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| {{#Wiki_filter:('A'19'(90RYjREGULARYINFORMATION DISTRIBUTI SYSTEM(RIDS)1ACCESSION NBR:9609130028 DOC.DATE: | | {{#Wiki_filter:('A'1 9'(90RY j REGULA RY INFORMATION DISTRIBUTI SYSTEM (RIDS)1 ACCESSION NBR:9609130028 DOC.DATE: 96/09/05 NOTARIZED: |
| 96/09/05NOTARIZED: | | NO DOCKET FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G 05000244 AUTH.NAME AUTHOR AFFILIATION MARTIN,J.T. |
| NODOCKETFACIL:50-244 RobertEmmetGinnaNuclearPlant,Unit1,Rochester G05000244AUTH.NAMEAUTHORAFFILIATION MARTIN,J.T.
| | Rochester Gas&Electric Corp.MERCREDY,R.C. |
| Rochester Gas&ElectricCorp.MERCREDY,R.C. | | Rochester Gas a Electric Corp.RECIP.NAME RECIPIENT AFFILIATION VISSINGiG.S. |
| Rochester GasaElectricCorp.RECIP.NAME RECIPIENT AFFILIATION VISSINGiG.S. | |
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| ==SUBJECT:== | | ==SUBJECT:== |
| LER96-011-00:on 960807,improper configuration ofcircuitbreakeroccurred.Due toundetected internalinterference, resulting inautomatic startofbothauxiliary feedwater pumps.RunningAFWpumpsweresecured.W/960905 ltr.DISTRIBUTION CODE:IE22TCOPIESRECEIVED:LTR
| | 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.DISTRIBUTION CODE: IE22T COPIES RECEIVED:LTR |
| /ENCL(SIZE:TITLE:50.73/50.9 LicenseeEventReport(LER),incidentRpt,etc.NOTES:License Expdateinaccordance with10CFR2,2.109(9/19/72). | | /ENCL (SIZE: 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). |
| 05000244ERECIPIENT IDCODE/NAME PD1-1PDINTERNAL:
| | 05000244 E RECIPIENT ID CODE/NAME PD1-1 PD INTERNAL: E./Mig/EQB FILE CENA~/5E/EELB NRR/DRCH/HHFB NRR/DRCH/HOLB NRR/DRPM/PECB NRR/DSSA/SRXB RGN1 FILE 01 COPIES LTTR ENCL 1 1 2 2 1 1 1 1 1 1 1 1 1 1 1 1 1 1 RECIPIENT ID CODE/NAME VISSING,G. |
| E./Mig/EQB FILECENA~/5E/EELBNRR/DRCH/HHFB NRR/DRCH/HOLB NRR/DRPM/PECB NRR/DSSA/SRXB RGN1FILE01COPIESLTTRENCL112211111111111111RECIPIENT IDCODE/NAME VISSING,G. | | AEOD/SPD/RRAB NRR/DE/ECGB NRR/DE/EMEB NRR/DRCH/HICB NRR/DRCH/HQMB NRR/DSSA/SPLB RES/DSIR/EIB COPIES LTTR ENCL 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 D 0 EXTERNAL: L ST LOBBY WARD NOAC MURPHY,G.A NRC PDR 1 1 1 1 1 1 LITCO BRYCE,J H.'vAC POORE,W.NUDOCS FULL TXT 2 2 1 1 1 1 N NOTE TO ALL"RIDS" RECIPIENTS: |
| AEOD/SPD/RRAB NRR/DE/ECGB NRR/DE/EMEB NRR/DRCH/HICB NRR/DRCH/HQMB NRR/DSSA/SPLB RES/DSIR/EIB COPIESLTTRENCL1111111111111111D0EXTERNAL: | | PLEASE HELP US TO REDUCE WASTE!CONTACT THE DOCUMENT CONTROL DESK, ROOM OWFN SD-5(EXT~415-2083)TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEEDl FULL TEXT CONVERSION REQUIRED TOTAL NUMBER OF COP,;-~S REQUIRED: LTTR 25 ENCL 25 4ND ROCHESTERGASANDELECTRICCORPORATION |
| LSTLOBBYWARDNOACMURPHY,G.A NRCPDR111111LITCOBRYCE,JH.'vACPOORE,W.NUDOCSFULLTXT221111NNOTETOALL"RIDS"RECIPIENTS:
| | ~89EASTAVfNUE,ROCHESTER,N.Y Id6d9000I 7 AREA CODE7165d62700 ROScRT C.MECREDY Vce President Nvctear Ooerrst'or s September 5, 1996 U.S.Nuclear Regulatory Commission Document Control Desk Attn: Guy S.Vissing Project Directorate I-1 Washington, D.C.20555 |
| PLEASEHELPUSTOREDUCEWASTE!CONTACTTHEDOCUMENTCONTROLDESK,ROOMOWFNSD-5(EXT~415-2083)
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| TOELIMINATE YOURNAMEFROMDISTRIBUTION LISTSFORDOCUMENTS YOUDON'TNEEDlFULLTEXTCONVERSION REQUIREDTOTALNUMBEROFCOP,;-~SREQUIRED:
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| LTTR25ENCL25 4NDROCHESTERGASANDELECTRICCORPORATION
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| ~89EASTAVfNUE,ROCHESTER,N.Y Id6d9000I 7AREACODE7165d62700 ROScRTC.MECREDYVcePresident NvctearOoerrst'or sSeptember 5,1996U.S.NuclearRegulatory Commission DocumentControlDeskAttn:GuyS.VissingProjectDirectorate I-1Washington, D.C.20555 | |
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| ==Subject:== | | ==Subject:== |
| LER96-011,ImproperConfiguration ofCircuitBreaker,DuetoUndetected InternalInterference, ResultsinAutomatic StartofBothAuxiliary Feedwater PumpsR.E.GinnaNuclearPowerPlantDocketNo.50-244
| | LER 96-011, Improper Configuration of Circuit Breaker, Due to Undetected Internal Interference, Results in Automatic Start of Both Auxiliary Feedwater Pumps R.E.Ginna Nuclear Power Plant Docket No.50-244 |
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| ==DearMr.Vissing:== | | ==Dear Mr.Vissing:== |
| Inaccordance with10CFR50.73,LicenseeEventReportSystem,item(a)(2)(iv),whichrequiresareportof,"Anyeventorcondition thatresultedinamanualorautomatic actuation ofanyengineered safetyfeature(ESF),including thereactorprotection system(RPS)",theattachedLicenseeEventReportLER96-011isherebysubmitted.
