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| {{#Wiki_filter:ACCELERATED DISTRIBUTION DEMON~0TIONSYSTEMREGULATORY INFORMATION DISTRIBUTION SYSTEM(RIDS)ACCESSION NBR:9108050066 DOC.DATE: | | {{#Wiki_filter:ACCELERATED DISTRIBUTION DEMON~0 TION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)ACCESSION NBR:9108050066 DOC.DATE: 91/07/29 NOTARIZED:, NO FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1,, Rochester G AUTH.NAME AUTHOR AFFILIATION |
| 91/07/29NOTARIZED:, | |
| NOFACIL:50-244 RobertEmmetGinnaNuclearPlant,Unit1,,Rochester GAUTH.NAMEAUTHORAFFILIATION
| |
| .BACKUS,W.H. | | .BACKUS,W.H. |
| Rochester Gas&ElectricCorp.MECREDY,R.C. | | Rochester Gas&Electric Corp.MECREDY,R.C. |
| 'ochester Gas&ElectricCorp.RECIP.NAME RECIPIENT AFFILIATION DOCKET05000244II | | 'ochester Gas&Electric Corp.RECIP.NAME RECIPIENT AFFILIATION DOCKET 05000244 II |
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| ==SUBJECT:== | | ==SUBJECT:== |
| LER91-006-00:on 910629,EDG Astartedautomatically duetoapparentundervoltage signalfromBus14undervoltage monitoring sys.Rootcausenotdetermined.Bus 14energized
| | LER 91-006-00:on 910629,EDG A started automatically due to apparent undervoltage signal from Bus 14 undervoltage monitoring sys.Root cause not determined.Bus 14 energized&EDG declared operable.W/910729 ltr.DISTRIBUTION CODE: IE22T COPIES RECEIVED:LTR |
| &EDGdeclaredoperable.W/910729 ltr.DISTRIBUTION CODE:IE22TCOPIESRECEIVED:LTR | | !ENCL I SIZE: 7 TITLE: 50.73/50.9 Licensee Event Report (LER), Incident Rpt, etc.NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72). |
| !ENCLISIZE:7TITLE:50.73/50.9 LicenseeEventReport(LER),IncidentRpt,etc.NOTES:License Expdateinaccordance with10CFR2,2.109(9/19/72). | | D 05000244 A RECIPIENT ID CODE/NAME PD1-3 LA JOHNSON,A INTERNAL: ACNW AEOD/DSP/TPAB NRR/DET/ECMB 9H NRR/DLPQ/LHFB10 NRR/DOEA/OEAB NRR/DST/SELB SD NRRfDST~LBSD1 REG F~02 RGN1 FILE 01 EXTERNAL: EG&G BRYCE,J.H NRC PDR NSIC POORE,W.~7&75 Htt<w'(COPIES LTTR ENCL 1 1 1 1 2 2 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1'1 3 3 1 1 1 1 RECIPIENT ID CODE/NAME PD1-3 PD AEOD/DOA AEOD/ROAB/DSP NRR/DET/EMEB 7E NRR/DLPQ/LPEB10 NRR/DREP/PRPB11 NRR/DST/SICBSH3 NRR/DST/SRXB SE RES/DSIR/EIB L ST LOBBY WARD NSIC MURPHY,G.A NUDOCS FULL TXT'OPIES LTTR ENCL 1 1 1 1 2 2 1 1 1 1 2 2 1 1 1'1 1 1 1 1 1 1 1 D D D NOTE TO ALL"RIDS" RECIPIENTS: |
| D05000244ARECIPIENT IDCODE/NAME PD1-3LAJOHNSON,A INTERNAL:
| | PLEASE HELP US TO REDUCE WASTE!CONTACT THE DOCUMENT CONTROL DESK, ROOiv!P 1-37 (EXT.20079)TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCU5!EiiTS YOU DON'T NEED!A D D S FULL TEXT CONVERSION REQUIRED-TOTAL NUMBER OF COPIES REQUIRED: LTTR 31 ENCL 31 |
| ACNWAEOD/DSP/TPAB NRR/DET/ECMB 9HNRR/DLPQ/LHFB10 NRR/DOEA/OEAB NRR/DST/SELB SDNRRfDST~LBSD1 REGF~02RGN1FILE01EXTERNAL:
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| EG&GBRYCE,J.H NRCPDRNSICPOORE,W.~7&75Htt<w'(COPIESLTTRENCL111122111111111111111'1331111RECIPIENT IDCODE/NAME PD1-3PDAEOD/DOAAEOD/ROAB/DSP NRR/DET/EMEB 7ENRR/DLPQ/LPEB10 NRR/DREP/PRPB11 NRR/DST/SICBSH3 NRR/DST/SRXB SERES/DSIR/EIB LSTLOBBYWARDNSICMURPHY,G.A NUDOCSFULLTXT'OPIES LTTRENCL111122111122111'11111111DDDNOTETOALL"RIDS"RECIPIENTS: | |
| PLEASEHELPUSTOREDUCEWASTE!CONTACTTHEDOCUMENTCONTROLDESK,ROOiv!P1-37(EXT.20079)TOELIMINATE YOURNAMEFROMDISTRIBUTION LISTSFORDOCU5!EiiTS YOUDON'TNEED!ADDSFULLTEXTCONVERSION REQUIRED-TOTALNUMBEROFCOPIESREQUIRED:
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| LTTR31ENCL31
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| ~Oo | | ~Oo |
| )rf/rrrritiirpdtisu'ift'rrlIr'!i! | | )rf/r rrri tii r pdti su'if t'rrlIr'!i! |
| ""/I'.;,rrrtii | | ""/I'.;,rrrtii |
| ","ROCHESTER GASANDELECTRICCORPORATION ROSERTCh1ECREDYVicePresident CtnnaNucfearPrnducticrn oe'I'a','',' | | "," ROCHESTER GAS AND ELECTRIC CORPORATION ROSERTC h1ECREDY Vice President Ctnna Nucfear Prnducticrn oe'I'a','','~1th~~'r Stale., 89 EAST AVENUE, ROCHESTER N.K 14649-0001 i TELEPHONE AAEACODETIB 546 2700 July 29, 1991 I U.S.Nuclear Regulatory Commission Document Control Desk Washington,- |
| ~1th~~'rStale.,89EASTAVENUE,ROCHESTER N.K14649-0001 iTELEPHONE AAEACODETIB 5462700July29,1991IU.S.NuclearRegulatory Commission DocumentControlDeskWashington,- | | DC 20555 |
| DC20555
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| ==Subject:== | | ==Subject:== |
| LER91-006,ApparentVoltageDroponSafeguards 480VoltBus14CausesanAutomatic Startofthe"A"Emergency DieselGenerator R.E.GinnaNuclearPowerPlantDocketNo.50-244In-accordance with10CFR50.73,LicenseeEventReportSystem,item(a)(2)(iv),
| | LER 91-006, Apparent Voltage Drop on Safeguards 480 Volt Bus 14 Causes an Automatic Start of the"A" Emergency Diesel Generator R.E.Ginna Nuclear Power Plant Docket No.50-244 In-accordance with 10 CFR 50.73, Licensee Event Report System, item (a)(2)(iv),which requires a report of,"any event or condition that resulted in manual or automatic actuation of any Engineered Safety Feature (ESF),"including the Reactor Protection System (RPS)", the attached Licensee Event Report LER 91-006 is hereby submitted. |
| whichrequiresareportof,"anyeventorcondition thatresultedinmanualorautomatic actuation ofanyEngineered SafetyFeature(ESF),"including theReactorProtection System(RPS)",theattachedLicenseeEventReportLER91-006isherebysubmitted.
| | This event has in no way affected the public's health and safety.Very truly yours, Robert C.Mecr dy xc U.S.Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 Ginna USNRC Senior Resident Inspector 9 i 080s00g,(, PDR ADOCK Ort.iot)-4 i |
| Thiseventhasinnowayaffectedthepublic'shealthandsafety.Verytrulyyours,RobertC.MecrdyxcU.S.NuclearRegulatory Commission RegionI475Allendale RoadKingofPrussia,PA19406GinnaUSNRCSeniorResidentInspector 9i080s00g,(,
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| PDRADOCKOrt.iot)-4 i
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| NACtaslliIOACILICENSEEEVENTREPORT(LERIUANUOLCAAAoovLATCAocc>>se&lcw Attleovto oleoNILOINolovCAOIACO.O)te/
| | NAC tas lli IOACI LICENSEE EVENT REPORT (LERI UA NUOLCAA AoovLATCAocc>>se&lcw Attleovto oleo NIL OIN olov CAOIACO.O)te/ |
| ~$)ACILITYNA<<)OIllR.E.GinnaNuclearPower.PlantOOCACTeeveeoCAOlo6ooo244ios ApparentVoltageDmpOnSafequards 480VoltBus14CausesanAutomatic StartoftheA"EmerencDieselGenerator CVCIITCATO14Lt1NveeocA14Al)O1TOATClllOTlet1)ACILITICC INVOLVCOIOI>>OI>>T>>eOAYYCAAYCAA~COveeee>>AL | | ~$)ACILITY NA<<)O Ill R.E.Ginna Nuclear Power.Plant OOCACT eeveeoCA Ol o 6 ooo244ios Apparent Voltage Dmp On Safequards 480 Volt Bus 14 Causes an Automatic Start of the A" Emer enc Diesel Generator CVCIIT CATO 14 Lt1 NveeocA 14 Al)O1T OATC lll OTlet1)ACILITICC INVOLVCO IOI>>OI>>T>>e OAY YCAA YCAA~COveeee>>AL |
| >>eV>>l11NONTNOAYYCAA)ACIUTYMA>>elAOOCACTAve)il1140600O062991910060007299106000Otl1ATIIIOe)OOtNl~OeeCALtvlL0e~r<<jM<+d>>%wII>>". | | >>e V>>l 1 1 NON TN OAY YCAA)ACIUTY MA>>elA OOCACT Ave)i l114 0 6 0 0 O 0 629919 1 006 00072 991 0 6 0 0 0 Otl 1ATIIIO e)OOt Nl~OeeCA LtvlL 0 e~r<<jM<+d>>%wII>>". |
| TIIIC1l)01TICVO<<IITTCO
| | TIIIC 1l)01T I CVO<<IITTCO)VACVANT T CO.<<OCNI CO.<<OO le I I I I I~CO.OOO le Ill I III To.eoc 4 I I I II>>I TOAOOlellllllel ti OOC I)I II I I el Tt.eotl el NWI)IIII NMNIICI N.T CN I 0 I I O N.T C4 I It I I~I N.T$4 IICIIWl N.'I Qe I lt l(NI=N.T ONIIC llel N.TONIICI leoI N.T C4IICIleeNW |
| )VACVANTTCO.<<OCNICO.<<OOleIIIII~CO.OOOleIllIIIITo.eoc4IIIII>>ITOAOOlellllllel tiOOCI)IIIIIelTt.eotlelNWI)IIIINMNIICIN.TCNI0IION.TC4IItII~IN.T$4IICIIWlN.'IQeIltl(NI=N.TONIICllelN.TONIICI leoIN.TC4IICIleeNW | | ~O.TONI Itl Ieell ICI N.TCNIltllel o TNC 1covl1 t<<ICNTo ot Io ct 1$: lc<<eeo<<ee a oeao o)o>>Ia>>ooe)I 0 I T%7141 TC.1 141 OTlet1 li)o)OV le AAeoeee~<<o>>e<<t S Te)L<<AC l<<s LICtNCCC CONTACT)OA Till Lt1 Iltl>>A<<et Wesley H.Backus Technical Assistant to the Operations Manager AIIOA COOl TILC)leONC NVQOCA 315 24-4 446 COeetLCTC ONC LINC)01 CAC>>l CO<<e)ONCNT)AILUAC OtlC1IOCO IN TNIC Att01T lltl cAvlc CYOTC<<e coco)oNCNT e)ANv t Ac TVACA ctoATACLC.+: "ke~~+p ju>>.~'TO Ie)AOC>>Aj~Yn~k,ee>>'~Qg, CAVlt CYOTCII s'>>>>>>'eh v+v;o>>>>~(e>>Q+PP+c~p, COee)ON C NT>>ANVtAC, TUACA CV)YLC4CNTAL AttOAT CA)CCTCO Ilel'YCC III tee, e<<ee<<e>>CA)CCTCO CV)<<IICCION CATO)X NO<<ACTAAcT IL<<evl s 1)00 eoas, I eeooeoeeev>>I) |
