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| {{#Wiki_filter:CATEGORYREGULATORY INFORMATION DISTRIBUTION SYSTEM(RIDS)ACCESSION NBR:9907200116, DOC.DATE: | | {{#Wiki_filter:CATEGORY REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)ACCESSION NBR:9907200116, DOC.DATE: 99/07/13 NOTARIZED: |
| 99/07/13NOTARIZED: | | NO DOCKET I FACIL:50-315 Donald C.Cook Nuclear Power Plant, Unit 1, Indiana M 05000315 AUTH, NAME AUTHOR AFFILIATION SNODGRASS,D.D. |
| NODOCKETIFACIL:50-315 DonaldC.CookNuclearPowerPlant,Unit1,IndianaM05000315AUTH,NAMEAUTHORAFFILIATION SNODGRASS,D.D.
| | Indiana Michigan Power.Co.(formerly Indiana&Michigan Ele BAKKEN,A.C. |
| IndianaMichiganPower.Co.(formerly Indiana&MichiganEleBAKKEN,A.C.
| | 'ndiana Michigan Power Co.(formerly Indiana&Michigan Ele RECIP.NAME RECIPIENT AFFILIATION |
| 'ndianaMichiganPowerCo.(formerly Indiana&MichiganEleRECIP.NAME RECIPIENT AFFILIATION | |
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| ==SUBJECT:== | | ==SUBJECT:== |
| LER99-016-00:on "990615,TS requirements forsourcerangeneutronfluxmonitorsnotmet.Caused byfailuretounderstand designbasisofplant.Procedures revised.With990713ltr.DISTRIBUTION CODE:IE22TCOPIESRECEIVED:
| | LER 99-016-00:on "990615,TS requirements for source range neutron flux monitors not met.Caused by failure to understand design basis of plant.Procedures revised.With 990713 ltr.DISTRIBUTION CODE: IE22T COPIES RECEIVED: LTR 7 ENCL i SIZE: TITLE: 50.73/50.9 Licensee Event Report (LER), Incident Rpt, etc.NOTES: RECIPIENT ID CODE/NAME LPD3-1 PD INTERNA: FILE CE E REXB RES/DET/ERAB RGN3 FILE 01 COPIES LTTR ENCL 1 1 1.1 1 1 1 1 1, 1 RECIPIENT ID CODE/NAME STANG, J NRR/CPM/IOLB NRR/DSSA/SPLB RES/DRAA/OERAB COPIES LTTR ENCL 1 1 1 1 1 1 1, 1 EXTERNAL: L ST LOBBY WARD NOAC POORE,W.NRC PDR 1 1 LMITCO MARSHALL 1 1 NOAC QUEENER,DS 1 1 NUDOCS FULL TXT 1 1 1'1 1 1 NOTE TO ALL"RIDS" RECIPIENTS: |
| LTR7ENCLiSIZE:TITLE:50.73/50.9 LicenseeEventReport(LER),IncidentRpt,etc.NOTES:RECIPIENT IDCODE/NAME LPD3-1PDINTERNA:FILECEEREXBRES/DET/ERAB RGN3FILE01COPIESLTTRENCL111.111111,1RECIPIENT IDCODE/NAME STANG,JNRR/CPM/IOLBNRR/DSSA/SPLB RES/DRAA/OERAB COPIESLTTRENCL1111111,1EXTERNAL:
| | PLEASE HELP US TO REDUCE WASTE.TO HAVE YOUR NAME OR ORGANIZATION REMOVED FROM DISTRIBUTION LIS OR REDUCE THE NUMBER OF COPIES RECEIVED BY YOU OR YOUR ORGANIZATION, CONTACT THE DOCUMENT CONTR DESK (DCD)ON EXTENSION 415-2083 FULL TEXT CONVERSION REQUIRED TOTAL NUMBER OF COPIES REQUIRED: LTTR 15 ENCL 15 |
| LSTLOBBYWARDNOACPOORE,W.NRCPDR11LMITCOMARSHALL11NOACQUEENER,DS 11NUDOCSFULLTXT111'111NOTETOALL"RIDS"RECIPIENTS:
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| PLEASEHELPUSTOREDUCEWASTE.TOHAVEYOURNAMEORORGANIZATION REMOVEDFROMDISTRIBUTION LISORREDUCETHENUMBEROFCOPIESRECEIVEDBYYOUORYOURORGANIZATION, CONTACTTHEDOCUMENTCONTRDESK(DCD)ONEXTENSION 415-2083FULLTEXTCONVERSION REQUIREDTOTALNUMBEROFCOPIESREQUIRED:
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| Indianariichigan PowerCompany~CookwtdearPlantOneCOOkrr1anrrridgnatb N49106616465590)IRONMANICHIGANPOMfERJuly13,1999UnitedStatesNuclearRegulatory Commission DocumentControlDesk"Washington, DC20555Operating LicenseDPR-58DocketNo.50-315DocumentControlManager:Inaccordance withthecriteriaestablished by10CFR50.73entitledLicenseeEventReort~estemthefollowing reportisbeingsubmitted:
| | Indiana riichigan Power Company~Cook wtdear Plant One COOk rr1anr rridgnatb N 49106 616 465 590)IRON MA NICHIGAN POMfER July 13, 1999 United States Nuclear Regulatory Commission Document Control Desk" Washington, DC 20555 Operating License DPR-58 Docket No.50-315 Document Control Manager: In accordance with the criteria established by 10 CFR 50.73 entitled Licensee Event Re ort~estem the following report is being submitted: |
| .~LER315/99-016-00, "Technical Specification Requirements forSourceRangeNeutronFluxMonitorsNotMet".Therearenocommitments identified inthisLER.Sincerely, A.Christopher Bakken,IIISiteVicePresident | | .~LER 315/99-016-00,"Technical Specification Requirements for Source Range Neutron Flux Monitors Not Met".There are no commitments identified in this LER.Sincerely, A.Christopher Bakken, III Site Vice President/mbd Attachment J.E.Dyer, Region III R.P.Powers P.A.Barrett G.P.Arent R.Whale D.Hahn Records Center, INPO NRC Resident Inspector'gr907200ii6 9''ir07i3 PDR ADQCK 0500031.5 S PDR Rh136r)U.S.NIICLEAR REGUL Y COMihllSSION LICENSEE EVENT REPORT (LER)(Sec reverse for required number of digits/characters for each block)APPROV OMB No.3160.0104 EXPIRES 06/30/2001 Estimated burden per response to comply with this mandatory information collecuon request: 50 hrs, Reported lessons learned are incorporated alto the Bcensing process and fed back to industry.Foward comments regarding burden estimate to the Records Management Branch (T.B F33), U.S.No@ear Regulatory Convnission, Washington, DC 20555400t~and to the Paperwork Reduction Project (3ISOOI04), Ogffxxi Of Management and Budget.Washington. |
| /mbdAttachment J.E.Dyer,RegionIIIR.P.PowersP.A.BarrettG.P.ArentR.WhaleD.HahnRecordsCenter,INPONRCResidentInspector | | DC 20503.If an Information collection does not display a currently vatid OMB control numberthe NRC may not conduct or sponsor, and a person is not required to respond to, the information collect'on. |
| 'gr907200ii6 9''ir07i3 PDRADQCK0500031.5 SPDR Rh136r)U.S.NIICLEARREGULYCOMihllSSION LICENSEEEVENTREPORT(LER)(Secreverseforrequirednumberofdigits/characters foreachblock)APPROVOMBNo.3160.0104 EXPIRES06/30/2001 Estimated burdenperresponsetocomplywiththismandatory information collecuon request:50hrs,Reportedlessonslearnedareincorporated altotheBcensingprocessandfedbacktoindustry. | | FACH.ITY NARIE (I)Cook Nuclear Plant Unit 1 DOCKET NUhtBER (2)05000-315 PAGE (3)1 OF 3 TITLE ta)Technical Specification Requirements for Source Range Neutron Flux Monitors Not Met EVENT DATE (5)LER NUMBER (6)REPORT DATE (7)OTIIER FACILITIES INVOLVED (8)MONTH DAY YEAR YEAR 1999 SEQUENTIAL REVISION NUMBER NUMBER MONTH DAY YEAR FACILITY NAME FACILITY NAME Cook Nuclear Plant Unit 2 DOCKET NUMBER DOCKET NUMBER 05000-316 OPERATING hlODE (9)LEVEL(10)20.2203(a)(l) 20,2203(a)(2)(ii) a v 20.2203(a)(3)(i) a II 20.2203(a)(4) a 50.73(a)(2)(ii) a I I I 50.73(a)(2)(iv) |
| Fowardcommentsregarding burdenestimatetotheRecordsManagement Branch(T.BF33),U.S.No@earRegulatory Convnission, Washington, DC20555400t
| | THIS REPORT IS SUBh1ITTED PURSUANT TOTIIE REQ UI REM ENTS OF 10 CFR g: (Check onc or niore)(11)a VI II 50.73(a)(2)(x) |
| ~andtothePaperwork Reduction Project(3ISOOI04), | | OTHER a ui a Iv LICENSEE CONTACT FOR TII IS LER a vn ci y n1 street ow or ill 1P F RC Form 366A NAhlE Mr.Dennis D.Snodgrass, Compliance Engineer TELEPHONE Nuhf BER (Include Area Code)(616)465-5901 X1627 COhlPLETE ONE LINE FOR EACII COMPONENT FAILURE.DE SCRIBED IN TIIIS REPORT (13)CAUSE SYSTEht COMPONENT MANUFACTURER REPORTABLE TO EPIX CAUSE SYSTEht COMPONENT MANUFACTURER REPORTABLE TO EPIX SUPPLEh1ENTAL REPORT EXPECTED (14)X YES (If yes, complete EXPECTED SUBMISSION DATE).NO EXPECI'ED MONTH 09 DAY 15'EAR 1999 ABSTRACT (Limit to 1400 spaces, i.c., approximately l5 single-spaced typewritten lines)(16)On June 15, 1999 at 1700 hours EST with both units in Mode 5, the Source Range Nuclear Instrumentation channels on both Units were determined to be inoperable. |
| OgffxxiOfManagement andBudget.Washington.