| | 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 a manual or automatic actuation of any engineered safety feature (ESF), including the reactor protection system (RPS)", the attached Licensee Event Report LER 96-011 is hereby submitted. |
| Th!seventhasinnowayaffectedthepublic'shealthandsafety.Verytrulyyours,RobertC.Mecredyxc:Mr.GuyS.Vissing(MailStop14C7)PWRProjectDirectorate I-1Washington, D.C.20555U.S.NuclearRegulatory Commission RegionI475Allendale RoadKingofPrussia,PA19406GinnaSeniorResidentInspector c7609i30028 960905PDRaOOCK0500044SPDR NRCFORM366(4-95)U.S.NUCLEARREGULATORY COMMISSIO LICENSEEEVENTREPORT(LER)(Seereverseforrequirednumberofdigits/characters fcreachblock)APPROVEDBYOMBNO.3160%104EXPIRES04/30/98ESTIMATED BURDENPERRESPONSEToCOMPLYWITHTHISMANDATORY INFORMATION COLLECTION REQUEST:50.0HRS.REPORTEDLESSONSLEARNEDAREINCORPORATED INTOTHELICENSING PROCESSANDFEDBACKToINDUSTRY. | | Th!s event has in no way affected the public's health and safety.Very truly yours, Robert C.Mecredy xc: Mr.Guy S.Vissing (Mail Stop 14C7)PWR Project Directorate I-1 Washington, D.C.20555 U.S.Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 Ginna Senior Resident Inspector c7609i30028 960905 PDR aOOCK 05000 44 S PDR NRC FORM 366 (4-95)U.S.NUCLEAR REGULATORY COMMISSIO LICENSEE EVENT REPORT (LER)(See reverse for required number of digits/characters fcr each block)APPROVED BY OMB NO.3160%104 EXPIRES 04/30/98 ESTIMATED BURDEN PER RESPONSE To COMPLY WITH THIS MANDATORY INFORMATION COLLECTION REQUEST: 50.0 HRS.REPORTED LESSONS LEARNED ARE INCORPORATED INTO THE LICENSING PROCESS AND FED BACK To INDUSTRY.FORWARD COMMENTS REGARDING BURDEN ESTIMATE To THE INFORMATION AND RECORDS MANAGEMENT BRANCH (T-6 F33), U.S.NUCI.EAR REGULATORY COMMISSION, WASHINGTON, DC 20555 cool, AND TO THE PAPERWORK REDUCTION PROJECT FACIUTY NAME II I R.E.Ginna Nuclear Power Plant DOCKET NUMBER I2)05000244 PAOE I3)1OF5 TITLE (4I Improper Configuration of Circuit Breaker, Due to Undetected Internal Interference, Results in Automatic Start of Both Auxiliary Feedwater Pumps EVENT DATE (6)LER NUMBER (6)REPORT DATE (7)OTHER FACILITIES INVOLVED (8)MONTH 08 DAY 07 YEAR 96 SEQUENTIAL REVISION NUMBER NUMBER 96-011-00 MONTH OAY 09 05 96 FACIUTY NAME FACIUTY NAME DOCKET NUMBER DOCKET NUMBER OPERATING MODE (9)POWER LEVEL (10)000 20.2201(b) 20.2203(a) |
| FORWARDCOMMENTSREGARDING BURDENESTIMATEToTHEINFORMATION ANDRECORDSMANAGEMENT BRANCH(T-6F33),U.S.NUCI.EARREGULATORY COMMISSION, WASHINGTON, DC20555cool,ANDTOTHEPAPERWORK REDUCTION PROJECTFACIUTYNAMEIIIR.E.GinnaNuclearPowerPlantDOCKETNUMBERI2)05000244PAOEI3)1OF5TITLE(4IImproperConfiguration ofCircuitBreaker,DuetoUndetected InternalInterference, ResultsinAutomatic StartofBothAuxiliary Feedwater PumpsEVENTDATE(6)LERNUMBER(6)REPORTDATE(7)OTHERFACILITIES INVOLVED(8)MONTH08DAY07YEAR96SEQUENTIAL REVISIONNUMBERNUMBER96-011-00MONTHOAY090596FACIUTYNAMEFACIUTYNAMEDOCKETNUMBERDOCKETNUMBEROPERATING MODE(9)POWERLEVEL(10)00020.2201(b) 20.2203(a)
| | (1)20.2203(a)(2)(i) 20.2203(a)(2)(ii) 20.2203(a)(2)(iii)20.2203(a) |
| (1)20.2203(a)(2)(i) 20.2203(a)(2)(ii) 20.2203(a)(2) | |
| (iii)20.2203(a) | |
| (2)(iv)20.2203(a) | | (2)(iv)20.2203(a) |
| (2)(v)20.2203(a) | | (2)(v)20.2203(a) |
| (3)(i)20.2203(a)(3) | | (3)(i)20.2203(a)(3)(ii)20.2203(a) |
| (ii)20.2203(a) | | (4)50.36(c)(1) 50.36(c)(2) 50.73(a)(2)(i)50.73(a)(2)(ii)50.73(a)(2)(iii)X 50.73(a)(2)(iv) 50.73(a)(2)(v) 50.73(a)(2)(vii) |
| (4)50.36(c)(1) 50.36(c)(2) 50.73(a)(2)(i)50.73(a)(2) | | THIS REPORT IS SUBMITTED PUR SUANT TO THE REQUIREMENTS OF 10 CFR%: (Check one or more)(11)50.73(a)(2)(viii)50.73(a)(2)(x)73.71 OTHER Specify in Abstract below or m NRC Form 366A NAME LICENSEE CONTACT FOR THIS LER (12)ELEFHONE NUMBER ilncrvde Area Codel John T.St.Martin-Technical Assistant COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESC (716)771-3641 RIBED IN THIS REPORT (13)CAUSE SYSTEM COMPONENT MANUFACTURER To NPRDS CAUSE SYSTEM COMPONENT MANUFACTURER REPORTABLE To NPROS SUPPLEMENTAL REPORT EXPECTED (14)YES (If yes, complete EXPECTED SUBMISSION DATE).X NO EXPECTED SUBMISSION DATE (16)MONTH DAY YEAR ABSTRACT (Limit to 1400 spaces, i.e., approximately 15 single-spaced typewritten lines)(16)On August 7, 1996, at approximately 2009 EDST, the plant was in IVlode 3 with the reactor coolant system being maintained at a temperature of 545 degrees F and a pressurizer pressure of 2235 PSIG.With no auxiliary feedwater pumps running and one main feedwater pump circuit breaker racked out in the"test" position,'n"AFW Bypass Switch" was moved from"Defeat" to"Normal".An undetected improper configuration of the circuit breaker created the logic that both main feedwater pump breakers were already open.This created the logic for autostart of both the"A" and"B" motor-driven auxiliary feedwater pumps.Immediate action was to stabilize auxiliary feedwater flow to both steam generators. |
| (ii)50.73(a)(2)(iii)X50.73(a)(2)(iv) 50.73(a)(2)(v) 50.73(a)(2)(vii) | | The underlying cause of the autostart was that the logic for autostart divas present due to an undetected internal interference within the circuit breaker between the racking arm and the actuating rod for the 52S auxiliary switch, which prevented this switch from opening to provide the circuit logic that the breaker was in the closed position.This event is NUREG-1022 Cause Code (A).Corrective action to prevent recurrence is outlined in Section V.B.NRC FORM 366 (4-95) |
| THISREPORTISSUBMITTED PURSUANTTOTHEREQUIREMENTS OF10CFR%:(Checkoneormore)(11)50.73(a)(2)(viii) 50.73(a)(2)
| | NRC FORM 366A (4-95)LICENSEE EVENT REPORT (LER)TEXT CONTINUATION U.S.NUCLEAR REGULATORY COMMISSION FACILITY NAME (1)R.E.Ginna Nuclear Power Plant DOCKET 05000244 LER NUMBER (6)YEAR SEQUENTIAL REVISION NUMBER NUMBER 96-011-00 PAGE (3)2 OF 5 TEXT iif more speceis required, use edditionef copies of NRC Form 366A j (17)PRE-EVENT PLANT CONDITIONS: |
