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| | issue date = 07/31/1994 | | | issue date = 07/31/1994 |
| | title = Monthly Operating Rept for Jul 1994 for DC Cook Nuclear Plant.W/940808 Ltr | | | title = Monthly Operating Rept for Jul 1994 for DC Cook Nuclear Plant.W/940808 Ltr |
| | author name = BLIND A A, JANISSE J D | | | author name = Blind A, Janisse J |
| | author affiliation = INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG | | | author affiliation = INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| | addressee name = | | | addressee name = |
| Line 17: |
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| =Text= | | =Text= |
| {{#Wiki_filter:ACCELERATED RIDS PROCESSING) | | {{#Wiki_filter:ACCELERATED RIDS PROCESSING) |
| REGULATORY INFORMATION DISTRIBUTXON SYSTEM (RIDS)ACCESSION NBR:9408220059 DOC.DATE: 94/07/31 NOTARIZED: | | REGULATORY INFORMATION DISTRIBUTXON SYSTEM (RIDS) |
| No DOCKET FACIL:50-315 Donald C.Cook Nuclear Power Plant, Unit 1, Indiana M 05000315 AUTH.NAME AUTHOR AFFXLIATION JANXSSE,J.D. | | 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 |
| 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 | |
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| ==SUBJECT:== | | ==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: | | Monthly operating rept for Jul 1994 for DC Cook Nuclear Plant.W/940808 ltr. |
| 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: | | DISTRIBUTION CODE: IE24D COPIES RECEIVED:LTR ENCL SIZE: 0 TITLE: Monthly Operating Report (per Tech Spec~s NOTES: |
| 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.
| | RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD3-1 PD 1 1 HXCKMAN,J 1 1 INTERNAL: AEOD/DS P/TPAB 1 1 RR/D- S OEAB 1 1 NRR/DRI L/RPEB 1 1 REG FIGE 01 1 1 RGN3 1 1 EXTERNAL EGGG BRYCE I J ~ H 1 1 NOAC 1 1 NRC PDR 1 1 D |
| 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
| | 0 C |
| '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.
| | N NOTE To ALL"RIDS" RECIPIENTS: |
| 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):
| | PLEASE HELP US To REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM P 1-37 (EXT. 504-2083 ) To ELIMINATEYOUR NAME FROM DISTRIBUTIONLISTS I'OR DOCUMENTS YOU DON'T NEEDI TOTAL NUMBER OF COPIES REQUIRED: LTTR 10 ENCL 10 |
| 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
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| 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
| | 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 D.R. Hahn III 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 |
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| DOCKET UNIT NAME: COMPLETED BY: TELEPHONE: | | N.R.C. OPERATING DATA REPORT DOCKET NO. 50-315 DATE 02/Aug/94 COMPLETED BY JD Janisse TELEPHONE 616-465-5901 OPERATING STATUS |
| 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 | | : l. Unit Name D. C. Cook Unit 1 |
| -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.