| | The Expanded System Readiness Review identified that the Technical Specification (T/S)3.3.1.1 and T/S 3.9.2 surveillance tests did not verify the Source Range"High Flux at Shutdown" alarm operable.This alarm function is required to be operable during modes 3, 4, 5 and 6.On June 15, 1999 at 2013 hours EST an ENS report was made in accordance with 10 CFR 50.72(b)(2)(iii)(D) for an event that could have prevented the fulfillment of the safety function of a system needed to mitigate the consequences of an accident.This LER is therefore submitted in accordance with 10 CFR 50.73(a)(2)(v)(D), and is also reportable per the requirements of 10 CFR 50.73(a)(2)(i)(B), as a condition prohibited by the plant's T/S.The apparent cause of this event is failure to understand the design basis of the plant.Upon declaring the Source Range Nuclear Instrumentation channels inoperable, Operations entered the action statements for T/S 3.3.1.1.Additional compensatory measures implemented by Operations included hourly checks of Source Range instrumentation response and the"High Flux at Shutdown" alarm clear.The surveillance procedures were revised and the"High Flux at Shutdown" alarm was.verified operable June 17, 1999 on ehch Unit.The Source Range"High Flux at Shutdown" alarm and the containment evacuation horns share common circuitry. |
| DC20503.IfanInformation collection doesnotdisplayacurrently vatidOMBcontrolnumbertheNRCmaynotconductorsponsor,andapersonisnotrequiredtorespondto,theinformation collect'on.
| | When the containment evacuation horns are verified operable by surveillance test, the"High Flux at Shutdown" alarm is received but not documented. |
| FACH.ITYNARIE(I)CookNuclearPlantUnit1DOCKETNUhtBER(2)05000-315 PAGE(3)1OF3TITLEta)Technical Specification Requirements forSourceRangeNeutronFluxMonitorsNotMetEVENTDATE(5)LERNUMBER(6)REPORTDATE(7)OTIIERFACILITIES INVOLVED(8)MONTHDAYYEARYEAR1999SEQUENTIAL REVISIONNUMBERNUMBERMONTHDAYYEARFACILITYNAMEFACILITYNAMECookNuclearPlantUnit2DOCKETNUMBERDOCKETNUMBER05000-316 OPERATING hlODE(9)LEVEL(10) 20.2203(a)(l) 20,2203(a)(2)(ii) av20.2203(a)(3)(i) aII20.2203(a)(4) a50.73(a)(2)(ii) aIII50.73(a)(2)(iv) | | Although not verified in the past by surveillance test, it is our belief the alarm has been functional. |
| THISREPORTISSUBh1ITTED PURSUANTTOTIIEREQUIREMENTSOF10CFRg:(Checkoncorniore)(11)aVIII50.73(a)(2)(x)
| | Therefore, there were minimal implications to the health and safety of the public as a result of this event. |
| OTHERauiaIvLICENSEECONTACTFORTIIISLERavnciyn1streetoworill1PFRCForm366ANAhlEMr.DennisD.Snodgrass, Compliance EngineerTELEPHONE NuhfBER(IncludeAreaCode)(616)465-5901X1627COhlPLETE ONELINEFOREACIICOMPONENT FAILURE.DE SCRIBEDINTIIISREPORT(13)CAUSESYSTEhtCOMPONENT MANUFACTURER REPORTABLE TOEPIXCAUSESYSTEhtCOMPONENT MANUFACTURER REPORTABLE TOEPIXSUPPLEh1ENTAL REPORTEXPECTED(14)XYES(Ifyes,completeEXPECTEDSUBMISSION DATE).NOEXPECI'ED MONTH09DAY15'EAR1999ABSTRACT(Limitto1400spaces,i.c.,approximately l5single-spaced typewritten lines)(16)OnJune15,1999at1700hoursESTwithbothunitsinMode5,theSourceRangeNuclearInstrumentation channelsonbothUnitsweredetermined tobeinoperable.
| | i<ill 3GGA U.S.NUCLEAR I LATORY CoillMISSIOiN LICENSEE EVENT REPORT (LER)TEXT CONTINUATION FACILITY iNA ME (I)DOCKET (2)Null DER (2)LER N(ijlllI ER (G)PACE (3)Cook Nuclear Plant Unit 1 05000-315 YEAR SEQUENTIAL NUMBER REVISION NUMBER 2 OF 3 1999 016 00 TEXT (If more space is required, use additional copies of PRC Fornr 3GGrI)(17)Conditions Prior To Event Unit 1 Mode 5 in Cold Shutdown Unit 2 Mode 5 in Cold Shutdown Descri tion Of The Event On June 15, 1999 at 1700 hours EST with both units in Mode 5, the Source Range Nuclear Instrumentation (EIIS: IG)channels for both Units were determined to be inoperable. |
| TheExpandedSystemReadiness Reviewidentified thattheTechnical Specification (T/S)3.3.1.1andT/S3.9.2surveillance testsdidnotverifytheSourceRange"HighFluxatShutdown" alarmoperable.
| | The Expanded System Readiness Review identified that the Technical Specification (T/S)3.3.1.1 and T/S 3.9.2 surveillance tests did not verify the Source Range"High Flux at Shutdown" alarm (EIIS: IG/RA)operable.This alarm is credited in the licensing basis for detection and mitigation of a boron dilution event and is required to be operable during modes 3, 4, 5 and 6.During the event investigation, the Source Range"Loss of Detector Voltage" alarm was also identified as not being verified operable by T/S surveillance test.This alarm is not explicitly credited in T/S or the Updated Final Safety Analysis Reportbut is relied upon to determine T/S equipment failure.Cause Of The Event The apparent cause of this event is failure to understand the design basis of the plant.Misapplication of the IEEE 279, 1968 definition of"channel resulted in the channel"High Flux at Shutdown" alarm being determined as not requiring operability verification. |
| Thisalarmfunctionisrequiredtobeoperableduringmodes3,4,5and6.OnJune15,1999at2013hoursESTanENSreportwasmadeinaccordance with10CFR50.72(b)(2)(iii)(D) foraneventthatcouldhaveprevented thefulfillment ofthesafetyfunctionofasystemneededtomitigatetheconsequences ofanaccident.
| | The IEEE 279, 1968 definition. |
| ThisLERistherefore submitted inaccordance with10CFR50.73(a)(2)(v)(D),
| | of"channel" states that a channel loses its identity when single action signals are combined.The alarm did not meet the IEEE 279, 1968 definition of"channel" for channel functional verification since both Source Range channels share the alarm.It was apparently overlooked that the alarm is credited in the licensing basis for detection and mitigation of a boron dilution.Consequently, operability verification has not been documented for the alarm on either Unit.Anal sis Of The Event On June 15, 1999 at 2013 hours EST an ENS report was made per 10 CFR 50.72(b)(2)(iii)(D), an event that alone could have prevented the fulfillment of the safety function of a system that is needed to mitigate the consequences of an accident.The Source Range channels on Units 1 and 2 were determined to be inoperable when it was identified that the Source Range"High Flux at Shutdown" alarm was not verified by T/S 3.3.1.1 and T/S 3.9.2 surveillance tests.This LER is therefore submitted in accordance with 10 CFR 50.73(a)(2)(v)(D), and is also reportable per the requirements of 10 CFR 50.73(a)(2)(i)(B), as a condition prohibited by the plant's T/S.The primary function of nuclear instrumentation is to,safeguard the reactor by monitoring the neutron flux and generating appropriate trips and alarms for various phases of reactor operating and shutdown conditions. |
| andisalsoreportable pertherequirements of10CFR50.73(a)(2)(i)(B),
| | The Source Range nuclear instrumentation provides control room indication, alarms and recording of signals proportional to reactor neutron flux during core loading, shutdown, startup as well as during subsequent refueling. |
| asacondition prohibited bytheplant'sT/S.Theapparentcauseofthiseventisfailuretounderstand thedesignbasisoftheplant.Upondeclaring theSourceRangeNuclearInstrumentation channelsinoperable, Operations enteredtheactionstatements forT/S3.3.1.1.Additional compensatory measuresimplemented byOperations includedhourlychecksofSourceRangeinstrumentation responseandthe"HighFluxatShutdown" alarmclear.Thesurveillance procedures wererevisedandthe"HighFluxatShutdown" alarmwas.verified operableJune17,1999onehchUnit.TheSourceRange"HighFluxatShutdown" alarmandthecontainment evacuation hornssharecommoncircuitry.
| | T/S 3.3.1.1 requires one channel of the source range neutron flux monitors to be operable in Modes 3, 4 8 5.T/S 3.9.2 requires two source range neutron flux monitors operable in Mode 6.1 T/S definitions requires the verification of"alarm and/or trip functions" to satisfy surveillance requirements. |
| Whenthecontainment evacuation hornsareverifiedoperablebysurveillance test,the"HighFluxatShutdown" alarmisreceivedbutnotdocumented.
| | The source range"High Flux at Shutdown" alarm operability verification has not been documented for either Unit.The containment evacuation horns operability is verified by surveillance test.The containment evacuation horns and the Source Range"High Flux at Shutdown" alarm share common circuitry. |
| Althoughnotverifiedinthepastbysurveillance test,itisourbeliefthealarmhasbeenfunctional.
| | The"High Flux at Shutdown" alarm is received but not documented when the containment evacuation horns response to high flux signals is verified by the surveillance test.Although not verified in the past by surveillance test, it is our belief the alarm has been functional. |
| Therefore, therewereminimalimplications tothehealthandsafetyofthepublicasaresultofthisevent. | | Therefore, there were minimal safety implications as a result of this event.NRC FORM 366A (G-I998) |
| i<ill3GGAU.S.NUCLEARILATORYCoillMISSIOiN LICENSEEEVENTREPORT(LER)TEXTCONTINUATION FACILITYiNAME(I)DOCKET(2)NullDER(2)LERN(ijlllIER(G)PACE(3)CookNuclearPlantUnit105000-315 YEARSEQUENTIAL NUMBERREVISIONNUMBER2OF3199901600TEXT(Ifmorespaceisrequired, useadditional copiesofPRCFornr3GGrI)(17)Conditions PriorToEventUnit1Mode5inColdShutdownUnit2Mode5inColdShutdownDescritionOfTheEventOnJune15,1999at1700hoursESTwithbothunitsinMode5,theSourceRangeNuclearInstrumentation (EIIS:IG)channelsforbothUnitsweredetermined tobeinoperable. | | FOIDI 3GGA U.S.NUCLEAR.R'GULATORY COAIMISSION |
| TheExpandedSystemReadiness Reviewidentified thattheTechnical Specification (T/S)3.3.1.1andT/S3.9.2surveillance testsdidnotverifytheSourceRange"HighFluxatShutdown" alarm(EIIS:IG/RA)operable.
