ML20236W286

Monthly Operating Rept for Sept 1987

ML20236W286
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 8712070374
Download: ML20236W286 (9)

Text

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N.R.C. OPERATING DATA REPORT DOCKET NO.

50-315 DATE 10/2/87 COMPLETED BY MICHAELSON TELEPHONE 616-465-5901 OPERATING STATUS

1. Unit Name D. C. Cook Unit 1

2. Reporting Period SEPT 87 : notes

3. Licensed Thermal Power (MWt) 3250 l l

4. Name Plate Rating (Gross MWe) 1152 l l

5. Design Electrical Rating (Net MWe) 1030

6. Maximum Dependable Capacity (GROSS MWe) 1056 l l

7. Maximum Dependable Capacity (Net MWe) 1020 -----------------------

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 111743.0

12. No. of Hrs. Reactor Was Critical 0.0 3908.7 79734.5

13. Reactor Reserve Shutdown Hours 0.0 0.0 463.0

14. Hours Generator on Line 0.0

-3886.3 78204.9

15. Unit Reserve Shutdown Hours 0.0 0.0 321.0

16. Gross Therm. Energy Gen. (MWH) 0 10823586 227456094

17. Gross Elect. Energy Gen. (MWH) 0 3465460 74361330

18. Net Elect. Energy Gen. (MWH) 0 3323568 71520799

19. Unit Service Factor 0.0 59.3 71.2

20. Unit Availability Factor 0.0 59.3 71.2

21. Unit Capacity Factor (MDC Net) 0.0 49.7 63.9

22. Unit Capacity Factor (DER Net) 0.0 49.3 61.7

23. Unit Forced Outage Rate 0.0 8.5 8.6

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

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

Completed cycle 9-10 refuelina and returned tn carvice on 10-6-87.

26. Units in Test Status (Prior to Commercial Operation):

Forcast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION

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AVERAGE DAILY POWER LEVEL (MWe-Net)

DOCKET NO.

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i DOCKET N0:

50-315-UNIT NAME:

D. C. Cook Unit 1 COMPLETED BY:

J. L. St. Amand TELEPHONE:

(616) 465-5901 i..

DATE: October 12, 1987 PAGE:

1 of 2 MONTHLY OPERATING ACTIVITIES - SEPTEMBER 1987' HIGHLIGHTS:

The reporting period began with the unit in Mode 5 with RCS Fill and Venting.

on hold. awaiting the return of the esst centrifugal charging pump. Mode 4 was entered, but the unit was returned to Mode 5 after finding fuel oil in certain Train "A" ECCS pump conduits, necessitating repairs and power cable replacements.

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 on September 17, 1987, after finding inadequate circuit breaker design on the electrical supply panels, potentially allowing a faul't in " balance-of plant" circuitry to prevent rapid closure of the main steam stop valves. The electrical panels were rewired to resolve the.

p.robl em.

Mode 4 was again entered on September 21. and Mode 3 followed on September'22.

Plant heat-up and start-up activities continued.

The-reporting period ended with'the unit.in Mode 3, cooling down to repair a.

weld leak on the #13 reactor coolant pump seal leakoff line.

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

SUMMARY

8-1-87 0000 The unit is in Mode 5; RCS Fill and Vent is on hold awaiting the. return of the east centrifugal charging pump for flow balance testing.

9-7-87 0452 Entered Mode 4.

1 9-12-87 2130 Mode 5 re-entered due to finding fuel oil in ECCS pump conduits.

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 to the NRC was made after determing inadequate circuit breaker design could possibly lead to loss of rapid closure function on main steam stop valves.

9-19-87 1828 All ECCS pump cablework completed.

= = _ _ -.

9-21-87 2002 Rewiring completed on breaker panels: for steam generator stop valve dump valves; valves are declared operable.

2359 Mode 4 entered.

9-22-87 0652 Mode 3 entered.

l The reporting period ended in Mode 3, cooling down to repair weld leak on #13 RCP seal leakoff line, l-e l

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DOCKET NO.

50-315 UNIT NAME D. C. Cook - Unit No. 1 DATE October 9, 1987 C0t'PLETED BY J. L. St. Amand TELEPHONE (616) 465-5901 PAGE 1 of 3 L

MAJOR SAFETY-RELATED MAINTENANCE SEPTEMBER, 1987 M-1 One ECCS power cable failed and two others were found damaged as a result of diesel fuel intrusion into embedded electrical conduits.

The replacement cables were pulled through spare conduits which are being monitored for diesel fuel intrusion. The source of the diesel fuel has not yet been determined.

M-2 1-SI-150 (1-IM0-390 between seat equalization line check valve) was leaking by. Replaced clapper, clapper arm and disc keeper nut. The valve tested satisfactorily.

