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| {{#Wiki_filter:REGULATORY INFORMATION DISTRIBUTION SYSTEM(RXDS)ACCESSZONNBR:9906080307 DOC.DATE: | | {{#Wiki_filter:REGULATORY INFORMATION DISTRIBUTION SYSTEM (RXDS)A CCESSZON NBR:9906080307 DOC.DATE: 99/06/02 NOTARIZED: |
| 99/06/02NOTARIZED: | | NO DOCKET I PACZL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G ter G 05000244 AUTH.NAME AUTHOR AFFILIATION ST MARTIN,J.T. |
| NODOCKETIPACZL:50-244 RobertEmmetGinnaNuclearPlant,Unit1,Rochester GterG05000244AUTH.NAMEAUTHORAFFILIATION STMARTIN,J.T.
| | Rochester Gas&.Electric Corp.MECREDY,R.C. |
| Rochester Gas&.ElectricCorp.MECREDY,R.C. | | ~Rochester Gas&.Electric Corp.RECIP.NAME |
| ~Rochester Gas&.ElectricCorp.RECIP.NAME | |
| ,RECIPIENT AFFILIATION VISSXNG,G.S. | | ,RECIPIENT AFFILIATION VISSXNG,G.S. |
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| ==SUBJECT:== | | ==SUBJECT:== |
| LER99-009-00:on 990503,instrumentation declaredinoperable inmultiplechannelsresultedincondition prohibited byTS.Causedbyunanticipated highfrequency ACvoltagerippe.EnteredTSLCO3.0.3.With 990602ltr.DISTRIBUTION CODEXE22TCOPIESRECEIVEDeLTRgENCL(SIZEaTITLE:50.73/50.9 LicenseeEventReport(LER),XncidentRpt,etc.NOTES:License Expdateinaccordance with10CPR2,2.109(9/19/72)
| | 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 ripp e.Entered TS LCO 3.0.3.With 990602 ltr.DISTRIBUTION CODE XE22T COPIES RECEIVED e LTR g ENCL (S I ZE a TITLE: 50.73/50.9 Licensee Event Report (LER), Xncident Rpt, etc.NOTES:License Exp date in accordance with 10CPR2,2.109(9/19/72) |
| .G050002440RECIPIENT ZDCODE/NAME LPD1-1PDINTERNAL: | | .G 05000244 0 RECIPIENT ZD CODE/NAME LPD1-1 PD INTERNAL: AEOD/SPD/RRAB NRR/DZPM/IOLB NRR/DRIP/REXB RES/DET/EIB EXTERNAL: L ST LOBBY WARD NOAC POORE,W.NRC PDR COPIES LTTR ENCL 1 1 1 1 1'1 1 1 1 1 1 1.1 1 1 RECIPIENT XD CODE/NAME VZSSXNG,G. |
| AEOD/SPD/RRAB NRR/DZPM/IOLB NRR/DRIP/REXB RES/DET/EIB EXTERNAL: | | FILE CENTER R/DXPM/XQMB NRR/DSSA/SPLB RGN1 PILE 01 LMXTCO MARSHALL NOAC QUEENER,DS NUDOCS FULL TXT COPIES LTTR ENCL 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 NOTE TO ALL"RIDS" RECIPIENTS: |
| LSTLOBBYWARDNOACPOORE,W.NRCPDRCOPIESLTTRENCL11111'1111111.111RECIPIENT XDCODE/NAME VZSSXNG,G.
| | PLEASE HELP US TO REDUCE WASTE.TO HAVE YOUR NAME OR ORGANIZATION REMOVED FROM DISTRIBUTION LISTS OR REDUCE THE NUMBER OF COPIES RECEIVED BY YOU OR YOUR ORGANIZATION< |
| FILECENTERR/DXPM/XQMB NRR/DSSA/SPLB RGN1PILE01LMXTCOMARSHALLNOACQUEENER,DS NUDOCSFULLTXTCOPIESLTTRENCL1111111111111111NOTETOALL"RIDS"RECIPIENTS:
| | CONTACT THE DOCUMENT CONTROL DESK (DCD)ON EXTENSION 41S-2083 FULL TEXT CONVERSION REQUIRED TOTAL NUMBER OF COPIES REQUIRED: LTTR 16 ENCL 16 4HD ROCHESTfR GAS AND E'ELECTRIC CORFORATION |
| PLEASEHELPUSTOREDUCEWASTE.TOHAVEYOURNAMEORORGANIZATION REMOVEDFROMDISTRIBUTION LISTSORREDUCETHENUMBEROFCOPIESRECEIVEDBYYOUORYOURORGANIZATION<
| | ~89EASTAVENUE, ROCHfSTER, N, Y I46d9.000I AREA CODE216 586-27M RosERT c.MEcREDY Vice Presislenl t4uc!eor Operosions June 2, 1999 U.S.Nuclear Regulatory Commission Document Control Desk Attn: Guy S.Vissing Project Directorate I-1 Washington, D.C.20555 |
| CONTACTTHEDOCUMENTCONTROLDESK(DCD)ONEXTENSION 41S-2083FULLTEXTCONVERSION REQUIREDTOTALNUMBEROFCOPIESREQUIRED:
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| LTTR16ENCL16 4HDROCHESTfR GASANDE'ELECTRIC CORFORATION
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| ~89EASTAVENUE, ROCHfSTER, N,YI46d9.000I AREACODE216586-27MRosERTc.MEcREDYVicePresislenl t4uc!eorOperosions June2,1999U.S.NuclearRegulatory Commission DocumentControlDeskAttn:GuyS.VissingProjectDirectorate I-1Washington, D.C.20555 | |
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| ==Subject:== | | ==Subject:== |
| .LER1999-009, Instrumentation DeclaredInoperable inMultipleChannelsResultsinCondition Prohibited byTechnical Specifications R.E.GinnaNuclearPowerPlantDocketNo.50-244 | | .LER 1999-009, Instrumentation Declared Inoperable in Multiple Channels Results in Condition Prohibited by Technical Specifications R.E.Ginna Nuclear Power Plant Docket No.50-244 |
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| ==DearMr.Vissing:== | | ==Dear Mr.Vissing:== |
| TheattachedLicenseeEventReportLER1999-009issubmitted inaccordance with10CFR50.73,LicenseeEventReportSystem,item(a)(2)(i)(B),"Anyoperation orcondition prohibited bytheplant'sTechnical Specifications".