| | 'v-1998)LICENSEE EVENT REPORT (LER)TEXT CONTINUATION FACILITY NAME (I)Cook Nuclear Plant Unit 1 DOCKET (2)NUMBER 2)05000-315 YEAR LER NUMBER (G)SEQUENTIAL REVISION NUMBER NUMBER PAGE (3)3 OF 3 1999 016 00 TEXT (lf more space is required, use addilional copies of/VRC Form 366')(I7)CORRECTIVE ACTIONS The Source Range channels were declared inoperable when it was identified that the Source Range"High Flux at Shutdown" alarm was'not verified by T/S surveillance tests.Upon declaring the Source Range Nuclear Instrumentation channels inoperable, Operations entered the action statements for T/S 3.3.1.1.Additional compensatory measures implemented by Operations included hourly checks of Source Range instrumentation response and the"High Flux at Shutdown" alarm clear until the Source Range channels were declared operable on June 17, 1999.The surveillance procedures were revised to include a documented operability verification of the Source Range"High Flux at Shutdown" alarm and the"Loss of Detector Voltage" alarm.The surveillance tests were performed to verify operability of the Units 1and 2"High Flux at Shutdown" and the"Loss of Detector Voltage" alarms.The Unit 1 Source Range channels were both declared operable by 2347 hours EST June 17, 1999.The Unjt 2 Source Range channels were both declared operable by 2225 hours EST June 17, 1999.AEP:NRC:1260GH,"Enforcement Actions 98-150, 98-151, 98-152 and 98-186 Reply to Notice Of Violation October 13, 1998", dated March 19, 1999, responded to identified programmatic weaknesses in the Technical Specification Surveillance Program and the plant Design and Licensing Basis.As part of the Restart effort, the adequacy of the T/S, surveillance program will be evaluated, This evaluation includes verification that T/S surveillance requirements for all modes of plant operation are incorporated into T/S surveillance test procedures. |
| Thisalarmiscreditedinthelicensing basisfordetection andmitigation ofaborondilutioneventandisrequiredtobeoperableduringmodes3,4,5and6.Duringtheeventinvestigation, theSourceRange"LossofDetectorVoltage"alarmwasalsoidentified asnotbeingverifiedoperablebyT/Ssurveillance test.Thisalarmisnotexplicitly creditedinT/SortheUpdatedFinalSafetyAnalysisReportbutisreliedupontodetermine T/Sequipment failure.CauseOfTheEventTheapparentcauseofthiseventisfailuretounderstand thedesignbasisoftheplant.Misapplication oftheIEEE279,1968definition of"channelresultedinthechannel"HighFluxatShutdown" alarmbeingdetermined asnotrequiring operability verification.
| | Also as part of the Restart effort, System and programmatic assessments in the Expanded System Readiness Reviews and Licensing Basis Reviews are reestablishing and documenting the plant's Design and Licensing Basis.The root cause investigation for this event is ongoing.The investigation will include a review of the Operations procedures associated with the"High Flux at Shutdown" alarm, and, the UFSAR sections which address the alarm and the boron dilution event, to determine if any revisions are required.Supplemental information, including any additional corrective actions, will be provided in an update to this LER.SIMILAR EVENTS 315/99-015-00 NRC F Rh1.66A (6.1998)}} |
| TheIEEE279,1968definition.
| |
| of"channel" statesthatachannellosesitsidentitywhensingleactionsignalsarecombined. | |
| ThealarmdidnotmeettheIEEE279,1968definition of"channel" forchannelfunctional verification sincebothSourceRangechannelssharethealarm.Itwasapparently overlooked thatthealarmiscreditedinthelicensing basisfordetection andmitigation ofaborondilution.
| |
| Consequently, operability verification hasnotbeendocumented forthealarmoneitherUnit.AnalsisOfTheEventOnJune15,1999at2013hoursESTanENSreportwasmadeper10CFR50.72(b)(2)(iii)(D), | |
| aneventthatalonecouldhaveprevented thefulfillment ofthesafetyfunctionofasystemthatisneededtomitigatetheconsequences ofanaccident.
| |
| TheSourceRangechannelsonUnits1and2weredetermined tobeinoperable whenitwasidentified thattheSourceRange"HighFluxatShutdown" alarmwasnotverifiedbyT/S3.3.1.1andT/S3.9.2surveillance tests.ThisLERistherefore submitted inaccordance with10CFR50.73(a)(2)(v)(D),
| |
| andisalsoreportable pertherequirements of10CFR50.73(a)(2)(i)(B),
| |
| asacondition prohibited bytheplant'sT/S.Theprimaryfunctionofnuclearinstrumentation isto,safeguard thereactorbymonitoring theneutronfluxandgenerating appropriate tripsandalarmsforvariousphasesofreactoroperating andshutdownconditions.
| |
| TheSourceRangenuclearinstrumentation providescontrolroomindication, alarmsandrecording ofsignalsproportional toreactorneutronfluxduringcoreloading,shutdown, startupaswellasduringsubsequent refueling.
| |
| T/S3.3.1.1requiresonechannelofthesourcerangeneutronfluxmonitorstobeoperableinModes3,485.T/S3.9.2requirestwosourcerangeneutronfluxmonitorsoperableinMode6.1T/Sdefinitions requirestheverification of"alarmand/ortripfunctions" tosatisfysurveillance requirements. | |
| Thesourcerange"HighFluxatShutdown" alarmoperability verification hasnotbeendocumented foreitherUnit.Thecontainment evacuation hornsoperability isverifiedbysurveillance test.Thecontainment evacuation hornsandtheSourceRange"HighFluxatShutdown" alarmsharecommoncircuitry.
| |
| The"HighFluxatShutdown" alarmisreceivedbutnotdocumented whenthecontainment evacuation hornsresponsetohighfluxsignalsisverifiedbythesurveillance test.Althoughnotverifiedinthepastbysurveillance test,itisourbeliefthealarmhasbeenfunctional. | |
| Therefore, therewereminimalsafetyimplications asaresultofthisevent.NRCFORM366A(G-I998) | |
| FOIDI3GGAU.S.NUCLEAR.R
| |
| 'GULATORY COAIMISSION | |
| 'v-1998)LICENSEEEVENTREPORT(LER)TEXTCONTINUATION FACILITYNAME(I)CookNuclearPlantUnit1DOCKET(2)NUMBER2)05000-315 YEARLERNUMBER(G)SEQUENTIAL REVISIONNUMBERNUMBERPAGE(3)3OF3199901600TEXT(lfmorespaceisrequired, useaddilional copiesof/VRCForm366')(I7)CORRECTIVE ACTIONSTheSourceRangechannelsweredeclaredinoperable whenitwasidentified thattheSourceRange"HighFluxatShutdown" alarmwas'notverifiedbyT/Ssurveillance tests.Upondeclaring theSourceRangeNuclearInstrumentation channelsinoperable, Operations enteredtheactionstatements forT/S3.3.1.1.Additional compensatory measuresimplemented byOperations includedhourlychecksofSourceRangeinstrumentation responseandthe"HighFluxatShutdown" alarmclearuntiltheSourceRangechannelsweredeclaredoperableonJune17,1999.Thesurveillance procedures wererevisedtoincludeadocumented operability verification oftheSourceRange"HighFluxatShutdown" alarmandthe"LossofDetectorVoltage"alarm.Thesurveillance testswereperformed toverifyoperability oftheUnits1and2"HighFluxatShutdown" andthe"LossofDetectorVoltage"alarms.TheUnit1SourceRangechannelswerebothdeclaredoperableby2347hoursESTJune17,1999.TheUnjt2SourceRangechannelswerebothdeclaredoperableby2225hoursESTJune17,1999.AEP:NRC:1260GH, "Enforcement Actions98-150,98-151,98-152and98-186ReplytoNoticeOfViolation October13,1998",datedMarch19,1999,responded toidentified programmatic weaknesses intheTechnical Specification Surveillance ProgramandtheplantDesignandLicensing Basis.AspartoftheRestarteffort,theadequacyoftheT/S,surveillance programwillbeevaluated, Thisevaluation includesverification thatT/Ssurveillance requirements forallmodesofplantoperation areincorporated intoT/Ssurveillance testprocedures. | |
| AlsoaspartoftheRestarteffort,Systemandprogrammatic assessments intheExpandedSystemReadiness ReviewsandLicensing BasisReviewsarereestablishing anddocumenting theplant'sDesignandLicensing Basis.Therootcauseinvestigation forthiseventisongoing.Theinvestigation willincludeareviewoftheOperations procedures associated withthe"HighFluxatShutdown" alarm,and,theUFSARsectionswhichaddressthealarmandtheborondilutionevent,todetermine ifanyrevisions arerequired.
