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| {{#Wiki_filter:PR.IC3R.IEY'..CELERATED RIDSPROCESSING) | | {{#Wiki_filter:PR.IC3 R.I EY'..CELERATED RIDS PROCESSING) |
| REGULATORY INFORMATION DISTRIBUTION SYSTEM(RIDS}ACCESSION NBR:9410260086 DOC.DATE: | | REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS}ACCESSION NBR:9410260086 DOC.DATE: 94/09/30 NOTARIZED: |
| 94/09/30NOTARIZED: | | NO DOCKET FACIL:50-315 Donald C.Cook Nuclear Power Plant, Unit 1, Indiana M 05000315 AUTH.NAME AUTHOR AFFILIATION JANISSE,J.D. |
| NODOCKETFACIL:50-315 DonaldC.CookNuclearPowerPlant,Unit1,IndianaM05000315AUTH.NAMEAUTHORAFFILIATION JANISSE,J.D.
| | Indiana Michigan Power Co.(formerly Indiana&Michigan Ele BUBLICK,,D.L. |
| IndianaMichiganPowerCo.(formerly Indiana&MichiganEleBUBLICK,,D.L.
| | Indiana Michigan Power Co.(formerly Indiana&Michigan Ele BLIND,A.A. |
| IndianaMichiganPowerCo.(formerly Indiana&MichiganEleBLIND,A.A.
| | Indiana Michigan Power Co.(formerly Indiana&Michigan Ele RECIP.NAME RECIPIENT AFFILIATION R |
| IndianaMichiganPowerCo.(formerly Indiana&MichiganEleRECIP.NAME RECIPIENT AFFILIATION R
| |
|
| |
|
| ==SUBJECT:== | | ==SUBJECT:== |
| Monthlyoperating reptforSept1994forDCCookNuclearPlant,Unit1.W/941017 ltr.DISTRIBUTION CODE:IE24DCOPIESRECEIVED:LTR ENCLSIZE:TITLE:MonthlyOperating Report(perTechSpecs)NOTESRECIPIENT IDCODE/NAME PD3-1PDINTERNAL:
| | Monthly operating rept for Sept 1994 for DC Cook Nuclear Plant, Unit 1.W/941017 ltr.DISTRIBUTION CODE: IE24D COPIES RECEIVED:LTR ENCL SIZE: TITLE: Monthly Operating Report (per Tech Specs)NOTES RECIPIENT ID CODE/NAME PD3-1 PD INTERNAL: AEOD/SPD/RRAB NRR/DORS/OEAB RGN3 EXTERNAL: EG&G BRYCE,J.H NRC PDR COPIES LTTR ENCL 1 1 1 1 1 1 1 1 1 1 1 1 RECIPIENT ID CODE/NAME HICKMAN,J FILE CENTER 01=/rRCB-NOAC COPIES LTTR ENCL 1 1 1 1 1 1 1 1 D 0 C N NOTE TO ALL"RIDS" RECIPIENTS: |
| AEOD/SPD/RRAB NRR/DORS/OEAB RGN3EXTERNAL: | | PLEASE HELP US TO REDUCE iVKSTE!CONTACT THE DOCL'if ENT CONTROL DESK, ROOhf PI-37 (EXT.504-083)TO ELI hf!NATE YOUR NAif L PRO%i DISTRIBUTION LISTS I'OR DOC!.0 IEN'I'S YOI: DON" I'L'ED!TOTAL NUMBER OF COPIES REQUIRED: LTTR 10 ENCL 10 Indiana Michigan Power Company Cook Nuclear Plant One Cook Place Bridgrnan, Ml 49106 616 465 5901 October 17, 1994 U.S.Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C.20555 Gentlemen: |