| | The attached Licensee Event Report LER 1999-009 is submitted in accordance with 10 CFR 50.73, Licensee Event Report System, item (a)(2)(i)(B),"Any operation or condition prohibited by the plant's Technical Specifications". |
| Veryrulyyours,XC:Mr.GuyS.Vissing(MailStop8C2)ProjectDirectorate I-1DivisionofReactorProjects-I/IIOfficeofNuclearReactorRegulation U.S.NuclearRegulatory Commission Washington, D.C.20555RegionalAdministrator, RegionIU.S.NuclearRegulatory Commission 475Allendale RoadKingofPrussia,PA19406U.S.NRCGinnaSeniorResidentInspector
| | Very ruly yours, XC: Mr.Guy S.Vissing (Mail Stop 8C2)Project Directorate I-1 Division of Reactor Projects-I/II Office of Nuclear Reactor Regulation U.S.Nuclear Regulatory Commission Washington, D.C.20555 Regional Administrator, Region I U.S.Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 U.S.NRC Ginna Senior Resident Inspector+t 990b080307 |
| +t990b080307 | | 'll's!0602 PDR ADQCK 05000244 S PDR NRC FORM 866 IB I%BI U.S.NUCLEAR REGULATORY COMMISSION LICENSEE EYENT REPORT (LER)fSoe reverse for required number of'digitslcharacters for each b(ockl M5Q''Ik rN p NIIsp@e i''gA'P%88Sy'nformation coBoctP)a rortuost: 50 hrs.Reported lessons learned are ncorporated krto the Bcenskrg process and fod back to hdustry.Forward comments regarding burden estimate to the Records Msnagernont Branch p4 F33), U.S.Nudear Regulatory Commfssbn, Wasfsngton, DC 205554001~and to the Paperwork Reduction Project (31500104), Ofree of Management and Budget, WasNngton, DC 20503.If an information coeect'on does not display a currendy vs M OMB, control number, the NRC may not conduct or sponsor.and a FACILITY NAME I 11 R.E.Ginna Nuc(ear Power Plant I DOCKET NUMBER I2)05000244 PAGE I3)1 OF 7 TITLE te)Instrumentation Declared Inoperable in Multiple Channels Results in Condition Prohibited by Technical Specifications 05 03 1999, EVENT DATE (5)OAY LER NUMBER (6)SEOUFNTIAL RENSION NUMBER NUMBER 1999", 009-00 MONTH ON 06 02 1999 REPORT DATE (7)DOCKET NUMSER 05000 OOCKETNUMSER 05000 FACfLITY NAME FACILrTY NAME OTHER FACILITIES INVOLVED (6)OPERATING MODE (9)POWER LEVEL (10)090 URSUANT TO THE REQUIREMEN THIS REPORT IS SUBMITTFD P 20.2203(a)(2)(v) 20.2203(a) |
| 'll's!0602PDRADQCK05000244SPDR NRCFORM866IBI%BIU.S.NUCLEARREGULATORY COMMISSION LICENSEEEYENTREPORT(LER)fSoereverseforrequirednumberof'digitslcharacters foreachb(ocklM5Q''IkrNpNIIsp@ei''gA'P%88Sy'nformation coBoctP)a rortuost: | | (3)(i)20.2201(b) 20.2203(a)(1) 20.2203(a)(3)(ii)20.2203(a) |
| 50hrs.Reportedlessonslearnedarencorporated krtotheBcenskrgprocessandfodbacktohdustry.Forwardcommentsregarding burdenestimatetotheRecordsMsnagernont Branchp4F33),U.S.NudearRegulatory Commfssbn, Wasfsngton, DC205554001
| |
| ~andtothePaperwork Reduction Project(31500104), | |
| OfreeofManagement andBudget,WasNngton, DC20503.Ifaninformation coeect'on doesnotdisplayacurrendyvsMOMB,controlnumber,theNRCmaynotconductorsponsor.andaFACILITYNAMEI11R.E.GinnaNuc(earPowerPlantIDOCKETNUMBERI2)05000244PAGEI3)1OF7TITLEte)Instrumentation DeclaredInoperable inMultipleChannelsResultsinCondition Prohibited byTechnical Specifications 05031999,EVENTDATE(5)OAYLERNUMBER(6)SEOUFNTIAL RENSIONNUMBERNUMBER1999",009-00MONTHON06021999REPORTDATE(7)DOCKETNUMSER05000OOCKETNUMSER 05000FACfLITYNAMEFACILrTYNAMEOTHERFACILITIES INVOLVED(6)OPERATING MODE(9)POWERLEVEL(10)090URSUANTTOTHEREQUIREMEN THISREPORTISSUBMITTFD P20.2203(a)(2)(v) 20.2203(a)
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| (3)(i)20.2201(b) 20.2203(a)(1) 20.2203(a)(3) | |
| (ii)20.2203(a) | |
| (2)(i)20.2203(a}(4) 50.36(cl(1) 20.2203(a)(2)(ii) 20.2203(a) | | (2)(i)20.2203(a}(4) 50.36(cl(1) 20.2203(a)(2)(ii) 20.2203(a) |
| (2)(iii}50.36(c)(2) 20.2203(a)(2)(iv) | | (2)(iii}50.36(c)(2) 20.2203(a)(2)(iv) |
| LICENSEECONTACTFORTHISLER(12)TSOF10CFRB:(Checkoneormore)(11)50.73(a)(2)
| | LICENSEE CONTACT FOR THIS LER (12)TS OF 10 CFR B: (Check one or more)(11)50.73(a)(2)(viii)50.73(a}(2}(x) |
| (viii)50.73(a}(2}(x) | | X 50.73(a)(2)(i)(B) 50.73(a)(2)(ii)73.71 50.73(a}(2l(iii) |
| X50.73(a)(2)(i)(B) 50.73(a)(2)(ii)73.7150.73(a}(2l(iii)
| | OTHER 50.73(a)(2wiv) 50.73(a)(2)(v) |
| OTHER50.73(a)(2wiv) 50.73(a)(2)(v)
| | Specify m Abstract below or in NRC Form 355A 50.73(a)(2)(vii) |
| SpecifymAbstractbeloworinNRCForm355A50.73(a)(2)(vii)
