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| {{#Wiki_filter:ACCELERATED RIDSPROCESSING) | | {{#Wiki_filter:ACCELERATED RIDS PROCESSING) |
| REGULATORY INFORMATION DISTRIBUTXON SYSTEM(RIDS)ACCESSION NBR:9408220059 DOC.DATE: | | REGULATORY INFORMATION DISTRIBUTXON SYSTEM (RIDS)ACCESSION NBR:9408220059 DOC.DATE: 94/07/31 NOTARIZED: |
| 94/07/31NOTARIZED: | | No DOCKET FACIL:50-315 Donald C.Cook Nuclear Power Plant, Unit 1, Indiana M 05000315 AUTH.NAME AUTHOR AFFXLIATION JANXSSE,J.D. |
| NoDOCKETFACIL:50-315 DonaldC.CookNuclearPowerPlant,Unit1,IndianaM05000315AUTH.NAMEAUTHORAFFXLIATION JANXSSE,J.D.
| | Indiana Michigan Power Co.(formerly Indiana 6 Michigan Ele P BLXND,A;A. |
| IndianaMichiganPowerCo.(formerly Indiana6MichiganElePBLXND,A;A.
| | Indiana Michigan Power Co.(formerly Indiana 6 Michigan Ele RECIP.NAME RECIPIENT AFFILIATION R |
| IndianaMichiganPowerCo.(formerly Indiana6MichiganEleRECIP.NAME RECIPIENT AFFILIATION R
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| ==SUBJECT:== | | ==SUBJECT:== |
| Monthlyoperating reptforJul1994forDCCookNuclearPlant.W/940808 ltr.DISTRIBUTION CODE:IE24DCOPIESRECEIVED:LTR ENCLSIZE:TITLE:MonthlyOperating Report(perTechSpec~sNOTES:0RECIPIENT IDCODE/NAME PD3-1PDINTERNAL:
| | Monthly operating rept for Jul 1994 for DC Cook Nuclear Plant.W/940808 ltr.DISTRIBUTION CODE: IE24D COPIES RECEIVED:LTR ENCL SIZE: TITLE: Monthly Operating Report (per Tech Spec~s NOTES: 0 RECIPIENT ID CODE/NAME PD3-1 PD INTERNAL: AEOD/DS P/TPAB NRR/DRI L/RPEB RGN3 EXTERNAL EGGG BRYCE I J~H NRC PDR COPIES LTTR ENCL 1 1 1 1 1 1 1 1 1 1 1 1 RECIPIENT ID CODE/NAME HXCKMAN,J RR/D-S OEAB REG FIGE 01 NOAC COPIES LTTR ENCL 1 1 1 1 1 1 1 1 D 0 C N NOTE To ALL"RIDS" RECIPIENTS: |
| AEOD/DSP/TPABNRR/DRIL/RPEBRGN3EXTERNALEGGGBRYCEIJ~HNRCPDRCOPIESLTTRENCL111111111111RECIPIENT IDCODE/NAME HXCKMAN,J RR/D-SOEABREGFIGE01NOACCOPIESLTTRENCL11111111D0CNNOTEToALL"RIDS"RECIPIENTS: | | PLEASE HELP US To REDUCE WASTE!CONTACT THE DOCUMENT CONTROL DESK, ROOM P 1-37 (EXT.504-2083)To ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS I'OR DOCUMENTS YOU DON'T NEEDI TOTAL NUMBER OF COPIES REQUIRED: LTTR 10 ENCL 10 Indiana Michigan Power Company Cook Nuclear Plant One Cook Place Bridgman, Ml 49106 616 465 5901 August 8, 1994 U.S.Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C.20555 Gentlemen: |
| PLEASEHELPUSToREDUCEWASTE!CONTACTTHEDOCUMENTCONTROLDESK,ROOMP1-37(EXT.504-2083)ToELIMINATE YOURNAMEFROMDISTRIBUTION LISTSI'ORDOCUMENTS YOUDON'TNEEDITOTALNUMBEROFCOPIESREQUIRED:
| | 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 July 1994 is submitted. |
| LTTR10ENCL10 IndianaMichiganPowerCompanyCookNuclearPlantOneCookPlaceBridgman, Ml491066164655901August8,1994U.S.NuclearRegulatory Commission ATTN:DocumentControlDeskWashington, D.C.20555Gentlemen:
| | Respectfully,.A.Blind Plant Manager Attachment cr NRC Region III D.R.Hahn R.C.Callen S.Hamming J.G.Keppler INPO Records Center ANI Nuclear Engineering Department E.E.Fitzpatrick R.L.Simms 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 prhAQj g~4v~~8(graf 9408220059 |
| Pursuanttotherequirements ofDonaldC.CookNuclearPlantUnit1Technical Specification 6.9.1.10, theattachedMonthlyOperating ReportforthemonthofJuly1994issubmitted.