| | : 2. Reporting Period July notes |
| A UNZT SHUTDOWNS AND POWER REDUCTIONS REPORT MONTH: JULY 1994 UNIT NAME: DATE: COMPLETED BY: TELEPHONE: | | : 3. Licensed Thermal Power (MWt) 3250 |
| 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}}
| | : 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: |
| | is o. r. to ate UIMl. |
| | ll. Hours in Reporting Period 744.0 5088.0 171648.0 |
| | : 12. No. of Hrs. Reactor Was Critical 744.0 2584.5 128238.9 |
| | : 13. Reactor Reserve Shutdown Hours 0.0 0.0 463.0 |
| | : 14. Hours Generator on Line 744.0 2547.1 126155.7 |
| | : 15. Unit Reserve Shutdown Hours 0.0 0.0 321.0 |
| | : 16. Gross Therm. Energy Gen. (HWH) 2402696 6903109 370428884 |
| | : 17. Gross Elect. Energy Gen. (MWH) 765140 2190460 120213120 |
| | : 18. Net Elect. Energy Gen. (MWH) 738097 2101539 115623337 |
| | : 19. Unit Service Factor 100.0 50.1 74.4 |
| | : 20. Unit Availability Factor 100.0 50.1 74.4 |
| | : 21. Unit Capacity Factor (HDC Net) 99.2 41.3 67.1 |
| | : 22. Unit Capacity Factor (DER Net) 97.3 , |
| | 40.5 65.3 |
| | : 23. Unit Forced Outage Rate 0.0 0.0 5.9 |
| | : 24. Shutdowns Scheduled over Next Six Months (Type, Date,and Duration): |
| | None |
| | : 25. ut own t n o eport erio , stimate ate o tartup: |
| | : 26. nits in est tatus rior to ommercia peration : |
| | Forcast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY COMHERC IAL OPERATION |
| | |
| | AVERAGE DAILY POWER LEVEL (MWe-Net) |
| | DOCKET NO. 50-315 UNIT ONE DATE 02/Aug/94 COMPLETED BY JD Janisse TELEPHONE 616-465-5901 MONTH July AVERAGE DAILY AVERAGE DAILY DAY POWER LEVEL DAY POWER LEVEL 94/07/01 996 94/07/17 995 94/07/02 999 94/07/18 1002 94/07/03 999 94/07/19 1002 94/07/04 995 94/07/20 990 94/07/05 994 94/07/21 991 94/07/06 988 94/07/22 988 94/07/07 985 94/07/23 915 94/07/08 985 94/07/24 " |
| | 988 94/07/09 1004 94/07/25 983 94/07/10 1002 94/07/26 985 94/07/11 1002 94/07/27 988 94/07/12 999 94/07/28 996 94/07/13 1001 94/07/29 996 94/07/14 1003 94/07/30 993 94/07/15 1004 94/07/31 987 94/07/16 1000 |
| | |
| | DOCKET 50-315 UNIT NAME: D.C. Cook Unit 1 COMPLETED BY: D. L. Bublick TELEPHONE: (616) 465-5901 DATE August 4, 1994 PAGE: 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 2200 Commenced reactor power reduction to 854 RTP for main turbine valve testing. |
| | 7-23-94 0300 Reactor power stabilized at 85~o RTP. |
| | 1015 Commenced power increase to 100% RTP. |
| | 1640 Reactor power stabilized at 1004 RTP. |
| | |
| | A UNZT SHUTDOWNS AND POWER REDUCTIONS UNIT NAME: D. C COOK UNIT 1 DATE: August 4, 1994 ~ |
| | REPORT MONTH: JULY 1994 COMPLETED BY: D. L. Bublic'k TELEPHONE: (616) 465-5901 Page 1 of 1 METHOD OF SHUTTING LICENSEE DURATZON DOWN EVENT SYSTEM COMPONENT CAUSE AND CORRECTIVE ACTION NO DATE TYPES'OURS REASON~ REACTOR~ REPORT NO. CODE CODEs TO PREVENT RECURRENCE None There were no unit shutdowns or significant power reductions fron~ |
| | 100% RTP this month. |
| | ~ |
| | 1 2 3 5 F Forced Reason: Method: Exhibit G - Instructions Exhibit Z: Same S Scheduled A: Equipment Failure (Explain) 1: Manual for preparation of data Source B: Maintenance or Test 2: Manual Scram entry sheets for Licensee C: Refueling 3: Automatic Scram Event Report (LER) File D: Regulatory Restriction 4: Other (Explain) (NUREG 1061) |
| | E: Operator Training and License Examination F: Administrative G: Operational Error (Explain) |
| | H: Other (Explain)}} |
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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
[Table view] |
Text
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: 0 TITLE: Monthly Operating Report (per Tech Spec~s NOTES:
RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD3-1 PD 1 1 HXCKMAN,J 1 1 INTERNAL: AEOD/DS P/TPAB 1 1 RR/D- S OEAB 1 1 NRR/DRI L/RPEB 1 1 REG FIGE 01 1 1 RGN3 1 1 EXTERNAL EGGG BRYCE I J ~ H 1 1 NOAC 1 1 NRC PDR 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 ELIMINATEYOUR NAME FROM DISTRIBUTIONLISTS 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 D.R. Hahn III 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:
is o. r. to ate UIMl.