| ~O.TONIItlIeellICIN.TCNIltllel oTNC1covl1t<<ICNTootIoct1$:lc<<eeo<<eeaoeaoo)o>>Ia>>ooe)I0IT%7141TC.1141OTlet1li)o)OVleAAeoeee~<<o>>e<<tSTe)L<<ACl<<sLICtNCCCCONTACT)OATillLt1Iltl>>A<<etWesleyH.BackusTechnical Assistant totheOperations ManagerAIIOACOOlTILC)leONC NVQOCA31524-4446COeetLCTC ONCLINC)01CAC>>lCO<<e)ONCNT | | III>>oe e<<etvvoeee Itoeeee>>I>>o |
| )AILUACOtlC1IOCO INTNICAtt01TlltlcAvlcCYOTC<<ecoco)oNCNT e)ANvtAcTVACActoATACLC | | <<esl 114 t1)CCTCO wo<<elttloN OATC Illl IIONT>>e CAY Y CAN On June 29, 1991 at 1754 EST with the reactor at approximately 98%full power, the"A" Emergency Diesel Generator started automatically due to an apparent undervoltage signal from the Bus 14 Undervoltage Monitoring System.The"A" Emergency Diesel Generator, after starting, attained proper voltage and frequency. |
| .+:"ke~~+pju>>.~'TOIe)AOC>>Aj~Yn~k,ee>>'~Qg, CAVltCYOTCIIs'>>>>>>'ehv+v;o>>>>~(e>>Q+PP+c~p, COee)ONCNT>>ANVtAC,TUACACV)YLC4CNTAL AttOATCA)CCTCOIlel'YCCIIItee,e<<ee<<e>>CA)CCTCOCV)<<IICCION CATO)XNO<<ACTAAcTIL<<evls1)00eoas,Ieeooeoeeev>>I) | | By design, it did not close into Bus 14 because Bus 14 was at its proper voltage and being fed from its normal power supply.Immediate operator action was to verify that Bus 14 was energized and that the"A" Emergency Diesel Generator was operating normally.Subsequently) the"A" Emergency Diesel Generator was stopped and realigned for auto-standby. |
| III>>oee<<etvvoeee Itoeeee>>I>>o | | The cause of the event has.not been positively determined, although off-site electrical disturbance is postulated. |
| <<esl114t1)CCTCOwo<<elttloN OATCIlllIIONT>>eCAYYCANOnJune29,1991at1754ESTwiththereactoratapproximately 98%fullpower,the"A"Emergency DieselGenerator startedautomatically duetoanapparentundervoltage signalfromtheBus14Undervoltage Monitoring System.The"A"Emergency DieselGenerator, afterstarting, attainedpropervoltageandfrequency. | | Since the cause of this event has not been positively determined at this time, we will continue to investigate for the underlying cause.Any further corrective action will depend on the re'suits of this investigation. |
| Bydesign,itdidnotcloseintoBus14becauseBus14wasatitspropervoltageandbeingfedfromitsnormalpowersupply.Immediate operatoractionwastoverifythatBus14wasenergized andthatthe"A"Emergency DieselGenerator wasoperating normally.
| | eeAC toes ON IOACI |
| Subsequently) the"A"Emergency DieselGenerator wasstoppedandrealigned forauto-standby. | |
| Thecauseoftheeventhas.notbeenpositively determined, althoughoff-siteelectrical disturbance ispostulated.
| |
| Sincethecauseofthiseventhasnotbeenpositively determined atthistime,wewillcontinuetoinvestigate fortheunderlying cause.Anyfurthercorrective actionwilldependonthere'suitsofthisinvestigation.
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| eeACtoesONIOACI
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| ~0~0 | | ~0~0 |
| ~e~H(ICFMmdddA(045)L'ICENSEE EVENTREPORTILERITEXTCONTINUATION 3U.d.HUCLCA(IHKOULATOHY COMM(dd(OH AFFHOVEOOMdHO5150M(04dkF(Added(5((55 FACILITYHAMd(IIR.E.GinnaNuclearPowerPlantTEXTIN'cccMcccHmdvckd.vccNMcckncc( | | ~e~H(IC FMm dddA (045)L'ICENSEE EVENT REPORT ILERI TEXT CONTINUATION 3 U.d.HUCLCA(I HKOULATOHY COMM(dd(OH AFFHOVEO OMd HO 5150M(04 dkF(Added(5((55 FACILITY HAMd (II R.E.Ginna Nuclear Power Plant TEXT IN'ccc Mccc H mdvckd.vcc NMcckncc(4(NC Fckm J(d(4'cl ((T(OOC((ET HUMddll (1(0 s 0 0 0 24 491 Ld(I HUMddll (dl 5~OVCHZIAL 4 HVM k-006 kdVMIOH HUM 0 FAOd (51 02 DFO 6 PRE-EVE2iT PLANT CONDITIONS The plant was at approximately 984 steady state full power with no'ajor activities in progress.II.DESCRIPTION OF%TENT A.DATES AND APPROXIMATE TIMES OP MAJOR OCCURRENCES: |
| 4(NCFckmJ(d(4'cl((T(OOC((ETHUMddll(1(0s00024491Ld(IHUMddll(dl5~OVCHZIAL4HVMk-006kdVMIOHHUM0FAOd(5102DFO6PRE-EVE2iT PLANTCONDITIONS Theplantwasatapproximately 984steadystatefullpowerwithno'ajoractivities inprogress. | | 0 0 0 June 29, 1991, 1754 EDST: Event Date and Time h June 29, 1991, 1754 EDST: Discovery Date and Time June 29, 1991, 2013 EDST: "A" Emergency Diesel Generator stopped and realigned for Auto-standby B.EVENT: On June 29, 1991 at 1754 EDST, with the reactor at approximately 98%full power, the Control Room received the following alarms: L-14 (Bus 14.Undervoltage |
| II.DESCRIPTION OF%TENTA.DATESANDAPPROXIMATE TIMESOPMAJOROCCURRENCES: | | -Safeguards) and J-24 (Emergency Diesel Gen 1A Panel).The Control Room operators immediately verified proper voltage on Bus 14 and that the normal power supply breaker was closed.The Control Room operators also verified that the"A" Emergency Diesel Generator had started and displayed proper voltage and frequency. |
| 000June29,1991,1754EDST:EventDateandTimehJune29,1991,1754EDST:Discovery DateandTimeJune29,1991,2013EDST:"A"Emergency DieselGenerator stoppedandrealigned forAuto-standby B.EVENT:OnJune29,1991at1754EDST,withthereactoratapproximately 98%fullpower,theControlRoomreceivedthefollowing alarms:L-14(Bus14.Undervoltage
| | By design, the"A" Emergency Diesel Generator did not close into Bus, 14, as the bus voltage was normal and Bus 14 was still being supplied by its normal power supply.HAC FOAM 544*(I ddl |
| -Safeguards) andJ-24(Emergency DieselGen1APanel).TheControlRoomoperators immediately verifiedpropervoltageonBus14andthatthenormalpowersupplybreakerwasclosed.TheControlRoomoperators alsoverifiedthatthe"A"Emergency DieselGenerator hadstartedanddisplayed propervoltageandfrequency. | |
| Bydesign,the"A"Emergency DieselGenerator didnotcloseintoBus,14,asthebusvoltagewasnormalandBus14wasstillbeingsuppliedbyitsnormalpowersupply.HACFOAM544*(Iddl
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| ~0 | | ~0 |
| ~0~eNRCSotw295A(042IL'ICENSEE EVENTREPORTILERITEXTCONTINUATION U.S.NUCLEARREQVLATORY COMMI55ION ASSROVEOOM9NOSISOWI04JEXSIRES,9121/99SACILITYNAME111OOCKETNVMEER121LERNVMQEII19155QUENTIAL NUMREVISIONNUMSAOEl21R.E.GinnaNuclearPowerPlantTEXTIIJ~<<>>5~N~.v>>NAS55JNJHRCFOnn2OEA'5IIITIo5ooo244,0060003pF06Subsequently, Auxiliary operators weredispatched tochecktheBus14Undervoltage Monitoring Systemcabinetsandtheoperation ofthe"A"Emergency DieselGenerator. | | ~0~e NRC Sotw 295A (042 I L'ICENSEE EVENT REPORT ILERI TEXT CONTINUATION U.S.NUCLEAR REQVLATORY COMMI55ION ASSROVEO OM9 NO SISOWI04 J EXSIRES, 9121/99 SACILITY NAME 111 OOCKET NVMEER 121 LER NVMQEII 191 55QUENTIAL NUM REVISION NUM SAOE l21 R.E.Ginna Nuclear Power Plant TEXT IIJ~<<>>5~N~.v>>NAS55JNJ HRC FOnn 2OEA'5I I ITI o 5 o o o2 44, 006 00 03pF 0 6 Subsequently, Auxiliary operators were dispatched to check the Bus 14 Undervoltage Monitoring System cabinets and the operation of the"A" Emergency Diesel Generator. |
| Theoperation ofthe"A"Emergency DieselGenerator wasfoundtobenormal.Noundervoltage triptargetswereobservedonBus14orBus18(boththesebusesarefedbythe"A"Emergency
| | The operation of the"A" Emergency Diesel Generator was found to be normal.No undervoltage trip targets were observed on Bus 14 or Bus 18 (both these buses are fed by the"A" Emergency.Diesel Generator). |
| .DieselGenerator). | | During this event, routine activities were occurring at off-site Station 204.At approximately the same time as the apparent undervoltage condition occurred on Bus 14, a 34.5 kv capacitor bank was being removed from service.This is a routine action to correct off-site voltage situations. |
| Duringthisevent,routineactivities wereoccurring atoff-siteStation204.Atapproximately thesametimeastheapparentundervoltage condition occurredonBus14,a34.5kvcapacitor bankwasbeingremovedfromservice.Thisisaroutineactiontocorrectoff-sitevoltagesituations.
