Calibration Procedure.Test Personnel Contributed to Cause of Event.Test & Calibration Procedures Will Be revised.W/930730 Ltr
ML20045J1201993-07-19019 July 1993
LER 93-011-00:on 930619,ESF Actuation Letdown Isolation Occurred While Synchronizing Main Unit Generator.Caused by Cooldown of RCS Due to Steam Demand.Plant Stabilized within Three Minutes & Pressurizer Level restored.W/930719 Ltr
ML20045G4591993-07-0808 July 1993
LER 93-010-00:on 930614,determined That TS Surveillance on SI Accumulator Samples Missed Due to Draining & Refilling Accumulators Several Times During Outage.Accumulators a & C Immediately sampled.W/930708 Ltr
ML20045F4711993-07-0202 July 1993
LER 93-009-00:on 930607,high Radiation Area Barrier Was Unlocked Due to Personnel Error.Comprehensive Confirmation Survey Performed,Personnel Interviewed & Task Force Formed. W/930702 Ltr
ML20044F1541993-05-21021 May 1993
LER 93-007-00:on 930423,discoverd That Original Piping Did Not Conform to Design Code Requirement.Caused by Design Deficiency.Headers Fitted W/Code Approved End Caps & Tested & Now Conform to Design requirements.W/930521 Ltr
ML20044F1521993-05-21021 May 1993
LER 93-008-00:on 930423,leakage Detected Through Two Check Valves in Chlorine Injection Line.Caused by Failure to Include Valves in ASME Section XI Testing Program.Check Valves Added to ASME Testing program.W/930521 Ltr
ML20044D5251993-05-14014 May 1993
LER 93-006-00:on 930415,two Operators Entered Posted Area W/O Radiation Monitoring Device & Entered Locked High Radiation Area & Left Barrier Open.Caused by Personnel Error in Judgement.Operators counseled.W/930514 Ltr
ML20024H1191991-05-15015 May 1991
LER 91-012-00:on 910415,excessive Max Operating Pressure Differential for Selected Solenoid Operated Valves Noted. Caused by Design Deficiencies.Equipment Mod Initiated to Replace Solenoid valve.W/910515 Ltr
ML20029B2541991-03-0404 March 1991
LER 91-005-00:on 910131,steam Leakage in Auxiliary Feedwater Pumproom Caused ESF Actuation.Caused by Personnel Error. Control Room Operator Closed Steam Supply Isolation Valve to Stop Steam Leaking & Event Will Be reviewed.W/910304 Ltr
ML17286B2651991-02-14014 February 1991
LER 90-006-01:on 900605,containment Isolation Valves Exceeded Stroke Time Limit,Per Tech Spec 3.6.3.1.Caused by Deficient Surveillance Program.Surveillance Procedures Revised to Include Stroke Time requirements.W/910214 Ltr
ML20028H7391991-01-23023 January 1991
LER 90-007-01:on 900622,containment Entry Performed to Determine If Flanges Installed,Per Info Notice 90-019. Flanges Immediately Removed.Caused by Procedural Deficiency. Transfer Canal Draining Procedures revised.W/910123 Ltr
ML20024F7441990-12-14014 December 1990
LER 90-021-00:on 901113,ESF Actuation & Feedwater Isolation Occurred During MSIV Stroke Testing.Caused by Operator Error.Feedwater Isolation Signal Reset & Isolation Valves reopened.W/901214 Ltr
ML20024F7431990-12-14014 December 1990
LER 90-023-00:on 901114,ESF Actuation & Feedwater Isolation Occurred in Response to Opening Condenser Steam Dump Valve. Caused by Operation of Steam Dump Sys in Steam Pressure Control Mode.Signal reset.W/901214 Ltr
ML17285B4731990-07-18018 July 1990
LER 90-007-00:on 900622,refueling Cavity Drain Flanges Found to Be Installed During Operation.Caused by Deficiency in Transfer Canal Draining Procedure.Procedure Revised to Verify Removal of Flanges After Canal drained.W/900717 Ltr
ML20043G5771990-06-15015 June 1990
LER 89-017-02:on 891218,atmospheric Steam Relief Valve C Opened to Lower MSIV C.Caused by Swell Phenomena Experienced After Opening MSIV C.Feedwater Isolation Signal Reset. W/900615 Ltr
ML20043B5171990-05-23023 May 1990
LER 90-004-00:on 900423,inadvertent ESF Actuation Occurred During Safeguards Protection Sys Testing.Caused by Personnel Closing Breaker Before Resetting Safety Injection Sys Signal.Signal reset.W/900523 Ltr
ML20043B5201990-05-23023 May 1990
LER 90-005-00:on 900423,inadvertent ESF Actuation Occurred During Quench Spray Flow Switch Calibr.Caused by Error in Procedure Resulting in Installation of Two Leads on Same Terminal.Discharge Valves opened.W/900523 Ltr
ML20043A4991990-05-16016 May 1990
LER 88-005-01:on 880219,startup Feedwater Pump Started, Causing Current Surge That Actuated Overcurrent Relay for Emergency Response Facility Transformer 3B.Caused by Faulty Transformer Relay.Relay replaced.W/900516 Ltr
