ML17329A457
| ML17329A457 | |
| Person / Time | |
|---|---|
| Site: | Cook |
| Issue date: | 03/31/1992 |
| From: | Blind A, Zygmont C INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9204210004 | |
| Download: ML17329A457 (8) | |
Text
ACCELERATED DI UTION DEMONST TION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS )
4 ACCESS~ON NBR: 9204210004 DOC. DATE: 9~0~i NOTARIZED:
NO DOCKET FACIL:50-315 Donald C.
Cook Nuclear Power Plant, Unit 1, Indiana M
05000315 AUTH.NAME AUTHOR AFFILIATION ZYGMONT,C.B.
(formerly Indiana
& Michigan Ele BLIND,A.A.
(formerly Indiana
& Michigan Ele RECIP.NAME RECIPIENT AFFILIATION
SUBJECT:
Month o crating rept for Mar 1992 for DC Cook Plant, Unit 1.W 920410 ltr.
DISTRIBUTION CODE:
IE24D COPIES RECEIVED:LTR I
ENCL Q SIZE:
TITLE: Monthly Operating Report (per Tech Specs)
NOTES'ECIPIENT ID CODE/NAME PD3-1 LA STANG,J INTERNAL: AEOD/DOA N
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1 RECIPIENT ID CODE/NAME PD3-1 PD AEOD/DSP/TPAB NRR/DOEA/OEAB RGN3 NRC PDR COP1ES LTTR ENCL 1
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NOTE TO ALL"RIDS" RECIPIENTS:
D D
PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT. 20079) TO ELIMINATEYOUR NAMEFROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!
TOTAL NUMBER OF COPIES REQUIRED:
LTTR 14 ENCL 14
Indiana Michigan Power Company Cook Nuclear Plant One Cook Place Bridgman, Ml 49106 616 465 5901 April 10, 1992 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 March 1992 is submitted.
Respectfully, A.A. Blind Plant Manager Attachment co NRC Region ZZI D.R.
Hahn R.C. Callen S.
Hamming J.G. Keppler INPO Records Center ANZ Nuclear Engineering Department D.H. Williams, Jr.
E.E. Fitzpatrick R.L.
S imms W.G. Smith, Jr.
D.A. Georgantis D.W. Paul S.H. Steinhart J.L. Leichner J.A.
Isom C.B.
Zygmont E.A. Smarrella J.C. Krieger B.A. Svensson D.F. Krause E.C.
Schimmel
,9204210004 920331 PDR, ADOCK 05000315
"""R PDR
N.R.C.
OPERATING DATA REPORT DOCKET NO.
50-315 DATE 03-Apr-92 COMPLETED BY CB Zygmont TELEPHONE 616-465-5901 OPERATING STATUS
- l. Unit Name D.
C.
Cook Unit 1
- 2. Reporting Period MAR.92
- 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) 1020 notes
- 8. If Changes Occur in Capacity Ratings (Items no.
3 through
- 7) Since Last Report Give Reasons 9.
Power Level To Which Restricted. If Any (Net MWe) 10.
Reasons For Restrictions. If Any:
- 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 Refueling outage to be in 920613 90 da s.
This Mo. Yr.'o Date Cumm.
744.0 2184.0 151200.0 744.0 2184.0 113325.3 0.0 0.0 463 '
744.0 2184 '
111340 '
0.0 0.0 321
~ 0 2287795 6941337 323873316 737330 2242930 105988690 710359 2162659 101934368 100.0 100.0 74 '
100.0 100.0 74.7 93.6 97.1 67.1 93.6 96.4 65.3 0.0 0.0 6 '
Months (Type, Date,and Duration):
for an estimated duration of
- 25. If Shut Down At End of Report Period, Estimated Date of Startup:
- 26. Units in Test Status (Prior to Commercial Operation):
Forcast INITIALCRITICALITY INITIALELECTRICITY COMMERCIAL OPERATION Achieved
AVERAGE DAILY POWER LEVEL (MWe-Net)
DOCKET NO.