| | Station 204'eeds Circuit 751, which was the normal off-site power supply to Buses 14 and 18.Control=Room operators notified higher supervision and the Nuclear Regulatory Commission of the event.To prove operability of the Undervoltage Monitoring System, the Results and Test (R&T)Department performed Periodic Test procedure PT-9.1 (Undervoltage Protection 480 Volt Safeguards Busses)on Bus 14.After PT-9.1.was successfully completed, the"A" Emergency Diesel Generator was stopped and realigned for Auto-standby. |
| Station204'eedsCircuit751,whichwasthenormaloff-sitepowersupplytoBuses14and18.Control=Roomoperators notifiedhighersupervision andtheNuclearRegulatory Commission oftheevent.Toproveoperability oftheUndervoltage Monitoring System,theResultsandTest(R&T)Department performed PeriodicTestprocedure PT-9.1(Undervoltage Protection 480VoltSafeguards Busses)onBus14.AfterPT-9.1.wassuccessfully completed, the"A"Emergency DieselGenerator wasstoppedandrealigned forAuto-standby.
| | C.INOPERABLE STRUC'HIRES, COMPONENTS s OR SYSTEMS THAT CONTRIBUTED TO THE EVENT: None.D.OTEGsR SYSTEMS OR SECONDARY PUNCTIONS AFFECTED: E.None.METHOD OP DISCOVERY: |
| C.INOPERABLE STRUC'HIRES, COMPONENTS sORSYSTEMSTHATCONTRIBUTED TOTHEEVENT:None.D.OTEGsRSYSTEMSORSECONDARY PUNCTIONS AFFECTED: | | The events were immediately apparent due to alarms and indications in the Control Room.NRC SORM 255A I94ll |
| E.None.METHODOPDISCOVERY: | |
| Theeventswereimmediately apparentduetoalarmsandindications intheControlRoom.NRCSORM255AI94ll
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| .OO | | .OO |
| <<ACSottoSSSA~eL'ICENSEE EVENTREPORT(LER)TEXTCONTINUATION V,S.<<UCLEAIIIlfOULATOIIY COMMISSIOII ASSAOYEOOMSHO3150MIOIIEXSIAES,SISIl95SACILITYNAMEIllR.E.GinnaNuclearPowerPlantTEXTillnave<<WCe<<nquseCvASOdakevWlYPCArm~'llIITIOOCKETIIUMSEII11Iosooo24LEII<<UMSEIIISI5~4UC<<VIAL'SV<<IONHUM<<'"<<UMf<<9-1-006-00~AOSISI04o~06F.OPERATORACTXON:Following theBus14Undervoltage Alarmandthe"A"Emergency DieselGenerator automatic start,theCo'ntrolRoomoperators immediately verifiedpropervoltageonBus14viathenormalpowersupplyand',thatthe"A"Emergency DieselGenerator displayed propervoltageandfrequency. | | <<AC Sotto SSSA~e L'ICENSEE EVENT REPORT (LER)TEXT CONTINUATION V,S.<<UCLEAII Ilf OULATOIIY COMMISSIOII ASSAOYEO OMS HO 3150MIOI I EXSIAES, SISI l95 SACILITY NAME Ill R.E.Ginna Nuclear Power Plant TEXT ill nave<<WCe<<nquseC vAS OdakevW lYPC Arm~'ll I ITI OOCKET IIUMSEII 11I o s o o o 2 4 LEII<<UMSEII ISI 5~4UC<<VIAL'S V<<ION HUM<<'"<<UM f<<9-1-0 06-00~AOS ISI 0 4 o~0 6 F.OPERATOR ACTXON: Following the Bus 14 Undervoltage Alarm and the"A" Emergency Diesel Generator automatic start, the Co'ntrol Room operators immediately verified proper voltage on Bus 14 via the normal power supply and',that the"A" Emergency Diesel Generator displayed proper voltage and frequency. |
| Subsequently, Auxiliary operators weredis'patched tocheck-theBus14undervoltage monitoring systemand"A"Emergency DieselGenerator operation. | | Subsequently, Auxiliary operators were dis'patched to check-the Bus 14 undervoltage monitoring system and"A" Emergency Diesel Generator operation. |
| The"A"Emergency DieselGenerator operation wasnormaland,noundervoltage triptargetswereobservedonBus14orBus18.'t"The"A"Emergency DieselGenerator wassubsequently stoppedandrealigned forAuto-standby. | | The"A" Emergency Diesel Generator operation was normal and ,no undervoltage trip targets were observed on Bus 14 or Bus 18.'t" The"A" Emergency Diesel Generator was subsequently stopped and realigned for Auto-standby. |
| G.SAFETXSXSTEMRESPONSES: | | G.SAFETX SXSTEM RESPONSES: |
| The"A"Emergency DieselGenerator automatically startedanddisplayed propervoltageandfrequency. | | The"A" Emergency Diesel Generator automatically started and displayed proper voltage and frequency. |
| 'IXI.CAUSEOFEV19Fl'.XMM1sDIATE CAUSE:Theautomatic actuation ofthe-"A"Emergency DieselGenerator wasduetoanapparentundervoltage signalfromtheBus14undervoltage monitoring system.B.ROOTCAUSE:Theunderlying, causeoftheapparentundervoltage signalfromtheBus14undervoltage monitoring systemisnotpositively determined atthistime..MACSO<<MSSSAI941l | | 'IXI.CAUSE OF EV19Fl'.XMM1sDIATE CAUSE: The automatic actuation of the-"A" Emergency Diesel Generator was due to an apparent undervoltage signal from the Bus 14 undervoltage monitoring system.B.ROOT CAUSE: The underlying, cause of the apparent undervoltage signal from the Bus 14 undervoltage monitoring system is not positively determined at this time..MAC SO<<M SSSA I941l |
| ~0 IIACSovvvv444A14451~eoeL'ICENSEE EVENTREPORT(LERITEXTCONTINUATION U,E.NUCLEAAAEOULATOAY COMMIEEIOII | | ~0 IIAC Sovvvv 444A 14451~e oe L'ICENSEE EVENT REPORT (LERI TEXT CONTINUATION U,E.NUCLEAA AEOULATOAY COMMIEEIOII |
| /ASSAOVEOOMEIVO1150MIOeEXSIAES,4151/45SACILITYIIAMEIllR.E.GinnaNuclearPawerPlantTExTlllnaveMeceaeevveevLvvMvneeevalvYACSevvnSELAYlIITICOCKETIvUMEEA111osooo244vEAALEIIIIUMEEA14154004VVTIAL~VUM006ntvlelOMVVVM00SAOEIEI050F06IV.ANALYSISOFEVENTTheeventisreportable inaccordance with10CFR50.73,LicenseeEventReportSystem,item(a)(2)(iv), | | /ASSAOVEO OME IVO 1150MIOe EXSIAES, 4151/45 SACILITY IIAME Ill R.E.Ginna Nuclear Pawer Plant TExT lll nave Mece a eevveevL vvM vneeeval vYAC Sevvn SELA Yl I ITI COCKET IvUMEEA 111 osooo244 vEAA LEII IIUMEEA 141 5 4 0 0 4 VV T I A L~VUM 0 0 6 ntvlelOM VVVM 0 0 SAOE IEI 0 50F 06 IV.ANALYSIS OF EVENT The event is reportable in accordance with 10 CFR 50.73, Licensee Event Report System, item (a)(2)(iv), which requires'eporting of,"any event or condition that resulted in manual or automatic actuation of any Engineered Safety Feature (ESF)including the Reactor.Protection System (RPS)".The starting of the"A" Emergency Diesel Generator was an automatic actuation of an ESF system.An assessment was performed considering both the safety consequences and implications of this event with the following results and conclusions: |
| whichrequires'eporting of,"anyeventorcondition thatresultedinmanualorautomatic actuation ofanyEngineered SafetyFeature(ESF)including theReactor.Protection System(RPS)".Thestartingofthe"A"Emergency DieselGenerator wasanautomatic actuation ofanESFsystem.Anassessment wasperformed considering boththesafetyconsequences andimplications ofthiseventwiththefollowing resultsandconclusions:
| | There were no operational or safety consequences or implications attributed to the starting of the"A" Emergency Diesel Generator because: 0 The"A" Emergency Diesel Generator operated as designed.o Both Bus 14 power supplies (i.e.normal and emergency) were either in use or available throughout the event.o The Bus 14 undervoltage monitoring system operation was in the conservative direction, (i.e.the operation actuated the automatic start of the"A" Emergency Diesel Generator). |
| Therewerenooperational orsafetyconsequences orimplications attributed tothestartingofthe"A"Emergency DieselGenerator because:0The"A"Emergency DieselGenerator operatedasdesigned.
| | Based on the above, it can be concluded that the public's health and safety was assured at all times.V.CORRECTIVE ACTION A.ACTION TAKEN TO RETURN AFFECTED SYSTEMS TO PRE-EVENT NORMAL STATUS: o The R&T Department successfully completed PT-9.1 on Bus 14 and the"A" Emergency Diesel Generator was stopped and aligned for Auto-standby. |
| oBothBus14powersupplies(i.e.normalandemergency) wereeitherinuseoravailable throughout theevent.oTheBus14undervoltage monitoring systemoperation wasintheconservative direction, (i.e.theoperation actuatedtheautomatic startofthe"A"Emergency DieselGenerator).
| | ~V A C S 0 VI M 544 A 14411 |
| Basedontheabove,itcanbeconcluded thatthepublic'shealthandsafetywasassuredatalltimes.V.CORRECTIVE ACTIONA.ACTIONTAKENTORETURNAFFECTEDSYSTEMSTOPRE-EVENT NORMALSTATUS:oTheR&TDepartment successfully completed PT-9.1onBus14andthe"A"Emergency DieselGenerator wasstoppedandalignedforAuto-standby.
| | ~1~0 NAC>arm SEEA I HEI~0 I.'ICENSEE EVENT REPORT (I.ER)TEXT CONTINUATION V.S.NVCLEAII IIEOVLATOIIY COMMISSION I Atf AOV EO OME HO$1$0MIOI E)CrllIES. |
| ~VACS0VIM544A14411 | | EISI4$FACILITY NAME III OOCIIET NVMEEII IEI YEAA LEII NVMEEII IEI IEQVEHTIAL 4 M IA AEV ISIO<NVM IA~ACE ISI R.E.Ginna Nuclear Power Plant TEIL ill mort apece e mewaf.wt aAkenV HAC Fiwn DELI'Il I I Tl o s o o o.24 4 9 1 006 0 006'F 0 6 B.ACTXON TAKEN OR PLANNED TO PREVENT RECURRENCE: |
| ~1~0 NAC>armSEEAIHEI~0I.'ICENSEE EVENTREPORT(I.ER)TEXTCONTINUATION V.S.NVCLEAIIIIEOVLATOIIY COMMISSION IAtfAOVEOOMEHO$1$0MIOIE)CrllIES. | | 0 0 0 As the underlying cause of the event has not been determined at this time, investigations will continue to positively determine the underlying cause of this event.Any further corrective actions will depend on the results of these investigations. |
| EISI4$FACILITYNAMEIIIOOCIIETNVMEEIIIEIYEAALEIINVMEEIIIEIIEQVEHTIAL 4MIAAEVISIO<NVMIA~ACEISIR.E.GinnaNuclearPowerPlantTEILillmortapeceemewaf.wtaAkenVHACFiwnDELI'IlIITlosooo.244910060006'F06B.ACTXONTAKENORPLANNEDTOPREVENTRECURRENCE: | | Electrical system monitoring records have been reviewed, and indicate that removal of the capacitor bank resulted in a small and routine voltage transient. |
| 000Astheunderlying causeoftheeventhasnotbeendetermined atthistime,investigations willcontinuetopositively determine theunderlying causeofthisevent.Anyfurthercorrective actionswilldependontheresultsoftheseinvestigations.