ML20012E6681990-03-29029 March 1990
LER 90-006-00:on 900227,plant Operation in Excess of Licensing Basis.Caused by Failure of Computer to Synchronize File Addresses in Task 3D.Heat Balance Calculations Reverified Using Data from Plant Variable Computer
ML20012C4141990-03-14014 March 1990
LER 90-002-00:on 900117,steam Generator B Channel 3 Pressure Transmitter Failed Low & Declared Inoperable.On 900119, Discovered That Channel Returned to Svc W/O Completing Required Time Response Testing on transmitter.W/900314 Ltr
ML20012C7271990-03-14014 March 1990
LER 90-002-00:on 900217,steam Generator B Channel 3 Pressure Transmitter Failed Low & Declared Inoperable.Caused by Failure to Complete Tech Spec Required post-maint Test. Post-maint Test Procedure revised.W/900314 Ltr
ML20012C0631990-03-0808 March 1990
LER 90-005-01:on 900209,defect Found in Casing of Limitorque Model HBC-1 Gear Operators,Causing Valve Motion to Cease Prematurely in Open Direction.Caused by Excess Matl on Housings.Also Reported Per Part 21.W/900308 Ltr
ML20012C0651990-03-0808 March 1990
LER 90-003-01:on 900110,determined That Recirculation Spray HX River Water Radiation Monitor Sample Line Lacked Automatic,Remote Manual or Locked Shut Containment Isolation Valve.Request for Exemption Submitted to NRC.W/900308 Ltr
ML20011F2761990-02-23023 February 1990
LER 90-004-00:on 900124:discovered That Control Rod Positions Not Recorded on Operator Logs on 890425 When Control Rod Insertion Limit Monitor & Deviation Alarm Out of Svc.Cause Not Stated.Personnel counseled.W/900223 Ltr
ML20006F2041990-02-20020 February 1990
LER 90-002-00:on 900114,120-volt Ac Inverter for Vital Bus 3 Experienced Blown Dc Input Fuse When Inverter Bypassed & Aligned to 480-volt Ac Emergency Power.Caused by Mgt Action. Administrative Guidance issued.W/900220 Ltr
ML20011E6341990-02-14014 February 1990
LER 90-005-00:on 900209,six Limitorque Corp Gear Operators, Model HBC-1,found to Contain Defect in Casting of Limit Stop Housing.Housings Machined to Remove Excess Matl.Item Reportable Per Part 21.W/900214 Ltr
ML17223A7461990-02-0909 February 1990
LER 90-003-00:on 900110,determined That Recirculation Spray HX River Water Radiation Monitor Sample Lines Lacked Automatic,Remote Manual or Locked Shut Isolation Valve. Exemption Request from GDC 57 initiated.W/900209 Ltr
ML20011E2501990-02-0606 February 1990
LER 90-001-00:on 900107,high Radiation Alarm Received on Steam Generator Blowdown (SGBD) Sample Radiation Monitor, Causing SGBD Sys Isolation.Caused by Crud Particles Swept Into Monitor.Monitor Purged & Returned to svc.W/890206 Ltr
ML20006B4031990-01-26026 January 1990
LER 89-018-01:on 891227,reactor Trip Occurred Following Initial Startup from Refueling Outage.Caused by Trip of 480 Volt Ac Feeder Breaker to Rod Drive Motor Generator Sets. Installed Spare Breaker tested.W/900126 Ltr
ML20006A8711990-01-23023 January 1990
LER 89-019-00:on 891227,discovered That Manual Reactor Trip Operating Surveillance Test Not Performed within Required Frequency Prior to Previous Reactor start-up on 891224. Caused by Inadequate start-up procedures.W/900123 Ltr
ML20006A8901990-01-23023 January 1990
LER 89-014-01:on 891101,routine Radiation Barrier Check Identified Faulty Door Locking Mechanism.Caused by Weld Latching Mechanism Plate Interfering W/Locking Action of Door.Mechanism Modified & Latch removed.W/900123 Ltr
ML20006A8721990-01-23023 January 1990
LER 89-009-01:on 890413,temporary Protection Covers Found on Five Temp Elements During Test of High Energy Line Break Temp Elements.Caused by Deficiency in Surveillance Program. Covers Immediately Removed from Temp elements.W/900123 Ltr
ML20006A8691990-01-23023 January 1990
LER 89-017-01:on 891218,feedwater Isolation ESF Actuation, Caused by Swell Phenomena Experienced After Opening of C Msiv.Feedwater Isolation Signal Reset & Restored to Prefeedwater Isolation conditions.W/900118 Ltr
ML19354E1551990-01-17017 January 1990
LER 89-017-00:on 891218,feedwater Isolation Occurred Due to Erroneous Level Transmitter Root Valve Position Indication. Operations Personnel Reset Feedwater Isolation Signal. W/900117 Ltr
ML19354E1071990-01-16016 January 1990
LER 89-016-00:on 891215 & 16,erratic Level Transmitter Behavior Caused Steam Generator B hi-hi Level Feedwater Isolation.Caused by Inner Plugs Remaining Partially Inserted After Valves Opened.Plugs Freed from seats.W/900116 Ltr
