ML20212M071

Monthly Operating Rept for Oct 1986

ML20212M071
Person / Time
Site:	Cook
Issue date:	10/31/1986
From:	Climer, Will Smith INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	NRC
References
NUDOCS 8701290498
Download: ML20212M071 (7)

Text

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

50-316 DATE 11/4/86 COMPLETED BY CLIMER TELEPHONE 616-465-5901 OPERATING STATUS

1. Unit Name D. C.

Cook Unit 2

2. Reporting Period OCT 86 l notes

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:

This Mo.

Yr. to Date Cumm.

11. Hours in Reporting Period 745.0 7296.0 77424.0

12. No. of Mrs. Reactor Was Critical 745.0 4096.5 53125.3

13. Reactor Reserve Shutdown Hours 0.0 0.0 0.0

14. Hours Generator on Line 745.0 3925.7 51779.3

15. Unit Reserve Shutdown Hours o.0 0.0 0.0

16. Gross Therm. Energy Gen. (MWH) 2014579 10407329 161677939

17. Gross Elect. Energy Gen. (MWH) 626430 3228990 52915580

18. Not Elect. Energy Gen. (MWH) 599002 3087124 50986393

19. Unit Service Factor 100.0 53.8 69.0

20. Unit Availability Factor 100.0 53.8 69.0

21. Unit Capacity Factor (MDC Net) 75.9 39.9 64.2

22. Unit Capacity Factor (DER Net) 73.1 38.5 62.7

23. Unit Forced Outage Rate 00 4.6 16.0

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

, Technical Specification required surveillance outage _, Marcha_1987, estimat;ed 2-week duration.

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 6

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AVERAGE DAILY-POWER. LEVEL (MWe-Net)

DOCKET NO.

50-316 UNIT TWO DATE 11/5/86 COMPLETED BY CLIMER TELEPHONE 616-465-5901 MONTH OCT 86 AVERAGE DAILY AVERAGE DAILY' DAY POWER LEVEL DAY POWER LEVEL 1

787 17 825 2

791 18 824 3

792 19 824 4

529 20 824-5 718 21 821 6

817 22 826 7

813 23 825 8

813 24 823 9

813 25 825 10 811 26 822 11 811 27 826 12 811 28 828 13 813 29 828 14 825 30 823 15 824 31 824 16 824

e IMM.'KET NO.

50-316 llNIT S4HlilMlWNS AND Powl;il NElllH'IIONS UNIT NAME D.C. Cook, Unit 2 11-5-86 DATE B.A. Svensson October, 1986 COMPI ETElt hY REPORT MONiil TER.I PilONE 616/465-5901 4

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4 NA HF HTEXCH Reactor power was reduced to 53%

to permit removal of main turbine condenser halves and one of the main feed pumps to. clean the main and feed pump turbine condenser water boxes. Reactor power was returned to 80% on 861005.

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Dockst No.:

50-316 Unit Nnm32 D.C. Cook Unit 2 Completed By:

A. S. Puplis Telephone:

(616) 465-5901 Date:. November 6, 1986 Page:

1 of 2 MONTHLY OPERATING ACTIVITIES - OCTOBER, 1986 HIGHLIGHTS:

The reporting period began with the Unit at 80% rated thermal power.

The Safety Parameter Display System (SPDS) was unavail-able most of the reporting period due to hardware problems.

Reactor power was reduced to approximately 58% and 53% respec-tively to permit cleaning of the main turbine and feed pump turbine condenser water boxes.

Power was later restored to 80%.

The reporting period ended with the reactor at 80% rated thermal power.

The gross electrical generation for October was 626,430 MWH.

SUMMARY

10-4-86 At 0113, a power reduction to 58% was commenced to permit removal of main turbine condenser valves from service to clean main condenser water boxes.

At 0308, reactor power at 58%.

At 1945, a power reduction from 58% was commenced to remove the East Main Feed Pump from service to permit cleaning of the feed pump turbine condenser water boxes.

At 2110, reactor power at 53%.

10-5-86 At 0612, a power increase at 6% per hour to 80% was commenced.

At 1035, reactor power was held at 78% pending chemis-try approval for operation above 78% power.

At 1220, reactor power was increased to 80%, which was reached at 1440, the same day.

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Docket No.:

50-316 Unit Namn D.C. Cook Unit 2 Completed By:

A.

S. Puplis Telephone:

(616) 465-5901 Date:

November.6, 1986 Page:

2 of 2 10-22-86 At 1236, a Unit shutdown from 80% was commenced due an apparent environmental qualification concern.

The concern was resolved and the power decrease terminated at 79%.

At approximately 1420 reactor power was restored to 80%.

10-24-86 At 1344, the Unit entered Technical Specification 3.0.3 due to a missed surveillance test on the 4 KV safeguards bus, T21A and T21D.

Action.was initiated to commence the shutdown.

The surveillance was started at 1354.

At 1440, a reactor shutdown was commenced from 80%.

At 1454, 2 of 3 under voltage relays on safeguards buses T21A and T21D were declared operable.

The Unit was no longer in the Technical Specification 3.0.3 action statement.

Reactor power was halted at 79%.

At 1703, reactor power was restored to 80%.

7 e

DOCKET NO.

50 - 316 UNIT NAME D. C. Cook - Unit No. 2 DATE 11-6-86 COMPLETED BY B. A. Svensson TELEPHONE (616) 465-5901 PAGE 1 of 1 MAJOR SAFETY-RELATED MAINTENANCE OCTOBER, 1986 I&C-1 Annunciator #10, Drop #31, Control Bank A low alarm came in with Bank A at 228 steps demand. The alarm came in and cleared once with no rod motion on that bank.

After a visual inspection of the rod insertion limit computing modules, jumpers were found missing which should have been in-stalled on 2ZY-412B, 422B, 432B and 442B to take out the Tave input and the jumper on 2ZY-412B to take out the AT input not installed. The result of the jumpers not being installed caused the output of the computing modules to be erroneous. This affected all of the control rod banks.

For control bank "A" it resulted in the output being high, causing the low alarm to come in.

The jumpers were installed and indications returned to the proper value.

I&C-2 The 2CD-2 battery charger would not handle the D.C. load.

Found the module gating and filter board and current control board to be defective. Replaced defective boards with new boards and verified correct operation.

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N[bNUN yst Donald C. Cook Nuclear Plant P.O. Son 458, Brnogrnan, Mchigan 49106 November 6, 1986 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 6.9.1.6, the attached Monthly Operating Report for the Month of October, 1986 is submitted.

Sincerely, V

Q W. G. Smith, Jr.

Plant Manager WGS:ab Attachments cc:

J. E. Dolan M. P. Alexich R. W. Jurgensen NRC Region III B. L. Jorgensen R. O. Bruggee R. C. Callen S. J. Mierzwa C. A. Erikson D. W. Paul D. R. Hahn Z.

Cordero J. J. Markowsky E. A. Morse PNSRC File INPO Records Center ANI Nuclear Engineering Department Lf f,

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