| EG&GBRYCE,J.H NRCPDRCOPIESLTTRENCL111111111111RECIPIENT IDCODE/NAME HICKMAN,J FILECENTER01=/rRCB-NOACCOPIESLTTRENCL11111111D0CNNOTETOALL"RIDS"RECIPIENTS: | | Pursuant to the requirements of Donald C.Cook Nuclear Plant Unit 1 Technical Specification 6.9.1.10, the attached Monthly Operating Report for the month of September 1994 is submitted. |
| PLEASEHELPUSTOREDUCEiVKSTE!CONTACTTHEDOCL'ifENTCONTROLDESK,ROOhfPI-37(EXT.504-083)TOELIhf!NATEYOURNAifLPRO%iDISTRIBUTION LISTSI'ORDOC!.0IEN'I'SYOI:DON"I'L'ED!TOTALNUMBEROFCOPIESREQUIRED:
| | Respectfully, A.A.Blind Plant Manager Attachment co NRC Region III D.R.Hahn R.C.Callen S.Hamming Z.G.Keppler INPO Records Center ANI Nuclear Engineering Department E.E.Fitzpatrick W.G.Smith, Jr.S.J.Brewer D.W.Paul S.H.Steinhart J.L.Leichner J.A.Isom D.G.Turner E.A.Smarrella J.C.Krieger D.F.Krause M.E.Russo 9410260086 940930 PDR ADOCK 05000315 R'DR N.R.C.OPERATING DATA REPORT DOCKET NO.50-315 DATE.04/Oct/94 COMPLETED BYJ D Janisse TELEPHONE 616-465-5901 OPERATING STATUS 1.Unit Name D.C.Cook Unit 1 2.Reporting Period September notes 3.Licensed Thermal Power (MWt)3250 4.Name Plate Rating (Gross MWe)1152 5.Design Electrical Rating (Net MWe)1020 6.Maximum Dependable Capacity (GROSS MWe)1056 7.Maximum Dependable Capacity (Net MWe)1000 8.If Changes Occur in Capacity Ratings (Items no.3 through 7)Since Last Report Give Reasons 9.'0.ower evei o ic estricte.Reasons For Restrictions. |
| LTTR10ENCL10 IndianaMichiganPowerCompanyCookNuclearPlantOneCookPlaceBridgrnan, Ml491066164655901October17,1994U.S.NuclearRegulatory Commission ATTN:DocumentControlDeskWashington, D.C.20555Gentlemen:
| | If Any: ny e e 11.Hours in Reporting Period 12.No.of Hrs.Reactor Was Critical 13.Reactor Reserve Shutdown Hours 14.Hours Generator on Line 15.Unit Reserve Shutdown Hours 16.Gross Therm.Energy Gen.(MWH)17.Gross Elect.Energy Gen.(MWH)18.Net Elect.Energy Gen.(MWH)19.Unit Service Factor 20.Unit Availability Factor 21.Unit Capacity Factor (MDC Net)22.Unit Capacity Factor (DER Net)23.Unit Forced Outage Rate 24.Shutdowns Scheduled over Next Six None is o.r.to ate 720.0 6552.0 720.0 4048.5 0.0 0.0 715.9 4007.0 0.0 0.0 2116670 11431649 678490 3643810 652628 3501826 99.4 61.2 99.4 61.2 90.6 53.4 88.9 52.4 0.0 0.0 Months (Type.Date.and umm.173112.0 129702.9 463.0 127615.6 321.0 374957424 121666470 117023624 74.6 74.6 67.3 65.6 5.9 Duration): |
| Pursuanttotherequirements ofDonaldC.CookNuclearPlantUnit1Technical Specification 6.9.1.10, theattachedMonthlyOperating ReportforthemonthofSeptember 1994issubmitted.