ML20005F8901990-01-12012 January 1990
LER 89-015-01:on 891213,operator Incorrectly Restored Solid State Protection Sys Generating Low Steamline Pressure Safety Injection Signal.Caused by Operator Error.Plant Restored to pre-safety Injection condition.W/900112 Ltr
ML19332F5051989-12-12012 December 1989
LER 89-013-00:on 891112,4 Kv Bus 1A Power Supply Breaker Tripped on Phase overcurrent,de-energizing Emergency Bus 1A. Caused by Incorrect Tap Setting on Overcurrrent Relay.Relay Taps Reset & Breaker replaced.W/891211 Ltr
ML20005D6631989-12-0606 December 1989
LER 89-027-00:on 891106,Train a Svc Water Pump Seal Water Supply Automatically Transferred to Backup Supply Due to Low Pressure.Caused by Seal Water Normal Supply Inadvertently Isolating While de-energizing.Manual revised.W/891206 Ltr
ML19332E4931989-12-0101 December 1989
LER 89-014-00:on 891108,routine Radiation Barrier Check Identified Faulty Door Locking Mechanism on North Door to East Valve Trench Area.Caused by Welded Latching Mechanism. Locking Mechanism modified.W/891201 Ltr
ML19332D2321989-11-20020 November 1989
LER 89-026-00:on 891020,automatic Start of Auxiliary Feedwater Pumps Caused Steam Generator Blowdown Isolation. Caused by Inadequate Communications & Radiation Monitor Setpoint.Setpoint adjusted.W/891120 Ltr
ML19325F1821989-11-0808 November 1989
LER 89-012-00:on 891010,in-core Instrumentation Guide Thimble Tubes Identified W/Degradation in Excess of 60% Wall Thickness.Caused by Mechanical Wear of Thimbles Against Reactor Vessel Internals.Tubes isolated.W/891108 Ltr
ML19327B8701989-10-31031 October 1989
LER 89-014-01:on 890506,supply Breaker to 480 Volt Essential Bus J Opened & Alternate Bus J Supply Breaker Did Not Close. Caused by Spurious Trip Due to Broken Circuit.Reset Button Returned to Normal Position & Breaker closed.W/891031 Ltr
ML19324C3741989-10-30030 October 1989
LER 88-002-01:on 880127,radiation Monitors for Control Room Deenergized,Resulting in Actuation of Control Room Emergency Bottled Air Pressurization Sys.Cause Not Determined.Pressure Transmitter to Be replaced.W/891030 Ltr
ML19327B1851989-10-20020 October 1989
LER 89-011-00:on 890920,engineering Determined That Rupture Restraint Gaps Were Opened to Greater than Original Design Analysis.Caused by Alignment Performed During Hot Functional Testing.Design Change Mod to Be performed.W/891020 Ltr
ML19325C6321989-10-10010 October 1989
LER 89-025-00:on 890910,high Temps on Steam Generators B & C Auxiliary Feedwater Lines Identified.Caused by Improper Seating of Auxiliary Feedwater Check Valves.Procedure Initiated to Verify & Correct condition.W/891010 Ltr
ML19325C8851989-09-0909 September 1989
LER 89-010-00:on 890907,UL Test Results Indicated That Horizontally Mounted Prototype Fire Dampers Failed to Comply W/Requirements of Ul Std 555-1968.Caused by Discrepancies Between as-fabricated & Required specs.W/891009 Ltr
ML18041A1891989-04-21021 April 1989
LER 89-005-00:on 890322,safety Injection Occurred Due to Low Pressurizer Pressure.Caused by Deficiencies in Safety Accumulator Check Valve Surveillance Test.Refueling Outage Calibr Procedures pre-reviewed by operators.W/890421 Ltr
ML18041A1881989-03-14014 March 1989
LER 89-003-00:on 890212,noticed Erratic Operation of Main Feedwater Regulating Valve C & Turbine Trip/Reactor Trip Occurred Due to High Water Level in Steam Generator C.Caused by Valve Vibration & Hydraulic forces.W/890314 Ltr
1994-05-06
[Table view]
Category:TEXT-SAFETY REPORT
MONTHYEARL-99-154, Monthly Operating Repts for Sept 199 for Bvps,Units 1 & 2. with1999-09-30030 September 1999
Monthly Operating Repts for Sept 199 for Bvps,Units 1 & 2. with
L-99-139, LER 99-S01-00:on 990813,uncompensated Loss of Ability to Detect within Single Intrusion Security Detection Zone Occurred.Caused by Procedure non-compliance.Involved Personnel Received Counseling Re Event.With1999-09-0202 September 1999
LER 99-S01-00:on 990813,uncompensated Loss of Ability to Detect within Single Intrusion Security Detection Zone Occurred.Caused by Procedure non-compliance.Involved Personnel Received Counseling Re Event.With
L-99-140, Monthly Operating Repts for Aug 1999 for Bvps,Units 1 & 2. with1999-08-31031 August 1999
Monthly Operating Repts for Aug 1999 for Bvps,Units 1 & 2. with
L-99-126, Monthly Operating Repts for Jul 1999 for Beaver Valley Power Station,Units 1 & 2.With1999-07-31031 July 1999
