ML20236W091

Monthly Operating Rept for Sept 1987

ML20236W091
Person / Time
Site:	Cook
Issue date:	09/30/1987
From:	Michaelson, Will Smith, St Amand J INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	NRC
References
NUDOCS 8712070270
Download: ML20236W091 (6)

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N.R.C. OPERATING DATA REPORT I

DOCKET NO.

50-316 DATE 10/2/87 COMPLETED BY MICHAELSON TELEPHONE 616-465-5901 OPERATING STATUS 1.

Unit Name D.

C. Cook Unit 2 2.

Reporting Period SEPT 87 l notes l

3. Licensed Thermal Power (MWt) 3411 l l

4.

Name Plate Rating (Gross MWe) 1133 l l

5. Design Electrical Rating (Net MWe) 1100 l l

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6. Maximum Dependable Capacity (GROSS MWe) 1100 l l

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7. Maximum Dependable Capacity (Net MWe) 1060 -----------------------

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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:

This Mo.

Yr. to Date Cumm.

11. Hours in Reporting Period 720.0 6551.0 85439.0

12. No. of Hrs. Reactor Was Critical 0.0 4316.6 58905.9

13. Reactor Reserve Shutdown Hours 0.0 0.0 0.0

14. Hours Generator on Line 0.0 4293.9 57537.2

15. Unit Reserve Shutdown Hours 0.0 0.0 0.0

13. Gross Therm. Energy Gen. (MWH) 0 11237287 176928491

17. Gross Elcet. Energy Gen. (MWH) 0 3565560 57783600

18. Net Elect. Energy Gen. (MWH) 0 3406204 55641040

19. Unit Service Factor 0.0 65.5 69.3 20 Unit Availability Factor 0.0 65.5 69.3

21. Unit Capacity Factor (MDC Net) 0.0 49.1 63.2

22. Unit Capacity Factor (DER Net) 0.0 47.3 61.7

23. Unit Forced Ou+. age Rate 0.0 24.8 15.5

24. Shutdowns Seb.duled over Next Six Months (Type,Date,and Duration):

25. If Shut D en At End of Report Period, Estimated Date of Startup:

ma i n tena nce /s u rygi 11 ance The uni 11.ss returned to service nn 1D-11 A7. fnlinwinn a

26. Units '.4 Test Status (Prior to Commercial Operation);

outage.

Forcast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION 1

D y,

8

I AVERAGE DAILY POWER' LEVEL:(MWe'-Net)

DOCKET NO.

50-316 UNIT-TWO DATE 10/2/87 COMPLETED BY MICHAELSON l-TELEPHONE 616-465-5901

. MONTH SEPT 87' AVERAGE DAILY

. AVERAGE DAILY DAY-POWER LEVEL-DAY POWER LEVEL 1

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DOCKET NO:

50-316 UNIT NAME:

D.C.-Cdok Unit:2 COMPLETED BY:

J. L. St. Amand TELEPHONE:

(616)465-5901 DATE:

October 12, 1987 PAGE:

1 of 1 4

MONTHLY OPERATING ACTIVITIES - SEPTEMBER 1987

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- HIGHLIGHTS q

The reporting period began with the unit in Mode 5, shutdown to repair faulty

- reactor coolant pump hatch cover bolts.

Bolt repairs, outage maintenance, and surveillance work continued throughout this period.

Half-loop level was achieved on 9-8-87.

On September 17,'at 2045, a 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> report was made to the NRC concerning inadequate circuit breaker design possibly allowing loss of rapid closure of the1 main steam stop valves. The electrical panels were rewired to seperate the B0P loads from the safety-related loads. Work continued throughout the remainder of the period.

The steam generators were eddy-current tested.

78 tubes were plugged based upon evaluation of the data.

Gross Electrical Generation for the month of September was 0 MWH.

SUMMARY

9-1-87 0000 The unit was in Mode 5, with repairs underway on the faulty reactor coolant pump hatch cover bolts.

9-8-87 0825-Half-loop level was declared.

9-17-87 2045 A 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> report was made to the NRC after finding inadequate circuit breaker design on the electrical panels controlling the rapid closure function of the main steam stop valves. The potential is thought to exist allowing a faulted B.0.P. circuit to disable main steam stop valve dump valves.

The reporting period ended with the unit in Mode 5.

Outage, maintenance, and surveillance work continues.

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9 a

'l DOCKET N0.-

50-316 UNIT NAME D.C. Cook-Unit No. 2 DATE_

October 12, 1987 COMPLETED BY

-J. L. St. Amand TELEPHONE (616) 465-5901 PAGE 1 of 1 MAJOR SAFETY-RELATED MAINTENANCE SEPTEMBER, 1987 M-1 2-DCR-330 (steam generator blowdown containment isolation valve) was chattering during operation.

The gaskets, stem, plug and cage were replaced. The valve tested satisfactorily.

was le)40A'(emergency diesel AB ' control air dryer outlet check valve)

M-2 2-DG-aking by. The valve was replaced with a new valve.

M-3

'2-DCR-320(steamgeneratorblowdowncontainmentisolationvalve) failed to stroke fully open. The gaskets' stem, plug and cage were replaced. The' valve tested satisfactorily.

I&C-1 FFI-230, the auxiliary feedwater flow indicator to steam generator 23 was indicating 100,000 lbs/hr with the valve closed and the pump off. The square root extractor.found to be defective, was replaced.

and recalibrates.

18C-2 FFC-220, the indicator for feedwater flow to steam generator 22 was indicating over 1 million lbs/hr with the unit shutdown and no feedwater flow'present. The transmitter was replaced and calibrated.

I&C-3 Wide range reactor coolant system pressure indication, NPS-121, was indicating 36 PSI lower than other indications. The amplifier was replaced and the transmitter recalibrates.

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indiana Michigan Po et Company C x. ',ny P'rt

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~nn mer INDIANA MICHIGAN P O W I f' Director, Office Of Management Information and Program Control U. S. Nuclear Regulatory Commission Washington, D. C.

20555 October 12, 1987 Gentlemen:

Pursuant to the requirements of Donald C. Cook Nuclear Plant Unit 2 Technicpl Specification 6.9.1.10, the attached Monthly Operating Report for the Month of September, 1987 is submitted.

Sincerely,

(, {.. : Ir ND L' W. G. Smith, r.

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 J

INP0 Records Center O

p[g ANI Nuclear Engineering Department i

T. R. Stephens NRC Region III

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B. L. Jorgensen

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