| (x)73.71OTHERSpecifyinAbstractbelowormNRCForm366ANAMELICENSEECONTACTFORTHISLER(12)ELEFHONENUMBERilncrvdeAreaCodelJohnT.St.Martin-Technical Assistant COMPLETEONELINEFOREACHCOMPONENT FAILUREDESC(716)771-3641RIBEDINTHISREPORT(13)CAUSESYSTEMCOMPONENT MANUFACTURER ToNPRDSCAUSESYSTEMCOMPONENT MANUFACTURER REPORTABLE ToNPROSSUPPLEMENTAL REPORTEXPECTED(14)YES(Ifyes,completeEXPECTEDSUBMISSION DATE).XNOEXPECTEDSUBMISSION DATE(16)MONTHDAYYEARABSTRACT(Limitto1400spaces,i.e.,approximately 15single-spaced typewritten lines)(16)OnAugust7,1996,atapproximately 2009EDST,theplantwasinIVlode3withthereactorcoolantsystembeingmaintained atatemperature of545degreesFandapressurizer pressureof2235PSIG.Withnoauxiliary feedwater pumpsrunningandonemainfeedwater pumpcircuitbreakerrackedoutinthe"test"position,'n "AFWBypassSwitch"wasmovedfrom"Defeat"to"Normal". | | On August 7, 1996, at approximately 2009 EDST, the plant was in Mode 3 as a result of a voluntary plant shutdown to upgrade motor-operated valves in the residual heat removal IRHR)system.Valve upgrades were completed and plant heatup and startup was in progress.The reactor coolant system IRCS)was being maintained at a temperature of approximately 545 degrees F and a pressurizer (PRZR)pressure of approximately 2235 PSIG.The circuit breaker for the"A" main feedwater IMFW)pump had jumpers installed and was closed in the"test" position, to comply with temporary administrative requirements. |
| Anundetected improperconfiguration ofthecircuitbreakercreatedthelogicthatbothmainfeedwater pumpbreakerswerealreadyopen.Thiscreatedthelogicforautostart ofboththe"A"and"B"motor-driven auxiliary feedwater pumps.Immediate actionwastostabilize auxiliary feedwater flowtobothsteamgenerators.
| | Auxiliary feedwater IAFW)pumps had just been secured as directed by these temporary administrative requirements, so there were no AFW pumps running.II.DESCRIPTION OF EVENT: A.DATES AND APPROXIMATE TIMES OF MAJOR OCCURRENCES: |
| Theunderlying causeoftheautostart wasthatthelogicforautostart divaspresentduetoanundetected internalinterference withinthecircuitbreakerbetweentherackingarmandtheactuating rodforthe52Sauxiliary switch,whichprevented thisswitchfromopeningtoprovidethecircuitlogicthatthebreakerwasintheclosedposition.
| | o August 7, 1996, 2009 EDST: Event date and time.o August 7, 1996, 2009 EDST: Discovery date and time.o August 7, 1996, 2024 EDST: One running AFW pump is secured.o August 7, 1996, 2135 EDST: All running AFW pumps are secured.EVENT: On August 7, 1996, at approximately 2009 EDST, the plant was in Mode 3.The RCS was being maintained at a temperature of approximately 545 degrees F and a PRZR pressure of approximately 2235 PSIG.As directed by Normal Operating Procedure 0-1.2,"Plant Startup From Hot Shutdown to Full Load", the Control Room operators moved an"AFW Bypass Switch" from the"Defeat" to the"Normal" position.Due to an undetected improper configuration of the circuit breaker for the"A" MFW pump, the 2 of 2 logic for both MFW pump breakers open was present, which caused an autostart of both the"A" and"B" AFW pumps.The Control Room operators observed the autostart of both the"A" and"B" AFW pumps, and controlled AFW flow to the desired flow rate for Mode 3 conditions. |
| ThiseventisNUREG-1022 CauseCode(A).Corrective actiontopreventrecurrence isoutlinedinSectionV.B.NRCFORM366(4-95)
| | One of the running AFW pumps was secured at approximately 2024 EDST.The Control Room operators requested that plant electricians investigate the problem.Electricians determined, when racking out the circuit breaker into the"test" position, the breaker positioning arm had travelled beyond its mechanical stop.This caused an undetected interference between the racking arm and the 52S auxiliary switch actuating rod, which prevented the 52S switch from opening to provide circuit logic that the breaker was in the closed position.The breaker was properly racked out, and electricians verified there was no interference and that the 52S switch had opened.NIIC FOAM 366A (4-95) tl NRC FORM 366A (4-95)LICENSEE EXTENT REPORT (LER)TEXT CONTINUATION U.S.NUCLEAR REGULATORY COMMISSION FACILITY NAME (1)R.E.Ginna Nuclear Power Plant DOCKET 05000244 LER NUMBER (6)YEAR SEQUENTIAL REVISION NUMBER NUMBER 96-011-00 PAGE (3)3 OF 5 TEXT (If more spece is required, use eddi donel copies of NRC Form 366AJ (17)C.INOPERABLE STRUCTURES, COMPONENTS, OR SYSTEMS THAT CONTRIBUTED TO THE EVENT: None D.OTHER SYSTEMS OR SECONDARY FUNCTIONS AFFECTED: None E.METHOD OF DISCOVERY: |
| NRCFORM366A(4-95)LICENSEEEVENTREPORT(LER)TEXTCONTINUATION U.S.NUCLEARREGULATORY COMMISSION FACILITYNAME(1)R.E.GinnaNuclearPowerPlantDOCKET05000244LERNUMBER(6)YEARSEQUENTIAL REVISIONNUMBERNUMBER96-011-00PAGE(3)2OF5TEXTiifmorespeceisrequired, useedditionef copiesofNRCForm366Aj(17)PRE-EVENT PLANTCONDITIONS:
| | This event was immediately apparent when both the"A" and"B" AFW pumps autostarted after the AFW Bypass Switch was placed in the"Normal".position.OPERATOR ACTION: After both the"A" and"B" AFW pumps autostarted, the Control Room operators took prompt actions to control AFW flow.They requested that the plant electricians determine the cause of the problem.The Control Room operators subsequently notified higher supervision and notified the NRC per 10CFR50.72 (b)(2)(ii), non-emergency four hour notification, at approximately 2226 EDST on August 7, 1996.G.SAFETY SYSTEM RESPONSES: |
| OnAugust7,1996,atapproximately 2009EDST,theplantwasinMode3asaresultofavoluntary plantshutdowntoupgrademotor-operated valvesintheresidualheatremovalIRHR)system.Valveupgradeswerecompleted andplantheatupandstartupwasinprogress.