M-3 On 1-WM0-754 (essential service water to east motor 1 riven auxiliary feed pump shutoff valve) a non-nuclear grade limitorque motor was replaced with a nuclear grade limitorque motor.

M-4 1-NRV-151 (pressurizer train 'B' pressure relief valve) was leaking by.

The valve internals were replaced and the valve tested satisfactorily.

M-5 1-ICM-311 (east residual heat removal to reactor coolant loops 1 & 4 cold legs containment isolation valve) had a packing leak due to a worn bonnet and stem. The bonnet and stem were replaced. The valve tested satisfactorily.

M-6 During MOVATS Testing, metal shavings were found in the limitorque motor operator for 1-IM0-263 (safety injection pumps mini-flow to refueling water storage tank train 'B' shutoff valve). The torque switch and worn shaft bearing were replaced. The valve operator tested satisfactorily. A 10 CFR Part 21 report has been submitted.

M-7 1-QRV-112 (reactor coolant normal letdown train 'B' shutoff valve) was leaking by. The plug, stem, pin, gaskets and diaphragm were replaced. The valve tested satisfactorily.

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M 1-QRV-111 (reactor coolant normal letdown train ' A' shutdown valve) was leaking by. The stem, plug and gaskets were replaced. The valve tested satisfactorily.

M-9

,1-NRV-164 (reactor coolant loop.#4 to pressurizer spray control valve) was leaking by. The trim assembly was replaced.

The valve tested satisfactorily.'.

.M-10 1-NRV-153 (pressurizer train ' A' pressure relief valve) was leaking by. The trim assembly was replaced and the valve tested satisfactorily.

M-11 1-RH-104W (re-circulation sump'to west residual heat removal pump suctionshutoffvalve)wasleakingby. The discs, gasket and packing were replaced and the valve tested satisfactorily.

M-12 Two pin hole weld leaks were discovered on the essential service water return line from the component cooling water heat exchanger.

A 90 degree elbow was replaced and the leaks stopped.

M-13 1-NS-p57(PASliquid.andgassamplingstationQC-1007samplewaste to Unit-1 containment check valve) failed type C Leak Rate Testing.

.The disc was _ replaced and the valve internals were cleaned. The valve tested satisfactorily.

M-14 1-N-176 (reactor plant nitrogen supply to accumulator tanks shutoff ~

valve) failed the type C Leak Rate Test. The disc, stem and packing were replaced. The valve tested satisfactorily.

M-15 1-SV-98N(northsafetyinjectionpumpdischargeheadersafetyvalve) failed Bench Testing. The nozzle and disc were replaced. The valve was re-adjusted,. tested satisfactorily and re-installed.

1-SV-16-CD (emergency diesel CD jacket water cooler essential M-16 service water outlet safety valve) failed Bench Testing.

Cleaned valve internals, lapped disc and seat and re-adjusted valve. Valve tested satisfactorily.

M-17 1-SV-96 (safety injection pumps suction header safety valve) failed Bench Testing.

The seat and disc were lapped. The valve tested satisfactorily and was re-installed.

l M-18 1-SV-15W (west component cooling water heat exchanger tube side safety valve) failed Bench Testing. Cleaned and lapped seats.

Valve tested satisfactorily.

M-19 1-PW-264 (primary water to chemical and volume control system charging pumps shutoff valve) was leaking by. The diaphragm was replaced and the valve tested satisfactorily.

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3-b' M-20 1-GRV-341 (nitrogen' supply to accumulator-tanks vent valve) was

' leaking by. The diaphragm was replaced. The valve tested satisfac-torily.' '

M-21 During MOVATS Testing, the worn gear and tripper. cams in the 3

limitorque motor operator for 1-IM0-54 (boron injection to reactor--

l coolant loop f4 shutoff valve) were found to be worn..The worn gear j

and tripper cams were replaced and the valve operator tested

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satisfactorily.

J i

I&C-1 The indication for intermediate range N-35. channel I was erratic due to a defective high voltage power supply. The power supply was replaced, calibrated, and performance tested.

I&C-2

'The reactor coolant drain tank level indication (DLC-150), was found failed low.

Investigation showed the transmitter had been submerged in water..The transmitter'was repaired, calibrated, and verified to indicate proper tank level.

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Indiana Michigan f

Pocer Company L '. Nr em Pm I

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mer INDIANA l

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1 VOWiD Director, Of fice Of Managetrent In f ortna t ion and Program Control U. S. Nuclear Regulatery Cor=1ssion Washington, D. C.

20555 October 12, 1987 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 September, 1987 is submitted.

Sincere'ly,

( D, p -> al W. G. Smith, Jr.

Plant Manager WGS/jd cc:

J. E. Dolan M. P. Alexich R. W. Jurgensen R. O. Eruggee 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 fr T. R. Stephers

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l NRC Region III y

g B. L. Jorgensen i

S. L. Hall D. A. Timberlake DE31GNggORIGIM

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