| |
| Supplemental information, including anyadditional corrective actions,willbeprovidedinanupdatetothisLER.SIMILAREVENTS315/99-015-00 NRCFRh1.66A(6.1998)}} | |
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Category:LICENSEE EVENT REPORT (SEE ALSO AO
MONTHYEARML17335A5641999-10-18018 October 1999 LER 99-024-00:on 990708,literal TS Requirements Were Not Met by Accumlator Valve Surveillance.Caused by Misjudgement Made in Conversion from Initial DC Cook TS to W Std Ts.Submitted License Amend Request.With 991018 Ltr ML17335A5531999-10-0707 October 1999 LER 99-023-00:on 990907,inadequate TS Surveillance Testing of ESW Pump ESF Response Time Noted.Caused by Inadequate Understanding of Plant Design Basis.Surveillance Tests Will Be Revised & Implemented ML17326A1291999-09-17017 September 1999 LER 99-022-00:on 990609,electrical Bus Degraded Voltage Setpoints Too Low for Safety Related Loads,Was Discovered. Caused by Lack of Understanding of Design of Plant.No Immediate Corrective Actions Necessary ML17326A1121999-08-27027 August 1999 LER 99-021-00:on 990728,determined That GL 96-01 Test Requirements Were Not Met in Surveillance Tests.Caused by Failure to Understand Full Extent of GL Requirements. Surveillance Procedures Will Be Revised or Developed ML17326A1011999-08-26026 August 1999 LER 99-020-00:on 990727,EDGs Were Declared Inoperable.Caused by Inadequate Protection of Air Intake,Exhaust & Room Ventilation Structures from Tornado Missile Hazards. Implemented Compensatory Measures in Form of ACs ML17326A0911999-08-16016 August 1999 LER 99-019-00:on 990716,noted Victoreen Containment Hrrms Not Environmentally Qualified to Withstand post-LOCA Conditions.Caused by Inadequate Design Control.Reviewing Options to Support Hrrms Operability in Modes 1-4 ML17326A0771999-08-0404 August 1999 LER 98-029-01:on 980422,noted That Fuel Handling Area Ventilation Sys Was Inoperable.Caused by Original Design Deficiency.Radiological Analysis for Spent Fuel Handling Accidents in Auxiliary Bldg Will Be Redone by 990830 ML17326A0741999-07-29029 July 1999 LER 99-018-00:on 990629,determined That Valve Yokes May Yield Under Combined Stress of Seismic Event & Static,Valve Closed,Stem Thrust.Caused by Inadequate Design of Associated Movs.Operability Determinations Were Performed for Valves ML17326A0661999-07-26026 July 1999 LER 99-017-00:on 990625,noted That Improperly Installed Fuel Oil Return Relief Valve Rendered EDG Inoperable.Caused by Personnel Error.Fuel Oil Return Valve Was Replaced with Valve in Correct Orientation.With 990722 Ltr ML17326A0651999-07-22022 July 1999 LER 98-014-03:on 980310,noted That Response to high-high Containment Pressure Procedure Was Not Consistent with Analysis of Record.Caused by Inadequate Interface with W. FRZ-1 Will Be Revised to Be Consistent with New Analysis ML17326A0491999-07-13013 July 1999 LER 99-016-00:on 990615,TS Requirements for Source Range Neutron Flux Monitors Not Met.Caused by Failure to Understand Design Basis of Plant.Procedures Revised.With 990713 Ltr ML17326A0331999-07-0101 July 1999 LER 99-004-01:on 971030,failure to Perform TS Surveillance Analyses of Reactor Coolant Chemistry with Fuel Removed Was Noted.Caused by Ineffective Mgt of Tss.Chemistry Personnel Have Been Instructed on Requirement to Follow TS as Written ML17326A0151999-06-18018 June 1999 LER 99-014-00:on 990521,determined That Boron Injection Tank Manway Bolts Were Not Included in ISI Program,Creating Missed Exam for Previous ISI Interval.Caused by Programmatic Weakness.Isi Program & Associated ISI Database Modified ML17325B6311999-06-0101 June 1999 LER 99-S03-00:on 990430,vital Area Barrier Degradation Was Noted.Caused by Inadequate Insp & Maint of Vital Area Barrier.Repairs & Mods Were Made to Barriers to Eliminate Degraded & Nonconforming Conditions ML17325B6421999-06-0101 June 1999 LER 99-013-00:on 990327,safety Injection & Centrifugal Charging Throttle Valve Cavitation During LOCA Could Have Led to ECCS Pump Failure.Caused by Inadequate Original Design Application of Si.Throttle Valves Will Be Developed ML17325B6351999-05-28028 May 1999 LER 99-S02-00:on 990428,vulnerability in Safeguard Sys That Could Allow Unauthorized Access to Protected Area Was Noted. Caused by Inadequate Original Plant Design.Mods Were Made to Wall Opening to Eliminate Nonconforming Conditions ML17265A8231999-05-24024 May 1999 LER 98-037-01:on 990422,determined That Ice Condenser Bypass Leakage Exceeds Design Basis Limit.Caused by Pressure Seal Required by Revised W Design Not Incorporated Into Aep Design.Numerous Matl Condition Walkdowns & Assessments Made ML17325B6001999-05-20020 May 1999 LER 99-012-00:on 990420,concluded That Auxiliary Bldg ESF Ventilation Sys Not Capable of Maintaining ESF Room Temps post-accident.Caused by Inadequate Control of Sys Design Inputs.Comprehensive Action Plan Being Developed ML17325B5861999-05-10010 May 1999 LER 99-002-00:on 990415,discovered That TS 4.0.5 Requirements Were Not Met Due to Improperly Performed Test. Caused by Incorrect Interpretation of ASME Code.App J Testing Will Be Completed & Procedures Will Be Revised ML17325B5811999-05-0404 May 1999 LER 99-011-00:on 990407,air Sys for EDG Will Not Support Long Operability.Caused by Original Design Error.Temporary Mod to Supply Makeup Air Capability in Modes 5 & 6 Was Prepared ML17325B5771999-05-0303 May 1999 LER 99-010-00:on 990401,RCS Leak Detection Sys Sensitivity Not in Accordance with Design Requirements Occurred.Caused by Inadequate Original Design of Containment Sump Level. Evaluation Will Be Performed to Clearly Define Design ML17325B5581999-04-16016 April 1999 LER 99-006-00:on 990115,personnel Identified Discrepancy Between TS 3.9.7 Impact Energy Limit & Procedure 12 Ohp 4030.STP.046.Caused by Lack of Design Basis Control.Placed Procedure 12 Ohp 4030.STP.046 on Administrative Hold ML17325B5471999-04-12012 April 1999 LER 99-009-00:on 990304,as-found RHR Safety Relief Valve Lift Setpoint Greater than TS Limit Occurred.Cause Investigation for Condition Has Not Been Completed.Update to LER Will Be Submitted,Upon Completion of Investigation ML17325B5321999-04-0707 April 1999 LER 99-S01-00:on 990308,discovered That Lock for Vital Gate Leading to Plant 4KV Switchgear Area Was Nonconforming & Vulnerable to Unauthorized Access.Caused by Inadequate Gate Design & Inadequate Procedures.Mods Are Being Made to Gate ML17325B5161999-04-0101 April 1999 LER 99-007-00:on 981020,calculations Showed That Divider Barrier Between Upper & Lower Containment Vols Were Overstressed.Engineers Are Currently Working on Analyses of Loads & Stress on Enclosures ML17325B5221999-03-29029 March 1999 LER 99-001-00:on 960610,degraded Component Cooling Water Flow to Containment Main Steam Line Penetrations,Identified on 990226.Caused by Inadequate Understanding of Design Basis.Additional Investigations Ongoing ML17325B4801999-03-18018 March 1999 LER 99-004-00:on 971030,failure to Perform TS Surveillance Analyses of Rc Chemistry with Fuel Removed Was Noted.Cause of Event Is Under Investigation.Corrected Written Job Order Activities Used to Control SD Chemistry Sampling ML17325B4741999-03-18018 March 1999 LER 99-005-00:on 940512,determined That Rt Breaker Manual Actuations During Rod Drop Testing Were Not Previously Reported.Caused by Lack of Training.Addl Corrective Actions,Including Preventative Actions May Be Developed ML17325B4571999-02-24024 February 1999 LER 99-003-00:on 990107,CR Pressurization Sys Surveillance Test Did Not Test Sys in Normal Operating Condition.Caused by Failure to Recognize Door 12DR-AUX415 as Part of CR Pressure Boundary.Performed Walkdown of Other Doors ML17335A5171999-02-11011 February 1999 LER 99-002-00:on 990112,determined That RCS Pressurizer PORVs Had Not Been Tested,Per Ts.Caused by Inadequate Scheduling Controls Allowing Personnel Error.Surveillance Procedure Was Completed & Updated LER Will Be Submitted ML17335A5141999-02-10010 February 1999 LER 99-001-00:on 990106,noted That GE Hfa Relays Installed in EDGs May Not Meet Seismic Qualification.Caused by Operating Experience Info Incorrectly Dispositioned in 1985. Updated LER Will Be Submitted by 990405 ML17335A5011999-02-0101 February 1999 LER 98-060-00:on 981231,identified That Rt Sys Response Time Testing Did Not Comply with TS Definition.Caused by Inadequate Procedures.Corrective Actions Will Be Developed & Update to LER Will Be Submitted by 990415.With 990201 Ltr ML17335A4951999-01-29029 January 1999 LER 98-059-00:on 981230,interim LER -single Failure in Containment Spray Sys Could Result in Containment Spray Ph Outside Design Occurred.Investigation Into Condition Continuing.Update Will Be Submitted by 990514 Ltr ML17335A4961999-01-27027 January 1999 LER 98-057-00:on 981228,discovered That AFW Valves Were Not Tested IAW Inservice Testing Program.Caused by Failure to Recognize Design Bases Features Re Afws by Personnel. Updated LER Will Be Submittted by 990415.With 990127 Ltr ML17335A4921999-01-19019 January 1999 LER 98-052-01:on 981128,no Analysis for NSR Sc Manual Loader for Tdafwp Could Be Found in Original Design.Cause Due to All Failure Modes Not Considered When Compressed Air Sys Originally Designed.Performed Review of Components ML17335A4721999-01-0606 January 1999 LER 98-055-00:on 981207,potential for Condition Outside of Design Bases for Rod Control Sys Was Noted.Caused by Calibration Error Coupled with Single Rod Failure.Condition Rept Investigation Is Ongoing ML17335A4691999-01-0606 January 1999 LER 98-056-00:on 981211,hot Leg Nozzle Gaps Resulted in Plant Being in Unanalyzed Condition.Analyses