| | 25.ut own n o eport erio.stimate ate o artup: 26.nits in est atus rior to ommercia INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION I peration: Forecast Achieved 0~I AVERAGE DAILY POWER LEVEL (MWe-Net)DOCKET NO.50-315 UNIT ONE DATE 10/Oct/94 COMPLETED BY J D Janisse TELEPHONE 616-465-5901 MONTH.September DAY 94/09/01 94/09/02 94/09/03 94/09/04 94/09/05 94/09/06 94/09/07 94/09/08 94/09/09 94/09/10 94/09/11 94/09/12 94/09/13 94/09/14 94/09/15 94/09/16 AVERAGE DAILY POWER LEVEL 1021 1020 1014 1017 744 949 1015 1014 1000 598 450 431 175 614 997 1009 DAY 94/09/17 94/09/18 94/09/19 94/09/20 94/09/21 94/09/22 94/09/23 94/09/24 94/09/25 94/09/26 94/09/27 94/09/28 94/09/29 94/09/30 AVERAGE DAILY POWER LEVEL 1009 1013 10051006 1012 1010 971 1024 1018 1017 1015 1014 1005 1006 DOCKET N UNIT NAME: COMPLETED BY: TELEPHONE: |
| Respectfully, A.A.BlindPlantManagerAttachment coNRCRegionIIID.R.HahnR.C.CallenS.HammingZ.G.KepplerINPORecordsCenterANINuclearEngineering Department E.E.Fitzpatrick W.G.Smith,Jr.S.J.BrewerD.W.PaulS.H.Steinhart J.L.LeichnerJ.A.IsomD.G.TurnerE.A.Smarrella J.C.KriegerD.F.KrauseM.E.Russo9410260086 940930PDRADOCK05000315R'DR N.R.C.OPERATING DATAREPORTDOCKETNO.50-315DATE.04/Oct/94 COMPLETED BYJDJanisseTELEPHONE 616-465-5901 OPERATING STATUS1.UnitNameD.C.CookUnit12.Reporting PeriodSeptember notes3.LicensedThermalPower(MWt)32504.NamePlateRating(GrossMWe)11525.DesignElectrical Rating(NetMWe)10206.MaximumDependable Capacity(GROSSMWe)10567.MaximumDependable Capacity(NetMWe)10008.IfChangesOccurinCapacityRatings(Itemsno.3through7)SinceLastReportGiveReasons9.'0.owereveioicestricte.ReasonsForRestrictions. | | DATE: PAGE 50-315 D.C.Cook Unit 1 D.L.Bublick (616)465-5901 October 7,1994 Page.1 of 2 MONTHLY OPERATING ACTIVITIES |
| IfAny:nyee11.HoursinReporting Period12.No.ofHrs.ReactorWasCritical13.ReactorReserveShutdownHours14.HoursGenerator onLine15.UnitReserveShutdownHours16.GrossTherm.EnergyGen.(MWH)17.GrossElect.EnergyGen.(MWH)18.NetElect.EnergyGen.(MWH)19.UnitServiceFactor20.UnitAvailability Factor21.UnitCapacityFactor(MDCNet)22.UnitCapacityFactor(DERNet)23.UnitForcedOutageRate24.Shutdowns Scheduled overNextSixNoneiso.r.toate720.06552.0720.04048.50.00.0715.94007.00.00.02116670114316496784903643810652628350182699.461.299.461.290.653.488.952.40.00.0Months(Type.Date.andumm.173112.0129702.9463.0127615.6321.0374957424 121666470 117023624 74.674.667.365.65.9Duration):
| | -SEPTEMBER 1994 HIGHLIGHTS The unit entered this reporting period in Mode 1 at 1004 RTP.The unit exited this reporting period in Mode 1 at 100>RTP.There were no challenges to the pressurizer safety valves or power operated relief valves.Gross Electrical generation for'the month of September was 678490 MWH.DETAILS 9-5-94 0845 Commenced Reactor power reduction due to problems with 1-WMO-13 (f13 Circ.Water Pump Discharge). |
| 25.utownnoeporterio.stimateateoartup:26.nitsinestatusriortoommerciaINITIALCRITICALITY INITIALELECTRICITY COMMERCIAL OPERATION Iperation:ForecastAchieved 0~I AVERAGEDAILYPOWERLEVEL(MWe-Net) | | Valve actuator appeared to be working itself loose.9-6-94 9-9-94 9-10-94 9-11-94 9-12-94 1000 1350 1400 1942 1450 1730 0825 2031 Reactor power at 494 RTP.Commenced reactor power increase to 1004 RTP.Reactor power stabilized at 1004 RTP.Commenced Reactor power reduction for Biocide application in the Circ.Water System.Started Circ.Water System Biocide application. |
