ML20237K716

Monthly Operating Rept for June 1987

ML20237K716
Person / Time
Site:	Cook
Issue date:	06/30/1987
From:	Will Smith, St Amand J, Tetzlaff B INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	NRC
References
NUDOCS 8708190381
Download: ML20237K716 (8)

Text

_ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _,

e N.R.C.

OPLRATING DATA REPORT DOCf.:ET NO.

50--316 DATE 7/3/87 COMPLETED DYART TETZLACF TELEPHONE 616-465-5901 OPERATINO STATUS 1.

Unit Name D.

C.

Cook Unit 2

- - - - - - - - - - - - - - ~ ~ - - - - - -

2.

Reporting Period JUNE 07 l notes l

3.

Licensed Thermal Power (MWt) 3411 l l

4.

Nome Plate Rating (Gross MWe) 1133 l l

S.

Design Electrical Rating (Net MWe) 1100 l l

6.

Manimum Dependable Capacity (GROSS MWe) 1100 l l

7.

Maximum Dependable Capacity (Net MWe) 10 6 0 - - -- -- - -

8.

If Changes Occur in Capacity Ratings (Items no. 3 through 7) Since Last Report Give Reasons _,______,,,_________________________________

9.

Power Level To Wnich Restricted. If Any (Net MWe>

10. Reasons For Restrictions. If Any:__,_______,__.________,____.______

This Mo.

Yr. to Date Camm.

11. Hours in Reporting Period 720.0 4343.0 83231.0

12. No. of Hrs. Reactor Wan Critical 695.7 3158.4 57747.7

13. Reactor Reserve Shutdown Hours 0.0 0.0 0.0

14. Hours Generator on Line 688.8 3144.7 56388.0

15. Unit Reserve Ghutd wn Hours O.O O. O O.0

16. Gross Therm. Energy Gen. (MWH) 1849770 8341873 174033077

17. Cross Elect. Energy Gen. (MWH) 567760 2696710 56914750

18. Net Elect. Energy Gen. (MWH) 542059 2580108 54814944

19. Unit Service Factor 95.7 72.4 69.8

20. Unit Availability Factor 95.7 72.4 69.8

21. Unit Capacity Factor (MDC Net) 71.0 56.0 64.0

22. Unit Capacity Factor (DER Net) 68.4 54.0 62.5

23. Unit Forced Outage Rate 4.3 27.6 15.5

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

_.d_u_r_v e i l_l a n c e _o u t a ge__te,n,t a t i_v e l y. _s,@ e d ule d _f_o_r_

_____________~_______________

Su

~

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

26. Un~its~ ~~ Teat ~ Status ~iPFio~r~~to Commercial ~6p~e r~At i on ii~ ~~~~~~~~~ ~~

~~ ~~~ ~~

~~

l in Forcast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY j

COMMERCIAL OPERATION 1

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1 AVERAGE DAILY POWER LEVEL (MWe-Net)

DOCKET NO.

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820 17 826 2

0 18 818 3

439 19 812 4

815 20 807 5

813 21 802 6

508 22 802 7

811 23 797 8

810 24 787 9

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DOCKET N0:

50-316-UNIT NAME:

0.C. Cook Unit 2 COMPLETED BY:

J. L. St. Amand TELEPHONE:

(616)465-5901 j

DATE:

July 7, 1987 PAGE:

1 of 2 l

L MONTHLY OPERATING ACTIVITIES - JUNE 1987 i

i HIGHLIGHTS l

The reporting period began with the unit in Mode 1 at the 80% power limit administratively imposed'to minimize. steam generator tube degradation. On 6-1-87, power was increased to 90% to satisfy demand from the system being on j

operating reserve.

Power reached 90% at 1405 hours0.0163 days <br />0.39 hours <br />0.00232 weeks <br />5.346025e-4 months <br /> the same day.

At 2341 hour0.0271 days <br />0.65 hours <br />0.00387 weeks <br />8.907505e-4 months <br />s:(same day)-the unit tripped due to loss of condenser vacuum.

I The loss was the result of a manual. isolation valve leaking through during maintenance activities.- The valve was replaced and the unit restarted, i

reaching criticality on 6

'.-87.

i Later <the came day, the reactor tripped from 4.5% power when the low-low level was reached in steam generator #3. The trip was the result of losing level while in manual control. The reactor was again taken critical on 6-3-87, and' paralleled to the grid at 0653 hours0.00756 days <br />0.181 hours <br />0.00108 weeks <br />2.484665e-4 months <br />.

Power was increased to 80% and remained stable.

An unusual event was declared on 6-10-87 due to a seismic event.

The Seismic-Monitors registered the event, later determined to have been of a magnitude of 5.0 on the richter scale, with an epicenter 55 miles north of Evansville, Indiana. The unusual event was terminated ten minutes after being declared.

On 6-15-87, a 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> unit shutdown was started per technical specification 3.0.3 when both containment spray pumps were declared inoperable due to

-incorrect flow instrument scales. An unusual event was declared and a p.ower reduction started. -The power reduction was halted with power at 78.5%. The unusual event was terminated when the east pump was declared operable.

Power was increased to 80% and stabilized.on 6-16-87, where it remained until 6-27-87, when a decrease to 55% was begun to facilitate condenser cleaning.