| | TELEPMONE NUMSER (Inrrude Ares Code)John T.St.Martin-Technical Assistant (716)771-3641 CAUSE SYSTEM COMPONOIT MANUFACTURER REPORTABLE TO EPOS CAUSE SYS'fEM MANUFACTURER REPORTABLE TO EPIX SUPPLEMENTAL REPORT EXPECTED (l4)YES (If yes, complete EXPECTED SUBMISSION DATE).NO X EXPECTED SUBMISSION DATE R5)IlONTH OAY ABSTRACT (Limit to 1400 spaces, i.e., approximately 15 single.spaced typewritten lines}(16)On May 3, 1999, the plant was in Mode 1 at approximately 90%steady state reactor power.It had previously been determined that Overtemperature Delta T and Overpower Delta T bistable trip setpoints were potentially non-conservative on three out of four reactor protection system channels, and an evaluation was in progress.At approximately 2330 EDST, instrumentation for these three channels was declared inoperable. |
| TELEPMONE NUMSER(InrrudeAresCode)JohnT.St.Martin-Technical Assistant (716)771-3641CAUSESYSTEMCOMPONOIT MANUFACTURER REPORTABLE TOEPOSCAUSESYS'fEMMANUFACTURER REPORTABLE TOEPIXSUPPLEMENTAL REPORTEXPECTED(l4)YES(Ifyes,completeEXPECTEDSUBMISSION DATE).NOXEXPECTEDSUBMISSION DATER5)IlONTHOAYABSTRACT(Limitto1400spaces,i.e.,approximately 15single.spacedtypewritten lines}(16)OnMay3,1999,theplantwasinMode1atapproximately 90%steadystatereactorpower.Ithadpreviously beendetermined thatOvertemperature DeltaTandOverpower DeltaTbistabletripsetpoints werepotentially non-conservative onthreeoutoffourreactorprotection systemchannels, andanevaluation wasinprogress. | | Immediate corrective action was to entei Technical Specification Limiting Condition for Operation 3.0.3, and take actions to restore the channels to operable status.Following replacement of the affected bistables with bistab(es of a different design, the bistable trip setpoints were recalibrated and three of four channels were declared operable.The plant exited Limiting Condition for Operation 3.0.3.The underlying cause of the event was an unanticipated high frequency AC voltage ripple on the Delta T signals that adversely affected the trip setpoints for the bistables. |
| Atapproximately 2330EDST,instrumentation forthesethreechannelswasdeclaredinoperable.
| | Corrective action to prevent recurrence is outlined in Section V.B. |
| Immediate corrective actionwastoenteiTechnical Specification LimitingCondition forOperation 3.0.3,andtakeactionstorestorethechannelstooperablestatus.Following replacement oftheaffectedbistables withbistab(es ofadifferent design,thebistabletripsetpoints wererecalibrated andthreeoffourchannelsweredeclaredoperable. | |
| TheplantexitedLimitingCondition forOperation 3.0.3.Theunderlying causeoftheeventwasanunanticipated highfrequency ACvoltagerippleontheDeltaTsignalsthatadversely affectedthetripsetpoints forthebistables.
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| Corrective actiontopreventrecurrence isoutlinedinSectionV.B. | |
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| ~'~~~III~~~~C~'SiI~~i~I'~~~~~I~'~~~'~~I'~~~~~~~~~~~~~~~~~~~~'~~~~'~;~~~~~~~~~~~~~'~~~~~~~~~~~~~~~~~~~~~~~~~~~~:~~'~~~~~~~~~~~~;~.~~~~~~~~~~~~~~~~'~~~~~'~~~~~~~~~~~~~~~~~'~~~~~~~~~~~~~~~~~~~'~~~~~~~~~~~~~~~~~~~I~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~''~~~~~~~~~~~'~~~~~~.~;~~~:-IIIIo~~~.~~~~~~~~~'~~~~~~..I.~~~~.~~~~~~~~I~~~~~~~'~~*~~~~~~~~~~.I~~:~~~~~~I~~~~~~~~~~~~~~~~~:~~~'~~~~~:~~~~~~~~~~~~~~~I~~~~~~~'~~.e~~~~~'~~~~~~~~~~~~~~~~I~'~~~~~~~~~~~~~~~~~~~~~~~~~~'~~~~~~~~'.~~~~~~~~o~~~I~~~~~~~~'~~~~ | | ~'~~~III~~~~C~'S i I~~i~I'~~~~~I~'~~~'~~I'~~~~~~~~~~~~~~~~~~~~'~~~~'~;~~~~~~~~~~~~~'~~~~~~~~~~~~~~~~~~~~~~~~~~~~:~~'~~~~~~~~~~~~;~.~~~~~~~~~~~~~~~~'~~~~~'~~~~~~~~~~~~~~~~~'~~~~~~~~~~~~~~~~~~~'~~~~~~~~~~~~~~~~~~~I~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~''~~~~~~~~~~~'~~~~~~.~;~~~:-I I I I o~~~.~~~~~~~~~'~~~~~~..I.~~~~.~~~~~~~~I~~~~~~~'~~*~~~~~~~~~~.I~~:~~~~~~I~~~~~~~~~~~~~~~~~:~~~'~~~~~:~~~~~~~~~~~~~~~I~~~~~~~'~~.e~~~~~'~~~~~~~~~~~~~~~~I~'~~~~~~~~~~~~~~~~~~~~~~~~~~'~~~~~~~~'.~~~~~~~~o~~~I~~~~~~~~'~~~~ |
| NRCFORM366A$1999)LICENSEEEVENTREPORT(LER)TEXTCONTINUATION U.S.NUCLEARREGULATORY COMMISSION FACILITYNAME(1)DOCKET(2)LERNUMBER(6)PAGE(3)..R.E.GinnaNuclearPowerPlant05000244SEOUEMTIA(
| | NRC FORM 366A$1999)LICENSEE EVENT REPORT (LER)TEXT CONTINUATION U.S.NUCLEAR REGULATORY COMMISSION FACILITY NAME (1)DOCKET (2)LER NUMBER (6)PAGE(3)..R.E.Ginna Nuclear Power Plant 05000244 SEOUEMTIA(8EVSIOII IIUMBN ImMBN 1999-009-00 3 OF 7 TEXT Iif more spaceis required, use additional copies of NRC Form 366'17)The Plant Operations Review Committee (PORC)was convened at approximately 1900 EDST to review this situation. |
| 8EVSIOIIIIUMBNImMBN1999-009-003OF7TEXTIifmorespaceisrequired, useadditional copiesofNRCForm366'17)ThePlantOperations ReviewCommittee (PORC)wasconvenedatapproximately 1900EDSTtoreviewthissituation.
