Text

Monthly Operating Rept for June 1987
	ML20237K442
Person / Time
Site:	Cook
Issue date:	06/30/1987
From:	Will Smith, St Amand J, Tetzlaff A; INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	; NRC
References
	NUDOCS 8708190257
	Download: ML20237K442 (9)
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N.R.C.

OPERATING DATA REPORT DDCKET NO.

S0-315 DATE 7/3/07 COMPLETED BYART TETZLAFF TELEPHONE 616-465-5901 OPERATING STATUS 1.

Unit Name D.

C.

Cool: Unit 1 2.

Reporting Period JUNE O'7 lnoteu ower (MWt) 3250 i l

3.

Licensed Thermal o 4.

Name Plate Rating (Gr oss MWe) 1152 :

5.

Design Electrical Rating (Net MWe) 1030 l 6.

Maximum Dependable Capacity (DROSS MWo) 1056 l l

7.

Maximum Dependable Capacity (Net MWe) 1020 8.

If Changes Occur in Capacity Ratings (Items no. 3 through 7) Gince Last Report G i v e R e a s o n s _ _,_ _ _ _ _ _ _, _ _ _, _ ___ _ _ _ _ _ _ _,_ _ _ _ _ _.,_ _ _.,_ _ _ _ _,._

_ _. _. _ _ _ _. _. _ _.. - _. _. _. _. _. _ _. _ _ _ _. _ _. _. _ _. _ _ _. _ _ _ _ _. _.. _ _. - _ ~ _. _. _ _. _ _ _ _. _ _.

9.

Power Level To Which Restricted. If Any (Net MWe) _. _. _.,, _ _ _ _. _, _ _. _, _ _

10. Reasons For Restrictions. If Anyt___.____________,________.__.,___,._

This Mo.

Yr. to Date Cumm.

11. Hours in Reporting Period 720.0 4343.0 109535.0

12. No. of Hrs. Reactor Was Critical 604 6 3900.7 79734.5

13. Reactor Reserve Shutdown Hours O.O O. O 463.O

14. Hours Generator on Line 593.7 3886.3 78204.9

15. Unit Reserve ShutAwn Hours O.O O.O 321.O

16. Gross Therm. Energy Gen. (MWH) 1635814 10823586 227456094

17. Gross Elect. Energy Gen. (MWH) 507230 3465460 74361330

18. Net Elect. Energy Gen. (MWH) 48537a c.a23568 71520799

19. Unit Service Factor 82.5 89.5 72.7

20. Unit Availability Factor 82.5 89.5 72.7

21. Unit Capacity Factor (MDC Net) 66.1 75.0 65.2

22. Unit Capacity Factor (DER Net) 65.4 74.3 63.0

23. Unit Forced Outage Rate 5.2

8. 5 0.6

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

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

lini.t. c.urrent.1)t_ shutdown fo.r. cycle._9-10._ref unl i g__Es.t i me nd _startup__date.is_ fi-24-87.

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

Forcast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION h p(,

B708190257 870630 PDR ADOCK 05000315 R

PDR_

' AVERAGE DAILY POWER LEVEL (MWe-Not)

DOCKET NO.

50-315 UNIT ONE DATE 7/3/87 COMPLETED BYART TETZLAFF TELEPHONE 616-465-5901

' MONTH JUNE 87 AVERAGE DAILY AVERAGE DAILY DAY POWER LEVEL DAY POWER LEVEL 1

870 17 972 2

878 18 943 3

873 19 922 4

326 20 910 5

60 21 889 6

382 22 873 7

448 23 797 8

738 24 742 9

885 25 733 10 900 26 663 11 901 27 6

12 888 28 0

13 885 29 0

14 877 30 0

15 885 16 977

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DOCKET NO: 50-315 l

1

, UNIT NAME:

D. C. Cook Unit 1 A

COMPLETED BY:

J. L. St. Amand TELEPHONE:

(616)465-5901 s

DATE: July 6, 1987 PAGE:

1 of 2 MONTHLY OPERATING ACTIVITIES - JUNE 19,87 I

HIGHLIGHTS:

The reporting period began with the unit in Mode 1 at 90% power, with

)

operating reserve in effect. On 6-4-87, the reat. tor tripped as a result of a turbine trip on high-high steam generator level. The high-high steam generator level occurred while changing the input channet.from steam generator level to the #2 feedwater regulating valve controller. W e signal was lost, causing the feedwater regulating valve to open fully.

During the subsequent start-up, the reactor was tripped twice while in Mode 3.

Both trips were from the P-7 permissive (automatic reactor trip due to turbine trip if power is greater than 10%) becoming unblocked when valves MM0-402 (the l

! eft moisture separator reheater coil inlet valve), and AM0-12 (reheat steam to feedpump turbine), leaked by, each causing one trip.

j On 6-5-87, the unit was successfully restarted, paralleling the grid at 1916 hours0.0222 days 0.532 hours 0.00317 weeks 7.29038e-4 months . The unit operated at 51% power until system demand increased, at which time the power was increased to 90%, and stabilized at 1245 hours0.0144 days 0.346 hours 0.00206 weeks 4.737225e-4 months on 6-8-87.

