ML20237H645
| ML20237H645 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 07/31/1987 |
| From: | Climer, Will Smith, St Amand J INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| To: | NRC OFFICE OF RESOURCE MANAGEMENT (ORM) |
| References | |
| NUDOCS 8708250094 | |
| Download: ML20237H645 (7) | |
Text
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N.R.C. OPERATING DATA REPORT DOCKET NO.
50-316 DATE 8/4/87 COMPLETED BY CLIMER TELEPHONE 616-465-5901 l
l OPERATING STATUS l
- 1. Unit Name D. C. Cook Unit 2
- 2. Reporting Period JULY 87 inotes
- 3. Licensed Thermal Power (MWt) 3411 l l
- 4. Name Plate Rating (Gross MWe) 1133 l l
S. Design Electrical Rating (Net MWe) 1100 l l
- 6. Maximum Dependable Capacity (GROSS MWe) 1100 l l
- 7. Maximum Dependable Capacity (Net MWe) 1060 -----------------------
- 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:
l l
This Mo.
Yr. to Date Cumm.
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- 11. Hours in Reporting Period 744.0 5087.0 83975.0 l
- 12. No. of Hrs. Reactor Was Critical 531.4 3689.8 58279.1
- 13. Reactor Reserve Shutdown Hours 0.0 0.0 0.0
- 14. Hours Generator on Line 522.7 3667.4 56910.7
- 15. Unit Reserve Shutdown Hours 0.0 0.0 0.0
- 16. Gross Therm. Energy Gen. (MWH) 1409763 9751636 175442839
- 17. Gross Elect. Energy Gen. (MWH) 423560 3120270 57338310 18.' Net Elect. Energy Gen. (MWH) 403959 2984067 55218903
- 19. Unit Service Factor 70.3 72.1 69.8
- 20. Unit Availability Factor 70.3 72.1 69.8
- 21. Unit Capacity Factor (MDC Net) 51.2 55.'3 63.9
- 22. Unit Capacity Factor (DER Net) 49.4 53.3 62.4
- 23. Unit Forced Outage Rate 29.7 27.9 15.7
- 24. Shutdowns Scheduled over Next Six Months (Type,Date,and Duration):
A nurveillnnen nnd mnintonnnen nutnen is schednind for the ?nd unnk in Oct. 10R7.
Estiented duration is 1-2 monthn-donnnannt nn ncngn nf unrk.
- 25. If Shut Down At End of Report Period, Estimated Date of Startup:
- 26. Units in Test Status (Prior to Commercial Operation):
Forcast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION s
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8708250094 B70731
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4 AVERAGE DAILY POWER LEVEL (MWe-Net)'
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DOCKET NO.
50-316 UNIT TWO DATE 8/4/87 COMPLETED'BY CLIMER TELEPHONE 616-465-5901 1
MONTH JULY 87 i
AVERAGE DAILY AVERAGE DAILY DAY POWER LEVEL DAY POWER LEVEL 1
797 17 0
1 1
2 795 18 0
3 792 19 0
4 793 20 0
5 810 21 0
6 F,04 22 0
7 790 23 128 8
784 24
.733 9
779
'25 765 10 776 26 771 11 772 27
'803 l
12 772 28 807 l
13 771 29 807 14 199 30 796 15 0
31 787 16 0
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DOCKET NO: 50-316 UNIT NAME:
D.C. C*nk Unit 2 l
COMPLETED BY:
J. L. St. Amand TELEPHONE:
(616)465-5901 DATE: Aug. 10, 1987 l
PAGE: 1 of 2 l
j MONTHLY OPERATING ACTIVITIES - JULY 1987 HIGHLIGHTS The reporting period began with the unit in Mode 1 at the 80% power limit administratively imposed to minimize steam generator tube degradation.
On 7-14-87, the unit tripped from 80%, due to undervoltage of the reactor coolant pump busses caused by loss of voltage regulation from the main generato'r.
The unit was returned to service on 7-22-87.
Later that day, the unit tripped from 20% during power escalation when a
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feedwater transient allowed the level in steam generator.#24 to reach the high
)
high setpoint. The unit was restarted and paralleled on 7-23-87, reaching 80%
on 7-24-87.
l The reporting period ended with the unit in Mode 1 at 80% power.
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Gross Electrical Generation for the month of July was 423,560 MWH.
I
SUMMARY
7-1-87 0000:
The unit is in Mode 1 at 80% power.
i 7-14-87 0707:
Reactor trip due to undervoltage on reactor coolant pump busses caused by failure of automatic voltage regulation on main generator. The CD die ni generator started and supplied busses T21C and T21D.
0724:
Transferred T21C and T2a0 busses to auxiliary feed.
0727:
Stopped CD diesel generator.
7-15-87 0830:
Entered Mode 4.
7-16-87 1406:
Entered Mode 5.
7-20-87 1802:
Entered Mode 4; unit heat-up in progress.
7-21-87 0958:
Entered Mode 3.
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l 7-22-87 1628:
Reactor Critical.
2154:
Unit paralleled to grid; power increase begun.
2233:
Reactor trip from 20% power; #24 steam generator exceeded high-high level setpoint. The feedpump AP controller had been switched from automatic to manual in response to a l
feedwater transient just prior to trip.
7-23-87 0910:
Reactor Critical.
1302:
Unit paralleled to grid.
7-24-87 0745:
Power at 80%.
The reporting period ended with the unit in Mode 1 at 80% power.
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DOCKET NO.
50-316.
j UNIT NAME D.C. Cook-Unit No. 2 DATE Aug. 10, 1987
(
COMPLETED BY J. L. St. Amand
)
i TELEPHONE (616) 465-5901 l
.PAGE 1 of 1 MAJOR SAFETY-RELATED MAINTENANCE i
1 JULY, 1987
)
l 180-1 The main generator automatic voltage regulator was repaired after i
failing and causing a unit trip. Many components were replaced before returning the unit to service.
I&C-2.
The AP controller meter for the #24 steam generator feed regulating valve was replaced and the valve checked'after.it was reported to be sticking. No abnonnal conditions were found, and the unit was returned to service.
i I&C-3 The alarm module for the #1 steam generator high-high level was
]
replaced after being found defective, causing an alarm. The module-q was operability tested and calibrated prior to returning the unit to j
service.
1 1
I&C-4 A transmitter board in NPS-121, reactor coolant system wide range l
pressure indicator was replaced after receiving serveral spikes, 1
I which occasionally failed the SSPS wide range iconic. The transmit-ter was calibrated and verified to be operating correctly before returning to service.
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i 0 '5jl L3rJNDIANARMlCHlGAN ELECTRlC COMPANY
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E DONALD C. COOK NUCLEAR PLANT P.O. Box 458, Bridgman, Michigan 49106 (616)465 5901 August 10, 1987 Director, Office Of Management Information J
and Program Control
)
U. S. Nuclear Regulatory Commission j
Washington, D. C.
20555
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I Gentlemen:
Pursuant to the requirements of Donald C. Cook Nuclear Plant Unit 2 fechnical Specification 6.9.1.10, the attached Monthly Operating Report for the Month of July, 1987 is submitted.
i Sincerely,
~
(,h./
W. G. Smith, Tr'.
Plant Manager WGS/jd cc:
J. E. Dolan M. P. Alexich R. W. Jurgensen R. O. Bruggee R. C. Callen C. A. Erikson D. W. Paul D. R. Hahn J. J. Markowsky E. A. Morse PNSRC File INPO Records Center ANI Nuclear Engineering Department T. R. Stephens NRC Region III B. L. Jorgensen S. L. Hall D. A. Timberlake G
T 1
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