| | PORC concurred that reducing power to 90%was a prudent measure.Channel 2 bistables, in service for more than 18 months, were not affected by this condition. |
| PORCconcurred thatreducingpowerto90%wasaprudentmeasure.Channel2bistables, inserviceformorethan18months,werenotaffectedbythiscondition.
| | Channel 2 was proven fully operable and channel 1 was currently in the tripped mode.Thus, continued plant operation was permissible, while bistable operability was assessed by NES personnel. |
| Channel2wasprovenfullyoperableandchannel1wascurrently inthetrippedmode.Thus,continued plantoperation waspermissible, whilebistableoperability wasassessedbyNESpersonnel.
| | Preliminary calculations were subsequently performed by NES staff.These calculations indicated that RPS channel 1 bistable trip setpoints were within design limits.The margin for OT DT and OP DT were low, but the bistables were considered operable.II.DESCRIPTION OF EVENT: A.DATES AND APPROXIMATE TIMES OF MAJOR OCCURRENCES'ay 3, 1999, 0820 EDST: RPS channel 1 is removed from service and declared inoperable to perform troubleshooting |
| Preliminary calculations weresubsequently performed byNESstaff.Thesecalculations indicated thatRPSchannel1bistabletripsetpoints werewithindesignlimits.ThemarginforOTDTandOPDTwerelow,butthebistables wereconsidered operable. | | ((per CPI-TRIP-TEST-5.10)). |
| II.DESCRIPTION OFEVENT:A.DATESANDAPPROXIMATE TIMESOFMAJOROCCURRENCES'ay 3,1999,0820EDST:RPSchannel1isremovedfromserviceanddeclaredinoperable toperformtroubleshooting | | May 3, 1999, dayshift: AC ripple is discovered in RPS channel 1.Later, AC ripple is discovered in RPS channels 3 and 4.May 3, 1999, 2330 EDST: Event Date and Time and Discovery Date and Time.May 3, 1999, 2347 EDST: Plant shutdown initiated. |
| ((perCPI-TRIP-TEST-5.10)). | | May 4, 1999, 0136 EDST: RPS channel 1 is declared operable.May 4, 1999, 0428 EDST: RPS channel 3 is declared operable.May 4, 1999, 0428 EDST: ITS LCO 3.0.3 is exited.Plant shutdown is stopped at 21%power.May 4, 1999, 2121 EDST: RPS channel 4 is declared operable.EVENT: On May 3, 1999, the plant was in Mode 1 at approximately 90%steady state reactor power after the power decrease from full power, which was started at approximately 1840 EDST and completed at approximately 2000 EDST.NES personnel completed the calculations, which now indicated that RPS channel 1 bistables were not operable.The Shift Supervisor and plant management were immediately notified.At approximately 2330 EDST, based on the revised calculational data, it was determined that three affected channels of RPS (channels 1, 3 and 4)be declared inoperable. |
| May3,1999,dayshift:
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| ACrippleisdiscovered inRPSchannel1.Later,ACrippleisdiscovered inRPSchannels3and4.May3,1999,2330EDST:EventDateandTimeandDiscovery DateandTime.May3,1999,2347EDST:Plantshutdowninitiated.
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| May4,1999,0136EDST:RPSchannel1isdeclaredoperable.
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| May4,1999,0428EDST:RPSchannel3isdeclaredoperable.
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| May4,1999,0428EDST:ITSLCO3.0.3isexited.Plantshutdownisstoppedat21%power.May4,1999,2121EDST:RPSchannel4isdeclaredoperable.
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| EVENT:OnMay3,1999,theplantwasinMode1atapproximately 90%steadystatereactorpowerafterthepowerdecreasefromfullpower,whichwasstartedatapproximately 1840EDSTandcompleted atapproximately 2000EDST.NESpersonnel completed thecalculations, whichnowindicated thatRPSchannel1bistables werenotoperable. | |
| TheShiftSupervisor andplantmanagement wereimmediately notified.
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| Atapproximately 2330EDST,basedontherevisedcalculational data,itwasdetermined thatthreeaffectedchannelsofRPS(channels 1,3and4)bedeclaredinoperable.