| | Electrical system monitoring has been increased on Circuit 751.0 The interface between the undervoltage monitoring system and diesel start circuitry will continue to be evaluated,'to determine if the undervoltage system is reacting as designed for small voltage fluctuations. |
| Electrical systemmonitoring recordshavebeenreviewed, andindicatethatremovalofthecapacitor bankresultedinasmallandroutinevoltagetransient. | | ADDXTXONAL XNFORMATION A.B.PAXLED COMPONENTS: |
| Electrical systemmonitoring hasbeenincreased onCircuit751.0Theinterface betweentheundervoltage monitoring systemanddieselstartcircuitry willcontinuetobeevaluated,'to determine iftheundervoltage systemisreactingasdesignedforsmallvoltagefluctuations. | | None.PREVXOUS LERs ON SIMILAR EVENTS: A similar LER event historical search was conducted with the following results: No documentation of similar LER events with an undetermined root cause at Ginna Station could be identified. |
| ADDXTXONAL XNFORMATION A.B.PAXLEDCOMPONENTS: | | C.SPECIAL COMMENTS None.%AC SOIIM SEEA ISA l |
| None.PREVXOUSLERsONSIMILAREVENTS:AsimilarLEReventhistorical searchwasconducted withthefollowing results:Nodocumentation ofsimilarLEReventswithanundetermined rootcauseatGinnaStationcouldbeidentified. | | ~0 1~f}} |
| C.SPECIALCOMMENTSNone.%ACSOIIMSEEAISAl | |
| ~01~f}} | |
Similar Documents at Ginna |
|---|
Category:LICENSEE EVENT REPORT (SEE ALSO AO
MONTHYEARML17265A7541999-09-22022 September 1999
LER 99-011-00:on 990823,small Tears Were Discovered in Flexible Duct Work Connector at Inlet of CR HVAC Sys Return Air Fan (AKF08).Caused by in-leakage Greater than That Assumed.Implemented Temporary Mod 99-029.With 990922 Ltr
ML17265A7431999-08-24024 August 1999
LER 99-004-01:on 990412,discovered That Containment Recirculation Fan Chevron Separator Vanes Were Installed Backwards.Caused by Improper Assembly by Mfg.Moisture Separator Vanes Were Dismantled & Correctly re-installed
ML17265A7181999-07-23023 July 1999
LER 99-007-01:on 990423,reactor Trip Occurred Due to Instrument & Control Technicians Inadvertently Pulling Fuses from Wrong Nuclear Instrument Channel.Setpoint Adjustments Were Completed by Different Crew of Technicians
ML17265A7081999-07-22022 July 1999
LER 98-003-02:on 980904,actuations of CR Emergency Air Treatment Sys Was Noted Due to Invalid Causes.Caused by Various Degraded Components in CR RM Sys.Creats Actuation Signal Was Reset & Normal Ventilation Was Restored
ML17265A7031999-07-19019 July 1999
LER 99-S01-00:on 990617,determined That Temporary Unescorted Access Had Been Granted to Contractor Employee.Caused by Incomplete Info Re Circumstances of Individual Military Separation.Individual Access Was Revoked.With 990719 Ltr
ML17265A7021999-07-15015 July 1999
LER 99-010-00:on 990615,ventilation Isolation of Auxiliary Bldg Occurred When Auxiliary Bldg Gas Radiation Monitor R-14 Reached High Alarm Setpoint.Cr Operators Rest Auxiliary Bldg Ventilation Isolation Signal.With 990715 Ltr
ML17265A6851999-06-21021 June 1999
LER 99-001-01:on 990222,deficiencies in NSSS Vendor steam- Line Brake Mass & Energy Release Analysis Results in Plant Being Outside Design Bases Occurred.Caused by Deficiencies in W.Temporary Administrative Replaced.With 990621 Ltr
ML17265A6661999-06-0202 June 1999
LER 99-009-00:on 990503,instrumentation Declared Inoperable in Multiple Channels Resulted in Condition Prohibited by Ts. Caused by Unanticipated High Frequency AC Voltage Ripple. Entered TS LCO 3.0.3.With 990602 Ltr
ML17309A6541999-05-27027 May 1999
LER 99-008-00:on 990427,overtemperature Delta T Reactor Trip Occurred Due to Faulted Bistable During Calibr of Redundant Channel.Plant Was Stabilized in Mode 3 & Faulted Bistable Was Subsequently Replaced.With 990527 Ltr
ML17265A6631999-05-24024 May 1999
LER 99-007-00:on 990423,technicians Inadvertently Pulled Fuses from Wrong Nuclear Instrument Cahnnel,Causing Reactor Trip,Due to High Range Flux Trip.Caused by Personnel Error. Labeling Scheme Improved
ML17265A6601999-05-21021 May 1999
LER 99-006-00:on 990421,start of turbine-driven Auxiliary Feedwater Pump Was Noted.Caused by MOV Being Left in Open Position.Closed Manual Isolation Valve to Secure Steam to Pump.With 990521 Ltr
ML17265A6441999-05-13013 May 1999
LER 99-005-00:on 990413,undervoltage Signal of Safeguards Bus During Testing Resulted in Automatic Start of B Edg. Caused by Personnel Error.Blown Fuse Was Replaced & Offsite Power Was Restored to Safeguards Bus 17.With 990513 Ltr
ML17265A6431999-05-12012 May 1999
LER 99-004-00:on 990412,discovered That Containment Recirculation Fan Moisture Separator Vanes Were Incorrectly Installed,Per 10CFR21.Caused by Improper Assembly by Mfg. Subject Vanes Were Dismantled & Correctly re-installed
ML17265A6141999-03-31031 March 1999
LER 99-003-00:on 990301,two Main Steam non-return Check Valves Were Declared Inoperable Due to Exceedance of Acceptance Criteria.Caused by Changes in Methodology & Matls.Packing Gland Torque Will Be Adjusted.With 990331 Ltr
ML17265A6131999-03-29029 March 1999
LER 99-002-00:on 990227,discovered That Surveillance Had Not Been Performed at Frequency,Per Ts.Caused by Personnel Error.Procedure O-6.13 Will Be Evaluated for Enhancement Documentation of Completion of ITS Srs.With 990329 Ltr
ML17265A6061999-03-24024 March 1999
LER 99-001-00:on 990222,plant Was Noted Outside Design Basis.Caused by Deficiencies in NSSS Vendor Slb Mass & Energy Release.Placed Temporary Administrative Restriction 40 Degrees F Max on Screenhouse Bay Temp
ML17265A4951998-12-21021 December 1998
LER 98-005-00:on 981120,loss of 34.5 Kv Offsite Power Circuit 751,resulted in Automatic Start of B Edg.Caused by Faulted Cable Splice.Performed Appropriate Actions of Abnormal Procedure AP-ELEC.1.With 981221 Ltr
ML17265A4931998-12-17017 December 1998
LER 98-004-00:on 971030,determined That Improperly Performed Surveillance Resulted in Condition Prohibited by Ts.Caused by Procedure non-adherence.Appropriate Calibr Procedures Were Properly Performed with 24 H of Condition Discovery
ML17265A4691998-11-25025 November 1998
LER 98-003-01:on 980904,actuations of CR Emergency Air Treatment Systems (Creats) Occurred.Caused by Radon build-up During Temp Inversion.Creats Actuation Signal Was Reset & Normal Ventilation Was Restored to CR
ML17265A4271998-10-0505 October 1998
LER 98-003-00:on 980904,actuations of CR Emergency Air Treatment Sys Occurred.Caused by Radon build-up During Temp Inversion.Air Samples Were Taken & Determined That Source of Radiation Was Naturally Occurring Radon.With 981005 Ltr
ML17265A3671998-07-14014 July 1998
LER 98-002-00:on 971019,CR Emergency Air Treatment Sys Actuating Function Was Not Operable.Caused by Mispositioned Switch.Revised Procedure CPI-MON-R37.W/980714 Ltr
ML17265A1921998-03-11011 March 1998
LER 98-001-00:on 980209,discovered That Boraflex Degradation in SPF Was Greater than Was Assumed.Caused by Dissolution of Boron on Boraflex Matrix,Per 10CFR50.21.Removed Spent Fuel Assemblies from Selected Degraded Storage Rack Cells
ML17265A1641998-02-0606 February 1998
LER 97-007-01:on 971117,reactor Engineer Recognized That Neutron Flux Low Range Trip Circuitry for Channel Was Not in Tripped Condition as Required.Caused by Technical Inadequacies.Channel Defeat Will Be Identified
ML17265A1601998-02-0606 February 1998
LER 97-006-01:on 971103,verification of B Concentration Was Not Performed Due to Misinterpretation of Event Sequence. Audible Count Rate Function Was Restored to Operable Status
ML17264B1441997-12-17017 December 1997
LER 97-007-00:on 971117,NF Low Range Trip Circuitry for Channel N-44 Was Not Placed in Tripped Condition.Caused by Technical Inadequacies in Procedures.Implemented EWR 4862 to Resolve Design deficiency.W/971217 Ltr
ML17264B1291997-12-0303 December 1997
LER 97-006-00:on 971103,NIS Audible Count Rate Function Was Inoperable.Caused by Misinterpretation of Event Sequence Due to Not Verifying Boron Concentration.B Verification Occurred Every 12 H Per ITS LCO Action 3.9.2.C.3.W/971203 Ltr
ML17264B1271997-12-0101 December 1997
LER 97-005-00:on 971031,undetected Unblocking of SI Actuation Signal Occurred at Low Pressure Condition,Due to Faulty Bistable Which Resulted in Inadvertent SI Actuation Signal.Sias,Ci & CVI Signals Were Reset
ML17264B1211997-11-24024 November 1997
LER 97-004-00:on 971024,radiation Monitor Alarm Were Noted Due to Higher than Normal Radioactive Gas Concentration Resulted in Cvi.New R-12 Alarm Setpoint Was Maintained for Duration of Refueling Outage
ML17264B0461997-09-29029 September 1997
LER 97-003-01:on 970730,bistable Instrument Trip Setpoint Could Have Exceeded Allowable Value.Caused by Insufficient Existing Margin Between Trip Setpoint & Allowable Value. Held Switches in Tripped configuration.W/970929 Ltr
ML17264B0111997-08-27027 August 1997
LER 97-003-00:on 970730,high Steam Flow Bistable Instrument Setpoint Plus Instrument Uncertainty Could Exceed Allowable Value in ITS Was Identified.Caused by Entry Into ITS LCO 3.0.3.Switches Placed in Tripped configuration.W/970827 Ltr
ML17264A9941997-08-19019 August 1997
LER 97-002-00:on 970720,34.5 Kv Offsite Power Circuit 751 Was Lost.Caused by Automatic Actuation of B Emergency DG Due to Undervoltage on Safeguards Buses 16 & 17.Offsite Power Restored to Safeguards Buses 16 & 17.W/970819 Ltr
ML17264A9911997-08-11011 August 1997
LER 96-009-02:on 960723,determined That Leak Rate Outside Containment Was Greater than Program Limit.Caused by Weld Defect.Isolated Leak & Cut Out & Replaced Leaking Pipe
ML17264A8271997-03-0303 March 1997
LER 97-001-00:on 970131,discovered Service Water Temp Was Less than Specified Value.Caused by non-representative Method of Monitoring.Increased Water Temp in Screenhouse Bay to Greater than 35 Degrees F.W/970303 Ltr