Are Being Performed by W to Resolve Problem.Updated LER Will Be Submitted by 990211.With 990106 Ltr ML17335A4661999-01-0505 January 1999 LER 98-049-00:on 981020,emergency Boron Injection Flow Path Was Inoperable.Caused by Original Design Deficiency. Engineering Evaluation of Event Is Continuing ML17335A4631999-01-0404 January 1999 LER 98-054-00:on 981202,discovered That at Least One MSSV Had Not Been Reset as Required by Ts.Engineering Is Continuing Review of Extent of Condition for Event.Updated LER Will Be Submitted by 990129.With 990104 Ltr ML17335A4481998-12-30030 December 1998 LER 98-053-00:on 981130,discovered Use of Inoperable Substitute Subcooling Margin Monitor.Caused by Condition Existing Since Installation of Plant Process Computer in 1992.Updated LER Will Be Submitted.With 981230 Ltr ML17335A4581998-12-28028 December 1998 LER 98-052-00:on 981128,turbine Driven AFW Pump Speed Controller Failure Mode Occurred.Caused Because Not All Failure Modes Were Considered When Compressed Air Sys Was Originally Designed.Verified Current Design Change Process ML17335A4281998-12-22022 December 1998 LER 98-051-00:on 981122,reactor Trip Signal from Manual Safety Injection Not Verified as Required by TS Surveillance,Was Discovered.Maintenance Currently Evaluating Significance & Cause of Event ML17335A4111998-12-17017 December 1998 LER 98-047-00:on 981117,potential for Increase Leakage from Reactor Coolant Pump Seals Was Identified.Util Is Working with W to Resolve Issue.Current Expectations Are to Submit Update to LER by 990215.With 981217 Ltr ML17335A4141998-12-16016 December 1998 LER 98-058-00:on 981216,postulated High Line Break Could Result in Condition Outside Design Bases for AF Occurred. Caused by Deficiencies Associated with Administration of HELB Program.Analysis of AF Will Be Completed by 990122 ML17335A4181998-12-16016 December 1998 LER 98-050-00:on 980814,ancillary Equipment Installed in Ice Condenser Was Not Designed to Withstand Design Basis Accident/Earthquake Loads.Caused by Lack of Established Design Criteria.Developed Design Criteria ML17335A3871998-12-11011 December 1998 LER 98-031-01:on 980610,potential Common Mode Failure of RHR Pumps Were Noted.Caused by Inaccurate Values.Accurate Miniflow Numbers Have Been Determined by Flow Testing ML17335A3821998-12-0808 December 1998 LER 98-039-01 Re EOP Step Conflicts with Small Break LOCA Analysis.Ler 98-039-00 Has Been Canceled.With 981208 Ltr ML17335A3781998-12-0707 December 1998 LER 98-007-00:on 981106,high Energy Line Break Effects in Auxiliary FW Sys Was Noted.Cause of Event Is Under Investigation & Will Be Completed by 990220.Updated LER Will Be Submitted by 990310.With 981207 Ltr ML17335A3771998-12-0303 December 1998 LER 98-046-00:on 981103,determined That Afs Was Unable to Meet Design Flow Requirements During Special Test.Caused by Failure to Consider All Aspects of Sys Operation in Design of Suction Basket Strainers.Sys Will Be Redesigned ML17335A3741998-12-0202 December 1998 LER 97-011-02:on 970822,operation Was Noted Outside Design Bases for ECCS & CSP for Switchover to Recirculation Sump Suction.Caused by Ineffective Change Mgt.Revised Procedure for Switchover 01(02) Ohp 4023.ES-1.3 1999-09-17
[Table view] Category:RO)
MONTHYEARML17335A5641999-10-18018 October 1999 LER 99-024-00:on 990708,literal TS Requirements Were Not Met by Accumlator Valve Surveillance.Caused by Misjudgement Made in Conversion from Initial DC Cook TS to W Std Ts.Submitted License Amend Request.With 991018 Ltr ML17335A5531999-10-0707 October 1999 LER 99-023-00:on 990907,inadequate TS Surveillance Testing of ESW Pump ESF Response Time Noted.Caused by Inadequate Understanding of Plant Design Basis.Surveillance Tests Will Be Revised & Implemented ML17326A1291999-09-17017 September 1999 LER 99-022-00:on 990609,electrical Bus Degraded Voltage Setpoints Too Low for Safety Related Loads,Was Discovered. Caused by Lack of Understanding of Design of Plant.No Immediate Corrective Actions Necessary ML17326A1121999-08-27027 August 1999 LER 99-021-00:on 990728,determined That GL 96-01 Test Requirements Were Not Met in Surveillance Tests.Caused by Failure to Understand Full Extent of GL Requirements. Surveillance Procedures Will Be Revised or Developed ML17326A1011999-08-26026 August 1999 LER 99-020-00:on 990727,EDGs Were Declared Inoperable.Caused by Inadequate Protection of Air Intake,Exhaust & Room Ventilation Structures from Tornado Missile Hazards. Implemented Compensatory Measures in Form of ACs ML17326A0911999-08-16016 August 1999 LER 99-019-00:on 990716,noted Victoreen Containment Hrrms Not Environmentally Qualified to Withstand post-LOCA Conditions.Caused by Inadequate Design Control.Reviewing Options to Support Hrrms Operability in Modes 1-4 ML17326A0771999-08-0404 August 1999 LER 98-029-01:on 980422,noted That Fuel Handling Area Ventilation Sys Was Inoperable.Caused by Original Design Deficiency.Radiological Analysis for Spent Fuel Handling Accidents in Auxiliary Bldg Will Be Redone by 990830 ML17326A0741999-07-29029 July 1999 LER 99-018-00:on 990629,determined That Valve Yokes May Yield Under Combined Stress of Seismic Event & Static,Valve Closed,Stem Thrust.Caused by Inadequate Design of Associated Movs.Operability Determinations Were Performed for Valves ML17326A0661999-07-26026 July 1999 LER 99-017-00:on 990625,noted That Improperly Installed Fuel Oil Return Relief Valve Rendered EDG Inoperable.Caused by Personnel Error.Fuel Oil Return Valve Was Replaced with Valve in Correct Orientation.With 990722 Ltr ML17326A0651999-07-22022 July 1999 LER 98-014-03:on 980310,noted That Response to high-high Containment Pressure Procedure Was Not Consistent with Analysis of Record.Caused by Inadequate Interface with W. FRZ-1 Will Be Revised to Be Consistent with New Analysis ML17326A0491999-07-13013 July 1999 LER 99-016-00:on 990615,TS Requirements for Source Range Neutron Flux Monitors Not Met.Caused by Failure to Understand Design Basis of Plant.Procedures Revised.With 990713 Ltr ML17326A0331999-07-0101 July 1999 LER 99-004-01:on 971030,failure to Perform TS Surveillance Analyses of Reactor Coolant Chemistry with Fuel Removed Was Noted.Caused by Ineffective Mgt of Tss.Chemistry Personnel Have Been Instructed on Requirement to Follow TS as Written ML17326A0151999-06-18018 June 1999 LER 99-014-00:on 990521,determined That Boron Injection Tank Manway Bolts Were Not Included in ISI Program,Creating Missed Exam for Previous ISI Interval.Caused by Programmatic Weakness.Isi Program & Associated ISI Database Modified ML17325B6311999-06-0101 June 1999 LER 99-S03-00:on 990430,vital Area Barrier Degradation Was Noted.Caused by Inadequate Insp & Maint of Vital Area Barrier.Repairs & Mods Were Made to Barriers to Eliminate Degraded & Nonconforming Conditions ML17325B6421999-06-0101 June 1999 LER 99-013-00:on 990327,safety Injection & Centrifugal Charging Throttle Valve Cavitation During LOCA Could Have Led to ECCS Pump Failure.Caused by Inadequate Original Design Application of Si.Throttle Valves Will Be Developed ML17325B6351999-05-28028 May 1999 LER 99-S02-00:on 990428,vulnerability in Safeguard Sys That Could Allow Unauthorized Access to Protected Area Was Noted. Caused by Inadequate Original Plant Design.Mods Were Made to Wall Opening to Eliminate Nonconforming Conditions ML17265A8231999-05-24024 May 1999 LER 98-037-01:on 990422,determined That Ice Condenser Bypass Leakage Exceeds Design Basis Limit.Caused by Pressure Seal Required by Revised W Design Not Incorporated Into Aep Design.Numerous Matl Condition Walkdowns & Assessments Made ML17325B6001999-05-20020 May 1999 LER 99-012-00:on 990420,concluded That Auxiliary Bldg ESF Ventilation Sys Not Capable of Maintaining ESF Room Temps post-accident.Caused by Inadequate Control of Sys Design Inputs.Comprehensive Action Plan Being Developed ML17325B5861999-05-10010 May 1999 LER 99-002-00:on 990415,discovered That TS 4.0.5 Requirements Were Not Met Due to Improperly Performed Test. Caused by Incorrect Interpretation of ASME Code.App J Testing Will Be Completed & Procedures Will Be Revised ML17325B5811999-05-0404 May 1999 LER 99-011-00:on 990407,air Sys for EDG Will Not Support Long Operability.Caused by Original Design Error.Temporary Mod to Supply Makeup Air Capability in Modes 5 & 6 Was Prepared ML17325B5771999-05-0303 May 1999 LER 99-010-00:on 990401,RCS Leak Detection Sys Sensitivity Not in Accordance with Design Requirements Occurred.Caused by Inadequate Original Design of Containment Sump Level. Evaluation Will Be Performed to Clearly Define Design ML17325B5581999-04-16016 April 1999 LER 99-006-00:on 990115,personnel Identified Discrepancy Between TS 3.9.7 Impact Energy Limit & Procedure 12 Ohp 4030.STP.046.Caused by Lack of Design Basis Control.Placed Procedure 12 Ohp 4030.STP.046 on Administrative Hold ML17325B5471999-04-12012 April 1999 LER 99-009-00:on 990304,as-found RHR Safety Relief Valve Lift Setpoint Greater than TS Limit Occurred.Cause Investigation for Condition Has Not Been Completed.Update to LER Will Be Submitted,Upon Completion of Investigation ML17325B5321999-04-0707 April 1999 LER 99-S01-00:on 990308,discovered That Lock for Vital Gate Leading to Plant 4KV Switchgear Area Was Nonconforming & Vulnerable to Unauthorized Access.Caused by Inadequate Gate Design & Inadequate Procedures.Mods Are Being Made to Gate ML17325B5161999-04-0101 April 1999 LER 99-007-00:on 981020,calculations Showed That Divider Barrier Between Upper & Lower Containment Vols Were Overstressed.Engineers Are Currently Working on Analyses of Loads & Stress on Enclosures ML17325B5221999-03-29029 March 1999 LER 99-001-00:on 960610,degraded Component Cooling Water Flow to Containment Main Steam Line Penetrations,Identified on 990226.Caused by Inadequate Understanding of Design Basis.Additional Investigations Ongoing ML17325B4801999-03-18018 March 1999 LER 99-004-00:on 971030,failure to Perform TS Surveillance Analyses of Rc Chemistry with Fuel Removed Was Noted.Cause of Event Is Under Investigation.Corrected Written Job Order Activities Used to Control SD Chemistry Sampling ML17325B4741999-03-18018 March 1999 LER 99-005-00:on 940512,determined That Rt Breaker Manual Actuations During Rod Drop Testing Were Not Previously Reported.Caused by Lack of Training.Addl Corrective Actions,Including Preventative Actions May Be Developed ML17325B4571999-02-24024 February 1999 LER 99-003-00:on 990107,CR Pressurization Sys Surveillance Test Did Not Test Sys in Normal Operating Condition.Caused by Failure to Recognize Door 12DR-AUX415 as Part of CR Pressure Boundary.Performed Walkdown of Other Doors ML17335A5171999-02-11011 February 1999 LER 99-002-00:on 990112,determined That RCS Pressurizer PORVs Had Not Been Tested,Per Ts.Caused by Inadequate Scheduling Controls Allowing Personnel Error.Surveillance Procedure Was Completed & Updated LER Will Be Submitted ML17335A5141999-02-10010 February 1999 LER 99-001-00:on 990106,noted That GE Hfa Relays Installed in EDGs May Not Meet Seismic Qualification.Caused by Operating Experience Info Incorrectly Dispositioned in 1985. Updated LER Will Be Submitted by 990405 ML17335A5011999-02-0101 February 1999 LER 98-060-00:on 981231,identified That Rt Sys Response Time Testing Did Not Comply with TS Definition.Caused by Inadequate Procedures.Corrective Actions Will Be Developed & Update to LER Will Be Submitted by 990415.With 990201 Ltr ML17335A4951999-01-29029 January 1999 LER 98-059-00:on 981230,interim LER -single Failure in Containment Spray Sys Could Result in Containment Spray Ph Outside Design Occurred.Investigation Into Condition Continuing.Update Will Be Submitted by 990514 Ltr ML17335A4961999-01-27027 January 1999 LER 98-057-00:on 981228,discovered That AFW Valves Were Not Tested IAW Inservice Testing Program.Caused by Failure to Recognize Design Bases Features Re Afws by Personnel. Updated LER Will Be Submittted by 990415.With 990127 Ltr ML17335A4921999-01-19019 January 1999 LER 98-052-01:on 981128,no Analysis for NSR Sc Manual Loader for Tdafwp Could Be Found in Original Design.Cause Due to All Failure Modes Not Considered When Compressed Air Sys Originally Designed.Performed Review of Components ML17335A4721999-01-0606 January 1999 LER 98-055-00:on 981207,potential for Condition Outside of Design Bases for Rod Control Sys Was Noted.Caused by Calibration Error Coupled with Single Rod Failure.Condition Rept Investigation Is Ongoing ML17335A4691999-01-0606 January 1999 LER 98-056-00:on 981211,hot Leg Nozzle Gaps Resulted in Plant Being in Unanalyzed Condition.Analyses Are Being Performed by W to Resolve Problem.Updated LER Will Be Submitted by 990211.With 990106 Ltr ML17335A4661999-01-0505 January 1999 LER 98-049-00:on 981020,emergency Boron Injection Flow Path Was Inoperable.Caused by Original Design Deficiency. Engineering Evaluation of Event Is Continuing ML17335A4631999-01-0404 January 1999 LER 98-054-00:on 981202,discovered That at Least One MSSV Had Not Been Reset as Required by Ts.Engineering Is Continuing Review of Extent of Condition for Event.Updated LER Will Be Submitted by 990129.With 990104 Ltr ML17335A4481998-12-30030 December 1998 LER 98-053-00:on 981130,discovered Use of Inoperable Substitute Subcooling Margin Monitor.Caused by Condition Existing Since Installation of Plant Process Computer in 1992.Updated LER Will Be Submitted.With 981230 Ltr ML17335A4581998-12-28028 December 1998 LER 98-052-00:on 981128,turbine Driven AFW Pump Speed Controller Failure Mode Occurred.Caused Because Not All Failure Modes Were Considered When Compressed Air Sys Was Originally Designed.Verified Current Design Change Process ML17335A4281998-12-22022 December 1998 LER 98-051-00:on 981122,reactor Trip Signal from Manual Safety Injection Not Verified as Required by TS Surveillance,Was Discovered.Maintenance Currently Evaluating Significance & Cause of Event ML17335A4111998-12-17017 December 1998 LER 98-047-00:on 981117,potential for Increase Leakage from Reactor Coolant Pump Seals Was Identified.Util Is Working with W to Resolve Issue.Current Expectations Are to Submit Update to LER by 990215.With 981217 Ltr ML17335A4141998-12-16016 December 1998 LER 98-058-00:on 981216,postulated High Line Break Could Result in Condition Outside Design Bases for AF Occurred. Caused by Deficiencies Associated with Administration of HELB Program.Analysis of AF Will Be Completed by 990122 ML17335A4181998-12-16016 December 1998 LER 98-050-00:on 980814,ancillary Equipment Installed in Ice Condenser Was Not Designed to Withstand Design Basis Accident/Earthquake Loads.Caused by Lack of Established Design Criteria.Developed Design Criteria ML17335A3871998-12-11011 December 1998 LER 98-031-01:on 980610,potential Common Mode Failure of RHR Pumps Were Noted.Caused by Inaccurate Values.Accurate Miniflow Numbers Have Been Determined by Flow Testing ML17335A3821998-12-0808 December 1998 LER 98-039-01 Re EOP Step Conflicts with Small Break LOCA Analysis.Ler 98-039-00 Has Been Canceled.With 981208 Ltr ML17335A3781998-12-0707 December 1998 LER 98-007-00:on 981106,high Energy Line Break Effects in Auxiliary FW Sys Was Noted.Cause of Event Is Under Investigation & Will Be Completed by 990220.Updated LER Will Be Submitted by 990310.With 981207 Ltr ML17335A3771998-12-0303 December 1998 LER 98-046-00:on 981103,determined That Afs Was Unable to Meet Design Flow Requirements During Special Test.Caused by Failure to Consider All Aspects of Sys Operation in Design of Suction Basket Strainers.Sys Will Be Redesigned ML17335A3741998-12-0202 December 1998 LER 97-011-02:on 970822,operation Was Noted Outside Design Bases for ECCS & CSP for Switchover to Recirculation Sump Suction.Caused by Ineffective Change Mgt.Revised Procedure for Switchover 01(02) Ohp 4023.ES-1.3 1999-09-17
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML17335A5641999-10-18018 October 1999 LER 99-024-00:on 990708,literal TS Requirements Were Not Met by Accumlator Valve Surveillance.Caused by Misjudgement Made in Conversion from Initial DC Cook TS to W Std Ts.Submitted License Amend Request.With 991018 Ltr ML17335A5531999-10-0707 October 1999 LER 99-023-00:on 990907,inadequate TS Surveillance Testing of ESW Pump ESF Response Time Noted.Caused by Inadequate Understanding of Plant Design Basis.Surveillance Tests Will Be Revised & Implemented ML17335A5631999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for DC Cook Nuclear Plant,Unit 1.With 991012 Ltr ML17335A5621999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for DC Cook Nuclear Plant,Unit 2.With 991012 Ltr ML17335A5481999-09-30030 September 1999 Non-proprietary DC Cook Nuclear Plant Units 1 & 2 Mods to Containment Sys W SE (Secl 99-076,Rev 3). ML17335A5451999-09-28028 September 1999 Rev 1 to Containment Sump Level Design Condition & Failure Effects Analysis for Potential Draindown Scenarios. ML17326A1291999-09-17017 September 1999 LER 99-022-00:on 990609,electrical Bus Degraded Voltage Setpoints Too Low for Safety Related Loads,Was Discovered. Caused by Lack of Understanding of Design of Plant.No Immediate Corrective Actions Necessary ML17326A1481999-09-17017 September 1999 Independent Review of Control Rod Insertion Following Cold Leg Lbloca,Dc Cook,Units 1 & 2. ML17326A1211999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Cook Nuclear Plant, Unit 2.With 990915 Ltr ML17326A1201999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Cook Nuclear Plant, Unit 1.With 990915 Ltr ML17326A1121999-08-27027 August 1999 LER 99-021-00:on 990728,determined That GL 96-01 Test Requirements Were Not Met in Surveillance Tests.Caused by Failure to Understand Full Extent of GL Requirements. Surveillance Procedures Will Be Revised or Developed ML17326A1011999-08-26026 August 1999 LER 99-020-00:on 990727,EDGs Were Declared Inoperable.Caused by Inadequate Protection of Air Intake,Exhaust & Room Ventilation Structures from Tornado Missile Hazards. Implemented Compensatory Measures in Form of ACs ML17326A0911999-08-16016 August 1999 LER 99-019-00:on 990716,noted Victoreen Containment Hrrms Not Environmentally Qualified to Withstand post-LOCA Conditions.Caused by Inadequate Design Control.Reviewing Options to Support Hrrms Operability in Modes 1-4 ML17326A0771999-08-0404 August 1999 LER 98-029-01:on 980422,noted That Fuel Handling Area Ventilation Sys Was Inoperable.Caused by Original Design Deficiency.Radiological Analysis for Spent Fuel Handling Accidents in Auxiliary Bldg Will Be Redone by 990830 ML17335A5461999-08-0202 August 1999 Rev 0 to Evaluation of Cook Recirculation Sump Level for Reduced Pump Flow Rates. ML17326A0871999-07-31031 July 1999 Monthly Operating Rept for July 1999 for DC Cook Nuclear Plant,Unit 1.With 990812 Ltr ML17326A0861999-07-31031 July 1999 Monthly Operating Rept for July 1999 for DC Cook Nuclear Plant,Units 2.With 990812 Ltr ML17326A0741999-07-29029 July 1999 LER 99-018-00:on 990629,determined That Valve Yokes May Yield Under Combined Stress of Seismic Event & Static,Valve Closed,Stem Thrust.Caused by Inadequate Design of Associated Movs.Operability Determinations Were Performed for Valves ML17326A0661999-07-26026 July 1999 LER 