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| I'e~~sI~~~II~'~'I'~~~'~'~~~'~~~~~~~~~~~~~'~~~~~~~~~~~~~~~'~~~~~'~~~~I~~~~~~~~~'~~~~~'~~~~~'~~~~~~~~~~~~0~~~~~~~~~''~~~~~~~~~'~~~~~~~~~~~~~~~~~~~~'~~~'~~~~~.~~~~~~~~~~~~~~~~~'~'~~~I~I~~~~~~~~~~~'~~~~~~a~I~~~~~~~~~~~~~~'~~~~~~~~~~~~.~~~~~~~~~~~~~~~~'~~~~~s~~~~~~~~~~~~o~'~~~~~~.~~~~~~~'~~~~~~~~~~~~~~'~~'~~~~~~~~~~~~~~~~~~ | | I'e~~s I~~~II~'~'I'~~~'~'~~~'~~~~~~~~~~~~~'~~~~~~~~~~~~~~~'~~~~~'~~~~I~~~~~~~~~'~~~~~'~~~~~'~~~~~~~~~~~~0~~~~~~~~~''~~~~~~~~~'~~~~~~~~~~~~~~~~~~~~'~~~'~~~~~.~~~~~~~~~~~~~~~~~'~'~~~I~I~~~~~~~~~~~'~~~~~~a~I~~~~~~~~~~~~~~'~~~~~~~~~~~~.~~~~~~~~~~~~~~~~'~~~~~s~~~~~~~~~~~~o~'~~~~~~.~~~~~~~'~~~~~~~~~~~~~~'~~'~~~~~~~~~~~~~~~~~~ |
| ~'0~~~~~II~IggI~~'~t'I4~~~~~~~~~'~~~~~~~~~~~~~''~~~~~~~~0~~.~~~I'~~~~~~~~~I~~~~~~~~~~.~~:~.~~~~~~~~~~~~~~~~~~~~~~~~~~'~~~~~~~~~~~~~~~~~~~~~'~~~~~~~~~~~~~~~~~~~~~'~~~~~'~~~~~~~~~~~~~~t~~~~'~'~'~~~~~~~~~ | | ~'0~~~~~II~I gg I~~'~t'I 4~~~~~~~~~'~~~~~~~~~~~~~''~~~~~~~~0~~.~~~I'~~~~~~~~~I~~~~~~~~~~.~~:~.~~~~~~~~~~~~~~~~~~~~~~~~~~'~~~~~~~~~~~~~~~~~~~~~'~~~~~~~~~~~~~~~~~~~~~'~~~~~'~~~~~~~~~~~~~~t~~~~'~'~'~~~~~~~~~ |
| 'I NRCFORM366A(CISSS)LlCENSEEEVENTREPORT(LER)TEXTCONTINUATION U.S.NUCLEARREGULATORY COMMISSION | | 'I NRC FORM 366A (CISSS)LlCENSEE EVENT REPORT (LER)TEXT CONTINUATION U.S.NUCLEAR REGULATORY COMMISSION |
| ~FACILITYNAMEI1)R.E.GinnaNuclearPowerPlantDOCKETI2)05000244LERNUMBERIe)YEARSEQUENTIAL REYISIONNUMSERNUMSER1999-009-00PAGEI3)6OF7TEXT(Ifmorespaceisrequired, useadditional copiesofitiRCForm366AJI17)IV.ANALYSISOFEVENT:Thiseventisreportable inaccordance with10CFR50.73,LicenseeEventReportSystem,item(a)(2)(i)(B),"Anyoperation orcondition prohibited bytheplant'sTechnical Specifications" | | ~FACILITY NAME I1)R.E.Ginna Nuclear Power Plant DOCKET I2)05000244 LER NUMBER Ie)YEAR SEQUENTIAL REYISION NUMSER NUMSER 1999-009-00 PAGE I3)6 OF 7 TEXT (If more spaceis required, use additional copies of itiRC Form 366AJ I17)IV.ANALYSIS OF EVENT: This event is reportable in accordance with 10 CFR 50.73, Licensee Event Report System, item (a)(2)(i)(B),"Any operation or condition prohibited by the plant's Technical Specifications"~The entry into ITS LCO 3.0.3 as a result of declaring more than one Function in ITS Table 3.3.1-1 inoperable is considered to be a condition prohibited by Technical Specifications. |
| ~TheentryintoITSLCO3.0.3asaresultofdeclaring morethanoneFunctioninITSTable3.3.1-1inoperable isconsidered tobeacondition prohibited byTechnical Specifications. | | An assessment was performed considering both the safety consequences and implications of this event with the following results and conclusions: |
| Anassessment wasperformed considering boththesafetyconsequences andimplications ofthiseventwiththefollowing resultsandconclusions:
| | There were no operational or safety consequences attributed to three RPS channels for OT DT and OP DT being inoperable. |
| Therewerenooperational orsafetyconsequences attributed tothreeRPSchannelsforOTDTandOPDTbeinginoperable.
| | A more detailed post-event review was performed. |
| Amoredetailedpost-event reviewwasperformed.
| | It has subsequently been determined that only one trip function (RPS channel 3 OP DT)was actually inoperable. |
| Ithassubsequently beendetermined thatonlyonetripfunction(RPSchannel3OPDT)wasactuallyinoperable.
| | This determination is based on the as-found data and a more rigorous analysis of the associated instrument uncertainties. |
| Thisdetermination isbasedontheas-founddataandamorerigorousanalysisoftheassociated instrument uncertainties.
| | All four OT DT channels were found to be within accident analysis assumptions, after accounting for the as-found margin to trip setpoint and incorporating the appropriate instrument uncertainties. |
| AllfourOTDTchannelswerefoundtobewithinaccidentanalysisassumptions, afteraccounting fortheas-foundmargintotripsetpointandincorporating theappropriate instrument uncertainties.
| | Hence, the only function that would not have actuated within the bounds of the Ginna Station accident analysis was one channel of OP DT.With three operable channels available and a 2 out of 4 logic to provide the required trip function, there is adequate assurance that the reactor protection system would have performed within its required envelope as assumed in the accident analysis.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: Following replacement of bistables and calibration of the bistables in RPS channels 1 and 3, three channels (channels 1 and 3 and previously unaffected channel 2)were declared operable.ACTION TAKEN OR PLANNED TO PREVENT RECURRENCE: |
| Hence,theonlyfunctionthatwouldnothaveactuatedwithintheboundsoftheGinnaStationaccidentanalysiswasonechannelofOPDT.Withthreeoperablechannelsavailable anda2outof4logictoprovidetherequiredtripfunction, thereisadequateassurance thatthereactorprotection systemwouldhaveperformed withinitsrequiredenvelopeasassumedintheaccidentanalysis. | | NUS indicated that they will be updating the parts list to remove the incorrectly sized component. |
| Basedontheabove,itcanbeconcluded thatthepublic'shealthandsafetywasassuredatalltimes.V.CORRECTIVE ACTION:A.ACTIONTAKENTORETURNAFFECTEDSYSTEMSTOPRE-EVENT NORMALSTATUS:Following replacement ofbistables andcalibration ofthebistables inRPSchannels1and3,threechannels(channels 1and3andpreviously unaffected channel2)weredeclaredoperable.
| | NES personnel designed a modification to the math modules to eliminate the effects of AC ripple on the OP DT and OT DT bistable trip setpoints. |
| ACTIONTAKENORPLANNEDTOPREVENTRECURRENCE:
| | This modification has been implemented. |
| NUSindicated thattheywillbeupdatingthepartslisttoremovetheincorrectly sizedcomponent.