Following cleaning, power was increased, reaching 80% on 6-29-87, where it

-remained through the end of the reporting period.

Gross Electrical Generation for the month of June was 567,760 MWH.

i I

.. _ =

t.

l

SUMMARY

6 _1-87 0000 hour0 days <br />0 hours <br />0 weeks <br />0 months <br />s:

The unit began the reporting period in Mode 1 at 80%

power.

0845 hour0.00978 days <br />0.235 hours <br />0.0014 weeks <br />3.215225e-4 months <br />s:

. Power increase to'90% started; operating reserve is in effect.

1405 hour0.0163 days <br />0.39 hours <br />0.00232 weeks <br />5.346025e-4 months <br />.s:

Reactor power is at 90%.

2341 hour0.0271 days <br />0.65 hours <br />0.00387 weeks <br />8.907505e-4 months <br />s:

A reactor trip occurred due to low condenser vacuum.

The low vacuum trip occurred due to air in-leakage while removing blank flange LPD-170, miscellaneous drain tank header isolation to unit-1 and the turbine '

room sump. During removal, manual isolation valve l

LPD-169 allowed excessive air in-leakage from the open drain tank discharge header. After the resulting trip, the valve, which had severe seat j

degradation, was replaced.

H 6-2-87 1919 hour0.0222 days <br />0.533 hours <br />0.00317 weeks <br />7.301795e-4 months <br />s:

Reactor is critical.

1950 hour0.0226 days <br />0.542 hours <br />0.00322 weeks <br />7.41975e-4 months <br />s:

The reactor tripped from 4.5% power due to #3 steam generator low-low level reached while controls werfin manual.

6-3-87 0028 hour3.240741e-4 days <br />0.00778 hours <br />4.62963e-5 weeks <br />1.0654e-5 months <br />s:

Reactor is critical.

0653 hour0.00756 days <br />0.181 hours <br />0.00108 weeks <br />2.484665e-4 months <br />s:

Unit paralleled to grid.

2022 hour0.0234 days <br />0.562 hours <br />0.00334 weeks <br />7.69371e-4 months <br />s:

Reactor power is at 80%.

6-10-87 1955 hour0.0226 days <br />0.543 hours <br />0.00323 weeks <br />7.438775e-4 months <br />s:

Declared an unusual event due to a seismic event.

2005 hour0.0232 days <br />0.557 hours <br />0.00332 weeks <br />7.629025e-4 months <br />s:

Terminated unusual event.

i 1

6-15-87 1855 hour0.0215 days <br />0.515 hours <br />0.00307 weeks <br />7.058275e-4 months <br />s:

Began Technical Specification 3.0.3 shutdown due to having bota trains of Containment Spray inoperable--declared unusual event.

l 2053 hour0.0238 days <br />0.57 hours <br />0.00339 weeks <br />7.811665e-4 months <br />s:

East containment spray pump is operable; exit Technical Specification 3.0.3; terminate unusual event.

2110 hour0.0244 days <br />0.586 hours <br />0.00349 weeks <br />8.02855e-4 months <br />s:

Power reduction stopped at 78.5%; began increase to just under 80%.

6-16-87 0032 hour3.703704e-4 days <br />0.00889 hours <br />5.291005e-5 weeks <br />1.2176e-5 months <br />s:

Power stabilized at 80%.

6-27-87 1127 hour0.013 days <br />0.313 hours <br />0.00186 weeks <br />4.288235e-4 months <br />s:

Start Power reduction to 55% for Condenser cleaning.

1625 hour0.0188 days <br />0.451 hours <br />0.00269 weeks <br />6.183125e-4 months <br />s:

Power at 55%.

6-29-87.

0000 hour0 days <br />0 hours <br />0 weeks <br />0 months <br />s:

Began power increase to 80% at 6%/ hour.

0500 hour0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br />s:

Power stabilitzed at 80%.

I 1

.l DOCKET N0.

50-316 l

UNIT NAME' D.C. Cook-Unit No. 2 1

DATE July 7, 1987 1

COMPLETED BY J. L. St. Amand TELEPHONE-(616) 465-5901 PAGE

L of 1 y

MAJOR SAFETY-RELATED MAINTENANCE JUNE, 1987

.il M-1 The #3 boric acid transfer pump was replaced after finding the shaft, mechanical seal, bearings, and pump cover worn. The new pump required repairs fut to the bearings running at unacceptably high q

temperatures.

Following repairs,.the pump was tested, verified 1

operable, and returned to service, i

M-2 The essential service water lines which provide backup cooling to the control room air conditioners were found plugged with sand. The j

valves were removed,'the lines flushed, the valves replaced, and-the systems returned to service.

I i

l l

\\

-- - _ - _ _-- a

pCS

• • • JNDIANA & MICHIGAN ELECTRIC COMPANY

\\y DONALD C. COOK NUCLEAR PLANT 1

P.O. Box 458, Bridgman, Michigan 49106

/

f (G 16) 465-5901 9

July 6, 1987 l

l Director, Office Of Management Information and Program Control U. S. Nuclear Regulatory Commission 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 Oper.ating Report for the Month of June, 1987 is submitted.

Sincerely, LY,lY W. G. Smith, Jr.

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 INP0 Records Center ANI Nuclear Engineering Department T. R. Stephens NRC Region III B. L. Jorgensen S. L. Hall D. A. Timberlake d

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