| | Both the"A" and"B" AFW pumps autostarted as per design.CAUSE OF EVENT: A.IMMEDIATE CAUSE: The immediate cause of the autostart of both the"A" and"B" AFW pumps was the autostart logic, which was satisfied by 52S contacts providing circuit logic that both MFW pump breakers were open and an AFW Bypass Switch in"Normal".B.INTERMEDIATE CAUSE: The intermediate cause of autostart logic being satisfied was an undetected improper configuration of the"A"'MFW pump circuit breaker.NRC FORM 36:6 I's) |
| ThereactorcoolantsystemIRCS)wasbeingmaintained atatemperature ofapproximately 545degreesFandapressurizer (PRZR)pressureofapproximately 2235PSIG.Thecircuitbreakerforthe"A"mainfeedwater IMFW)pumphadjumpersinstalled andwasclosedinthe"test"position, tocomplywithtemporary administrative requirements.
| | NRC FORM 366A (4-95)LICENSEE EVENT REPORT (LER)TEXT CONTINUATION U.S.NUCLEAR REGULATORY COMMISSION FACILITY NAME (1)DOCKET LER NUMBER (6)PAGE (3)R.E.Ginna Nuclear Power Plant 05000244 YEAR SEQUENTIAL REVISION NUMBER NUMBER 4 OF 5 96-011-00 TEXT Iif more space is required, use additional copies of NRC Form 36@A/(17)C.ROOT CAUSE: The underlying cause of the improper configuration was an undetected internal interference within the"A" MFW pump circuit breaker.When the breaker was racked out to the test position, the breaker positioning arm travelled beyond its mechanical stop.This caused interference between the racking arm and the actuating rod for the 52S auxiliary contact switch.Therefore, while the breaker was physically closed in the"test" position, the auxiliary switch did not provide circuit logic that the breaker was in the closed position.This situation was created to be in compliance with the Ginna Station Improved Technical Specifications (ITS)Table 3.3.2-1 Function 6.f.To prevent an unnecessary actuation of both AFW pumps during Mode 2 conditions, a MFW pump breaker may be administratively closed in the test position, provided it is capable of being tripped on undervoltage and overcurrent conditions. |
| Auxiliary feedwater IAFW)pumpshadjustbeensecuredasdirectedbythesetemporary administrative requirements, sotherewerenoAFWpumpsrunning.II.DESCRIPTION OFEVENT:A.DATESANDAPPROXIMATE TIMESOFMAJOROCCURRENCES: | | The administrative requirements were established to comply with ITS Table 3.3.2-1, which requires the autostart function of the motor-driven AFW pump upon opening of both MFW pump breakers during Modes 1 and 2.Prior to Amendment No.61 to the ITS, this function was only required in Mode 1 when the MFW pumps were actually in service.The addition of Mode 2 (when the MFW pumps may not be in service)was inadvertently added to the ITS by Amendment No.61.This event is NUREG-1022 Cause Code (A),"Personnel Error".This error was a cognitive error on the part of a plant electrician, who did not detect the interference between the racking arm and the actuating rod.This error was associated with activities that were covered by an approved procedure, and was not contrary to that procedure. |
| oAugust7,1996,2009EDST:Eventdateandtime.oAugust7,1996,2009EDST:Discovery dateandtime.oAugust7,1996,2024EDST:OnerunningAFWpumpissecured.oAugust7,1996,2135EDST:AllrunningAFWpumpsaresecured.EVENT:OnAugust7,1996,atapproximately 2009EDST,theplantwasinMode3.TheRCSwasbeingmaintained atatemperature ofapproximately 545degreesFandaPRZRpressureofapproximately 2235PSIG.AsdirectedbyNormalOperating Procedure 0-1.2,"PlantStartupFromHotShutdowntoFullLoad",theControlRoomoperators movedan"AFWBypassSwitch"fromthe"Defeat"tothe"Normal"position.
| | The procedural guidance was correct, but enhancements to the procedure have been identified. |
| Duetoanundetected improperconfiguration ofthecircuitbreakerforthe"A"MFWpump,the2of2logicforbothMFWpumpbreakersopenwaspresent,whichcausedanautostart ofboththe"A"and"B"AFWpumps.TheControlRoomoperators observedtheautostart ofboththe"A"and"B"AFWpumps,andcontrolled AFWflowtothedesiredflowrateforMode3conditions.
| | There were no unusual characteristics of the location of this breaker that contributed to this event.Note that this interference can only be created when racking the breaker out to the test position.The autostart of the AFW pump does not meet the NUMARC 93-01,"Industry Guideline for Monitoring the Effectiveness of Maintenance at Nuclear Power Plants", definition of a"Maintenance Preventable Functional Failure".IV.ANALYSIS OF EVENT: This event is reportable 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 a manual or automatic actuation of any engineered safety feature (ESF), including the reactor protection system (RPS)".The start of an AFW pump is an actuation nf an ESF.An assessment was performed considering both the safety consequences and implications of this event with the following results and conclusions: |
| OneoftherunningAFWpumpswassecuredatapproximately 2024EDST.TheControlRoomoperators requested thatplantelectricians investigate theproblem.Electricians determined, whenrackingoutthecircuitbreakerintothe"test"position, thebreakerpositioning armhadtravelled beyonditsmechanical stop.Thiscausedanundetected interference betweentherackingarmandthe52Sauxiliary switchactuating rod,whichprevented the52Sswitchfromopeningtoprovidecircuitlogicthatthebreakerwasintheclosedposition.