ML17264A8071997-01-22022 January 1997
LER 96-015-00:on 961223,discovered Thermally Induced Overpressure Transient Could Occur.Caused by Thermal Expansion of Fluid During Design Basis Accident Condition. Installed Relief Valve on Affected line.W/970122 Ltr
ML17264A7471996-11-27027 November 1996
LER 96-013-00:on 961029,circuit Breakers Closed While in Mode 3 & Resulted in Condition Prohibited by TS Due to Personnel Error.Circuit Breakers for MOV-878B & MOV-878D Were re-opened.W/961127 Ltr
ML17264A6051996-09-19019 September 1996
LER 96-012-00:on 960820,feedwater Transient Occurred,Due to Closure of Feedwater Regulating Valve,Causing Lo Lo Steam Generator Level Reactor Trip.Sgs Were Restored & Missing Screw in 1/P-476 Was replaced.W/960919 Ltr
ML17264A6061996-09-19019 September 1996
LER 96-009-01:on 960723,leakage Outside Containment Occurred,Due to Weld Defect,Resulting in Leak Rate Greater than Program Limits.Source of Leakage Isolated from RWST by Freeze Seal,Allowing Exit from ITS LCO 3.0.3.W/960919 Ltr
ML17264A5911996-09-0505 September 1996
LER 96-011-00:on 960807,improper Configuration of Circuit Breaker Occurred,Due to Undetected Internal Interference, Resulting in Automatic Start of Both Auxiliary Feedwater Pumps.Running AFW Pumps Were secured.W/960905 Ltr
ML17264A5921996-09-0505 September 1996
LER 96-010-00:on 960806,latching of Main Turbine While in Mode 4 Occurred,Due to Defective Procedure,Resulting in Automatic Start of Auxiliary Feedwater Pump.Caused by Defective Maint Procedure.Procedure revised.W/960905 Ltr
ML17264A5891996-08-22022 August 1996
LER 96-009-00:on 960723,determined Leak on Piping Sys Outside Containment Greater than Program Limit.Caused by Weld Defect.Pipe & Socket Welds Were Cut Out & Replaced. W/960822 Ltr
ML17264A5781996-08-0606 August 1996
LER 96-008-00:on 960707,main Feedwater Pump Breakers Opened. Caused by Change in Seal Water Differential Pressure Occurred During Sys Realignment.Afw Flow Controlled as Desired to Maintain S/G level.W/960806 Ltr
ML17264A5561996-07-12012 July 1996
LER 96-007-00:on 960612,CR Operators Identified Control Rods Misaligned & Not Moving in Proper Sequence.Caused by Faulty Firing Circuit Card in Rod Control Sys.Faulty Firing Circuit Card in 1BD Power Cabinet replaced.W/960712 Ltr
ML17264A5421996-06-20020 June 1996
LER 96-006-00:on 960521,discovered Containment Penetration Not in Required Status.Caused by Personnel Error.Installed Flange Inside Containment Penetration 2.W/960620 Ltr
ML17264A5411996-06-17017 June 1996
LER 96-005-00:on 960516,PORC Determined Deficient Procedures Do Not Meet SRs for Testing safety-related Logic Circuits. Caused by Inadequancies in Individual Testing Procedures. Procedures Re Improved TSs revised.W/960617 Ltr
ML17264A5051996-05-17017 May 1996
LER 96-003-01:on 960308,identified That Both Pressurizer PORVs Inoperable Concurrently Due to Disconnection of Flex Hose to Both PORV Actuators to Install air-sets for Benchset & Limit Switch Activities.Hpes Completed
ML17264A4481996-04-0808 April 1996
LER 96-003-00:on 960308,both Pressurizer Relief Valves Inoperable.Hpes Evaluation Is Being Conducted to Determined Cause of Event.C/As:Both PORVs restored.W/960408 Ltr
ML17264A4471996-04-0808 April 1996
LER 96-002-00:on 960307,secondary Transient Occurred.Caused by Loss of B Condenser Circulating Water Pump.C/As: Thermography performed.W/960408 Ltr
ML17264A4101996-03-18018 March 1996
LER 96-001-00:on 950504,inservice Test Not Performed During Refueling Outage.Caused by Inadequate Tracking of Surveillance Frequency.Valve Test Performed & Disassembled. W/960318 Ltr
ML17264A2971995-12-14014 December 1995
LER 95-009-00:on 950817,surveillance Was Not Performed Due to Improper Application of TS Requirements Resulting in TS Violation.Testing of MOV-515 Was Performed on 951115.W/ 951214 Ltr
ML17264A1711995-09-25025 September 1995
LER 95-008-00:on 950825,secondary Transient Occurred.Caused by Loss of B Condenser Circulating Water Pump That Resulted in Manual Rt.Returned S/G Levels to Normal Operating levels.W/950925 Ltr
1999-09-22
[Table view]
Category:RO)
MONTHYEARML17265A7541999-09-22022 September 1999
LER 99-011-00:on 990823,small Tears Were Discovered in Flexible Duct Work Connector at Inlet of CR HVAC Sys Return Air Fan (AKF08).Caused by in-leakage Greater than That Assumed.Implemented Temporary Mod 99-029.With 990922 Ltr
ML17265A7431999-08-24024 August 1999
LER 99-004-01:on 990412,discovered That Containment Recirculation Fan Chevron Separator Vanes Were Installed Backwards.Caused by Improper Assembly by Mfg.Moisture Separator Vanes Were Dismantled & Correctly re-installed
ML17265A7181999-07-23023 July 1999
LER 99-007-01:on 990423,reactor Trip Occurred Due to Instrument & Control Technicians Inadvertently Pulling Fuses from Wrong Nuclear Instrument Channel.Setpoint Adjustments Were Completed by Different Crew of Technicians
ML17265A7081999-07-22022 July 1999
LER 98-003-02:on 980904,actuations of CR Emergency Air Treatment Sys Was Noted Due to Invalid Causes.Caused by Various Degraded Components in CR RM Sys.Creats Actuation Signal Was Reset & Normal Ventilation Was Restored
ML17265A7031999-07-19019 July 1999
LER 99-S01-00:on 990617,determined That Temporary Unescorted Access Had Been Granted to Contractor Employee.Caused by Incomplete Info Re Circumstances of Individual Military Separation.Individual Access Was Revoked.With 990719 Ltr
ML17265A7021999-07-15015 July 1999
LER 99-010-00:on 990615,ventilation Isolation of Auxiliary Bldg Occurred When Auxiliary Bldg Gas Radiation Monitor R-14 Reached High Alarm Setpoint.Cr Operators Rest Auxiliary Bldg Ventilation Isolation Signal.With 990715 Ltr
ML17265A6851999-06-21021 June 1999
LER 99-001-01:on 990222,deficiencies in NSSS Vendor steam- Line Brake Mass & Energy Release Analysis Results in Plant Being Outside Design Bases Occurred.Caused by Deficiencies in W.Temporary Administrative Replaced.With 990621 Ltr
ML17265A6661999-06-0202 June 1999
LER 99-009-00:on 990503,instrumentation Declared Inoperable in Multiple Channels Resulted in Condition Prohibited by Ts. Caused by Unanticipated High Frequency AC Voltage Ripple. Entered TS LCO 3.0.3.With 990602 Ltr
ML17309A6541999-05-27027 May 1999
LER 99-008-00:on 990427,overtemperature Delta T Reactor Trip Occurred Due to Faulted Bistable During Calibr of Redundant Channel.Plant Was Stabilized in Mode 3 & Faulted Bistable Was Subsequently Replaced.With 990527 Ltr
ML17265A6631999-05-24024 May 1999
LER 99-007-00:on 990423,technicians Inadvertently Pulled Fuses from Wrong Nuclear Instrument Cahnnel,Causing Reactor Trip,Due to High Range Flux Trip.Caused by Personnel Error. Labeling Scheme Improved
ML17265A6601999-05-21021 May 1999
LER 99-006-00:on 990421,start of turbine-driven Auxiliary Feedwater Pump Was Noted.Caused by MOV Being Left in Open Position.Closed Manual Isolation Valve to Secure Steam to Pump.With 990521 Ltr
ML17265A6441999-05-13013 May 1999
LER 99-005-00:on 990413,undervoltage Signal of Safeguards Bus During Testing Resulted in Automatic Start of B Edg. Caused by Personnel Error.Blown Fuse Was Replaced & Offsite Power Was Restored to Safeguards Bus 17.With 990513 Ltr
ML17265A6431999-05-12012 May 1999
LER 99-004-00:on 990412,discovered That Containment Recirculation Fan Moisture Separator Vanes Were Incorrectly Installed,Per 10CFR21.Caused by Improper Assembly by Mfg. Subject Vanes Were Dismantled & Correctly re-installed
ML17265A6141999-03-31031 March 1999
LER 99-003-00:on 990301,two Main Steam non-return Check Valves Were Declared Inoperable Due to Exceedance of Acceptance Criteria.Caused by Changes in Methodology & Matls.Packing Gland Torque Will Be Adjusted.With 990331 Ltr
ML17265A6131999-03-29029 March 1999
LER 99-002-00:on 990227,discovered That Surveillance Had Not Been Performed at Frequency,Per Ts.Caused by Personnel Error.Procedure O-6.13 Will Be Evaluated for Enhancement Documentation of Completion of ITS Srs.With 990329 Ltr
ML17265A6061999-03-24024 March 1999
LER 99-001-00:on 990222,plant Was Noted Outside Design Basis.Caused by Deficiencies in NSSS Vendor Slb Mass & Energy Release.Placed Temporary Administrative Restriction 40 Degrees F Max on Screenhouse Bay Temp
ML17265A4951998-12-21021 December 1998
LER 98-005-00:on 981120,loss of 34.5 Kv Offsite Power Circuit 751,resulted in Automatic Start of B Edg.Caused by Faulted Cable Splice.Performed Appropriate Actions of Abnormal Procedure AP-ELEC.1.With 981221 Ltr
ML17265A4931998-12-17017 December 1998
LER 98-004-00:on 971030,determined That Improperly Performed Surveillance Resulted in Condition Prohibited by Ts.Caused by Procedure non-adherence.Appropriate Calibr Procedures Were Properly Performed with 24 H of Condition Discovery
ML17265A4691998-11-25025 November 1998
LER 98-003-01:on 980904,actuations of CR Emergency Air Treatment Systems (Creats) Occurred.Caused by Radon build-up During Temp Inversion.Creats Actuation Signal Was Reset & Normal Ventilation Was Restored to CR
ML17265A4271998-10-0505 October 1998
LER 98-003-00:on 980904,actuations of CR Emergency Air Treatment Sys Occurred.Caused by Radon build-up During Temp Inversion.Air Samples Were Taken & Determined That Source of Radiation Was Naturally Occurring Radon.With 981005 Ltr
ML17265A3671998-07-14014 July 1998
LER 98-002-00:on 971019,CR Emergency Air Treatment Sys Actuating Function Was Not Operable.Caused by Mispositioned Switch.Revised Procedure CPI-MON-R37.W/980714 Ltr
ML17265A1921998-03-11011 March 1998