50-315 UNIT ONE DATE 03-Apr-92 COMPLETED BY CB Zygmont TELEPHONE 616-465-5901 DAY 1
2 3
4 5
6 7
8 9
10ll 12 13 14 15 16 MONTH AVERAGE DAILY POWER LEVEL 1011 1012 1005 1015 1012 1014 1006 1005 995 1002 1002 611 567 569 603 989 MAR.92 DAY 17 18 19 20 21 22 23 24 25 26 27 28 29 30 31 AVERAGE DAILY POWER LEVEL 1010 1004 1012 1010 1009 1011 1013 1012 1014 1014 1013 1014 1012 1017 1015
UNIT SHVZIXNNS AND HNER REDUCZIONS REPORZ MONIH:
Kuxh 1992 DKZCET NO:
UNIT NAME:
DATE CGMPIZZED BY:
TELEPHONE 50-315 D.C.
COOK UNIT 1 April 3, 1992 G.J. Costello (616) 465-5901 MEIHOD OF SHVITING LICENSEE DURATION DOWN EVENT NO.
DATE TYPE HOURS REASON REACIOR BEKGRZ NO.
SYSTEM COMFONENT CAUSE AND CGRR1KTDTE ACZION TO CODE CGDE5 FREVENZ RZXX31KENCE 299 920311 F
106. 1 N/A N/A The unit power was reduced from 100%
RZP to 60% RZP due to high No.
13 Circulating Water pump motor stator taq~ture and a rumble noise ccaning from below the screenhouse floor.
The rumble noise and high stator temperature was deteonined to be caused by the flow restriction caused by the traveling screen 1-4 being out of service.
The traveling screen and Circulating Water pump were returned to service and the unit pcarer was increased from 60% RIP to 100% RZP.
1 F
S 2
Forced Reason:
Scheduled A:
Equipment Failure (Explain)
B:
Maintenance or Test C:
Refueling D:
Regulatory Restriction E:
Oge~tor Training and 3
Method 1:
Manual 2:
Manual Scram 3:
Automatic Scrm 4:
Other (Explain) 4 5
Exhibit G Instructions Exhibit I:
Same Source for preparation of data entry sheets for Licensee Event Report (IZR) File (NUREG 0161)
DOCKET NO:
UNIT NAME:
COMPLETED BY:
TELEPHONE:
DATE PAGE:
50-315 D.C.
Cook Unit 1 G.J. Costello (616) 465-5901 April 3, 1992 1 of 1 MONTHLY OPERATING ACTIVITIES March 1992 HIGHLIGHTS The unit entered the reporting period at 1004 RTP.
Reactor power was slowly decreased to 60% RTP on March 11, 1992 to remove the No.
13 Circulating Water pump from service due to high motor stator temperature and a rumble noise emanating from below the screenhouse floor.
Power was stabilized at 60~~
RTP on March 12, 1992.
Following the removal of the pump from service, it was identified that the rumble noise was caused by flow perturbations due to the traveling screen 1-4 being out of service.
In addition, the flow restriction caused by the traveling screen being out of service was determined to be sufficient. to increase the loading on the No.
13 Circulating Water pump to cause the increased stator temperature.
Following the restoration of the traveling screen 1-4 and No.
13 Circulating Water pump, the Reactor power was slowly increased from 60:
RTP on March 15, 1992.
The power was stabilized at 100%
RTP on March 16, 1992 and the unit operated at 100%
RTP through the remainder of this reporting period.
There were no challenges to the pressurizer safety valves or power operated relief valves.
Gross electrical generation for the month of March was 737330 MWH.
DETAILS 3-11-92 2000 Commenced Reactor power reduction from 100%
3-12-92 0727 3-15-92 1700 The unit is at 60: RTP.
Commenced Reactor power increase from 604 RTP to 1004 RTP.
3-16-92 0605 The unit is at 100% RTP.
DOCKET NO:
UNIT NAME:
COMPLETED BY:
TELEPHONE:
DATE:
PAGE:
50-315 D.C.
Cook Unit 1 E.C.
Schimmel (616) 465-5901 April 10, 1992 1 of 1 MAJOR SAFETY-RELATED MAINTENANCE March 1992 There were no major safety-related maintenance items during the month of March.
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