On 6-10-87, an unusual event was declared at 1955 hours0.0226 days 0.543 hours 0.00323 weeks 7.438775e-4 months due to a seismic event. The Seismic Monitors registered the event which was later determined to have registered 5.0 on the richter scale. The epicenter was located 55 miles north of Evansville, Indiana. The unusual event was terminated ten minutes after being declared.

On 6-15-87, a power increase was started, reaching 100% at 1030 on 6-16-87.

From 100%, a coastdown was begun until 1900 hours0.022 days 0.528 hours 0.00314 weeks 7.2295e-4 months on 6-26-87, when a power reduction of 8%/ hour was begun. The reactor was subcritical on 6-27-87 at 0253 hours0.00293 days 0.0703 hours 4.183201e-4 weeks 9.62665e-5 months , entering Mede 4 at 1820 hours0.0211 days 0.506 hours 0.00301 weeks 6.9251e-4 months on the same date.

The reporting period ended with the unit in Mode 5 beginning the cycle 9-10 refueling outage.

Gross Electrical Generation for the month of June was 507,230 MWH.

l l

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SUMMARY

6-1-87 0840 hour0.00972 days 0.233 hours 0.00139 weeks 3.1962e-4 months s:

. Unit at 90% power; operating. reserve in effect.

6-4-87 1034 hour0.012 days 0.287 hours 0.00171 weeks 3.93437e-4 months s:

Reactor. trip due to turbine l trip on high-high steam generator level as a result of lost input when switching channels on the #2 feedwater regulating valve controller.

2105 hour0.0244 days 0.585 hours 0.00348 weeks 8.009525e-4 months s:

In Mode 3 with.all rods in, the reactor tripped due to P-7 (Automatic reactor. trip if turbine trips at

>10% power) becoming. unblocked when MM0-402 (left moisture separator reheater inlet valve) leaked

.through.

6-5-87 0538 hour0.00623 days 0.149 hours 8.895503e-4 weeks 2.04709e-4 months s:

In Mode 3 with shutdown banks out, the reactor tripped due to P-7 being reset when AM0-12 (Reheat steani to feedpump turbine) leaked by, pressurizing the system such that a signal was 99nerated indicating the turbine power was greater than 10%.

0853 hour0.00987 days 0.237 hours 0.00141 weeks 3.245665e-4 months s:.

The reactor reached criticality.

'1916 hour0.0222 days 0.532 hours 0.00317 weeks 7.29038e-4 months s:

Paralleled the generator to the grid.

6-6-87 1240 h'urs:

Holding at 51% power, waiting for system demand'to o

increase.

6-8-87

-124t, hours:

Stable at 90% power.

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

An unusual event was declared due to a seismic event.

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

Terminated unusual event.

6-15-87,2025. hours:

Started power increase to 100%.

6-16-87 1030 hour0.0119 days 0.286 hours 0.0017 weeks 3.91915e-4 months s:

Power stable at 100%.

6-17-87 Power. coastdown startcd.

j 6-23-87 2015 hour0.0233 days 0.56 hours 0.00333 weeks 7.667075e-4 months s:

Reactor power at 80%.

6-26-87 1900 hour0.022 days 0.528 hours 0.00314 weeks 7.2295e-4 months s:

Started decreasing power at 8%/hr.

j 6-27-87 0253 hour0.00293 days 0.0703 hours 4.183201e-4 weeks 9.62665e-5 months s:

Reactor is subcritical.

j 1820 hour0.0211 days 0.506 hours 0.00301 weeks 6.9251e-4 months s:

Unit is in Mode 4, beginning cycle 3-10 refueling outage.

6-29-87 '0523 hour0.00605 days 0.145 hours 8.647487e-4 weeks 1.990015e-4 months s:

Mode 5.

F

. r, 1

DOCKET NO.

50-315 UNIT NAME D. C. Cook - Unit No. 1 DATE July 6, 1987 COMPLETED BY J. L. St. Amand TELEPHONE (616) 465-5901 PAGE 1 of 1 MAJOR SAFETY-RELATED MAINTENANCE JUNE, 1987 M-1 The #1 Boric Acid Transfer pump mechanical seal and casing gasket were replaced after being found leaking.

The pump was successfully operability tested prior to returning to service.

9'

-y pcs e

i c.

v5 tem--lNOS5$$ M}CHlGAKELECTRIC_COMMNY DONALD C. COOK NUCLEAR PLANT P.O.' Box 458, Bridgman, Michigan 49106 (616) 465-6901

. July 6,,1987 Director, Offi n 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 1. Technical Specification 6.9.1.10, the attached Monthly Operating Report for the Month of June, 1987 is submitted.

Sincerely,.

h W..G.

Smith, Jr.

Plant Manager..

' WGS/jd cc:

.J. E. Dolan.

M. P. Alexich R. W. Jurgersen R. O. Bruggee R.'C. Callen C. A. Erikson i

D. W. Paul I

D. R. Hahn i

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 6' &

- -

ML20237K442

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