Monthly Operating Repts for Jul 1999 for Beaver Valley Power Station,Units 1 & 2.With
L-99-107, Monthly Operating Repts for June 1999 for Bvps,Units 1 & 2. with1999-06-30030 June 1999
Monthly Operating Repts for June 1999 for Bvps,Units 1 & 2. with
ML20209D9531999-06-27027 June 1999
Inservice Insp Ninety-Day Rept Bvps,Unit 2 Outage 7,Year 1999
L-99-096, Monthly Operating Repts for May 1999 for BVPS Units 1 & 2. with1999-05-31031 May 1999
Monthly Operating Repts for May 1999 for BVPS Units 1 & 2. with
L-99-078, Special Rept:On 990326,seismic Monitoring Instruments Were Declared Inoperable.Caused by Resolution of Potential TS Compliance Issue & Work Scheduling Issue.Instrumentation Was Returned to Svc Following Calibr & Declared Operable1999-05-0303 May 1999
Special Rept:On 990326,seismic Monitoring Instruments Were Declared Inoperable.Caused by Resolution of Potential TS Compliance Issue & Work Scheduling Issue.Instrumentation Was Returned to Svc Following Calibr & Declared Operable
L-99-079, Monthly Operating Repts for Apr 1999 for Beaver Valley Power Station,Units 1 & 2.With1999-04-30030 April 1999
Monthly Operating Repts for Apr 1999 for Beaver Valley Power Station,Units 1 & 2.With
ML20205L0401999-04-0909 April 1999
SER Accepting Util Relief Requests for Inservice Insp Second 10-year Interval for Beaver Valley Power Station, Unit 2
L-99-054, Special Rept:On 990320,meteorological Tower Wind Speed Sensors Were Declared Inoperable.Caused by Calibration Completed by Vendor Did Not Adequately Cover Full Operating Range of Sensors.Removed Sensors & Sent Offsite1999-04-0505 April 1999
Special Rept:On 990320,meteorological Tower Wind Speed Sensors Were Declared Inoperable.Caused by Calibration Completed by Vendor Did Not Adequately Cover Full Operating Range of Sensors.Removed Sensors & Sent Offsite
L-99-058, Monthly Operating Repts for Mar 1999 for Bvps,Units 1 & 2. with1999-03-31031 March 1999
Monthly Operating Repts for Mar 1999 for Bvps,Units 1 & 2. with
ML20196K7981999-03-25025 March 1999
Rev 4 to COLR, for Cycle 8
L-99-038, Monthly Operating Repts for Feb 1999 for Bvps,Units 1 & 2. with1999-02-28028 February 1999
Monthly Operating Repts for Feb 1999 for Bvps,Units 1 & 2. with
ML20203E1181999-02-10010 February 1999
SER Accepting Proposed Revs to Plant,Units 1 & 2 Quality Assurance Program Description
L-99-019, Special Rept:On 990120,meteorological Tower Wind Speed Sensors Declared Inoperable.Caused by Processor Card for Sensor Locked Up & Needed to Be Reset.Heater That Fit Around Shaft of Sensor Replaced1999-02-0505 February 1999
Special Rept:On 990120,meteorological Tower Wind Speed Sensors Declared Inoperable.Caused by Processor Card for Sensor Locked Up & Needed to Be Reset.Heater That Fit Around Shaft of Sensor Replaced
ML20196F7011999-01-31031 January 1999
BVPS Unit 2 Heatup & Cooldown Limit Curves During Normal Operation at 15 EFPY Using Code Case N-626
ML20203D4811999-01-31031 January 1999
Monthly Operating Repts for Jan 1999 for Bvps,Units 1 & 2, in Accordance with NRC GL 97-02.With
ML20207E6631999-01-28028 January 1999
Rev 0 to EMECH-0713-1, Operational Assessment of SG Tubing at Beaver Valley Unit 1,Cycle 13
ML20210G7041999-01-22022 January 1999
BVPS Unit 1 Facility Changes,Tests & Experiments for 980123-990122
ML20207E5861998-12-31031 December 1998
Annual Rept 1998 for Toledo Edison
ML20207E5601998-12-31031 December 1998
Annual Rept 1998 for Pennpower
ML20198B9021998-12-31031 December 1998
BVPS Unit 1 Simulator Four Yr Certification Rept for 1995-1998
ML20207E5901998-12-31031 December 1998
Dqe 1998 Annual Rept to Shareholders
ML20199C9971998-12-31031 December 1998
Monthly Operating Repts for Dec 1998 for Bvps,Units 1 & 2. with
ML20207E5521998-12-31031 December 1998
Annual Rept 1998 for Ohio Edison
ML20207E5761998-12-31031 December 1998
Annual Rept 1998 for Illuminating Co
ML20204J6751998-12-31031 December 1998
1998 Annual Rept for Dbnps,Unit 1,PNPP,Unit 1 & BVPS Units 1 & 2
ML20199F5341998-12-29029 December 1998
Safety Evaluation Granting Relief Requests 1-TYP-3-B3.140-1, 1-TYP-3-B5.70-1,1-TYP-3-RH-E-1-1,1-TYP-3-B-G-1, 1-TYP-3-APP-I-1,1-TYP-3-UT-1,1-TYP-3-N-509,1-TYP-3-N-521, 1-TYP-3-N-524,1-TYP-3-B3.120-1 & 1-TYP-3-C6.10-1
ML20198K8551998-12-21021 December 1998
SER Granting Relief Request PRR-5 for Third 10-year Inservice Testing for Beaver Valley Power Station,Unit 1
ML20198A1631998-12-0909 December 1998