| | '74073i PDR ADDCK 05000313 R PDR N.R.C.OPERATING DATA REPORT DOCKET NO.50-315 DATE 02/Aug/94 COMPLETED BY JD Janisse TELEPHONE 616-465-5901 OPERATING STATUS l.Unit Name D.C.Cook Unit 1 2.Reporting Period July notes 3.Licensed Thermal Power (MWt)3250 4.Name Plate Rating (Gross MWe)1152 5.Design Electrical Rating (Net HWe)1020 6.Maximum Dependable Capacity (GROSS HWe)1056 7.Maximum Dependable Capacity (Net HWe)1000 8.If Changes Occur in Capacity Ratings (Items no.3 through 7)Since Last Report Give Reasons 9.ower eve o ic estricte.ny et e 10.Reasons For Restrictions. |
| Respectfully, | | If Any: ll.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.(HWH)17.Gross Elect.Energy Gen.(MWH)18.Net Elect.Energy Gen.(MWH)19.Unit Service Factor 20.Unit Availability Factor 21.Unit Capacity Factor (HDC Net)22.Unit Capacity Factor (DER Net)23.Unit Forced Outage Rate 24.Shutdowns Scheduled over Next Six None is o.r.to ate 744.0 5088.0 744.0 2584.5 0.0 0.0 744.0 2547.1 0.0 0.0 2402696 6903109 765140 2190460 738097 2101539 100.0 50.1 100.0 50.1 99.2 41.3 97.3 , 40.5 0.0 0.0 Months (Type, Date,and UIMl.171648.0 128238.9 463.0 126155.7 321.0 370428884 120213120 115623337 74.4 74.4 67.1 65.3 5.9 Duration): |
| .A.BlindPlantManagerAttachment crNRCRegionIIID.R.HahnR.C.CallenS.HammingJ.G.KepplerINPORecordsCenterANINuclearEngineering Department E.E.Fitzpatrick R.L.SimmsW.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.RussoprhAQjg~4v~~8(graf9408220059 | | 25.ut own t n o eport erio , stimate ate o tartup: 26.nits in est tatus rior to ommercia INITIAL CRITICALITY INITIAL ELECTRICITY COMHERC IAL OPERATION peration: Forcast Achieved |
| '74073iPDRADDCK05000313RPDR N.R.C.OPERATING DATAREPORTDOCKETNO.50-315DATE02/Aug/94 COMPLETED BYJDJanisseTELEPHONE 616-465-5901 OPERATING STATUSl.UnitNameD.C.CookUnit12.Reporting PeriodJulynotes3.LicensedThermalPower(MWt)32504.NamePlateRating(GrossMWe)11525.DesignElectrical Rating(NetHWe)10206.MaximumDependable Capacity(GROSSHWe)10567.MaximumDependable Capacity(NetHWe)10008.IfChangesOccurinCapacityRatings(Itemsno.3through7)SinceLastReportGiveReasons9.owereveoicestricte.nyete10.ReasonsForRestrictions. | |
| IfAny:ll.HoursinReporting Period12.No.ofHrs.ReactorWasCritical13.ReactorReserveShutdownHours14.HoursGenerator onLine15.UnitReserveShutdownHours16.GrossTherm.EnergyGen.(HWH)17.GrossElect.EnergyGen.(MWH)18.NetElect.EnergyGen.(MWH)19.UnitServiceFactor20.UnitAvailability Factor21.UnitCapacityFactor(HDCNet)22.UnitCapacityFactor(DERNet)23.UnitForcedOutageRate24.Shutdowns Scheduled overNextSixNoneiso.r.toate744.05088.0744.02584.50.00.0744.02547.10.00.02402696690310976514021904607380972101539100.050.1100.050.199.241.397.3,40.50.00.0Months(Type,Date,andUIMl.171648.0128238.9463.0126155.7321.0370428884 120213120 115623337 74.474.467.165.35.9Duration):