| | There were no operational or safety consequences or implications attributed to the autostart of both the"A" and"B" AFW pumps because: o The autostart occurred with acceptable levels in both S/Gs.AFW flow was controlled to maintain these levels.NRC FOR)A 366A (4.95) |
| Thebreakerwasproperlyrackedout,andelectricians verifiedtherewasnointerference andthatthe52Sswitchhadopened.NIICFOAM366A(4-95) tl NRCFORM366A(4-95)LICENSEEEXTENTREPORT(LER)TEXTCONTINUATION U.S.NUCLEARREGULATORY COMMISSION FACILITYNAME(1)R.E.GinnaNuclearPowerPlantDOCKET05000244LERNUMBER(6)YEARSEQUENTIAL REVISIONNUMBERNUMBER96-011-00PAGE(3)3OF5TEXT(Ifmorespeceisrequired, useeddidonelcopiesofNRCForm366AJ(17)C.INOPERABLE STRUCTURES, COMPONENTS, ORSYSTEMSTHATCONTRIBUTED TOTHEEVENT:NoneD.OTHERSYSTEMSORSECONDARY FUNCTIONS AFFECTED:
| | NRC FORM 366A (4-96)LICENSEE EVENT REPORT (LER)TEXT CONTINUATION U.S.NUCLEAR REGULATORY COMMISSION FACILITY NAME (1)R.E.Ginna Nuclear Power Plant DOCKET 05000244 LER NUMBER (6)YEAR SEQUENTIAL REVISION NUMBER NUMBER 96-011-00 PAGE (3)5 OF 5 TEXT llf more spaceis required, use additional copies of NRC Form 366A/(17)o The limiting case for the supply of AFW is the Loss of Feedwater accident at 100'/o power.The plant condition at the time of this event was less than 5%power.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: AFW flow was controlled as desired to maintain S/G level.o The running AFW pumps were secured.B.ACTION TAKEN OR PLANNED TO PREVENT RECURRENCE: |
| NoneE.METHODOFDISCOVERY:
| | The ITS will be revised to eliminate the need for having a MFW pump breaker closed in the test position during Mode 2 conditions. |
| Thiseventwasimmediately apparentwhenboththe"A"and"B"AFWpumpsautostarted aftertheAFWBypassSwitchwasplacedinthe"Normal".
| | Procedure 0-2.1 will be enhanced to include specifically addressing that the 52S switch actuating rod is in the correct position when the breaker is racked out in the test position.Vi.ADDITIONAL INFORMATION: |
| position. | | A.FAILED COMPONENTS: |
| OPERATORACTION:Afterboththe"A"and"B"AFWpumpsautostarted, theControlRoomoperators tookpromptactionstocontrolAFWflow.Theyrequested thattheplantelectricians determine thecauseoftheproblem.TheControlRoomoperators subsequently notifiedhighersupervision andnotifiedtheNRCper10CFR50.72 (b)(2)(ii),non-emergency fourhournotification, atapproximately 2226EDSTonAugust7,1996.G.SAFETYSYSTEMRESPONSES:
| | None B.PREVIOUS LERs ON SIMILAR EVENTS: A similar LER event historical search was conducted with the following results: No documentation of similar LER events with the same root cause could be identified. |
| Boththe"A"and"B"AFWpumpsautostarted asperdesign.CAUSEOFEVENT:A.IMMEDIATE CAUSE:Theimmediate causeoftheautostart ofboththe"A"and"B"AFWpumpswastheautostart logic,whichwassatisfied by52Scontactsproviding circuitlogicthatbothMFWpumpbreakerswereopenandanAFWBypassSwitchin"Normal".
| | However, LERs 96-004, 96-008, and 96-010 are similar events with different root causes.C.SPECIAL COMfvlENTS: |
| B.INTERMEDIATE CAUSE:Theintermediate causeofautostart logicbeingsatisfied wasanundetected improperconfiguration ofthe"A"'MFWpumpcircuitbreaker.NRCFORM36:6I's) | | None NRC FORM 9"~A (4-95)}} |
| NRCFORM366A(4-95)LICENSEEEVENTREPORT(LER)TEXTCONTINUATION U.S.NUCLEARREGULATORY COMMISSION FACILITYNAME(1)DOCKETLERNUMBER(6)PAGE(3)R.E.GinnaNuclearPowerPlant05000244YEARSEQUENTIAL REVISIONNUMBERNUMBER4OF596-011-00TEXTIifmorespaceisrequired, useadditional copiesofNRCForm36@A/(17)C.ROOTCAUSE:Theunderlying causeoftheimproperconfiguration wasanundetected internalinterference withinthe"A"MFWpumpcircuitbreaker.Whenthebreakerwasrackedouttothetestposition, thebreakerpositioning armtravelled beyonditsmechanical stop.Thiscausedinterference betweentherackingarmandtheactuating rodforthe52Sauxiliary contactswitch.Therefore, whilethebreakerwasphysically closedinthe"test"position, theauxiliary switchdidnotprovidecircuitlogicthatthebreakerwasintheclosedposition.
| |
| Thissituation wascreatedtobeincompliance withtheGinnaStationImprovedTechnical Specifications (ITS)Table3.3.2-1Function6.f.Topreventanunnecessary actuation ofbothAFWpumpsduringMode2conditions, aMFWpumpbreakermaybeadministratively closedinthetestposition, provideditiscapableofbeingtrippedonundervoltage andovercurrent conditions.
| |
| Theadministrative requirements wereestablished tocomplywithITSTable3.3.2-1,whichrequirestheautostart functionofthemotor-driven AFWpumpuponopeningofbothMFWpumpbreakersduringModes1and2.PriortoAmendment No.61totheITS,thisfunctionwasonlyrequiredinMode1whentheMFWpumpswereactuallyinservice.TheadditionofMode2(whentheMFWpumpsmaynotbeinservice)wasinadvertently addedtotheITSbyAmendment No.61.ThiseventisNUREG-1022 CauseCode(A),"Personnel Error".Thiserrorwasacognitive erroronthepartofaplantelectrician, whodidnotdetecttheinterference betweentherackingarmandtheactuating rod.Thiserrorwasassociated withactivities thatwerecoveredbyanapprovedprocedure, andwasnotcontrarytothatprocedure.