LER 98-001-00:on 980209,discovered That Boraflex Degradation in SPF Was Greater than Was Assumed.Caused by Dissolution of Boron on Boraflex Matrix,Per 10CFR50.21.Removed Spent Fuel Assemblies from Selected Degraded Storage Rack Cells
ML17265A1641998-02-0606 February 1998
LER 97-007-01:on 971117,reactor Engineer Recognized That Neutron Flux Low Range Trip Circuitry for Channel Was Not in Tripped Condition as Required.Caused by Technical Inadequacies.Channel Defeat Will Be Identified
ML17265A1601998-02-0606 February 1998
LER 97-006-01:on 971103,verification of B Concentration Was Not Performed Due to Misinterpretation of Event Sequence. Audible Count Rate Function Was Restored to Operable Status
ML17264B1441997-12-17017 December 1997
LER 97-007-00:on 971117,NF Low Range Trip Circuitry for Channel N-44 Was Not Placed in Tripped Condition.Caused by Technical Inadequacies in Procedures.Implemented EWR 4862 to Resolve Design deficiency.W/971217 Ltr
ML17264B1291997-12-0303 December 1997
LER 97-006-00:on 971103,NIS Audible Count Rate Function Was Inoperable.Caused by Misinterpretation of Event Sequence Due to Not Verifying Boron Concentration.B Verification Occurred Every 12 H Per ITS LCO Action 3.9.2.C.3.W/971203 Ltr
ML17264B1271997-12-0101 December 1997
LER 97-005-00:on 971031,undetected Unblocking of SI Actuation Signal Occurred at Low Pressure Condition,Due to Faulty Bistable Which Resulted in Inadvertent SI Actuation Signal.Sias,Ci & CVI Signals Were Reset
ML17264B1211997-11-24024 November 1997
LER 97-004-00:on 971024,radiation Monitor Alarm Were Noted Due to Higher than Normal Radioactive Gas Concentration Resulted in Cvi.New R-12 Alarm Setpoint Was Maintained for Duration of Refueling Outage
ML17264B0461997-09-29029 September 1997
LER 97-003-01:on 970730,bistable Instrument Trip Setpoint Could Have Exceeded Allowable Value.Caused by Insufficient Existing Margin Between Trip Setpoint & Allowable Value. Held Switches in Tripped configuration.W/970929 Ltr
ML17264B0111997-08-27027 August 1997
LER 97-003-00:on 970730,high Steam Flow Bistable Instrument Setpoint Plus Instrument Uncertainty Could Exceed Allowable Value in ITS Was Identified.Caused by Entry Into ITS LCO 3.0.3.Switches Placed in Tripped configuration.W/970827 Ltr
ML17264A9941997-08-19019 August 1997
LER 97-002-00:on 970720,34.5 Kv Offsite Power Circuit 751 Was Lost.Caused by Automatic Actuation of B Emergency DG Due to Undervoltage on Safeguards Buses 16 & 17.Offsite Power Restored to Safeguards Buses 16 & 17.W/970819 Ltr
ML17264A9911997-08-11011 August 1997
LER 96-009-02:on 960723,determined That Leak Rate Outside Containment Was Greater than Program Limit.Caused by Weld Defect.Isolated Leak & Cut Out & Replaced Leaking Pipe
ML17264A8271997-03-0303 March 1997
LER 97-001-00:on 970131,discovered Service Water Temp Was Less than Specified Value.Caused by non-representative Method of Monitoring.Increased Water Temp in Screenhouse Bay to Greater than 35 Degrees F.W/970303 Ltr
ML17264A8071997-01-22022 January 1997
LER 96-015-00:on 961223,discovered Thermally Induced Overpressure Transient Could Occur.Caused by Thermal Expansion of Fluid During Design Basis Accident Condition. Installed Relief Valve on Affected line.W/970122 Ltr
ML17264A7471996-11-27027 November 1996
LER 96-013-00:on 961029,circuit Breakers Closed While in Mode 3 & Resulted in Condition Prohibited by TS Due to Personnel Error.Circuit Breakers for MOV-878B & MOV-878D Were re-opened.W/961127 Ltr
ML17264A6051996-09-19019 September 1996
LER 96-012-00:on 960820,feedwater Transient Occurred,Due to Closure of Feedwater Regulating Valve,Causing Lo Lo Steam Generator Level Reactor Trip.Sgs Were Restored & Missing Screw in 1/P-476 Was replaced.W/960919 Ltr
ML17264A6061996-09-19019 September 1996
LER 96-009-01:on 960723,leakage Outside Containment Occurred,Due to Weld Defect,Resulting in Leak Rate Greater than Program Limits.Source of Leakage Isolated from RWST by Freeze Seal,Allowing Exit from ITS LCO 3.0.3.W/960919 Ltr
ML17264A5911996-09-0505 September 1996
LER 96-011-00:on 960807,improper Configuration of Circuit Breaker Occurred,Due to Undetected Internal Interference, Resulting in Automatic Start of Both Auxiliary Feedwater Pumps.Running AFW Pumps Were secured.W/960905 Ltr
ML17264A5921996-09-0505 September 1996
LER 96-010-00:on 960806,latching of Main Turbine While in Mode 4 Occurred,Due to Defective Procedure,Resulting in Automatic Start of Auxiliary Feedwater Pump.Caused by Defective Maint Procedure.Procedure revised.W/960905 Ltr
ML17264A5891996-08-22022 August 1996
LER 96-009-00:on 960723,determined Leak on Piping Sys Outside Containment Greater than Program Limit.Caused by Weld Defect.Pipe & Socket Welds Were Cut Out & Replaced. W/960822 Ltr
ML17264A5781996-08-0606 August 1996
LER 96-008-00:on 960707,main Feedwater Pump Breakers Opened. Caused by Change in Seal Water Differential Pressure Occurred During Sys Realignment.Afw Flow Controlled as Desired to Maintain S/G level.W/960806 Ltr
ML17264A5561996-07-12012 July 1996
LER 96-007-00:on 960612,CR Operators Identified Control Rods Misaligned & Not Moving in Proper Sequence.Caused by Faulty Firing Circuit Card in Rod Control Sys.Faulty Firing Circuit Card in 1BD Power Cabinet replaced.W/960712 Ltr
ML17264A5421996-06-20020 June 1996
LER 96-006-00:on 960521,discovered Containment Penetration Not in Required Status.Caused by Personnel Error.Installed Flange Inside Containment Penetration 2.W/960620 Ltr
ML17264A5411996-06-17017 June 1996
LER 96-005-00:on 960516,PORC Determined Deficient Procedures Do Not Meet SRs for Testing safety-related Logic Circuits. Caused by Inadequancies in Individual Testing Procedures. Procedures Re Improved TSs revised.W/960617 Ltr
ML17264A5051996-05-17017 May 1996
LER 96-003-01:on 960308,identified That Both Pressurizer PORVs Inoperable Concurrently Due to Disconnection of Flex Hose to Both PORV Actuators to Install air-sets for Benchset & Limit Switch Activities.Hpes Completed
ML17264A4481996-04-0808 April 1996
LER 96-003-00:on 960308,both Pressurizer Relief Valves Inoperable.Hpes Evaluation Is Being Conducted to Determined Cause of Event.C/As:Both PORVs restored.W/960408 Ltr
ML17264A4471996-04-0808 April 1996
LER 96-002-00:on 960307,secondary Transient Occurred.Caused by Loss of B Condenser Circulating Water Pump.C/As: Thermography performed.W/960408 Ltr
ML17264A4101996-03-18018 March 1996
LER 96-001-00:on 950504,inservice Test Not Performed During Refueling Outage.Caused by Inadequate Tracking of Surveillance Frequency.Valve Test Performed & Disassembled. W/960318 Ltr
ML17264A2971995-12-14014 December 1995
LER 95-009-00:on 950817,surveillance Was Not Performed Due to Improper Application of TS Requirements Resulting in TS Violation.Testing of MOV-515 Was Performed on 951115.W/ 951214 Ltr
ML17264A1711995-09-25025 September 1995
LER 95-008-00:on 950825,secondary Transient Occurred.Caused by Loss of B Condenser Circulating Water Pump That Resulted in Manual Rt.Returned S/G Levels to Normal Operating levels.W/950925 Ltr
1999-09-22
[Table view]
Category:TEXT-SAFETY REPORT
MONTHYEARML17265A7601999-10-0505 October 1999
Part 21 Rept Re W2 Switch Supplied by W Drawn from Stock, Did Not Operate Properly After Being Installed on 990409. Switch Returned to W on 990514 for Evaluation & Root Cause Analysis
ML17265A7621999-09-30030 September 1999
Monthly Operating Rept for Sept 1999 for Re Ginna Npp.With 991008 Ltr
ML17265A7531999-09-23023 September 1999
Part 21 Rept Re Corrective Action & Closeout of 10CFR21 Rept of Noncompliance Re Unacceptable Part for 30-4 Connector. Unacceptable Parts Removed from Stock & Scrapped
ML17265A7541999-09-22022 September 1999
LER 99-011-00:on 990823,small Tears Were Discovered in Flexible Duct Work Connector at Inlet of CR HVAC Sys Return Air Fan (AKF08).Caused by in-leakage Greater than That Assumed.Implemented Temporary Mod 99-029.With 990922 Ltr
ML17265A7471999-08-31031 August 1999
Monthly Operating Rept for Aug 1999 for Re Ginna Npp.With 990909 Ltr
ML17265A7431999-08-24024 August 1999
LER 99-004-01:on 990412,discovered That Containment Recirculation Fan Chevron Separator Vanes Were Installed Backwards.Caused by Improper Assembly by Mfg.Moisture Separator Vanes Were Dismantled & Correctly re-installed
ML17265A7341999-07-31031 July 1999
Monthly Operating Rept for July 1999 for Re Ginna Npp.With 990806 Ltr
ML17265A7291999-07-29029 July 1999
Interim Part 21 Rept Re safety-related DB-25 Breaker Mechanism Procured from W Did Not Pas Degradatin Checks When Drawn from Stock to Be Installed Into BUS15/03A.Holes Did Not line-up & Tripper Pan Bent
ML17265A7181999-07-23023 July 1999
LER 99-007-01:on 990423,reactor Trip Occurred Due to Instrument & Control Technicians Inadvertently Pulling Fuses from Wrong Nuclear Instrument Channel.Setpoint Adjustments Were Completed by Different Crew of Technicians
ML17265A7081999-07-22022 July 1999
LER 98-003-02:on 980904,actuations of CR Emergency Air Treatment Sys Was Noted Due to Invalid Causes.Caused by Various Degraded Components in CR RM Sys.Creats Actuation Signal Was Reset & Normal Ventilation Was Restored
ML17265A7131999-07-22022 July 1999
Special Rept:On 990407,radiation Monitor RM-14A Was Declared Inoperable.Caused by Failed Communication Link from TSC to Plant Process Computer Sys.Communication Link Was re-established & RM-14A Was Declaed Operable on 990521
ML17265A7031999-07-19019 July 1999
LER 99-S01-00:on 990617,determined That Temporary Unescorted Access Had Been Granted to Contractor Employee.Caused by Incomplete Info Re Circumstances of Individual Military Separation.Individual Access Was Revoked.With 990719 Ltr
ML17265A7211999-07-19019 July 1999
ISI Rept for Third Interval (1990-1999) Third Period, Second Outage (1999) at Re Ginna Npp.