99-017-00:on 990625,noted That Improperly Installed Fuel Oil Return Relief Valve Rendered EDG Inoperable.Caused by Personnel Error.Fuel Oil Return Valve Was Replaced with Valve in Correct Orientation.With 990722 Ltr ML17326A0651999-07-22022 July 1999 LER 98-014-03:on 980310,noted That Response to high-high Containment Pressure Procedure Was Not Consistent with Analysis of Record.Caused by Inadequate Interface with W. FRZ-1 Will Be Revised to Be Consistent with New Analysis ML17326A0491999-07-13013 July 1999 LER 99-016-00:on 990615,TS Requirements for Source Range Neutron Flux Monitors Not Met.Caused by Failure to Understand Design Basis of Plant.Procedures Revised.With 990713 Ltr ML17326A0331999-07-0101 July 1999 LER 99-004-01:on 971030,failure to Perform TS Surveillance Analyses of Reactor Coolant Chemistry with Fuel Removed Was Noted.Caused by Ineffective Mgt of Tss.Chemistry Personnel Have Been Instructed on Requirement to Follow TS as Written ML17326A0511999-06-30030 June 1999 Monthly Operating Rept for June 1999 for DC Cook Nuclear Plant,Unit 2.With 990709 Ltr ML17326A0501999-06-30030 June 1999 Monthly Operating Rept for June 1999 for DC Cook Nuclear Plant,Unit 1.With 990709 Ltr ML17326A0151999-06-18018 June 1999 LER 99-014-00:on 990521,determined That Boron Injection Tank Manway Bolts Were Not Included in ISI Program,Creating Missed Exam for Previous ISI Interval.Caused by Programmatic Weakness.Isi Program & Associated ISI Database Modified ML17325B6421999-06-0101 June 1999 LER 99-013-00:on 990327,safety Injection & Centrifugal Charging Throttle Valve Cavitation During LOCA Could Have Led to ECCS Pump Failure.Caused by Inadequate Original Design Application of Si.Throttle Valves Will Be Developed ML17325B6311999-06-0101 June 1999 LER 99-S03-00:on 990430,vital Area Barrier Degradation Was Noted.Caused by Inadequate Insp & Maint of Vital Area Barrier.Repairs & Mods Were Made to Barriers to Eliminate Degraded & Nonconforming Conditions ML17326A0061999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Dcp.With 990609 Ltr ML17326A0071999-05-31031 May 1999 Monthly Operating Rept for May 1999 for DC Cook Nuclear Plant,Unit 2.With 990609 Ltr ML17325B6351999-05-28028 May 1999 LER 99-S02-00:on 990428,vulnerability in Safeguard Sys That Could Allow Unauthorized Access to Protected Area Was Noted. Caused by Inadequate Original Plant Design.Mods Were Made to Wall Opening to Eliminate Nonconforming Conditions ML17265A8231999-05-24024 May 1999 LER 98-037-01:on 990422,determined That Ice Condenser Bypass Leakage Exceeds Design Basis Limit.Caused by Pressure Seal Required by Revised W Design Not Incorporated Into Aep Design.Numerous Matl Condition Walkdowns & Assessments Made ML17325B6001999-05-20020 May 1999 LER 99-012-00:on 990420,concluded That Auxiliary Bldg ESF Ventilation Sys Not Capable of Maintaining ESF Room Temps post-accident.Caused by Inadequate Control of Sys Design Inputs.Comprehensive Action Plan Being Developed ML17325B5861999-05-10010 May 1999 LER 99-002-00:on 990415,discovered That TS 4.0.5 Requirements Were Not Met Due to Improperly Performed Test. Caused by Incorrect Interpretation of ASME Code.App J Testing Will Be Completed & Procedures Will Be Revised ML17325B5811999-05-0404 May 1999 LER 99-011-00:on 990407,air Sys for EDG Will Not Support Long Operability.Caused by Original Design Error.Temporary Mod to Supply Makeup Air Capability in Modes 5 & 6 Was Prepared ML17325B5771999-05-0303 May 1999 LER 99-010-00:on 990401,RCS Leak Detection Sys Sensitivity Not in Accordance with Design Requirements Occurred.Caused by Inadequate Original Design of Containment Sump Level. Evaluation Will Be Performed to Clearly Define Design ML17335A5301999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for DC Cook Nuclear Plant,Unit 1.With 990508 Ltr ML17335A5291999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for DC Cook Nuclear Plant,Unit 2.With 990508 Ltr ML17325B5581999-04-16016 April 1999 LER 99-006-00:on 990115,personnel Identified Discrepancy Between TS 3.9.7 Impact Energy Limit & Procedure 12 Ohp 4030.STP.046.Caused by Lack of Design Basis Control.Placed Procedure 12 Ohp 4030.STP.046 on Administrative Hold ML17325B5471999-04-12012 April 1999 LER 99-009-00:on 990304,as-found RHR Safety Relief Valve Lift Setpoint Greater than TS Limit Occurred.Cause Investigation for Condition Has Not Been Completed.Update to LER Will Be Submitted,Upon Completion of Investigation ML17325B5321999-04-0707 April 1999 LER 99-S01-00:on 990308,discovered That Lock for Vital Gate Leading to Plant 4KV Switchgear Area Was Nonconforming & Vulnerable to Unauthorized Access.Caused by Inadequate Gate Design & Inadequate Procedures.Mods Are Being Made to Gate ML17325B5161999-04-0101 April 1999 LER 99-007-00:on 981020,calculations Showed That Divider Barrier Between Upper & Lower Containment Vols Were Overstressed.Engineers Are Currently Working on Analyses of Loads & Stress on Enclosures ML17325B5491999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for DC Cook Nuclear Plant Unit 2.With 990408 Ltr ML17325B5441999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for DC Cook Nuclear Plant,Unit 1.With 990408 Ltr ML17325B5221999-03-29029 March 1999 LER 99-001-00:on 960610,degraded Component Cooling Water Flow to Containment Main Steam Line Penetrations,Identified on 990226.Caused by Inadequate Understanding of Design Basis.Additional Investigations Ongoing ML17325B4801999-03-18018 March 1999 LER 99-004-00:on 971030,failure to Perform TS Surveillance Analyses of Rc Chemistry with Fuel Removed Was Noted.Cause of Event Is Under Investigation.Corrected Written Job Order Activities Used to Control SD Chemistry Sampling ML17325B4741999-03-18018 March 1999 LER 99-005-00:on 940512,determined That Rt Breaker Manual Actuations During Rod Drop Testing Were Not Previously Reported.Caused by Lack of Training.Addl Corrective Actions,Including Preventative Actions May Be Developed ML17325B5671999-03-0202 March 1999 Summary of Unit 1 Steam Generator Layup Chemistry from 980101 to 990218. ML17325B4631999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for DC Cook Nuclear Power Station,Unit 2.With 990308 Ltr ML17325B4621999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for DC Cook Nuclear Plant,Unit 1.With 990308 Ltr ML17325B4571999-02-24024 February 1999 LER 99-003-00:on 990107,CR Pressurization Sys Surveillance Test Did Not Test Sys in Normal Operating Condition.Caused by Failure to Recognize Door 12DR-AUX415 as Part of CR Pressure Boundary.Performed Walkdown of Other Doors 1999-09-30
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CATEGORY REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)ACCESSION NBR:9907200116, DOC.DATE: 99/07/13 NOTARIZED:
NO DOCKET I FACIL:50-315 Donald C.Cook Nuclear Power Plant, Unit 1, Indiana M 05000315 AUTH, NAME AUTHOR AFFILIATION SNODGRASS,D.D.
Indiana Michigan Power.Co.(formerly Indiana&Michigan Ele BAKKEN,A.C.
'ndiana Michigan Power Co.(formerly Indiana&Michigan Ele RECIP.NAME RECIPIENT AFFILIATION
SUBJECT:
LER 99-016-00:on "990615,TS requirements for source range neutron flux monitors not met.Caused by failure to understand design basis of plant.Procedures revised.With 990713 ltr.DISTRIBUTION CODE: IE22T COPIES RECEIVED: LTR 7 ENCL i SIZE: TITLE: 50.73/50.9 Licensee Event Report (LER), Incident Rpt, etc.NOTES: RECIPIENT ID CODE/NAME LPD3-1 PD INTERNA: FILE CE E REXB RES/DET/ERAB RGN3 FILE 01 COPIES LTTR ENCL 1 1 1.1 1 1 1 1 1, 1 RECIPIENT ID CODE/NAME STANG, J NRR/CPM/IOLB NRR/DSSA/SPLB RES/DRAA/OERAB COPIES LTTR ENCL 1 1 1 1 1 1 1, 1 EXTERNAL: L ST LOBBY WARD NOAC POORE,W.NRC PDR 1 1 LMITCO MARSHALL 1 1 NOAC QUEENER,DS 1 1 NUDOCS FULL TXT 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 LIS OR REDUCE THE NUMBER OF COPIES RECEIVED BY YOU OR YOUR ORGANIZATION, CONTACT THE DOCUMENT CONTR DESK (DCD)ON EXTENSION 415-2083 FULL TEXT CONVERSION REQUIRED TOTAL NUMBER OF COPIES REQUIRED: LTTR 15 ENCL 15
Indiana riichigan Power Company~Cook wtdear Plant One COOk rr1anr rridgnatb N 49106 616 465 590)IRON MA NICHIGAN POMfER July 13, 1999 United States Nuclear Regulatory Commission Document Control Desk" Washington, DC 20555 Operating License DPR-58 Docket No.50-315 Document Control Manager: In accordance with the criteria established by 10 CFR 50.73 entitled Licensee Event Re ort~estem the following report is being submitted:
.~LER 315/99-016-00,"Technical Specification Requirements for Source Range Neutron Flux Monitors Not Met".There are no commitments identified in this LER.Sincerely, A.Christopher Bakken, III Site Vice President/mbd Attachment J.E.Dyer, Region III R.P.Powers P.A.Barrett G.P.Arent R.Whale D.Hahn Records Center, INPO NRC Resident Inspector'gr907200ii6 9ir07i3 PDR ADQCK 0500031.5 S PDR Rh136r)U.S.NIICLEAR REGUL Y COMihllSSION LICENSEE EVENT REPORT (LER)(Sec reverse for required number of digits/characters for each block)APPROV OMB No.3160.0104 EXPIRES 06/30/2001 Estimated burden per response to comply with this mandatory information collecuon request: 50 hrs, Reported lessons learned are incorporated alto the Bcensing process and fed back to industry.Foward comments regarding burden estimate to the Records Management Branch (T.B F33), U.S.No@ear Regulatory Convnission, Washington, DC 20555400t~and to the Paperwork Reduction Project (3ISOOI04), Ogffxxi Of Management and Budget.Washington.
DC 20503.If an Information collection does not display a currently vatid OMB control numberthe NRC may not conduct or sponsor, and a person is not required to respond to, the information collect'on.