| |
| 25.utowntnoeporterio,stimateateotartup:26.nitsinesttatusriortoommerciaINITIALCRITICALITY INITIALELECTRICITY COMHERCIALOPERATION peration:ForcastAchieved | |
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| AVERAGEDAILYPOWERLEVEL(MWe-Net)
| | AVERAGE DAILY POWER LEVEL (MWe-Net)MONTH DOCKET NO.50-315 UNIT ONE DATE 02/Aug/94 COMPLETED BY JD Janisse TELEPHONE 616-465-5901 July DAY 94/07/01 94/07/02 94/07/03 94/07/04 94/07/05 94/07/06 94/07/07 94/07/08 94/07/09 94/07/10 94/07/11 94/07/12 94/07/13 94/07/14 94/07/15 94/07/16 AVERAGE DAILY POWER LEVEL 996 999 999 995 994 988 985 985 1004 1002 1002 999 1001 1003 1004 1000 DAY 94/07/17 94/07/18 94/07/19 94/07/20 94/07/21 94/07/22 94/07/23 94/07/24 94/07/25" 94/07/26 94/07/27 94/07/28 94/07/29 94/07/30 94/07/31 AVERAGE DAILY POWER LEVEL 995 1002 1002 990 991 988 915 988 983 985 988 996 996 993 987 |
| MONTHDOCKETNO.50-315UNITONEDATE02/Aug/94 COMPLETED BYJDJanisseTELEPHONE 616-465-5901 JulyDAY94/07/0194/07/0294/07/0394/07/0494/07/0594/07/0694/07/0794/07/0894/07/0994/07/1094/07/1194/07/1294/07/1394/07/1494/07/1594/07/16AVERAGEDAILYPOWERLEVEL9969999999959949889859851004100210029991001100310041000DAY94/07/1794/07/1894/07/1994/07/2094/07/2194/07/2294/07/2394/07/2494/07/25"94/07/2694/07/2794/07/2894/07/2994/07/3094/07/31AVERAGEDAILYPOWERLEVEL99510021002990991988915988983985988996996993987
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| DOCKETUNITNAME:COMPLETED BY:TELEPHONE:
| | DOCKET UNIT NAME: COMPLETED BY: TELEPHONE: |
| DATEPAGE:50-315D.C.CookUnit1D.L.Bublick(616)465-5901August4,1994Page1of1MONTHLYOPERATING ACTIVITIES
| | DATE PAGE: 50-315 D.C.Cook Unit 1 D.L.Bublick (616)465-5901 August 4, 1994 Page 1 of 1 MONTHLY OPERATING ACTIVITIES |
| -JULY1994HIGHLIGHTS Theunitenteredthisreporting periodinMode1at99%RTP.Theunitexitedthisreporting periodinMode1at100%RTP.Therewerenochallenges tothepressurizer safetyvalvesorpoweroperatedreliefvalves.GrossElectrical generation forthemonthofJulywas765140MWH.DETAILS7-22-947-23-942200030010151640Commenced reactorpowerreduction to854RTPformainturbinevalvetesting.Reactorpowerstabilized at85~oRTP.Commenced powerincreaseto100%RTP.Reactorpowerstabilized at1004RTP. | | -JULY 1994 HIGHLIGHTS The unit entered this reporting period in Mode 1 at 99%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 July was 765140 MWH.DETAILS 7-22-94 7-23-94 2200 0300 1015 1640 Commenced reactor power reduction to 854 RTP for main turbine valve testing.Reactor power stabilized at 85~o RTP.Commenced power increase to 100%RTP.Reactor power stabilized at 1004 RTP. |