| DOCKETNO.50-315UNITONEDATE10/Oct/94 COMPLETED BYJDJanisseTELEPHONE 616-465-5901 MONTH.September DAY94/09/0194/09/0294/09/0394/09/0494/09/0594/09/0694/09/0794/09/0894/09/0994/09/1094/09/1194/09/1294/09/1394/09/1494/09/1594/09/16AVERAGEDAILYPOWERLEVEL10211020101410177449491015101410005984504311756149971009DAY94/09/1794/09/1894/09/1994/09/2094/09/2194/09/2294/09/2394/09/2494/09/2594/09/2694/09/2794/09/2894/09/2994/09/30AVERAGEDAILYPOWERLEVEL1009101310051006101210109711024101810171015101410051006 DOCKETNUNITNAME:COMPLETED BY:TELEPHONE:
| | Reactor power stabilized at 50%RTP.Circ.Water System Biocide application complete.Commenced Reactor power reduction to allow oil addition to gl3 RCP, repair of West MFP Suction Strainer and repairs to the Main Turbine Trip Solenoid.9-13-94 0335 0742 0938 1435 Reactor power stabilized at 30>RTP.Commenced Reactor power reduction. |
| DATE:PAGE50-315D.C.CookUnit1D.L.Bublick(616)465-5901October7,1994Page.1of2MONTHLYOPERATING ACTIVITIES | | Reactor power stabilized at 15~RTP.Commenced Reactor power increase. |
| -SEPTEMBER 1994HIGHLIGHTS Theunitenteredthisreporting periodinMode1at1004RTP.Theunitexitedthisreporting periodinMode1at100>RTP.Therewerenochallenges tothepressurizer safetyvalvesorpoweroperatedreliefvalves.GrossElectrical generation for'themonthofSeptember was678490MWH.DETAILS9-5-940845Commenced Reactorpowerreduction duetoproblemswith1-WMO-13(f13Circ.WaterPumpDischarge). | | DOCKET N UNIT NAME: COMPLETED BY: TELEPHONE: |
| Valveactuatorappearedtobeworkingitselfloose.9-6-949-9-949-10-949-11-949-12-9410001350140019421450173008252031Reactorpowerat494RTP.Commenced reactorpowerincreaseto1004RTP.Reactorpowerstabilized at1004RTP.Commenced Reactorpowerreduction forBiocideapplication intheCirc.WaterSystem.StartedCirc.WaterSystemBiocideapplication.
| | DATE PAGE: 50-315 D.C.Cook Unit 1 D.L.Bublick (616)465-5901 October 7,1994 Page 2 of 2 MONTHLY OPERATING ACTIVITIES |
| Reactorpowerstabilized at50%RTP.Circ.WaterSystemBiocideapplication complete.
| | -SEPTEMBER 1994 1710 1945 0505 Reactor power stabilized at 304 RTP.Commenced Reactor power increase.Reactor power stabilized at 1004 RTP. |
| Commenced Reactorpowerreduction toallowoiladditiontogl3RCP,repairofWestMFPSuctionStrainerandrepairstotheMainTurbineTripSolenoid. | | UNIT SHUTDOWNS AND POWER REDUCTIONS Report Month: SEPTEMBER 1994 UNIT NAME DATE: COMPLETED BY: TELEPHONE: |
| 9-13-940335074209381435Reactorpowerstabilized at30>RTP.Commenced Reactorpowerreduction. | | PAGE: D.C.COOK UNIT, 1 Oct 7, 1994 D.L.Bublick (616)465-5901 Page 1 of 1 DURATION NO.DATE TYPE HOURS METHOD OF SHUTTING DOWN REASON~REACTOR~LICENSEE EVENT SYSTEM COMPONENT CAUSE AND CORRECTIVE ACTION REPORT NO CODE CODE~TO PREVENT RECURRENCE 311 940905 S 3.8 N/A N/A N/A After decreasing and stabilizing Reactor Power at 49%RTP on 940905, maintenance activities commenced on 1-WMO-13 (813 Circ.~Water Pump Discharge) valve actuator.The reactor was returned to 100%RTP on 940906 at 1400.312 940910 S 313 940913 S 17.6 N/A N/A N/A N/A N/A N/A N/A After increasing and stabilizing reactor power at 100%RTP on 940906, reactor power was reduced to 50%RTP on 940910 to support.Zebra Mussel cleanup in the Circ.Water System.The Reactor was returned to 100%RTP on 940915 at 0505.After decreasing and stabilizing Reactor Power at 15%RTP on 940913, oil addition commenced to f13 RCP.The reactor was returned to 100%RTP on 940915 a 0505.1 F: Forced S: Scheduled 2 Reason: A: Equipment Failure (Explain)B: Maintenance or Test C: Refueling D: Regulatory Restriction E: Operator Training and License Examination F: Administrative G: Operational Error (Explain)H: Other (Explain)3 Method: 1: Manual 2: Manual Scram 3: Automatic Scram 4: Other (Explain)4 Exhibit G-Instructions for preparation of data entry sheets for Licensee Event Report (LER)File (NUREG 1061)5 Exhibit I Same Source r i~r A}} |
| Reactorpowerstabilized at15~RTP.Commenced Reactorpowerincrease.