ML17265A7021999-07-15015 July 1999
LER 99-010-00:on 990615,ventilation Isolation of Auxiliary Bldg Occurred When Auxiliary Bldg Gas Radiation Monitor R-14 Reached High Alarm Setpoint.Cr Operators Rest Auxiliary Bldg Ventilation Isolation Signal.With 990715 Ltr
ML17265A7661999-06-30030 June 1999
1999 Rept of Facility Changes,Tests & Experiments Conducted Without Prior NRC Approval for Jan 1998 Through June 1999, Per 10CFR50.59.With 991020 Ltr
ML17265A7011999-06-30030 June 1999
Monthly Operating Rept for June 1999 for Re Ginna Npp.With 990712 Ltr
ML17265A6851999-06-21021 June 1999
LER 99-001-01:on 990222,deficiencies in NSSS Vendor steam- Line Brake Mass & Energy Release Analysis Results in Plant Being Outside Design Bases Occurred.Caused by Deficiencies in W.Temporary Administrative Replaced.With 990621 Ltr
ML17265A6761999-06-16016 June 1999
Part 21 Rept Re Defects & noncompliances,10CFR21(d)(3)(ii), Which Requires Written Notification to NRC on Identification of Defect or Failure to Comply. Relays Were Returned to Eaton for Evaluation & Root Cause Analysis
ML17265A6661999-06-0202 June 1999
LER 99-009-00:on 990503,instrumentation Declared Inoperable in Multiple Channels Resulted in Condition Prohibited by Ts. Caused by Unanticipated High Frequency AC Voltage Ripple. Entered TS LCO 3.0.3.With 990602 Ltr
ML17265A6681999-05-31031 May 1999
Monthly Operating Rept for May 1999 for Re Ginna Nuclear Power Plant.With 990608 Ltr
ML17265A6651999-05-27027 May 1999
Interim Rept Re W2 Control Switch,Procured from W,Did Not Operate Satisfactorily When Drawn from Stock to Be Installed in Main Control Board for 1C2 Safety Injection Pump. Estimated That Evaluation Will Be Completed by 991001
ML17309A6541999-05-27027 May 1999
LER 99-008-00:on 990427,overtemperature Delta T Reactor Trip Occurred Due to Faulted Bistable During Calibr of Redundant Channel.Plant Was Stabilized in Mode 3 & Faulted Bistable Was Subsequently Replaced.With 990527 Ltr
ML17265A6631999-05-24024 May 1999
LER 99-007-00:on 990423,technicians Inadvertently Pulled Fuses from Wrong Nuclear Instrument Cahnnel,Causing Reactor Trip,Due to High Range Flux Trip.Caused by Personnel Error. Labeling Scheme Improved
ML17265A6601999-05-21021 May 1999
LER 99-006-00:on 990421,start of turbine-driven Auxiliary Feedwater Pump Was Noted.Caused by MOV Being Left in Open Position.Closed Manual Isolation Valve to Secure Steam to Pump.With 990521 Ltr
ML17265A6591999-05-17017 May 1999
Part 21 Rept Re Relay Deficiency Detected During pre-installation Testing.Caused by Incorrectly Wired Relay Coil.Relays Were Returned to Eaton Corp for Investigation. Relays Were Repaired & Retested
ML17265A6441999-05-13013 May 1999
LER 99-005-00:on 990413,undervoltage Signal of Safeguards Bus During Testing Resulted in Automatic Start of B Edg. Caused by Personnel Error.Blown Fuse Was Replaced & Offsite Power Was Restored to Safeguards Bus 17.With 990513 Ltr
ML17265A6431999-05-12012 May 1999
LER 99-004-00:on 990412,discovered That Containment Recirculation Fan Moisture Separator Vanes Were Incorrectly Installed,Per 10CFR21.Caused by Improper Assembly by Mfg. Subject Vanes Were Dismantled & Correctly re-installed
ML17265A6381999-05-0707 May 1999
Part 21 Rept Re Replacement Turbocharger Exhaust Turbine Side Drain Port Not Functioning as Design Intended.Caused by Manufacturing Deficiency.Turbocharger Was Reaasembled & Reinstalled on B EDG
ML17265A6391999-04-30030 April 1999
Monthly Operating Rept for Apr 1999 for Re Ginna Nuclear Power Plant.With 990510 Ltr
ML17265A6361999-04-23023 April 1999
Part 21 Rept Re Power Supply That Did Not Work Properly When Drawn from Stock & Installed in -25 Vdc Slot.Power Supply Will Be Sent to Vendor to Perform Failure Mode Assessment.Evaluation Will Be Completed by 991001
ML17265A6301999-04-18018 April 1999
Rev 1 to Cycle 28 COLR for Re Ginna Npp.
ML17265A6251999-04-15015 April 1999
Special Rept:On 990309,halon Systems Were Removed from Svc & Fire Door F502 Was Blocked Open.Caused by Mods Being Made to CR Emergency Air Treatment Sys.Continuous Fire Watch Was Established with Backup Fire Suppression Equipment
ML17265A6551999-04-0909 April 1999
Initial Part 21 Rept Re Mfg Deficiency in Replacement Turbocharger for B EDG Supplied by Coltec Industries. Deficiency Consisted of Missing Drain Port in Intermediate Casing.Required Oil Drain Port Machined Open
ML17265A6291999-03-31031 March 1999
Rev 0 to Cycle 28 COLR for Re Ginna Npp.
ML17265A6241999-03-31031 March 1999
Monthly Operating Rept for Mar 1999 for Ginna Station.With 990409 Ltr
ML17265A6141999-03-31031 March 1999
LER 99-003-00:on 990301,two Main Steam non-return Check Valves Were Declared Inoperable Due to Exceedance of Acceptance Criteria.Caused by Changes in Methodology & Matls.Packing Gland Torque Will Be Adjusted.With 990331 Ltr
ML17265A6131999-03-29029 March 1999
LER 99-002-00:on 990227,discovered That Surveillance Had Not Been Performed at Frequency,Per Ts.Caused by Personnel Error.Procedure O-6.13 Will Be Evaluated for Enhancement Documentation of Completion of ITS Srs.With 990329 Ltr
ML17265A6061999-03-24024 March 1999
LER 99-001-00:on 990222,plant Was Noted Outside Design Basis.Caused by Deficiencies in NSSS Vendor Slb Mass & Energy Release.Placed Temporary Administrative Restriction 40 Degrees F Max on Screenhouse Bay Temp
ML17265A5661999-03-0101 March 1999
Rev 26 to QA Program for Station Operation.
ML17265A5961999-02-28028 February 1999
Monthly Operating Rept for Feb 1999 for Ginna Nuclear Power Plant.With 990310 Ltr
ML17265A5371999-01-31031 January 1999
Monthly Operating Rept for Jan 1999 for Re Ginna Nuclear Power Plant.With 990205 Ltr
ML17265A5951998-12-31031 December 1998
Rg&E 1998 Annual Rept.
ML17265A5001998-12-21021 December 1998
Rev 26 to QA Program for Station Operation.
ML17265A4951998-12-21021 December 1998
LER 98-005-00:on 981120,loss of 34.5 Kv Offsite Power Circuit 751,resulted in Automatic Start of B Edg.Caused by Faulted Cable Splice.Performed Appropriate Actions of Abnormal Procedure AP-ELEC.1.With 981221 Ltr
ML17265A4931998-12-17017 December 1998
LER 98-004-00:on 971030,determined That Improperly Performed Surveillance Resulted in Condition Prohibited by Ts.Caused by Procedure non-adherence.Appropriate Calibr Procedures Were Properly Performed with 24 H of Condition Discovery
ML17265A4761998-11-30030 November 1998
Monthly Operating Rept for Nov 1998 for Re Ginna Nuclear Power Plant.With 981210 Ltr
ML17265A4691998-11-25025 November 1998
LER 98-003-01:on 980904,actuations of CR Emergency Air Treatment Systems (Creats) Occurred.Caused by Radon build-up During Temp Inversion.Creats Actuation Signal Was Reset & Normal Ventilation Was Restored to CR
ML17265A4531998-10-31031 October 1998
Monthly Operating Rept for Oct 1998 for Re Ginna Nuclear Power Plant.With 981110 Ltr
ML17265A4271998-10-0505 October 1998
LER 98-003-00:on 980904,actuations of CR Emergency Air Treatment Sys Occurred.Caused by Radon build-up During Temp Inversion.Air Samples Were Taken & Determined That Source of Radiation Was Naturally Occurring Radon.With 981005 Ltr
ML17265A4291998-09-30030 September 1998
Monthly Operating Rept for Sept 1998 for Re Ginna Nuclear Power Plant.With 981009 Ltr
1999-09-30
[Table view] |
Text
ACCELERATED DISTRIBUTION DEMON~0 TION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)ACCESSION NBR:9108050066 DOC.DATE: 91/07/29 NOTARIZED:, NO FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1,, Rochester G AUTH.NAME AUTHOR AFFILIATION
.BACKUS,W.H.
Rochester Gas&Electric Corp.MECREDY,R.C.
'ochester Gas&Electric Corp.RECIP.NAME RECIPIENT AFFILIATION DOCKET 05000244 II
SUBJECT:
LER 91-006-00:on 910629,EDG A started automatically due to apparent undervoltage signal from Bus 14 undervoltage monitoring sys.Root cause not determined.Bus 14 energized&EDG declared operable.W/910729 ltr.DISTRIBUTION CODE: IE22T COPIES RECEIVED:LTR
!ENCL I SIZE: 7 TITLE: 50.73/50.9 Licensee Event Report (LER), Incident Rpt, etc.NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72).
D 05000244 A RECIPIENT ID CODE/NAME PD1-3 LA JOHNSON,A INTERNAL: ACNW AEOD/DSP/TPAB NRR/DET/ECMB 9H NRR/DLPQ/LHFB10 NRR/DOEA/OEAB NRR/DST/SELB SD NRRfDST~LBSD1 REG F~02 RGN1 FILE 01 EXTERNAL: EG&G BRYCE,J.H NRC PDR NSIC POORE,W.~7&75 Htt<w'(COPIES LTTR ENCL 1 1 1 1 2 2 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1'1 3 3 1 1 1 1 RECIPIENT ID CODE/NAME PD1-3 PD AEOD/DOA AEOD/ROAB/DSP NRR/DET/EMEB 7E NRR/DLPQ/LPEB10 NRR/DREP/PRPB11 NRR/DST/SICBSH3 NRR/DST/SRXB SE RES/DSIR/EIB L ST LOBBY WARD NSIC MURPHY,G.A NUDOCS FULL TXT'OPIES LTTR ENCL 1 1 1 1 2 2 1 1 1 1 2 2 1 1 1'1 1 1 1 1 1 1 1 D D D NOTE TO ALL"RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE!CONTACT THE DOCUMENT CONTROL DESK, ROOiv!P 1-37 (EXT.20079)TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCU5!EiiTS YOU DON'T NEED!A D D S FULL TEXT CONVERSION REQUIRED-TOTAL NUMBER OF COPIES REQUIRED: LTTR 31 ENCL 31
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"," ROCHESTER GAS AND ELECTRIC CORPORATION ROSERTC h1ECREDY Vice President Ctnna Nucfear Prnducticrn oe'I'a',,'~1th~~'r Stale., 89 EAST AVENUE, ROCHESTER N.K 14649-0001 i TELEPHONE AAEACODETIB 546 2700 July 29, 1991 I U.S.Nuclear Regulatory Commission Document Control Desk Washington,-
DC 20555
Subject:
LER 91-006, Apparent Voltage Drop on Safeguards 480 Volt Bus 14 Causes an Automatic Start of the"A" Emergency Diesel Generator R.E.Ginna Nuclear Power Plant Docket No.50-244 In-accordance with 10 CFR 50.73, Licensee Event Report System, item (a)(2)(iv),which requires a report of,"any event or condition that resulted in manual or automatic actuation of any Engineered Safety Feature (ESF),"including the Reactor Protection System (RPS)", the attached Licensee Event Report LER 91-006 is hereby submitted.