| A UNZTSHUTDOWNS ANDPOWERREDUCTIONS REPORTMONTH:JULY1994UNITNAME:DATE:COMPLETED BY:TELEPHONE: | | A UNZT SHUTDOWNS AND POWER REDUCTIONS REPORT MONTH: JULY 1994 UNIT NAME: DATE: COMPLETED BY: TELEPHONE: |
| Page1of1D.CCOOKUNIT1August4,1994~D.L.Bublic'k(616)465-5901DURATZONNODATETYPES'OURS METHODOFSHUTTINGDOWNREASON~REACTOR~LICENSEEEVENTREPORTNO.SYSTEMCODECOMPONENT CODEsCAUSEANDCORRECTIVE ACTIONTOPREVENTRECURRENCE NoneTherewerenounitshutdowns or~significant powerreductions fron~100%RTPthismonth.1FSForcedScheduled 2Reason:A:Equipment Failure(Explain)
| | Page 1 of 1 D.C COOK UNIT 1 August 4, 1994~D.L.Bublic'k (616)465-5901 DURATZON NO DATE TYPES'OURS METHOD OF SHUTTING DOWN REASON~REACTOR~LICENSEE EVENT REPORT NO.SYSTEM CODE COMPONENT CODEs CAUSE AND CORRECTIVE ACTION TO PREVENT RECURRENCE None There were no unit shutdowns or~significant power reductions fron~100%RTP this month.1 F S Forced 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)Exhibit G-Instructions for preparation of data entry sheets for Licensee Event Report (LER)File (NUREG 1061)5 Exhibit Z: Same Source}} |
| 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) | |
| ExhibitG-Instructions forpreparation ofdataentrysheetsforLicenseeEventReport(LER)File(NUREG1061)5ExhibitZ:SameSource}}
| |
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[Table view] Category:TEXT-SAFETY REPORT
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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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ACCELERATED RIDS PROCESSING)
REGULATORY INFORMATION DISTRIBUTXON SYSTEM (RIDS)ACCESSION NBR:9408220059 DOC.DATE: 94/07/31 NOTARIZED:
No DOCKET FACIL:50-315 Donald C.Cook Nuclear Power Plant, Unit 1, Indiana M 05000315 AUTH.NAME AUTHOR AFFXLIATION JANXSSE,J.D.
Indiana Michigan Power Co.(formerly Indiana 6 Michigan Ele P BLXND,A;A.
Indiana Michigan Power Co.(formerly Indiana 6 Michigan Ele RECIP.NAME RECIPIENT AFFILIATION R
SUBJECT:
Monthly operating rept for Jul 1994 for DC Cook Nuclear Plant.W/940808 ltr.DISTRIBUTION CODE: IE24D COPIES RECEIVED:LTR ENCL SIZE: TITLE: Monthly Operating Report (per Tech Spec~s NOTES: 0 RECIPIENT ID CODE/NAME PD3-1 PD INTERNAL: AEOD/DS P/TPAB NRR/DRI L/RPEB RGN3 EXTERNAL EGGG BRYCE I J~H NRC PDR COPIES LTTR ENCL 1 1 1 1 1 1 1 1 1 1 1 1 RECIPIENT ID CODE/NAME HXCKMAN,J RR/D-S OEAB REG FIGE 01 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 WASTE!CONTACT THE DOCUMENT CONTROL DESK, ROOM P 1-37 (EXT.504-2083)To ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS I'OR DOCUMENTS YOU DON'T NEEDI TOTAL NUMBER OF COPIES REQUIRED: LTTR 10 ENCL 10 Indiana Michigan Power Company Cook Nuclear Plant One Cook Place Bridgman, Ml 49106 616 465 5901 August 8, 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 July 1994 is submitted.