| |
| DOCKETNUNITNAME:COMPLETED BY:TELEPHONE:
| |
| DATEPAGE:50-315D.C.CookUnit1D.L.Bublick(616)465-5901October7,1994Page2of2MONTHLYOPERATING ACTIVITIES
| |
| -SEPTEMBER 1994171019450505Reactorpowerstabilized at304RTP.Commenced Reactorpowerincrease. | |
| Reactorpowerstabilized at1004RTP.
| |
| UNITSHUTDOWNS ANDPOWERREDUCTIONS ReportMonth:SEPTEMBER 1994UNITNAMEDATE:COMPLETED BY:TELEPHONE:
| |
| PAGE:D.C.COOKUNIT,1Oct7,1994D.L.Bublick(616)465-5901Page1of1DURATIONNO.DATETYPEHOURSMETHODOFSHUTTINGDOWNREASON~REACTOR~LICENSEEEVENTSYSTEMCOMPONENT CAUSEANDCORRECTIVE ACTIONREPORTNOCODECODE~TOPREVENTRECURRENCE 311940905S3.8N/AN/AN/AAfterdecreasing andstabilizing ReactorPowerat49%RTPon940905,maintenance activities commenced on1-WMO-13(813Circ.~WaterPumpDischarge) valveactuator. | |
| Thereactorwasreturnedto100%RTPon940906at1400.312940910S313940913S17.6N/AN/AN/AN/AN/AN/AN/AAfterincreasing andstabilizing reactorpowerat100%RTPon940906,reactorpowerwasreducedto50%RTPon940910tosupport.ZebraMusselcleanupintheCirc.WaterSystem.TheReactorwasreturnedto100%RTPon940915at0505.Afterdecreasing andstabilizing ReactorPowerat15%RTPon940913,oiladditioncommenced tof13RCP.Thereactorwasreturnedto100%RTPon940915a0505.1F:ForcedS:Scheduled 2Reason:A:Equipment Failure(Explain)
| |
| B:Maintenance orTestC:Refueling D:Regulatory Restriction E:OperatorTrainingandLicenseExamination F:Administrative G:Operational Error(Explain) | |
| H:Other(Explain) 3Method:1:Manual2:ManualScram3:Automatic Scram4:Other(Explain) 4ExhibitG-Instructions forpreparation ofdataentrysheetsforLicenseeEventReport(LER)File(NUREG1061)5ExhibitISameSource ri~rA}} | |
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[Table view] Category:TEXT-SAFETY REPORT
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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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PR.IC3 R.I EY'..CELERATED RIDS PROCESSING)
REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS}ACCESSION NBR:9410260086 DOC.DATE: 94/09/30 NOTARIZED:
NO DOCKET FACIL:50-315 Donald C.Cook Nuclear Power Plant, Unit 1, Indiana M 05000315 AUTH.NAME AUTHOR AFFILIATION JANISSE,J.D.
Indiana Michigan Power Co.(formerly Indiana&Michigan Ele BUBLICK,,D.L.
Indiana Michigan Power Co.(formerly Indiana&Michigan Ele BLIND,A.A.
