ML17331B353
| ML17331B353 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 03/31/1994 |
| From: | Blind A, Janisse J, Reynnells R INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9404200298 | |
| Download: ML17331B353 (7) | |
Text
ACCELERATED DISTRIBUTION DEMONSTRATION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR:9404200298 DOC.DATE: ~'59jjMl NOTARIZED-'O DOCKET FACIL:50-316 Donald C.
Cook Nuclear Power Plant, Unit 2, Indiana M
05000316 AUTH.NAME AUTHOR AFFILIATION JANISSE,J.D.
(formerly Indiana
& Michigan Ele REYNNELLS,R.D.
(formerly Indiana 6 Michigan Ele <
BLIND,A.A.
Indiana Michigan Power Co. (formerly Indiana 6 Michigan Ele RECIP.NAME RECIPIENT AFFILIATION
SUBJECT:
Monthly operatin e t for Mar 1994 for DC Cook Nuclear Plant Unit 2.W 40408 ltr.
DISTRIBUTION CODE:
IE24D COPIES RECEIVED:LTR t ENCL /
SIZE:
TITLE: Monthly Operating Report (per Tech Specs)
NOTES:
D RECIPIENT ID CODE/NAME PD3-1 PD INTERNAL: AEOD/DOA N
S OEAB EG 01 EXTERNAL EGGG BRYCE iJ
~ H NSIC COPIES LTTR ENCL 1
1 1
1 1
1 1
1 1
1 1
1 RECIPIENT ID CODE/NAME HICKMAN,J AEOD/DSP/TPAB NRR/DRIL/RPEB RGN3 NRC PDR COPIES LTTR ENCL 1
1 1
1 1
1 1
1 1
1 D
D R
D NOTE TO ALL"RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE iVASTE! 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 11 ENCL 11 D
D
indiana Michigan~
Power Company ~
Cook Nuclear Plant One Cook Place Bridgman, Ml 49106 616 465 5901 IMENdhl8ll NECiIlGQM PWM April 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 2 Technical Specification 6.9.1.10, the attached Monthly Operating Report for the month of March 1994 is submitted.
Respectfully, A.A. Blind Plant Manager Attachment c'RC 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.P. Krause M.E. Russo
, 9404200298 940331.,
PDRADQCK'500031b.
1, R"'"r>',
~ PD 4
4
N.R.C.
OPERATING DATA REPORT DOCKET NO.
50-316 DATE 01/Apr/94 COMPLETED BY JD Janisse TELEPHONE 616-465-5901 OPERATING STATUS
- 1. Unit Name
- 2. Reporting Period
- 3. Licensed Thermal Power (MWt)
. 4.
Name Plate Rating (Gross MWe) 5.
Design Electrical Rating (Net MWe) 6.
Maximum Dependable Capacity (GROSS MWe) 7.
Maximum Dependable Capacity (Net MWe)
D.
C.
Cook Unit MAR 2
94 3411 1133 1090 1100 1060 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 Refuelin outa e
of 70 da s.
This Mo.
Yr. to Date 744.0 2160.0 76.1 1212.1 0.0 0.0 0.0 1116.9 0.0 0.0 13835 2860598 0
904970 0
866986 0.0 51.7 0.0 51.7 0.0
- 37. 9 0.0
- 36. 8 100.0 44.2 Months (Type, Date,and Cumm.
142416.0 96061.1 0.0 92892.8 0.0 284974693 92512870 89092968 66.3 66.3 59.9 58.4 15.8 Duration):
- 25. If Shut Down At End of Report Period, Estimated Date of Startup:
A ril 13 1994
- 26. Units in Test Status (Prior to Commercial Operation):
Forcast INITIALCRITICALITY INITIALELECTRICITY COMMERCIAL OPERATION Achieved
AVERAGE DAILY POWER LEVEL (MWe-Net)
DOCKET NO.
UNIT TELEPHONE 50-316 TWO 11/Apr/94 JD Janisse 616-465-5901 MAR 94 DAY 94/03/01 94/03/02 94/03/03 94/03/04 94/03/05 94/03/06 94/03/07 94/03/08 94/03/09 94/03/10 94/03/11 94/03/12 94/03/13 94/03/14 94/03/15 94/03/16 AVERAGE DAILY POWER LEVEL DAY 94/03/17 94/03/18 94/03/19 94/03/20 94/03/21 94/03/22 94/03/23 94/03/24 94/03/25 94/03/26 94/03/27 94/03/28 94/03/29 94/03/30 94/03/31 AVERAGE DAILY POWER LEVEL 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
UNIT SHUTDOWNS AND POWER REDUCTIONS REPORT MONTH: MARCH 1994 UNIT NAME:
DATE:-
COMPLETED BY:
TELEPHONE:
PAGE 1 OF 1
D. C.
COOK UNIT 2
'pril 2,
1994 R. D. Reynnells (616) 465-5901 DURATION NO.
DATE TYPE'OURS METHOD OF SHUTTING LICENSEE DOWN EVENT SYSTEM COMPONENT CAUSE AND CORRECTIVE ACTION REASON REACTOR~
REPORT NO.
CODE CODE TO PREVENT RECURRENCE 234 940221 F
744 H
94-01/U-2 SB ISV The unit remained off line throughout this entire reporting~
period.
The reactor was started up on 940303, however problems with the main generator rotor prevented the unit from being paralleled
".o the grid.
1 F:
S Forced Scheduled 2
Reason:
A:
Equipment Failure (Explain)
B:
Maintenance or Test C:
Refueling D:
Regulatory Restriction E:
Operator Training and Iicense Examination F:
Administrative G:
Operational Error (Explain)
H:
Other (Explain) 3 Method:
1:
Manual 2:
Manual Scram 3:
Other (Explain) 4Exhibit G - Instructions for preparation of data entry sheets for Licensee Event Report (LBR) File (NUREG 1061) 5Exhibit I:
Same Source
DOCKET UNIT NAME:
COMPLETED BY-TELEPHONE:
DATE PAGE 50-316 D.C.
Cook Unit 2 R.
D. Reynnells (616) 465-5901 April 2, 1994 Page 1 of 1 MONTHLY OPERATING ACTIVITIES MARCH 1994 HIGHLIGHTS The unit entered the reporting period in Mode 3 at 0% RTP.
During main turbine roll up on March 3, 1994 the turbine was manually tripped due to high vibrations.
Subsequent turbine testing through March 6, 1994 identified unrepairable problems with the generator rotor.
The unit exited this reporting period in Mode 4 at 0% RTP.
There were no challenges to the pressurizer safety valves or power operated relief valves.
Gross Electrical generation for the month of March was 0
MWH.
DETAILS 03-03-94 03-04-94 1237 1324 1942 1706 1727 The reactor is in Mode 2.
The reactor is Critical.
The reactor is in Mode 1.
Manually tripped the main turbine due to high vibration.
The reactor is in Mode 2.
03-06-94 0854 The reactor is in Mode 1.
03-24-94 1015 1640 1708 1728 0158 0550 Main turbine off turning gear.
Turbine rolled to investigate high vibration concerns.
Manually tripped main turbine.
The reactor is, in Mode 2.
The reactor is in Mode 3.
Commenced RCS cooldown to Mode 4.
The RCS is in Mode 4.
0
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