This event has in no way affected the public's health and safety.Very truly yours, Robert C.Mecr dy xc U.S.Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 Ginna USNRC Senior Resident Inspector 9 i 080s00g,(, PDR ADOCK Ort.iot)-4 i
NAC tas lli IOACI LICENSEE EVENT REPORT (LERI UA NUOLCAA AoovLATCAocc>>se&lcw Attleovto oleo NIL OIN olov CAOIACO.O)te/
~$)ACILITY NA<<)O Ill R.E.Ginna Nuclear Power.Plant OOCACT eeveeoCA Ol o 6 ooo244ios Apparent Voltage Dmp On Safequards 480 Volt Bus 14 Causes an Automatic Start of the A" Emer enc Diesel Generator CVCIIT CATO 14 Lt1 NveeocA 14 Al)O1T OATC lll OTlet1)ACILITICC INVOLVCO IOI>>OI>>T>>e OAY YCAA YCAA~COveeee>>AL
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<<esl 114 t1)CCTCO wo<<elttloN OATC Illl IIONT>>e CAY Y CAN On June 29, 1991 at 1754 EST with the reactor at approximately 98%full power, the"A" Emergency Diesel Generator started automatically due to an apparent undervoltage signal from the Bus 14 Undervoltage Monitoring System.The"A" Emergency Diesel Generator, after starting, attained proper voltage and frequency.
By design, it did not close into Bus 14 because Bus 14 was at its proper voltage and being fed from its normal power supply.Immediate operator action was to verify that Bus 14 was energized and that the"A" Emergency Diesel Generator was operating normally.Subsequently) the"A" Emergency Diesel Generator was stopped and realigned for auto-standby.
The cause of the event has.not been positively determined, although off-site electrical disturbance is postulated.
Since the cause of this event has not been positively determined at this time, we will continue to investigate for the underlying cause.Any further corrective action will depend on the re'suits of this investigation.
eeAC toes ON IOACI
~0~0
~e~H(IC FMm dddA (045)L'ICENSEE EVENT REPORT ILERI TEXT CONTINUATION 3 U.d.HUCLCA(I HKOULATOHY COMM(dd(OH AFFHOVEO OMd HO 5150M(04 dkF(Added(5((55 FACILITY HAMd (II R.E.Ginna Nuclear Power Plant TEXT IN'ccc Mccc H mdvckd.vcc NMcckncc(4(NC Fckm J(d(4'cl ((T(OOC((ET HUMddll (1(0 s 0 0 0 24 491 Ld(I HUMddll (dl 5~OVCHZIAL 4 HVM k-006 kdVMIOH HUM 0 FAOd (51 02 DFO 6 PRE-EVE2iT PLANT CONDITIONS The plant was at approximately 984 steady state full power with no'ajor activities in progress.II.DESCRIPTION OF%TENT A.DATES AND APPROXIMATE TIMES OP MAJOR OCCURRENCES:
0 0 0 June 29, 1991, 1754 EDST: Event Date and Time h June 29, 1991, 1754 EDST: Discovery Date and Time June 29, 1991, 2013 EDST: "A" Emergency Diesel Generator stopped and realigned for Auto-standby B.EVENT: On June 29, 1991 at 1754 EDST, with the reactor at approximately 98%full power, the Control Room received the following alarms: L-14 (Bus 14.Undervoltage
-Safeguards) and J-24 (Emergency Diesel Gen 1A Panel).The Control Room operators immediately verified proper voltage on Bus 14 and that the normal power supply breaker was closed.The Control Room operators also verified that the"A" Emergency Diesel Generator had started and displayed proper voltage and frequency.
By design, the"A" Emergency Diesel Generator did not close into Bus, 14, as the bus voltage was normal and Bus 14 was still being supplied by its normal power supply.HAC FOAM 544*(I ddl
~0
~0~e NRC Sotw 295A (042 I L'ICENSEE EVENT REPORT ILERI TEXT CONTINUATION U.S.NUCLEAR REQVLATORY COMMI55ION ASSROVEO OM9 NO SISOWI04 J EXSIRES, 9121/99 SACILITY NAME 111 OOCKET NVMEER 121 LER NVMQEII 191 55QUENTIAL NUM REVISION NUM SAOE l21 R.E.Ginna Nuclear Power Plant TEXT IIJ~<<>>5~N~.v>>NAS55JNJ HRC FOnn 2OEA'5I I ITI o 5 o o o2 44, 006 00 03pF 0 6 Subsequently, Auxiliary operators were dispatched to check the Bus 14 Undervoltage Monitoring System cabinets and the operation of the"A" Emergency Diesel Generator.
The operation of the"A" Emergency Diesel Generator was found to be normal.No undervoltage trip targets were observed on Bus 14 or Bus 18 (both these buses are fed by the"A" Emergency.Diesel Generator).
During this event, routine activities were occurring at off-site Station 204.At approximately the same time as the apparent undervoltage condition occurred on Bus 14, a 34.5 kv capacitor bank was being removed from service.This is a routine action to correct off-site voltage situations.
Station 204'eeds Circuit 751, which was the normal off-site power supply to Buses 14 and 18.Control=Room operators notified higher supervision and the Nuclear Regulatory Commission of the event.To prove operability of the Undervoltage Monitoring System, the Results and Test (R&T)Department performed Periodic Test procedure PT-9.1 (Undervoltage Protection 480 Volt Safeguards Busses)on Bus 14.After PT-9.1.was successfully completed, the"A" Emergency Diesel Generator was stopped and realigned for Auto-standby.
C.INOPERABLE STRUC'HIRES, COMPONENTS s OR SYSTEMS THAT CONTRIBUTED TO THE EVENT: None.D.OTEGsR SYSTEMS OR SECONDARY PUNCTIONS AFFECTED: E.None.METHOD OP DISCOVERY:
The events were immediately apparent due to alarms and indications in the Control Room.NRC SORM 255A I94ll
.OO
<<AC Sotto SSSA~e L'ICENSEE EVENT REPORT (LER)TEXT CONTINUATION V,S.<<UCLEAII Ilf OULATOIIY COMMISSIOII ASSAOYEO OMS HO 3150MIOI I EXSIAES, SISI l95 SACILITY NAME Ill R.E.Ginna Nuclear Power Plant TEXT ill nave<<WCe<<nquseC vAS OdakevW lYPC Arm~'ll I ITI OOCKET IIUMSEII 11I o s o o o 2 4 LEII<<UMSEII ISI 5~4UC<<VIAL'S V<<ION HUM<<'"<<UM f<<9-1-0 06-00~AOS ISI 0 4 o~0 6 F.OPERATOR ACTXON: Following the Bus 14 Undervoltage Alarm and the"A" Emergency Diesel Generator automatic start, the Co'ntrol Room operators immediately verified proper voltage on Bus 14 via the normal power supply and',that the"A" Emergency Diesel Generator displayed proper voltage and frequency.
Subsequently, Auxiliary operators were dis'patched to check-the Bus 14 undervoltage monitoring system and"A" Emergency Diesel Generator operation.
The"A" Emergency Diesel Generator operation was normal and ,no undervoltage trip targets were observed on Bus 14 or Bus 18.'t" The"A" Emergency Diesel Generator was subsequently stopped and realigned for Auto-standby.
G.SAFETX SXSTEM RESPONSES:
The"A" Emergency Diesel Generator automatically started and displayed proper voltage and frequency.
'IXI.CAUSE OF EV19Fl'.XMM1sDIATE CAUSE: The automatic actuation of the-"A" Emergency Diesel Generator was due to an apparent undervoltage signal from the Bus 14 undervoltage monitoring system.B.ROOT CAUSE: The underlying, cause of the apparent undervoltage signal from the Bus 14 undervoltage monitoring system is not positively determined at this time..MAC SO<<M SSSA I941l
~0 IIAC Sovvvv 444A 14451~e oe L'ICENSEE EVENT REPORT (LERI TEXT CONTINUATION U,E.NUCLEAA AEOULATOAY COMMIEEIOII
/ASSAOVEO OME IVO 1150MIOe EXSIAES, 4151/45 SACILITY IIAME Ill R.E.Ginna Nuclear Pawer Plant TExT lll nave Mece a eevveevL vvM vneeeval vYAC Sevvn SELA Yl I ITI COCKET IvUMEEA 111 osooo244 vEAA LEII IIUMEEA 141 5 4 0 0 4 VV T I A L~VUM 0 0 6 ntvlelOM VVVM 0 0 SAOE IEI 0 50F 06 IV.ANALYSIS OF EVENT The event is reportable in accordance with 10 CFR 50.73, Licensee Event Report System, item (a)(2)(iv), which requires'eporting of,"any event or condition that resulted in manual or automatic actuation of any Engineered Safety Feature (ESF)including the Reactor.Protection System (RPS)".The starting of the"A" Emergency Diesel Generator was an automatic actuation of an ESF system.An assessment was performed considering both the safety consequences and implications of this event with the following results and conclusions:
There were no operational or safety consequences or implications attributed to the starting of the"A" Emergency Diesel Generator because: 0 The"A" Emergency Diesel Generator operated as designed.o Both Bus 14 power supplies (i.e.normal and emergency) were either in use or available throughout the event.o The Bus 14 undervoltage monitoring system operation was in the conservative direction, (i.e.the operation actuated the automatic start of the"A" Emergency Diesel Generator).
Based on the above, it can be concluded that the public's health and safety was assured at all times.V.CORRECTIVE ACTION A.ACTION TAKEN TO RETURN AFFECTED SYSTEMS TO PRE-EVENT NORMAL STATUS: o The R&T Department successfully completed PT-9.1 on Bus 14 and the"A" Emergency Diesel Generator was stopped and aligned for Auto-standby.
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~1~0 NAC>arm SEEA I HEI~0 I.'ICENSEE EVENT REPORT (I.ER)TEXT CONTINUATION V.S.NVCLEAII IIEOVLATOIIY COMMISSION I Atf AOV EO OME HO$1$0MIOI E)CrllIES.
EISI4$FACILITY NAME III OOCIIET NVMEEII IEI YEAA LEII NVMEEII IEI IEQVEHTIAL 4 M IA AEV ISIO<NVM IA~ACE ISI R.E.Ginna Nuclear Power Plant TEIL ill mort apece e mewaf.wt aAkenV HAC Fiwn DELI'Il I I Tl o s o o o.24 4 9 1 006 0 006'F 0 6 B.ACTXON TAKEN OR PLANNED TO PREVENT RECURRENCE:
0 0 0 As the underlying cause of the event has not been determined at this time, investigations will continue to positively determine the underlying cause of this event.Any further corrective actions will depend on the results of these investigations.
Electrical system monitoring records have been reviewed, and indicate that removal of the capacitor bank resulted in a small and routine voltage transient.
Electrical system monitoring has been increased on Circuit 751.0 The interface between the undervoltage monitoring system and diesel start circuitry will continue to be evaluated,'to determine if the undervoltage system is reacting as designed for small voltage fluctuations.
ADDXTXONAL XNFORMATION A.B.PAXLED COMPONENTS:
None.PREVXOUS LERs ON SIMILAR EVENTS: A similar LER event historical search was conducted with the following results: No documentation of similar LER events with an undetermined root cause at Ginna Station could be identified.
C.SPECIAL COMMENTS None.%AC SOIIM SEEA ISA l
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