Indiana Michigan Power Co.(formerly Indiana&Michigan Ele RECIP.NAME RECIPIENT AFFILIATION R
SUBJECT:
Monthly operating rept for Sept 1994 for DC Cook Nuclear Plant, Unit 1.W/941017 ltr.DISTRIBUTION CODE: IE24D COPIES RECEIVED:LTR ENCL SIZE: TITLE: Monthly Operating Report (per Tech Specs)NOTES RECIPIENT ID CODE/NAME PD3-1 PD INTERNAL: AEOD/SPD/RRAB NRR/DORS/OEAB RGN3 EXTERNAL: EG&G BRYCE,J.H NRC PDR COPIES LTTR ENCL 1 1 1 1 1 1 1 1 1 1 1 1 RECIPIENT ID CODE/NAME HICKMAN,J FILE CENTER 01=/rRCB-NOAC COPIES LTTR ENCL 1 1 1 1 1 1 1 1 D 0 C N NOTE TO ALL"RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE iVKSTE!CONTACT THE DOCL'if ENT CONTROL DESK, ROOhf PI-37 (EXT.504-083)TO ELI hf!NATE YOUR NAif L PRO%i DISTRIBUTION LISTS I'OR DOC!.0 IEN'I'S YOI: DON" I'L'ED!TOTAL NUMBER OF COPIES REQUIRED: LTTR 10 ENCL 10 Indiana Michigan Power Company Cook Nuclear Plant One Cook Place Bridgrnan, Ml 49106 616 465 5901 October 17, 1994 U.S.Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C.20555 Gentlemen:
Pursuant to the requirements of Donald C.Cook Nuclear Plant Unit 1 Technical Specification 6.9.1.10, the attached Monthly Operating Report for the month of September 1994 is submitted.
Respectfully, A.A.Blind Plant Manager Attachment co NRC Region III D.R.Hahn R.C.Callen S.Hamming Z.G.Keppler INPO Records Center ANI Nuclear Engineering Department E.E.Fitzpatrick W.G.Smith, Jr.S.J.Brewer D.W.Paul S.H.Steinhart J.L.Leichner J.A.Isom D.G.Turner E.A.Smarrella J.C.Krieger D.F.Krause M.E.Russo 9410260086 940930 PDR ADOCK 05000315 R'DR N.R.C.OPERATING DATA REPORT DOCKET NO.50-315 DATE.04/Oct/94 COMPLETED BYJ D Janisse TELEPHONE 616-465-5901 OPERATING STATUS 1.Unit Name D.C.Cook Unit 1 2.Reporting Period September notes 3.Licensed Thermal Power (MWt)3250 4.Name Plate Rating (Gross MWe)1152 5.Design Electrical Rating (Net MWe)1020 6.Maximum Dependable Capacity (GROSS MWe)1056 7.Maximum Dependable Capacity (Net MWe)1000 8.If Changes Occur in Capacity Ratings (Items no.3 through 7)Since Last Report Give Reasons 9.'0.ower evei o ic estricte.Reasons For Restrictions.
If Any: ny e e 11.Hours in Reporting Period 12.No.of Hrs.Reactor Was Critical 13.Reactor Reserve Shutdown Hours 14.Hours Generator on Line 15.Unit Reserve Shutdown Hours 16.Gross Therm.Energy Gen.(MWH)17.Gross Elect.Energy Gen.(MWH)18.Net Elect.Energy Gen.(MWH)19.Unit Service Factor 20.Unit Availability Factor 21.Unit Capacity Factor (MDC Net)22.Unit Capacity Factor (DER Net)23.Unit Forced Outage Rate 24.Shutdowns Scheduled over Next Six None is o.r.to ate 720.0 6552.0 720.0 4048.5 0.0 0.0 715.9 4007.0 0.0 0.0 2116670 11431649 678490 3643810 652628 3501826 99.4 61.2 99.4 61.2 90.6 53.4 88.9 52.4 0.0 0.0 Months (Type.Date.and umm.173112.0 129702.9 463.0 127615.6 321.0 374957424 121666470 117023624 74.6 74.6 67.3 65.6 5.9 Duration):
25.ut own n o eport erio.stimate ate o artup: 26.nits in est atus rior to ommercia INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION I peration: Forecast Achieved 0~I AVERAGE DAILY POWER LEVEL (MWe-Net)DOCKET NO.50-315 UNIT ONE DATE 10/Oct/94 COMPLETED BY J D Janisse TELEPHONE 616-465-5901 MONTH.September DAY 94/09/01 94/09/02 94/09/03 94/09/04 94/09/05 94/09/06 94/09/07 94/09/08 94/09/09 94/09/10 94/09/11 94/09/12 94/09/13 94/09/14 94/09/15 94/09/16 AVERAGE DAILY POWER LEVEL 1021 1020 1014 1017 744 949 1015 1014 1000 598 450 431 175 614 997 1009 DAY 94/09/17 94/09/18 94/09/19 94/09/20 94/09/21 94/09/22 94/09/23 94/09/24 94/09/25 94/09/26 94/09/27 94/09/28 94/09/29 94/09/30 AVERAGE DAILY POWER LEVEL 1009 1013 10051006 1012 1010 971 1024 1018 1017 1015 1014 1005 1006 DOCKET N UNIT NAME: COMPLETED BY: TELEPHONE:
DATE: PAGE 50-315 D.C.Cook Unit 1 D.L.Bublick (616)465-5901 October 7,1994 Page.1 of 2 MONTHLY OPERATING ACTIVITIES
-SEPTEMBER 1994 HIGHLIGHTS The unit entered this reporting period in Mode 1 at 1004 RTP.The unit exited this reporting period in Mode 1 at 100>RTP.There were no challenges to the pressurizer safety valves or power operated relief valves.Gross Electrical generation for'the month of September was 678490 MWH.DETAILS 9-5-94 0845 Commenced Reactor power reduction due to problems with 1-WMO-13 (f13 Circ.Water Pump Discharge).