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| NESpersonnel designedamodification tothemathmodulestoeliminate theeffectsofACrippleontheOPDTandOTDTbistabletripsetpoints.
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| Thismodification hasbeenimplemented.
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| NRCFORM366AgIBBBILICENSEEEVENTREPORT(LER)TEXTCONTINUATION U.S.NUCLEARREGULATORY COMMISSION
| | NRC FORM 366A g IBBBI LICENSEE EVENT REPORT (LER)TEXT CONTINUATION U.S.NUCLEAR REGULATORY COMMISSION |
| ~FACILITYNAMEI1)R.E.GinnaNuclearPowerPlantDOCKETI2)05000244LERNUMBERI6)SB)UalTIAl RSNSIOHIIUMBIAIIUMBBI1999-003-00PAGEI3)7OF7TEXTllfmorespaceisrequired, useadditional copiesofNRCForm866AJI17)oThiseventisbeingreviewedforanypotential lessonstobelearnedandappliedtotheappropriate partsoftheGinnamodification process:design,procurement, installation, testing.TheindustrywillbenotifiedofthiseventviaanentryintheNuclearNETWORKsystem.VI~ADDITIONAL INFORMATION: | | ~FACILITY NAME I1)R.E.Ginna Nuclear Power Plant DOCKET I2)05000244 LER NUMBER I6)SB)UalTIAl RSNSIOH IIUMBIA IIUMBBI 1999-003-00 PAGE I3)7 OF 7 TEXT llf more spaceis required, use additional copies of NRC Form 866AJ I17)o This event is being reviewed for any potential lessons to be learned and applied to the appropriate parts of the Ginna modification process: design, procurement, installation, testing.The industry will be notified of this event via an entry in the Nuclear NETWORK system.VI~ADDITIONAL INFORMATION: |
| A.FAILEDCOMPONENTS: | | A.FAILED COMPONENTS: |
| NoneB.PREVIOUSLERsONSIMILAREVENTS:AsimilarLEReventhistorical searchwasconducted withthefollowing results:Nodocumentation ofsimilarLEReventswiththesamerootcauseatGinnaNuclearPowerPlantcouldbeidentified.
| | 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 at Ginna Nuclear Power Plant could be identified. |
| C.SPECIALCOMMENTS: | | C.SPECIAL COMMENTS: None}} |
| None}} | |
Similar Documents at Ginna |
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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
REGULATORY INFORMATION DISTRIBUTION SYSTEM (RXDS)A CCESSZON NBR:9906080307 DOC.DATE: 99/06/02 NOTARIZED:
NO DOCKET I PACZL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G ter G 05000244 AUTH.NAME AUTHOR AFFILIATION ST MARTIN,J.T.
Rochester Gas&.Electric Corp.MECREDY,R.C.
~Rochester Gas&.Electric Corp.RECIP.NAME
,RECIPIENT AFFILIATION VISSXNG,G.S.
SUBJECT:
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 ripp e.Entered TS LCO 3.0.3.With 990602 ltr.DISTRIBUTION CODE XE22T COPIES RECEIVED e LTR g ENCL (S I ZE a TITLE: 50.73/50.9 Licensee Event Report (LER), Xncident Rpt, etc.NOTES:License Exp date in accordance with 10CPR2,2.109(9/19/72)
.G 05000244 0 RECIPIENT ZD CODE/NAME LPD1-1 PD INTERNAL: AEOD/SPD/RRAB NRR/DZPM/IOLB NRR/DRIP/REXB RES/DET/EIB EXTERNAL: L ST LOBBY WARD NOAC POORE,W.NRC PDR COPIES LTTR ENCL 1 1 1 1 1'1 1 1 1 1 1 1.1 1 1 RECIPIENT XD CODE/NAME VZSSXNG,G.
FILE CENTER R/DXPM/XQMB NRR/DSSA/SPLB RGN1 PILE 01 LMXTCO MARSHALL NOAC QUEENER,DS NUDOCS FULL TXT COPIES LTTR ENCL 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 NOTE TO ALL"RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE.TO HAVE YOUR NAME OR ORGANIZATION REMOVED FROM DISTRIBUTION LISTS OR REDUCE THE NUMBER OF COPIES RECEIVED BY YOU OR YOUR ORGANIZATION<
CONTACT THE DOCUMENT CONTROL DESK (DCD)ON EXTENSION 41S-2083 FULL TEXT CONVERSION REQUIRED TOTAL NUMBER OF COPIES REQUIRED: LTTR 16 ENCL 16 4HD ROCHESTfR GAS AND E'ELECTRIC CORFORATION
~89EASTAVENUE, ROCHfSTER, N, Y I46d9.000I AREA CODE216 586-27M RosERT c.MEcREDY Vice Presislenl t4uc!eor Operosions June 2, 1999 U.S.Nuclear Regulatory Commission Document Control Desk Attn: Guy S.Vissing Project Directorate I-1 Washington, D.C.20555
Subject:
.LER 1999-009, Instrumentation Declared Inoperable in Multiple Channels Results in Condition Prohibited by Technical Specifications R.E.Ginna Nuclear Power Plant Docket No.50-244
Dear Mr.Vissing:
The attached Licensee Event Report LER 1999-009 is submitted in accordance with 10 CFR 50.73, Licensee Event Report System, item (a)(2)(i)(B),"Any operation or condition prohibited by the plant's Technical Specifications".