SER Approving Implementation Program to Resolve USI A-46 at Facility That Has Adequately Addressed Purpose of 10CFR50.54(f) Request
L-98-229, Monthly Operating Repts for Nov 1998 for Bvps,Units 1 & 2. with1998-11-30030 November 1998
Monthly Operating Repts for Nov 1998 for Bvps,Units 1 & 2. with
ML20195J3131998-11-12012 November 1998
Safety Evaluation Granting First & Second 10-yr Interval Inservice Insp Request for Relief
L-98-210, Monthly Operating Repts for Oct 1998 for Bvps,Units 1 & 2. with1998-10-31031 October 1998
Monthly Operating Repts for Oct 1998 for Bvps,Units 1 & 2. with
ML20206G0291998-10-31031 October 1998
BVPS Unit 2 Facility Changes,Tests & Experiments for Period 971101-981031
ML20154R9121998-10-20020 October 1998
Safety Evaluation Accepting Proposed Changes to QA Program Description in Chapter 17.2 of BVPS-2 Ufsar.Proposed Changes Would Modify QA Organization to Allow Warehouse QC Inspectors to Report to Manager of Nuclear Procurement Dept
ML20154P7491998-10-19019 October 1998
SE Accepting Second ten-year Interval Inservice Insp Request for Relief RR-1-TYP-2-B5.40-1,Rev 0,for Plant, Unit 1
ML20198F7611998-10-0606 October 1998
Duquesne Light Co,Beaver Valley Power Station 1998 Emergency Preparedness Ingestion Zone Exercise, Conducted on 981006
ML20154C6711998-10-0101 October 1998
Safety Evaluation Concluding That Revised Model Identified in Dl Submittal Was Appropriate for Analysis of Installed Conduit Ampacity Limits.Determined That There Are No Outstanding Safety Concerns with Respect to Ampacity
ML20154D5001998-09-30030 September 1998
Special Rept on Overview of BVPS-1 & BVPS-2 TS Compliance Issues & Corrective Action Taken
L-98-197, Monthly Operating Repts for Sept 1998 for Beaver Valley Power Station,Units 1 & 2.With1998-09-30030 September 1998
Monthly Operating Repts for Sept 1998 for Beaver Valley Power Station,Units 1 & 2.With
ML20154E2171998-09-28028 September 1998
Follow-up Part 21 Rept Re Defect with 1200AC & 1200BC Recorders Built Under Westronics 10CFR50 App B Program. Westronics Has Notified Bvps,Ano & RBS & Is Currently Making Arrangements to Implement Design Mods
L-98-188, Special Rept:During 1998,Unit 2 SG Eddy Current exam,26 Tubes Were Improperly Encoded in SG 2RCS-SG21C During Previous Outage.Use of Independent Databases to Track New Indications Being Implemented as Preventive Measure1998-09-21021 September 1998
Special Rept:During 1998,Unit 2 SG Eddy Current exam,26 Tubes Were Improperly Encoded in SG 2RCS-SG21C During Previous Outage.Use of Independent Databases to Track New Indications Being Implemented as Preventive Measure
L-98-178, Monthly Operating Repts for Aug 1998 for Bvps,Units 1 & 2. with1998-08-31031 August 1998
Monthly Operating Repts for Aug 1998 for Bvps,Units 1 & 2. with
ML20155B5871998-08-28028 August 1998
Non-proprietary Rev 1 to 51-5001925-01, Risk Assessment for Installation of Electrosleeves at BVPS & Callaway Plant
ML20236X2351998-08-0505 August 1998
Part 21 Rept Re Defect Associated W/Westronics 1200AC & 1200BC Recorders Built Under Westronics 10CFR50,App B Program.Beaver Valley,Arkansas Nuclear One & River Bend Station Notified.Design Mod Is Being Developed
L-98-168, Monthly Operating Repts for July 1998 for Bvps,Units 1 & 21998-07-31031 July 1998
Monthly Operating Repts for July 1998 for Bvps,Units 1 & 2
L-98-157, Special Rept:On 980423,inoperability of Seismic Monitoring Instrument Noted.Caused by Obsolescence of Instrument & Inability to Obtain Necessary Spare Parts.Design Change Is Being Pursued to Obtain Replacement Product1998-07-29029 July 1998
Special Rept:On 980423,inoperability of Seismic Monitoring Instrument Noted.Caused by Obsolescence of Instrument & Inability to Obtain Necessary Spare Parts.Design Change Is Being Pursued to Obtain Replacement Product
L-98-139, Monthly Operating Repts for June 1998 for Bvps,Units 1 & 21998-06-30030 June 1998
Monthly Operating Repts for June 1998 for Bvps,Units 1 & 2
L-98-119, Monthly Operating Repts for Bvps,Units 1 & 21998-05-31031 May 1998
Monthly Operating Repts for Bvps,Units 1 & 2
1999-09-30
[Table view] |
Text
ACCELERATED DISIKBUTION DEMONSTRA.TION SYSTEM REGULAT INFORMATION DISTRIBUTION+STEM (RIDE)ACCESSION NBR:8903220424 DOC.DATE: 89/03/14 NOTARIZED:
NO DOCKET FACIL:50-4lg Beaver Valley Power Station, Unit 2, Duquesne Light C 05000412 AUTH.NAME AUTHOR AFFILIATION NOONANFT.P.