Valve actuator appeared to be working itself loose.9-6-94 9-9-94 9-10-94 9-11-94 9-12-94 1000 1350 1400 1942 1450 1730 0825 2031 Reactor power at 494 RTP.Commenced reactor power increase to 1004 RTP.Reactor power stabilized at 1004 RTP.Commenced Reactor power reduction for Biocide application in the Circ.Water System.Started Circ.Water System Biocide application.
Reactor power stabilized at 50%RTP.Circ.Water System Biocide application complete.Commenced Reactor power reduction to allow oil addition to gl3 RCP, repair of West MFP Suction Strainer and repairs to the Main Turbine Trip Solenoid.9-13-94 0335 0742 0938 1435 Reactor power stabilized at 30>RTP.Commenced Reactor power reduction.
Reactor power stabilized at 15~RTP.Commenced Reactor power increase.
DOCKET N UNIT NAME: COMPLETED BY: TELEPHONE:
DATE PAGE: 50-315 D.C.Cook Unit 1 D.L.Bublick (616)465-5901 October 7,1994 Page 2 of 2 MONTHLY OPERATING ACTIVITIES
-SEPTEMBER 1994 1710 1945 0505 Reactor power stabilized at 304 RTP.Commenced Reactor power increase.Reactor power stabilized at 1004 RTP.
UNIT SHUTDOWNS AND POWER REDUCTIONS Report Month: SEPTEMBER 1994 UNIT NAME DATE: COMPLETED BY: TELEPHONE:
PAGE: D.C.COOK UNIT, 1 Oct 7, 1994 D.L.Bublick (616)465-5901 Page 1 of 1 DURATION NO.DATE TYPE HOURS METHOD OF SHUTTING DOWN REASON~REACTOR~LICENSEE EVENT SYSTEM COMPONENT CAUSE AND CORRECTIVE ACTION REPORT NO CODE CODE~TO PREVENT RECURRENCE 311 940905 S 3.8 N/A N/A N/A After decreasing and stabilizing Reactor Power at 49%RTP on 940905, maintenance activities commenced on 1-WMO-13 (813 Circ.~Water Pump Discharge) valve actuator.The reactor was returned to 100%RTP on 940906 at 1400.312 940910 S 313 940913 S 17.6 N/A N/A N/A N/A N/A N/A N/A After increasing and stabilizing reactor power at 100%RTP on 940906, reactor power was reduced to 50%RTP on 940910 to support.Zebra Mussel cleanup in the Circ.Water System.The Reactor was returned to 100%RTP on 940915 at 0505.After decreasing and stabilizing Reactor Power at 15%RTP on 940913, oil addition commenced to f13 RCP.The reactor was returned to 100%RTP on 940915 a 0505.1 F: Forced S: Scheduled 2 Reason: A: Equipment Failure (Explain)B: Maintenance or Test C: Refueling D: Regulatory Restriction E: Operator Training and License Examination F: Administrative G: Operational Error (Explain)H: Other (Explain)3 Method: 1: Manual 2: Manual Scram 3: Automatic Scram 4: Other (Explain)4 Exhibit G-Instructions for preparation of data entry sheets for Licensee Event Report (LER)File (NUREG 1061)5 Exhibit I Same Source r i~r A