Respectfully,.A.Blind Plant Manager Attachment cr NRC Region III D.R.Hahn R.C.Callen S.Hamming J.G.Keppler INPO Records Center ANI Nuclear Engineering Department E.E.Fitzpatrick R.L.Simms 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 prhAQj g~4v~~8(graf 9408220059
'74073i PDR ADDCK 05000313 R PDR N.R.C.OPERATING DATA REPORT DOCKET NO.50-315 DATE 02/Aug/94 COMPLETED BY JD Janisse TELEPHONE 616-465-5901 OPERATING STATUS l.Unit Name D.C.Cook Unit 1 2.Reporting Period July notes 3.Licensed Thermal Power (MWt)3250 4.Name Plate Rating (Gross MWe)1152 5.Design Electrical Rating (Net HWe)1020 6.Maximum Dependable Capacity (GROSS HWe)1056 7.Maximum Dependable Capacity (Net HWe)1000 8.If Changes Occur in Capacity Ratings (Items no.3 through 7)Since Last Report Give Reasons 9.ower eve o ic estricte.ny et e 10.Reasons For Restrictions.
If Any: ll.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.(HWH)17.Gross Elect.Energy Gen.(MWH)18.Net Elect.Energy Gen.(MWH)19.Unit Service Factor 20.Unit Availability Factor 21.Unit Capacity Factor (HDC Net)22.Unit Capacity Factor (DER Net)23.Unit Forced Outage Rate 24.Shutdowns Scheduled over Next Six None is o.r.to ate 744.0 5088.0 744.0 2584.5 0.0 0.0 744.0 2547.1 0.0 0.0 2402696 6903109 765140 2190460 738097 2101539 100.0 50.1 100.0 50.1 99.2 41.3 97.3 , 40.5 0.0 0.0 Months (Type, Date,and UIMl.171648.0 128238.9 463.0 126155.7 321.0 370428884 120213120 115623337 74.4 74.4 67.1 65.3 5.9 Duration):
25.ut own t n o eport erio , stimate ate o tartup: 26.nits in est tatus rior to ommercia INITIAL CRITICALITY INITIAL ELECTRICITY COMHERC IAL OPERATION peration: Forcast Achieved
AVERAGE DAILY POWER LEVEL (MWe-Net)MONTH DOCKET NO.50-315 UNIT ONE DATE 02/Aug/94 COMPLETED BY JD Janisse TELEPHONE 616-465-5901 July DAY 94/07/01 94/07/02 94/07/03 94/07/04 94/07/05 94/07/06 94/07/07 94/07/08 94/07/09 94/07/10 94/07/11 94/07/12 94/07/13 94/07/14 94/07/15 94/07/16 AVERAGE DAILY POWER LEVEL 996 999 999 995 994 988 985 985 1004 1002 1002 999 1001 1003 1004 1000 DAY 94/07/17 94/07/18 94/07/19 94/07/20 94/07/21 94/07/22 94/07/23 94/07/24 94/07/25" 94/07/26 94/07/27 94/07/28 94/07/29 94/07/30 94/07/31 AVERAGE DAILY POWER LEVEL 995 1002 1002 990 991 988 915 988 983 985 988 996 996 993 987
DOCKET UNIT NAME: COMPLETED BY: TELEPHONE:
DATE PAGE: 50-315 D.C.Cook Unit 1 D.L.Bublick (616)465-5901 August 4, 1994 Page 1 of 1 MONTHLY OPERATING ACTIVITIES
-JULY 1994 HIGHLIGHTS The unit entered this reporting period in Mode 1 at 99%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 July was 765140 MWH.DETAILS 7-22-94 7-23-94 2200 0300 1015 1640 Commenced reactor power reduction to 854 RTP for main turbine valve testing.Reactor power stabilized at 85~o RTP.Commenced power increase to 100%RTP.Reactor power stabilized at 1004 RTP.
A UNZT SHUTDOWNS AND POWER REDUCTIONS REPORT MONTH: JULY 1994 UNIT NAME: DATE: COMPLETED BY: TELEPHONE:
Page 1 of 1 D.C COOK UNIT 1 August 4, 1994~D.L.Bublic'k (616)465-5901 DURATZON NO DATE TYPES'OURS METHOD OF SHUTTING DOWN REASON~REACTOR~LICENSEE EVENT REPORT NO.SYSTEM CODE COMPONENT CODEs CAUSE AND CORRECTIVE ACTION TO PREVENT RECURRENCE None There were no unit shutdowns or~significant power reductions fron~100%RTP this month.1 F S Forced 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)Exhibit G-Instructions for preparation of data entry sheets for Licensee Event Report (LER)File (NUREG 1061)5 Exhibit Z: Same Source