Duquesne Light Co.RECIP.NAME RECIPIENT AFFILIATION
SUBJECT:
LER 89-003-00:on 890212,reactor tripped due to main feedwater regulating valve failure.W/890314 ltr.W/8 DISTRIBUTION CODE: IE22D COPIES RECEIVED:LTR t ENCL I SIZE: TITLE: 50.73 Licensee Event Report (LER), Incident Rpt, etc.NOTES:LPDR 2cys Transcripts.
LPDR 2cys PDR Documents.
Application for permit renewal filed.05000412 RECIPIENT ID CODE/NAME PDl-4 LA TAMFP INTERNAL: ACRS MICHELSON ACRS WYLIE AEOD/DSP/TPAB ARM/DCTS/DAB NRR/DEST/ADE 8H NRR/DEST/CEB 8H NRR/DEST/ICSB 7 NRR/DEST/MTB 9H.NRR/DEST/RSB 8E NRR/DLPQ/HFB 10 NRR/DOEA/EAB 11 NRR/DREP/RPB 10 NUDOCS-ABSTRACT RES/DSIR/EIB RGN1 FILE 01 EXTERNAL: EGSG WILLIAMSFS H ST LOBBY WARD NRC PDR NSIC MURPHYFG.A NOTES: COPIES LTTR ENCL 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 2 2 1 1 1 1 1 1 4 4 1 1 1'1 1 2 2 RECIPIENT ID CODE/NAME PD1-4 PD ACRS MOELLER AEOD/DOA AEOD/ROAB/DSP DEDRO NRR/DEST/ADS 7E NRR/DEST/ESB 8D NRR/DEST/MEB 9H NRR/DEST/PSB 8D NRR/DEST/SGB 8D NRR/DLPQ/QAB 10 NRR/DREP/RAB 10 NRRJ3/SIB 9A REG Fjj 02 RES/DSR/FRAB FORD BLDG HOYFA LPDR NSIC MAYSFG COPIES LTTR ENCL 1 1 2 2 1 1 2 2 1 1 1 0 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 NOZE'IO ALL'RIDS" RICIPZEPIS:
PIZASE HELP US IO IlEDUCE%ASTl CGKPACT IHE DCjCUNEÃZ CGÃIK)L DESKF ROC'l-37 (EXT.20079)%0 EIZKBRXS YOUR MHB HKH DISTBZBUTICN LIBTS FOR DOC(IMENIS YOU DQHFT NEED<TOTAL NUMBER OF COPIES REQUIRED: LTTR 47 ENCL 46
NRC Form 388 (9.83)I(LICENSEE EVENT REPORT ILER)U.S.NUCLEAR REGULATORY COMMISSION APPROVEO OMB NO.31504104 EXPIRES: 8/31/88 F AC I LIT Y N A ME I I I TITLE (4)Reactor Trip Due to Main Feedwater Regulating Valve Failure DOCKET NUMBER (2)0 5 0 0 0 PAGE 3/1 OF 0 FVENT DATE (5)LER NUMBER (5)REPORT DATE I7)OTHER FACILI'TIFS INVOLVED (8)MONTH OAY YEAR YEAR SEGVENTIAL NVMSEA yh'.REVISION'Ai NUMBER MONTH OAY YEAR FACILITY NAMES DOCKET NUMBER(s)0 5 0 0 0 212 89 89 003 0 0 03 4 89 N/A 0 5 0 0 0 OPERATING MODE (SI POWE R LEYEL P 5 5 (10)5?'PNryr'Q?y r'rc'yvynHX rg?e"@.gp.'0.402(bl 20.405(el(I i(i)20.405(e l(1)(ii)20.405(e I)I I (ii))20.405(~l(l)I Iv)20.405(~l(1)(vl 20A05(cl 50.35(cl(II 50.35 Ic I (2)50 73(el(2)li)d0.73(~l(2)(i/I 50.73(e)(2 I (iii)LICENSEE CONTACT FOR THIS LER (12)50.73(e)(2)(iv)50.73(~)(2)(v)50,73(~)(21(viil 50.73(~)(2)(wii)IAI 50.73(~)12)(wii)IBI 50.73(~)(2)(rrl 0 THE REOUIREMENTS OF 10 CFR (I:/Check one or morc OI tnc IoliowrnP/
(11)THIS REPORT IS SUBMITTED PURSUANT T 73.71(b)73.71Icl OTHER/Spetiry In AprrreCt oe/ow enriin Tert, NIIC Form 366AI NAME Mr.Thomas P.Noonan, Plant Manager TELEPHONE NUMBER AREA CODE 41 264 3-1 25 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE OESCRIBEO IN THIS REPORT (13)CAUSE SYSTEM COMPONENT MANUFAC.TURER REPORTABLE p CAUSE SYSTEM COMPONENT MANVFAC.TVRER X JB FCV C63 5 Y$P:,".'SVPPLEMEN1'AL REPORT EXPECTFD (14)YES//I ycr, comp/etc EXPECTED SU84IISSIOIY DATE/ABSTRACT ILimrt to/400 rpeccr./c,, epprovimeteiy
/i/teen r/nple torte tyPcwrinen
/inn/l(d)EXPECTED SU 8 M I SS I 0 N DATE (15I MONTH OAY YEAR NRC Form 358 (9 83)On 2/12/89, with the Unit in Power Operation, a power reduction from 904 reactor power to 50%reactor power was in progress as part of End of Core Life programs.At 0048 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, operators noticed erratic operation of the"C" Main Feedwater Regulating Valve (MFRV).The operators placed the"C" MFRV in manual to control steam generator level.At 0108 hours0.00125 days <br />0.03 hours <br />1.785714e-4 weeks <br />4.1094e-5 months <br /> at approximately 55~reactor power, the"A" Main Feedwater Pump was shutdown to reduce the pressure differential across the valve allowing easier valve movement and control.At 0120 hours0.00139 days <br />0.0333 hours <br />1.984127e-4 weeks <br />4.566e-5 months <br />, a turbine trip/reactor trip occurred due to a high water level in the"C" steam generator.