Very ruly yours, XC: Mr.Guy S.Vissing (Mail Stop 8C2)Project Directorate I-1 Division of Reactor Projects-I/II Office of Nuclear Reactor Regulation U.S.Nuclear Regulatory Commission Washington, D.C.20555 Regional Administrator, Region I U.S.Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 U.S.NRC Ginna Senior Resident Inspector+t 990b080307
'll's!0602 PDR ADQCK 05000244 S PDR NRC FORM 866 IB I%BI U.S.NUCLEAR REGULATORY COMMISSION LICENSEE EYENT REPORT (LER)fSoe reverse for required number of'digitslcharacters for each b(ockl M5QIk rN p NIIsp@e igA'P%88Sy'nformation coBoctP)a rortuost: 50 hrs.Reported lessons learned are ncorporated krto the Bcenskrg process and fod back to hdustry.Forward comments regarding burden estimate to the Records Msnagernont Branch p4 F33), U.S.Nudear Regulatory Commfssbn, Wasfsngton, DC 205554001~and to the Paperwork Reduction Project (31500104), Ofree of Management and Budget, WasNngton, DC 20503.If an information coeect'on does not display a currendy vs M OMB, control number, the NRC may not conduct or sponsor.and a FACILITY NAME I 11 R.E.Ginna Nuc(ear Power Plant I DOCKET NUMBER I2)05000244 PAGE I3)1 OF 7 TITLE te)Instrumentation Declared Inoperable in Multiple Channels Results in Condition Prohibited by Technical Specifications 05 03 1999, EVENT DATE (5)OAY LER NUMBER (6)SEOUFNTIAL RENSION NUMBER NUMBER 1999", 009-00 MONTH ON 06 02 1999 REPORT DATE (7)DOCKET NUMSER 05000 OOCKETNUMSER 05000 FACfLITY NAME FACILrTY NAME OTHER FACILITIES INVOLVED (6)OPERATING MODE (9)POWER LEVEL (10)090 URSUANT TO THE REQUIREMEN THIS REPORT IS SUBMITTFD P 20.2203(a)(2)(v) 20.2203(a)
(3)(i)20.2201(b) 20.2203(a)(1) 20.2203(a)(3)(ii)20.2203(a)
(2)(i)20.2203(a}(4) 50.36(cl(1) 20.2203(a)(2)(ii) 20.2203(a)
(2)(iii}50.36(c)(2) 20.2203(a)(2)(iv)
LICENSEE CONTACT FOR THIS LER (12)TS OF 10 CFR B: (Check one or more)(11)50.73(a)(2)(viii)50.73(a}(2}(x)
X 50.73(a)(2)(i)(B) 50.73(a)(2)(ii)73.71 50.73(a}(2l(iii)
OTHER 50.73(a)(2wiv) 50.73(a)(2)(v)
Specify m Abstract below or in NRC Form 355A 50.73(a)(2)(vii)
TELEPMONE NUMSER (Inrrude Ares Code)John T.St.Martin-Technical Assistant (716)771-3641 CAUSE SYSTEM COMPONOIT MANUFACTURER REPORTABLE TO EPOS CAUSE SYS'fEM MANUFACTURER REPORTABLE TO EPIX SUPPLEMENTAL REPORT EXPECTED (l4)YES (If yes, complete EXPECTED SUBMISSION DATE).NO X EXPECTED SUBMISSION DATE R5)IlONTH OAY ABSTRACT (Limit to 1400 spaces, i.e., approximately 15 single.spaced typewritten lines}(16)On May 3, 1999, the plant was in Mode 1 at approximately 90%steady state reactor power.It had previously been determined that Overtemperature Delta T and Overpower Delta T bistable trip setpoints were potentially non-conservative on three out of four reactor protection system channels, and an evaluation was in progress.At approximately 2330 EDST, instrumentation for these three channels was declared inoperable.
Immediate corrective action was to entei Technical Specification Limiting Condition for Operation 3.0.3, and take actions to restore the channels to operable status.Following replacement of the affected bistables with bistab(es of a different design, the bistable trip setpoints were recalibrated and three of four channels were declared operable.The plant exited Limiting Condition for Operation 3.0.3.The underlying cause of the event was an unanticipated high frequency AC voltage ripple on the Delta T signals that adversely affected the trip setpoints for the bistables.
Corrective action to prevent recurrence is outlined in Section V.B.
~'~~~III~~~~C~'S i I~~i~I'~~~~~I~'~~~'~~I'~~~~~~~~~~~~~~~~~~~~'~~~~'~;~~~~~~~~~~~~~'~~~~~~~~~~~~~~~~~~~~~~~~~~~~:~~'~~~~~~~~~~~~;~.~~~~~~~~~~~~~~~~'~~~~~'~~~~~~~~~~~~~~~~~'~~~~~~~~~~~~~~~~~~~'~~~~~~~~~~~~~~~~~~~I~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~'~~~~~~.~;~~~:-I I I I o~~~.~~~~~~~~~'~~~~~~..I.~~~~.~~~~~~~~I~~~~~~~'~~*~~~~~~~~~~.I~~:~~~~~~I~~~~~~~~~~~~~~~~~:~~~'~~~~~:~~~~~~~~~~~~~~~I~~~~~~~'~~.e~~~~~'~~~~~~~~~~~~~~~~I~'~~~~~~~~~~~~~~~~~~~~~~~~~~'~~~~~~~~'.~~~~~~~~o~~~I~~~~~~~~'~~~~
NRC FORM 366A$1999)LICENSEE EVENT REPORT (LER)TEXT CONTINUATION U.S.NUCLEAR REGULATORY COMMISSION FACILITY NAME (1)DOCKET (2)LER NUMBER (6)PAGE(3)..R.E.Ginna Nuclear Power Plant 05000244 SEOUEMTIA(8EVSIOII IIUMBN ImMBN 1999-009-00 3 OF 7 TEXT Iif more spaceis required, use additional copies of NRC Form 366'17)The Plant Operations Review Committee (PORC)was convened at approximately 1900 EDST to review this situation.