| |
| Theprocedural guidancewascorrect,butenhancements totheprocedure havebeenidentified.
| |
| Therewerenounusualcharacteristics ofthelocationofthisbreakerthatcontributed tothisevent.Notethatthisinterference canonlybecreatedwhenrackingthebreakerouttothetestposition.
| |
| Theautostart oftheAFWpumpdoesnotmeettheNUMARC93-01,"Industry Guideline forMonitoring theEffectiveness ofMaintenance atNuclearPowerPlants",definition ofa"Maintenance Preventable Functional Failure".
| |
| IV.ANALYSISOFEVENT:Thiseventisreportable inaccordance with10CFR50.73,LicenseeEventReportSystem,item(a)(2)(iv),whichrequiresareportof,"Anyeventorcondition thatresultedinamanualorautomatic actuation ofanyengineered safetyfeature(ESF),including thereactorprotection system(RPS)".ThestartofanAFWpumpisanactuation nfanESF.Anassessment wasperformed considering boththesafetyconsequences andimplications ofthiseventwiththefollowing resultsandconclusions: | |
| Therewerenooperational orsafetyconsequences orimplications attributed totheautostart ofboththe"A"and"B"AFWpumpsbecause:oTheautostart occurredwithacceptable levelsinbothS/Gs.AFWflowwascontrolled tomaintaintheselevels.NRCFOR)A366A(4.95)
| |
| NRCFORM366A(4-96)LICENSEEEVENTREPORT(LER)TEXTCONTINUATION U.S.NUCLEARREGULATORY COMMISSION FACILITYNAME(1)R.E.GinnaNuclearPowerPlantDOCKET05000244LERNUMBER(6)YEARSEQUENTIAL REVISIONNUMBERNUMBER96-011-00PAGE(3)5OF5TEXTllfmorespaceisrequired, useadditional copiesofNRCForm366A/(17)oThelimitingcaseforthesupplyofAFWistheLossofFeedwater accidentat100'/opower.Theplantcondition atthetimeofthiseventwaslessthan5%power.Basedontheabove,itcanbeconcluded thatthepublic'shealthandsafetywasassuredatalltimes.V.CORRECTIVE ACTION:A.ACTIONTAKENTORETURNAFFECTEDSYSTEMSTOPRE-EVENT NORMALSTATUS:AFWflowwascontrolled asdesiredtomaintainS/Glevel.oTherunningAFWpumpsweresecured.B.ACTIONTAKENORPLANNEDTOPREVENTRECURRENCE:
| |
| TheITSwillberevisedtoeliminate theneedforhavingaMFWpumpbreakerclosedinthetestpositionduringMode2conditions.
| |
| Procedure 0-2.1willbeenhancedtoincludespecifically addressing thatthe52Sswitchactuating rodisinthecorrectpositionwhenthebreakerisrackedoutinthetestposition. | |
| Vi.ADDITIONAL INFORMATION: | |
| A.FAILEDCOMPONENTS: | |
| NoneB.PREVIOUSLERsONSIMILAREVENTS:AsimilarLEReventhistorical searchwasconducted withthefollowing results:Nodocumentation ofsimilarLEReventswiththesamerootcausecouldbeidentified.
| |
| However,LERs96-004,96-008,and96-010aresimilareventswithdifferent rootcauses.C.SPECIALCOMfvlENTS: | |
| NoneNRCFORM9"~A(4-95)}}
| |
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
('A'1 9'(90RY j REGULA RY INFORMATION DISTRIBUTI SYSTEM (RIDS)1 ACCESSION NBR:9609130028 DOC.DATE: 96/09/05 NOTARIZED:
NO DOCKET FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G 05000244 AUTH.NAME AUTHOR AFFILIATION MARTIN,J.T.
Rochester Gas&Electric Corp.MERCREDY,R.C.
Rochester Gas a Electric Corp.RECIP.NAME RECIPIENT AFFILIATION VISSINGiG.S.
SUBJECT:
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.DISTRIBUTION CODE: IE22T COPIES RECEIVED:LTR
/ENCL (SIZE: 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).
05000244 E RECIPIENT ID CODE/NAME PD1-1 PD INTERNAL: E./Mig/EQB FILE CENA~/5E/EELB NRR/DRCH/HHFB NRR/DRCH/HOLB NRR/DRPM/PECB NRR/DSSA/SRXB RGN1 FILE 01 COPIES LTTR ENCL 1 1 2 2 1 1 1 1 1 1 1 1 1 1 1 1 1 1 RECIPIENT ID CODE/NAME VISSING,G.
AEOD/SPD/RRAB NRR/DE/ECGB NRR/DE/EMEB NRR/DRCH/HICB NRR/DRCH/HQMB NRR/DSSA/SPLB RES/DSIR/EIB COPIES LTTR ENCL 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 D 0 EXTERNAL: L ST LOBBY WARD NOAC MURPHY,G.A NRC PDR 1 1 1 1 1 1 LITCO BRYCE,J H.'vAC POORE,W.NUDOCS FULL TXT 2 2 1 1 1 1 N NOTE TO ALL"RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE!CONTACT THE DOCUMENT CONTROL DESK, ROOM OWFN SD-5(EXT~415-2083)TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEEDl FULL TEXT CONVERSION REQUIRED TOTAL NUMBER OF COP,;-~S REQUIRED: LTTR 25 ENCL 25 4ND ROCHESTERGASANDELECTRICCORPORATION
~89EASTAVfNUE,ROCHESTER,N.Y Id6d9000I 7 AREA CODE7165d62700 ROScRT C.MECREDY Vce President Nvctear Ooerrst'or s September 5, 1996 U.S.Nuclear Regulatory Commission Document Control Desk Attn: Guy S.Vissing Project Directorate I-1 Washington, D.C.20555
Subject:
LER 96-011, Improper Configuration of Circuit Breaker, Due to Undetected Internal Interference, Results in Automatic Start of Both Auxiliary Feedwater Pumps R.E.Ginna Nuclear Power Plant Docket No.50-244
Dear Mr.Vissing:
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 a manual or automatic actuation of any engineered safety feature (ESF), including the reactor protection system (RPS)", the attached Licensee Event Report LER 96-011 is hereby submitted.