The operators stabilized the plant in Hot Shutdown utilizing the Emergency Operating Procedures.
The HC" MFRV was found to have sheared anti-rotation pins and the stem detached from the valve plug.The cause for the valve failure was attributed to hydraulic forces and vibration acting over time.The MFRVs were all disassembled, inspected and repaired as necessary.
This event was reported to the Nuclear Regulatory Commission at 0300 hours0.00347 days <br />0.0833 hours <br />4.960317e-4 weeks <br />1.1415e-4 months <br />, in accordance with 10CFR50.72.b.2.ii.
There were no safety implications to the public as a result of this event.This type of event has previously been analyzed as stated in the Updated Final Safety Analysis Report, Section 15.1.2,"Feedwater System Malfunctions Causing an Increase In Feedwater Flow".8903220424 8903i4$)PDR ADOCK 05000412 S PNU
NRC Form 3SSA (943)LICENSEE E ENT REPORT ILER)TEXT CONTINUATION U.S.NUCLEAR RFOULATORY COMMISSION APPROVED OMB NO.3150-CI04 EXPIRES: 8/3)/88 FACILITY NAME<>co/r roqo/rod.o>>odd/I/orM/HRC Form36548l
<<7)8 9 0 0 3 00 02 QF 0 4 DESCRIPTION On 2/12/89, with the Unit in Power Operation (Operating Mode 1), Operations personnel were reducing reactor power from 90%to 50<as part of End of Core Life programs.Prior to the Operating crew assuming the shift at 2300 hours0.0266 days <br />0.639 hours <br />0.0038 weeks <br />8.7515e-4 months <br /> on 2/11/89, the<<B<<Main Feedwater Regulating Valve (MFRV)had previously exhibited erratic valve control for steam generator water level.The<<B<<MFRV was in the automatic mode, however, the valve was not controlling smoothly.At 0048 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, operators noticed erratic operation of the<<C<<MFRV.At 0108 hours0.00125 days <br />0.03 hours <br />1.785714e-4 weeks <br />4.1094e-5 months <br />, at approximately 554 power, the<<A<<Main Feedwater Pump was shutdown.At 0120 hours0.00139 days <br />0.0333 hours <br />1.984127e-4 weeks <br />4.566e-5 months <br />, the water level in the<<C<<steam generator increased to the high-high level setpoint (75%)causing.a turbine trip and feedwater isolation signal.The turbine trip caused a reactor trip, since reactor power was above the trip permissive of 49'.The feedwater isolation signal caused the following actions to occur: 1)trip of the running main feedwater pump, 2)auto-start of the auxiliary feedwater pumps, and 3)closure of the main feedwater regulating valves and bypass valves.Following the reactor trip, the operators utilized the Emergency Operating Procedures (E-0"Reactor Trip or Safety Injection<<
and ES-0.1"Reactor Trip Response")to stabilize the plant in Hot Standby (Operating Mode 3).APPARENT CAUSE OF THE EVENT The cause for this event was attributed to the failure of the<<C<<Main.Feedwater Regulating Valve (2FHS*FCV498).
This valve is a Copes-Vulcan, Model No.D-100-160, Part No.16-FA37RG.
The valve failure was attributed to the hydraulic forces and vibration, which over time, mechanically excite the valve, damaging the anti-rotation cage slots, plug guides, retaining pins and valve stem.The<<B<<Main Feedwater Regulating Valve was found to have damaged anti-rotation pins.Nr)C FORM 300A IS 83)'U.S~CPCI)988-33<')09 000)0
NRC Form 366A 194)3)LICENSEE ENT REPORT (LERI TEXT CONTINUA ON U.S.NUCLEAR REGULATORY COMMISSION APPROVED OMB NO.3160&)04 EXPIRES: 8/31/88 FACILITY NAME (1)DOCKET NUMBER (2)YEAR LER NUMBER (6)SEQUENTIAL
+"'2 REVISION NVM8ER):.1 NUMSSR PAGE (3)Beaver Valley Power Station, Unit 2 o s o o o 4 1 2 8 9 TEXT/lf moro spinto/4 rtr)o/rod, oto tddr)/ono/IVRC Form 3664'4/OS)0 0 3 0 0 03oF 0 4 CORRECTIVE ACTIONS The following corrective actions were taken as a result of this event: Immediate:
1).Operations personnel utilized the Emergency Operating Procedures to stabilize the plant in Hot Standby.2).The main feedwater regulating valves were disassembled and inspected.