PORC concurred that reducing power to 90%was a prudent measure.Channel 2 bistables, in service for more than 18 months, were not affected by this condition.
Channel 2 was proven fully operable and channel 1 was currently in the tripped mode.Thus, continued plant operation was permissible, while bistable operability was assessed by NES personnel.
Preliminary calculations were subsequently performed by NES staff.These calculations indicated that RPS channel 1 bistable trip setpoints were within design limits.The margin for OT DT and OP DT were low, but the bistables were considered operable.II.DESCRIPTION OF EVENT: A.DATES AND APPROXIMATE TIMES OF MAJOR OCCURRENCES'ay 3, 1999, 0820 EDST: RPS channel 1 is removed from service and declared inoperable to perform troubleshooting
((per CPI-TRIP-TEST-5.10)).
May 3, 1999, dayshift: AC ripple is discovered in RPS channel 1.Later, AC ripple is discovered in RPS channels 3 and 4.May 3, 1999, 2330 EDST: Event Date and Time and Discovery Date and Time.May 3, 1999, 2347 EDST: Plant shutdown initiated.
May 4, 1999, 0136 EDST: RPS channel 1 is declared operable.May 4, 1999, 0428 EDST: RPS channel 3 is declared operable.May 4, 1999, 0428 EDST: ITS LCO 3.0.3 is exited.Plant shutdown is stopped at 21%power.May 4, 1999, 2121 EDST: RPS channel 4 is declared operable.EVENT: On May 3, 1999, the plant was in Mode 1 at approximately 90%steady state reactor power after the power decrease from full power, which was started at approximately 1840 EDST and completed at approximately 2000 EDST.NES personnel completed the calculations, which now indicated that RPS channel 1 bistables were not operable.The Shift Supervisor and plant management were immediately notified.At approximately 2330 EDST, based on the revised calculational data, it was determined that three affected channels of RPS (channels 1, 3 and 4)be declared inoperable.
I'e~~s I~~~II~'~'I'~~~'~'~~~'~~~~~~~~~~~~~'~~~~~~~~~~~~~~~'~~~~~'~~~~I~~~~~~~~~'~~~~~'~~~~~'~~~~~~~~~~~~0~~~~~~~~~~~~~~~~~~'~~~~~~~~~~~~~~~~~~~~'~~~'~~~~~.~~~~~~~~~~~~~~~~~'~'~~~I~I~~~~~~~~~~~'~~~~~~a~I~~~~~~~~~~~~~~'~~~~~~~~~~~~.~~~~~~~~~~~~~~~~'~~~~~s~~~~~~~~~~~~o~'~~~~~~.~~~~~~~'~~~~~~~~~~~~~~'~~'~~~~~~~~~~~~~~~~~~
~'0~~~~~II~I gg I~~'~t'I 4~~~~~~~~~'~~~~~~~~~~~~~~~~~~~~~0~~.~~~I'~~~~~~~~~I~~~~~~~~~~.~~:~.~~~~~~~~~~~~~~~~~~~~~~~~~~'~~~~~~~~~~~~~~~~~~~~~'~~~~~~~~~~~~~~~~~~~~~'~~~~~'~~~~~~~~~~~~~~t~~~~'~'~'~~~~~~~~~
'I NRC FORM 366A (CISSS)LlCENSEE EVENT REPORT (LER)TEXT CONTINUATION U.S.NUCLEAR REGULATORY COMMISSION
~FACILITY NAME I1)R.E.Ginna Nuclear Power Plant DOCKET I2)05000244 LER NUMBER Ie)YEAR SEQUENTIAL REYISION NUMSER NUMSER 1999-009-00 PAGE I3)6 OF 7 TEXT (If more spaceis required, use additional copies of itiRC Form 366AJ I17)IV.ANALYSIS OF EVENT: This event is reportable in accordance with 10 CFR 50.73, Licensee Event Report System, item (a)(2)(i)(B),"Any operation or condition prohibited by the plant's Technical Specifications"~The entry into ITS LCO 3.0.3 as a result of declaring more than one Function in ITS Table 3.3.1-1 inoperable is considered to be a condition prohibited by Technical Specifications.
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 attributed to three RPS channels for OT DT and OP DT being inoperable.
A more detailed post-event review was performed.
It has subsequently been determined that only one trip function (RPS channel 3 OP DT)was actually inoperable.
This determination is based on the as-found data and a more rigorous analysis of the associated instrument uncertainties.
All four OT DT channels were found to be within accident analysis assumptions, after accounting for the as-found margin to trip setpoint and incorporating the appropriate instrument uncertainties.
Hence, the only function that would not have actuated within the bounds of the Ginna Station accident analysis was one channel of OP DT.With three operable channels available and a 2 out of 4 logic to provide the required trip function, there is adequate assurance that the reactor protection system would have performed within its required envelope as assumed in the accident analysis.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: Following replacement of bistables and calibration of the bistables in RPS channels 1 and 3, three channels (channels 1 and 3 and previously unaffected channel 2)were declared operable.ACTION TAKEN OR PLANNED TO PREVENT RECURRENCE:
NUS indicated that they will be updating the parts list to remove the incorrectly sized component.
NES personnel designed a modification to the math modules to eliminate the effects of AC ripple on the OP DT and OT DT bistable trip setpoints.
This modification has been implemented.
NRC FORM 366A g IBBBI LICENSEE EVENT REPORT (LER)TEXT CONTINUATION U.S.NUCLEAR REGULATORY COMMISSION
~FACILITY NAME I1)R.E.Ginna Nuclear Power Plant DOCKET I2)05000244 LER NUMBER I6)SB)UalTIAl RSNSIOH IIUMBIA IIUMBBI 1999-003-00 PAGE I3)7 OF 7 TEXT llf more spaceis required, use additional copies of NRC Form 866AJ I17)o This event is being reviewed for any potential lessons to be learned and applied to the appropriate parts of the Ginna modification process: design, procurement, installation, testing.The industry will be notified of this event via an entry in the Nuclear NETWORK system.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 at Ginna Nuclear Power Plant could be identified.
C.SPECIAL COMMENTS: None