Th!s event has in no way affected the public's health and safety.Very truly yours, Robert C.Mecredy xc: Mr.Guy S.Vissing (Mail Stop 14C7)PWR Project Directorate I-1 Washington, D.C.20555 U.S.Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 Ginna Senior Resident Inspector c7609i30028 960905 PDR aOOCK 05000 44 S PDR NRC FORM 366 (4-95)U.S.NUCLEAR REGULATORY COMMISSIO LICENSEE EVENT REPORT (LER)(See reverse for required number of digits/characters fcr each block)APPROVED BY OMB NO.3160%104 EXPIRES 04/30/98 ESTIMATED BURDEN PER RESPONSE To COMPLY WITH THIS MANDATORY INFORMATION COLLECTION REQUEST: 50.0 HRS.REPORTED LESSONS LEARNED ARE INCORPORATED INTO THE LICENSING PROCESS AND FED BACK To INDUSTRY.FORWARD COMMENTS REGARDING BURDEN ESTIMATE To THE INFORMATION AND RECORDS MANAGEMENT BRANCH (T-6 F33), U.S.NUCI.EAR REGULATORY COMMISSION, WASHINGTON, DC 20555 cool, AND TO THE PAPERWORK REDUCTION PROJECT FACIUTY NAME II I R.E.Ginna Nuclear Power Plant DOCKET NUMBER I2)05000244 PAOE I3)1OF5 TITLE (4I Improper Configuration of Circuit Breaker, Due to Undetected Internal Interference, Results in Automatic Start of Both Auxiliary Feedwater Pumps EVENT DATE (6)LER NUMBER (6)REPORT DATE (7)OTHER FACILITIES INVOLVED (8)MONTH 08 DAY 07 YEAR 96 SEQUENTIAL REVISION NUMBER NUMBER 96-011-00 MONTH OAY 09 05 96 FACIUTY NAME FACIUTY NAME DOCKET NUMBER DOCKET NUMBER OPERATING MODE (9)POWER LEVEL (10)000 20.2201(b) 20.2203(a)
(1)20.2203(a)(2)(i) 20.2203(a)(2)(ii) 20.2203(a)(2)(iii)20.2203(a)
(2)(iv)20.2203(a)
(2)(v)20.2203(a)
(3)(i)20.2203(a)(3)(ii)20.2203(a)
(4)50.36(c)(1) 50.36(c)(2) 50.73(a)(2)(i)50.73(a)(2)(ii)50.73(a)(2)(iii)X 50.73(a)(2)(iv) 50.73(a)(2)(v) 50.73(a)(2)(vii)
THIS REPORT IS SUBMITTED PUR SUANT TO THE REQUIREMENTS OF 10 CFR%: (Check one or more)(11)50.73(a)(2)(viii)50.73(a)(2)(x)73.71 OTHER Specify in Abstract below or m NRC Form 366A NAME LICENSEE CONTACT FOR THIS LER (12)ELEFHONE NUMBER ilncrvde Area Codel John T.St.Martin-Technical Assistant COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESC (716)771-3641 RIBED IN THIS REPORT (13)CAUSE SYSTEM COMPONENT MANUFACTURER To NPRDS CAUSE SYSTEM COMPONENT MANUFACTURER REPORTABLE To NPROS SUPPLEMENTAL REPORT EXPECTED (14)YES (If yes, complete EXPECTED SUBMISSION DATE).X NO EXPECTED SUBMISSION DATE (16)MONTH DAY YEAR ABSTRACT (Limit to 1400 spaces, i.e., approximately 15 single-spaced typewritten lines)(16)On August 7, 1996, at approximately 2009 EDST, the plant was in IVlode 3 with the reactor coolant system being maintained at a temperature of 545 degrees F and a pressurizer pressure of 2235 PSIG.With no auxiliary feedwater pumps running and one main feedwater pump circuit breaker racked out in the"test" position,'n"AFW Bypass Switch" was moved from"Defeat" to"Normal".An undetected improper configuration of the circuit breaker created the logic that both main feedwater pump breakers were already open.This created the logic for autostart of both the"A" and"B" motor-driven auxiliary feedwater pumps.Immediate action was to stabilize auxiliary feedwater flow to both steam generators.
The underlying cause of the autostart was that the logic for autostart divas present due to an undetected internal interference within the circuit breaker between the racking arm and the actuating rod for the 52S auxiliary switch, which prevented this switch from opening to provide the circuit logic that the breaker was in the closed position.This event is NUREG-1022 Cause Code (A).Corrective action to prevent recurrence is outlined in Section V.B.NRC FORM 366 (4-95)
NRC FORM 366A (4-95)LICENSEE EVENT REPORT (LER)TEXT CONTINUATION U.S.NUCLEAR REGULATORY COMMISSION FACILITY NAME (1)R.E.Ginna Nuclear Power Plant DOCKET 05000244 LER NUMBER (6)YEAR SEQUENTIAL REVISION NUMBER NUMBER 96-011-00 PAGE (3)2 OF 5 TEXT iif more speceis required, use edditionef copies of NRC Form 366A j (17)PRE-EVENT PLANT CONDITIONS:
On August 7, 1996, at approximately 2009 EDST, the plant was in Mode 3 as a result of a voluntary plant shutdown to upgrade motor-operated valves in the residual heat removal IRHR)system.Valve upgrades were completed and plant heatup and startup was in progress.The reactor coolant system IRCS)was being maintained at a temperature of approximately 545 degrees F and a pressurizer (PRZR)pressure of approximately 2235 PSIG.The circuit breaker for the"A" main feedwater IMFW)pump had jumpers installed and was closed in the"test" position, to comply with temporary administrative requirements.
Auxiliary feedwater IAFW)pumps had just been secured as directed by these temporary administrative requirements, so there were no AFW pumps running.II.DESCRIPTION OF EVENT: A.DATES AND APPROXIMATE TIMES OF MAJOR OCCURRENCES:
o August 7, 1996, 2009 EDST: Event date and time.o August 7, 1996, 2009 EDST: Discovery date and time.o August 7, 1996, 2024 EDST: One running AFW pump is secured.o August 7, 1996, 2135 EDST: All running AFW pumps are secured.EVENT: On August 7, 1996, at approximately 2009 EDST, the plant was in Mode 3.The RCS was being maintained at a temperature of approximately 545 degrees F and a PRZR pressure of approximately 2235 PSIG.As directed by Normal Operating Procedure 0-1.2,"Plant Startup From Hot Shutdown to Full Load", the Control Room operators moved an"AFW Bypass Switch" from the"Defeat" to the"Normal" position.Due to an undetected improper configuration of the circuit breaker for the"A" MFW pump, the 2 of 2 logic for both MFW pump breakers open was present, which caused an autostart of both the"A" and"B" AFW pumps.The Control Room operators observed the autostart of both the"A" and"B" AFW pumps, and controlled AFW flow to the desired flow rate for Mode 3 conditions.