The anti-rotation pins were replaced on all main feedwater regulating valves.Long-term:
An Engineering Memorandum has been generated requesting Engineering to identify an actuator and valve design which will eliminate the main feedwater regulating valve problems due to the hydraulic forces and vibration which over time, progressively damage the valves.2).All three steam generators will be inspected during the First Refueling Outage for potent'ial loose objects.SAFETY IMPLICATIONS There were no safety implications to the public as a result of this event.This type of event has previously been analyzed as stated in the Updated Final Safety Analysis Report (UFSAR), Section 15.1.2,"Feedwater System Malfunctions Causing an Increase in Feedwater Flow".Additionally, all the required Engineered Safety Features (ESF)system components actuated as follows as a result of the steam generator high-high water level condition 1).Turbine trip, causing a reactor trip because reactor power was greater than the P-9 trip permissive, 2).Feedwater following:
Isolation (FWI)signal, causing the NRC FORM 34OA (94)3)A).Trip of the running main feedwater pump, B).Automatic start of the auxiliary feedwater pumps 2FWE*P22, 23A and 23B), C).Closure of the main feedwater regulating valves and bypass valves.~V.S.CPOI)988-920-889
~OOOTO
NRC Form 388A (94)3)LICENSEE ENT REPORT ILER)TEXT CONTINUA ON V.S.NUCLEAR REGULATORY COMMISSION APPROVED OMB NO.3)50&)04 EXPIRES: 8/31/88 FACILITY NAME (I)DOCKET NUMBER (2)LER NUMBER (8)YEAR gg SEOUENTIAL PP?r NUMBER.Rrr.REvrsKIN NUMBER PAGE (3)8eaver gal le Power Station, Unit 2 o s o o o 4 1 2 TEXT III moro Z>>oo/4 re/rr/rod, Iroo EdcNane/HRC
%%dmr 3684 9/lll)8 9 003 0 0 0 4 OF 0 4 In addition, the Nuclear Steam System Supplier (NSSS)has evaluated the utility's engineering interpretation of the Steam Generator Parametric Loose Object Licensing Report (WCAP-12101), which addressed the safety significance of the potential loose part (anti-rotation pin from 2FWS*FCV498) which could be trapped in the"C" steam generator tubesheet annulus.It was concluded that the estimated time required for the loose object to wear into a tube to the minimum allowable wall thickness, is 2.4 years.The NSSS concurred with this safety evaluation justifying continued operation of the remaining operating cycle.REPORTABI LITY This event was reported to the Nuclear Regulatory Commission at 0300 hours0.00347 days <br />0.0833 hours <br />4.960317e-4 weeks <br />1.1415e-4 months <br /> in accordance with 10CFR50.72.b.2.ii.
This written report is being provided in accordance with 10CFR50.73.a.2.iv, as an event involving a reactor protection system (RPS)or engineered safety fea'tures (ESF)system actuation.
PREVIOUS OCCURRENCES There have been no previous Licensee Event Reports issued on this type of event/equipment failure at Beaver Valley Power Station Unit 2.NRC FORM 388A l94)3)AU.S.GPOr IOSS SSB SSP I)0r)10
gled~Duquesne lt Nuclear Group P,O, Box 4 Shippingporh PA 15077~TelephOne (412)393-6000 March 14, 1989 ND3SPM:0422 Beaver Valley Power Station, Unit No.2 Docket No.50-412, License No.NPF-73 LER 89-003-00 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen:
In accordance with Appendix A, Beaver Valley Technical Specifications, the following Licensee Event Report is submitted:
LER 89-003-00, 10 CFR 50.73 a.2.iv,"Reactor Trip Due to Main Feedwater Regulating Valve Failure".Very truly yours, T.P.Noonan Plant Manager vhy Attachment
March 14, 1989 ND3SPM'0422 Page two CC: Mr.William T.Russell Regional Administrator United States Nuclear Regulatory Commission Region 1 475 Allendale Rd.King of Prussia, PA 19406 C.A.Roteck, Ohio Edison Mr.Peter Tam, BVPS Licensing Project Manager United States Nuclear Regulatory Commission Washington, DC 20555 J.Beall, Nuclear Regulatory Commission, BVPS Senior Resident Inspector Mr.Alex Timme, CAPCO Nuclear Projects Coordinator Toledo Edison INPO Records Center Suite 1500 1100 Circle 75 Parkway Atlanta, GA 30339 G.E.Muckle, Factory Mutual Engineering, Pittsburgh Mr.J.N.Steinmetz, Operating Plant Projects Manager Mid Atlantic Area Westinghouse Electric Corporation Energy Systems Service Division Box 355 Pittsburgh, PA 15230 American Nuclear Insurers c/o Dottie Sherman, ANI Library The Exchange Suite 245 270 Farmington Avenue Farmington, CT 06032 Mr.Richard Janati Department of Environmental Resources P.O.Box 2063 16th Floor, Fulton Building*Harrisburg, PA 17120 Director, Safety Evaluation
&Control Virginia Electric 6 Power Co.P.O.Box 26666 One James River Plaza Richmond, VA 23261
,/