ll. Hours in Reporting Period 744.0 5088.0 171648.0
- 12. No. of Hrs. Reactor Was Critical 744.0 2584.5 128238.9
- 13. Reactor Reserve Shutdown Hours 0.0 0.0 463.0
- 14. Hours Generator on Line 744.0 2547.1 126155.7
- 15. Unit Reserve Shutdown Hours 0.0 0.0 321.0
- 16. Gross Therm. Energy Gen. (HWH) 2402696 6903109 370428884
- 17. Gross Elect. Energy Gen. (MWH) 765140 2190460 120213120
- 18. Net Elect. Energy Gen. (MWH) 738097 2101539 115623337
- 19. Unit Service Factor 100.0 50.1 74.4
- 20. Unit Availability Factor 100.0 50.1 74.4
- 21. Unit Capacity Factor (HDC Net) 99.2 41.3 67.1
- 22. Unit Capacity Factor (DER Net) 97.3 ,
40.5 65.3
- 23. Unit Forced Outage Rate 0.0 0.0 5.9
- 24. Shutdowns Scheduled over Next Six Months (Type, Date,and Duration):
None
- 25. ut own t n o eport erio , stimate ate o tartup:
- 26. nits in est tatus rior to ommercia peration :
Forcast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY COMHERC IAL OPERATION
AVERAGE DAILY POWER LEVEL (MWe-Net)
DOCKET NO. 50-315 UNIT ONE DATE 02/Aug/94 COMPLETED BY JD Janisse TELEPHONE 616-465-5901 MONTH July AVERAGE DAILY AVERAGE DAILY DAY POWER LEVEL DAY POWER LEVEL 94/07/01 996 94/07/17 995 94/07/02 999 94/07/18 1002 94/07/03 999 94/07/19 1002 94/07/04 995 94/07/20 990 94/07/05 994 94/07/21 991 94/07/06 988 94/07/22 988 94/07/07 985 94/07/23 915 94/07/08 985 94/07/24 "
988 94/07/09 1004 94/07/25 983 94/07/10 1002 94/07/26 985 94/07/11 1002 94/07/27 988 94/07/12 999 94/07/28 996 94/07/13 1001 94/07/29 996 94/07/14 1003 94/07/30 993 94/07/15 1004 94/07/31 987 94/07/16 1000
DOCKET 50-315 UNIT NAME: D.C. Cook Unit 1 COMPLETED BY: D. L. Bublick TELEPHONE: (616) 465-5901 DATE August 4, 1994 PAGE: 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 2200 Commenced reactor power reduction to 854 RTP for main turbine valve testing.
7-23-94 0300 Reactor power stabilized at 85~o RTP.
1015 Commenced power increase to 100% RTP.
1640 Reactor power stabilized at 1004 RTP.
A UNZT SHUTDOWNS AND POWER REDUCTIONS UNIT NAME: D. C COOK UNIT 1 DATE: August 4, 1994 ~
REPORT MONTH: JULY 1994 COMPLETED BY: D. L. Bublic'k TELEPHONE: (616) 465-5901 Page 1 of 1 METHOD OF SHUTTING LICENSEE DURATZON DOWN EVENT SYSTEM COMPONENT CAUSE AND CORRECTIVE ACTION NO DATE TYPES'OURS REASON~ REACTOR~ REPORT NO. CODE CODEs TO PREVENT RECURRENCE None There were no unit shutdowns or significant power reductions fron~
100% RTP this month.
~
1 2 3 5 F Forced Reason: Method: Exhibit G - Instructions Exhibit Z: Same S Scheduled A: Equipment Failure (Explain) 1: Manual for preparation of data Source B: Maintenance or Test 2: Manual Scram entry sheets for Licensee C: Refueling 3: Automatic Scram Event Report (LER) File D: Regulatory Restriction 4: Other (Explain) (NUREG 1061)
E: Operator Training and License Examination F: Administrative G: Operational Error (Explain)
H: Other (Explain)