One of the running AFW pumps was secured at approximately 2024 EDST.The Control Room operators requested that plant electricians investigate the problem.Electricians determined, when racking out the circuit breaker into the"test" position, the breaker positioning arm had travelled beyond its mechanical stop.This caused an undetected interference between the racking arm and the 52S auxiliary switch actuating rod, which prevented the 52S switch from opening to provide circuit logic that the breaker was in the closed position.The breaker was properly racked out, and electricians verified there was no interference and that the 52S switch had opened.NIIC FOAM 366A (4-95) tl NRC FORM 366A (4-95)LICENSEE EXTENT REPORT (LER)TEXT CONTINUATION U.S.NUCLEAR REGULATORY COMMISSION FACILITY NAME (1)R.E.Ginna Nuclear Power Plant DOCKET 05000244 LER NUMBER (6)YEAR SEQUENTIAL REVISION NUMBER NUMBER 96-011-00 PAGE (3)3 OF 5 TEXT (If more spece is required, use eddi donel copies of NRC Form 366AJ (17)C.INOPERABLE STRUCTURES, COMPONENTS, OR SYSTEMS THAT CONTRIBUTED TO THE EVENT: None D.OTHER SYSTEMS OR SECONDARY FUNCTIONS AFFECTED: None E.METHOD OF DISCOVERY:
This event was immediately apparent when both the"A" and"B" AFW pumps autostarted after the AFW Bypass Switch was placed in the"Normal".position.OPERATOR ACTION: After both the"A" and"B" AFW pumps autostarted, the Control Room operators took prompt actions to control AFW flow.They requested that the plant electricians determine the cause of the problem.The Control Room operators subsequently notified higher supervision and notified the NRC per 10CFR50.72 (b)(2)(ii), non-emergency four hour notification, at approximately 2226 EDST on August 7, 1996.G.SAFETY SYSTEM RESPONSES:
Both the"A" and"B" AFW pumps autostarted as per design.CAUSE OF EVENT: A.IMMEDIATE CAUSE: The immediate cause of the autostart of both the"A" and"B" AFW pumps was the autostart logic, which was satisfied by 52S contacts providing circuit logic that both MFW pump breakers were open and an AFW Bypass Switch in"Normal".B.INTERMEDIATE CAUSE: The intermediate cause of autostart logic being satisfied was an undetected improper configuration of the"A"'MFW pump circuit breaker.NRC FORM 36:6 I's)
NRC FORM 366A (4-95)LICENSEE EVENT REPORT (LER)TEXT CONTINUATION U.S.NUCLEAR REGULATORY COMMISSION FACILITY NAME (1)DOCKET LER NUMBER (6)PAGE (3)R.E.Ginna Nuclear Power Plant 05000244 YEAR SEQUENTIAL REVISION NUMBER NUMBER 4 OF 5 96-011-00 TEXT Iif more space is required, use additional copies of NRC Form 36@A/(17)C.ROOT CAUSE: The underlying cause of the improper configuration was an undetected internal interference within the"A" MFW pump circuit breaker.When the breaker was racked out to the test position, the breaker positioning arm travelled beyond its mechanical stop.This caused interference between the racking arm and the actuating rod for the 52S auxiliary contact switch.Therefore, while the breaker was physically closed in the"test" position, the auxiliary switch did not provide circuit logic that the breaker was in the closed position.This situation was created to be in compliance with the Ginna Station Improved Technical Specifications (ITS)Table 3.3.2-1 Function 6.f.To prevent an unnecessary actuation of both AFW pumps during Mode 2 conditions, a MFW pump breaker may be administratively closed in the test position, provided it is capable of being tripped on undervoltage and overcurrent conditions.
The administrative requirements were established to comply with ITS Table 3.3.2-1, which requires the autostart function of the motor-driven AFW pump upon opening of both MFW pump breakers during Modes 1 and 2.Prior to Amendment No.61 to the ITS, this function was only required in Mode 1 when the MFW pumps were actually in service.The addition of Mode 2 (when the MFW pumps may not be in service)was inadvertently added to the ITS by Amendment No.61.This event is NUREG-1022 Cause Code (A),"Personnel Error".This error was a cognitive error on the part of a plant electrician, who did not detect the interference between the racking arm and the actuating rod.This error was associated with activities that were covered by an approved procedure, and was not contrary to that procedure.
The procedural guidance was correct, but enhancements to the procedure have been identified.
There were no unusual characteristics of the location of this breaker that contributed to this event.Note that this interference can only be created when racking the breaker out to the test position.The autostart of the AFW pump does not meet the NUMARC 93-01,"Industry Guideline for Monitoring the Effectiveness of Maintenance at Nuclear Power Plants", definition of a"Maintenance Preventable Functional Failure".IV.ANALYSIS OF EVENT: This event is reportable 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 a manual or automatic actuation of any engineered safety feature (ESF), including the reactor protection system (RPS)".The start of an AFW pump is an actuation nf an ESF.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 autostart of both the"A" and"B" AFW pumps because: o The autostart occurred with acceptable levels in both S/Gs.AFW flow was controlled to maintain these levels.NRC FOR)A 366A (4.95)
NRC FORM 366A (4-96)LICENSEE EVENT REPORT (LER)TEXT CONTINUATION U.S.NUCLEAR REGULATORY COMMISSION FACILITY NAME (1)R.E.Ginna Nuclear Power Plant DOCKET 05000244 LER NUMBER (6)YEAR SEQUENTIAL REVISION NUMBER NUMBER 96-011-00 PAGE (3)5 OF 5 TEXT llf more spaceis required, use additional copies of NRC Form 366A/(17)o The limiting case for the supply of AFW is the Loss of Feedwater accident at 100'/o power.The plant condition at the time of this event was less than 5%power.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: AFW flow was controlled as desired to maintain S/G level.o The running AFW pumps were secured.B.ACTION TAKEN OR PLANNED TO PREVENT RECURRENCE:
The ITS will be revised to eliminate the need for having a MFW pump breaker closed in the test position during Mode 2 conditions.
Procedure 0-2.1 will be enhanced to include specifically addressing that the 52S switch actuating rod is in the correct position when the breaker is racked out in the test position.Vi.ADDITIONAL INFORMATION:
A.FAILED COMPONENTS:
None B.PREVIOUS LERs ON SIMILAR EVENTS: A similar LER event historical search was conducted with the following results: No documentation of similar LER events with the same root cause could be identified.
However, LERs96-004, 96-008, and 96-010 are similar events with different root causes.C.SPECIAL COMfvlENTS:
None NRC FORM 9"~A (4-95)