FACH.ITY NARIE (I)Cook Nuclear Plant Unit 1 DOCKET NUhtBER (2)05000-315 PAGE (3)1 OF 3 TITLE ta)Technical Specification Requirements for Source Range Neutron Flux Monitors Not Met EVENT DATE (5)LER NUMBER (6)REPORT DATE (7)OTIIER FACILITIES INVOLVED (8)MONTH DAY YEAR YEAR 1999 SEQUENTIAL REVISION NUMBER NUMBER MONTH DAY YEAR FACILITY NAME FACILITY NAME Cook Nuclear Plant Unit 2 DOCKET NUMBER DOCKET NUMBER 05000-316 OPERATING hlODE (9)LEVEL(10)20.2203(a)(l) 20,2203(a)(2)(ii) a v 20.2203(a)(3)(i) a II 20.2203(a)(4) a 50.73(a)(2)(ii) a I I I 50.73(a)(2)(iv)
THIS REPORT IS SUBh1ITTED PURSUANT TOTIIE REQ UI REM ENTS OF 10 CFR g: (Check onc or niore)(11)a VI II 50.73(a)(2)(x)
OTHER a ui a Iv LICENSEE CONTACT FOR TII IS LER a vn ci y n1 street ow or ill 1P F RC Form 366A NAhlE Mr.Dennis D.Snodgrass, Compliance Engineer TELEPHONE Nuhf BER (Include Area Code)(616)465-5901 X1627 COhlPLETE ONE LINE FOR EACII COMPONENT FAILURE.DE SCRIBED IN TIIIS REPORT (13)CAUSE SYSTEht COMPONENT MANUFACTURER REPORTABLE TO EPIX CAUSE SYSTEht COMPONENT MANUFACTURER REPORTABLE TO EPIX SUPPLEh1ENTAL REPORT EXPECTED (14)X YES (If yes, complete EXPECTED SUBMISSION DATE).NO EXPECI'ED MONTH 09 DAY 15'EAR 1999 ABSTRACT (Limit to 1400 spaces, i.c., approximately l5 single-spaced typewritten lines)(16)On June 15, 1999 at 1700 hours0.0197 days <br />0.472 hours <br />0.00281 weeks <br />6.4685e-4 months <br /> EST with both units in Mode 5, the Source Range Nuclear Instrumentation channels on both Units were determined to be inoperable.
The Expanded System Readiness Review identified that the Technical Specification (T/S)3.3.1.1 and T/S 3.9.2 surveillance tests did not verify the Source Range"High Flux at Shutdown" alarm operable.This alarm function is required to be operable during modes 3, 4, 5 and 6.On June 15, 1999 at 2013 hours0.0233 days <br />0.559 hours <br />0.00333 weeks <br />7.659465e-4 months <br /> EST an ENS report was made in accordance with 10 CFR 50.72(b)(2)(iii)(D) for an event that could have prevented the fulfillment of the safety function of a system needed to mitigate the consequences of an accident.This LER is therefore submitted in accordance with 10 CFR 50.73(a)(2)(v)(D), and is also reportable per the requirements of 10 CFR 50.73(a)(2)(i)(B), as a condition prohibited by the plant's T/S.The apparent cause of this event is failure to understand the design basis of the plant.Upon declaring the Source Range Nuclear Instrumentation channels inoperable, Operations entered the action statements for T/S 3.3.1.1.Additional compensatory measures implemented by Operations included hourly checks of Source Range instrumentation response and the"High Flux at Shutdown" alarm clear.The surveillance procedures were revised and the"High Flux at Shutdown" alarm was.verified operable June 17, 1999 on ehch Unit.The Source Range"High Flux at Shutdown" alarm and the containment evacuation horns share common circuitry.
When the containment evacuation horns are verified operable by surveillance test, the"High Flux at Shutdown" alarm is received but not documented.
Although not verified in the past by surveillance test, it is our belief the alarm has been functional.
Therefore, there were minimal implications to the health and safety of the public as a result of this event.
i<ill 3GGA U.S.NUCLEAR I LATORY CoillMISSIOiN LICENSEE EVENT REPORT (LER)TEXT CONTINUATION FACILITY iNA ME (I)DOCKET (2)Null DER (2)LER N(ijlllI ER (G)PACE (3)Cook Nuclear Plant Unit 1 05000-315 YEAR SEQUENTIAL NUMBER REVISION NUMBER 2 OF 3 1999 016 00 TEXT (If more space is required, use additional copies of PRC Fornr 3GGrI)(17)Conditions Prior To Event Unit 1 Mode 5 in Cold Shutdown Unit 2 Mode 5 in Cold Shutdown Descri tion Of The Event On June 15, 1999 at 1700 hours0.0197 days <br />0.472 hours <br />0.00281 weeks <br />6.4685e-4 months <br /> EST with both units in Mode 5, the Source Range Nuclear Instrumentation (EIIS: IG)channels for both Units were determined to be inoperable.
The Expanded System Readiness Review identified that the Technical Specification (T/S)3.3.1.1 and T/S 3.9.2 surveillance tests did not verify the Source Range"High Flux at Shutdown" alarm (EIIS: IG/RA)operable.This alarm is credited in the licensing basis for detection and mitigation of a boron dilution event and is required to be operable during modes 3, 4, 5 and 6.During the event investigation, the Source Range"Loss of Detector Voltage" alarm was also identified as not being verified operable by T/S surveillance test.This alarm is not explicitly credited in T/S or the Updated Final Safety Analysis Reportbut is relied upon to determine T/S equipment failure.Cause Of The Event The apparent cause of this event is failure to understand the design basis of the plant.Misapplication of the IEEE 279, 1968 definition of"channel resulted in the channel"High Flux at Shutdown" alarm being determined as not requiring operability verification.
The IEEE 279, 1968 definition.
of"channel" states that a channel loses its identity when single action signals are combined.The alarm did not meet the IEEE 279, 1968 definition of"channel" for channel functional verification since both Source Range channels share the alarm.It was apparently overlooked that the alarm is credited in the licensing basis for detection and mitigation of a boron dilution.Consequently, operability verification has not been documented for the alarm on either Unit.Anal sis Of The Event On June 15, 1999 at 2013 hours0.0233 days <br />0.559 hours <br />0.00333 weeks <br />7.659465e-4 months <br /> EST an ENS report was made per 10 CFR 50.72(b)(2)(iii)(D), an event that alone could have prevented the fulfillment of the safety function of a system that is needed to mitigate the consequences of an accident.The Source Range channels on Units 1 and 2 were determined to be inoperable when it was identified that the Source Range"High Flux at Shutdown" alarm was not verified by T/S 3.3.1.1 and T/S 3.9.2 surveillance tests.This LER is therefore submitted in accordance with 10 CFR 50.73(a)(2)(v)(D), and is also reportable per the requirements of 10 CFR 50.73(a)(2)(i)(B), as a condition prohibited by the plant's T/S.The primary function of nuclear instrumentation is to,safeguard the reactor by monitoring the neutron flux and generating appropriate trips and alarms for various phases of reactor operating and shutdown conditions.
The Source Range nuclear instrumentation provides control room indication, alarms and recording of signals proportional to reactor neutron flux during core loading, shutdown, startup as well as during subsequent refueling.
T/S 3.3.1.1 requires one channel of the source range neutron flux monitors to be operable in Modes 3, 4 8 5.T/S 3.9.2 requires two source range neutron flux monitors operable in Mode 6.1 T/S definitions requires the verification of"alarm and/or trip functions" to satisfy surveillance requirements.
The source range"High Flux at Shutdown" alarm operability verification has not been documented for either Unit.The containment evacuation horns operability is verified by surveillance test.The containment evacuation horns and the Source Range"High Flux at Shutdown" alarm share common circuitry.
The"High Flux at Shutdown" alarm is received but not documented when the containment evacuation horns response to high flux signals is verified by the surveillance test.Although not verified in the past by surveillance test, it is our belief the alarm has been functional.
Therefore, there were minimal safety implications as a result of this event.NRC FORM 366A (G-I998)
FOIDI 3GGA U.S.NUCLEAR.R'GULATORY COAIMISSION
'v-1998)LICENSEE EVENT REPORT (LER)TEXT CONTINUATION FACILITY NAME (I)Cook Nuclear Plant Unit 1 DOCKET (2)NUMBER 2)05000-315 YEAR LER NUMBER (G)SEQUENTIAL REVISION NUMBER NUMBER PAGE (3)3 OF 3 1999 016 00 TEXT (lf more space is required, use addilional copies of/VRC Form 366')(I7)CORRECTIVE ACTIONS The Source Range channels were declared inoperable when it was identified that the Source Range"High Flux at Shutdown" alarm was'not verified by T/S surveillance tests.Upon declaring the Source Range Nuclear Instrumentation channels inoperable, Operations entered the action statements for T/S 3.3.1.1.Additional compensatory measures implemented by Operations included hourly checks of Source Range instrumentation response and the"High Flux at Shutdown" alarm clear until the Source Range channels were declared operable on June 17, 1999.The surveillance procedures were revised to include a documented operability verification of the Source Range"High Flux at Shutdown" alarm and the"Loss of Detector Voltage" alarm.The surveillance tests were performed to verify operability of the Units 1and 2"High Flux at Shutdown" and the"Loss of Detector Voltage" alarms.The Unit 1 Source Range channels were both declared operable by 2347 hours0.0272 days <br />0.652 hours <br />0.00388 weeks <br />8.930335e-4 months <br /> EST June 17, 1999.The Unjt 2 Source Range channels were both declared operable by 2225 hours0.0258 days <br />0.618 hours <br />0.00368 weeks <br />8.466125e-4 months <br /> EST June 17, 1999.AEP:NRC:1260GH,"Enforcement Actions98-150, 98-151,98-152 and 98-186 Reply to Notice Of Violation October 13, 1998", dated March 19, 1999, responded to identified programmatic weaknesses in the Technical Specification Surveillance Program and the plant Design and Licensing Basis.As part of the Restart effort, the adequacy of the T/S, surveillance program will be evaluated, This evaluation includes verification that T/S surveillance requirements for all modes of plant operation are incorporated into T/S surveillance test procedures.
Also as part of the Restart effort, System and programmatic assessments in the Expanded System Readiness Reviews and Licensing Basis Reviews are reestablishing and documenting the plant's Design and Licensing Basis.The root cause investigation for this event is ongoing.The investigation will include a review of the Operations procedures associated with the"High Flux at Shutdown" alarm, and, the UFSAR sections which address the alarm and the boron dilution event, to determine if any revisions are required.Supplemental information, including any additional corrective actions, will be provided in an update to this LER.SIMILAR EVENTS 315/99-015-00 NRC F Rh1.66A (6.1998)