ML20137V082

Monthly Operating Rept for Nov 1985

ML20137V082
Person / Time
Site:	Cook
Issue date:	11/30/1985
From:	Bruck D, Climer, Svensson B INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
NUDOCS 8602190421
Download: ML20137V082 (9)

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. i N.R.C. OPERATING' DATA REPORT-DOCKET NO. 50-315 DATE 12/3/85 COMPLETED BY CLIMER.

TELEPHONE 616-465-5901 OPERATING STATUS

1. Unit Name D. C. Cook Unit 1 ---== - ------------

'2. Reporting Period NOV B5 Inotes  !

3. Licensed Thermal-Power (MWt) 3250-l  !

4. Name Plate Rating (Gross MWe) 1 1152 I t

5. Design Electrical Rating (Net NWe) 1030 t t

6. Maximum Dependable Capacity (GROSS MWe) 1056 I t

7. Maximum Dependable Capacity (Not MWe) 1020 --

8. If Changes Occur in Capacity Ratings (Items no. 3 through 7) Since Last Report Give Reasons __ _ - _ _ _ -----------------

- - = = ---

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. - - - - - - - - - - - - - - - - - = - _ - - - - = = - - - - - - - - - - - - - - = .

9. Power Level To Which Restricted. If Any (Net MWe) _________________

10. Reasons For Restrictions. If Any:______ ____ ______ _------_

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This Mo. Yr. to Date Cumm.

11. Hours in Reporting Period 720.0 8016.0 95688.0

12. No. of Hrs. Reactor Was Critical 294.6 2162.6 67856.4

13. Reactor Reserve Shutdown Hours 0.0 0.0 463.0

14. Hours Generator on Line 213.1 2069.3 66430.8

15. Unit Reserve Shutdown Hours 0.0 0.0 321.0

16. Gross Therm. Energy Gen. (MWH) 297751 5716272 193885776

17. Gross Elect. Energy Gen. (MWH) 86040 1847800 63619770

18. Net Elect. Energy Gen. (MWH) 78548 1773401 61204496

19. Unit Service Factor 29.6 25.8 70.8

20. Unit Availability Factor 29.6 25.8 70.8

21. Unit Capacity Factor (MDC Net) 10.7 21.7 64.0

22. Unit Capacity Factor (DER Net) 10.6 21.5 61.6

23. Unit Forced Outage Rate 3o.3 5.5 7.4

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

25. Ii"5huI~Do n At 5nd'Ei RepoEt PeFI5d, 5AtINAt$d Date of StIrtup:~

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UNIT SHUT DOWN FOR VALVE REPAIRS, EXPECTED STARTUP 12/13/85

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

Forcast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION DR k

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AVERAGE DAILY POWER LEVEL (MWe-Net)

DOCKET NO. 50-315 UNIT ONE DATE 12/3/85 COMPLETED BY CLIMER TELEPHONE 616-465-5901 MONTH NOV B5 AVERAGE DAILY AVERAGE DAILY l DAY POWER LEVEL DAY ' POWER LEVEL 1 0 17 138 2 0 18 207 3 0 19 210 l

4 0 20 204 5 0 21 391 6 0 22 427~

7 0 23 431 8 0 24 616 9 0 25 636 10 0 26 0 11 0 27 0 12 0 28 O 13 0 29 0 14 0 30 0 15 0 31 0 16 13 d

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e IMM KET No. 50-315 llNITSilllllWIWNS ANilPOWEM ItElstR TIONS UNIT NAME D.C. Cook - Unit 1 IDA1E 12-6-85 COMPI ETEll gy B.A. Svensson Movember, 1985 Itiroit's MONiil 1El.FrlHINE 616/465-5901 .

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246 850406 S 382.1 B&C 2 N.A. ZZ ZZZZZZ The Unit was removed from service on Cont'd .

850406 for the scheduled Ten-Year ISI and Cycle VIII - IX Refueling /

Maintenance outage.. The outage work has been completed and initial criticality for Cycle V occurred on

. 851113. Low power physics testing was completed on 851115 and the Unit was paralleled to the System at 2206 hours0.0255 days <br />0.613 hours <br />0.00365 weeks <br />8.39383e-4 months <br /> on 851116. The reactor power was increased to 30% for turbine warming prior to overspeed testing.

The total length of the outage was-5395.7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br />.

247 851117 S 3.5 B 1 N.A. ZZ ZZZZZZ At 1517 hours0.0176 days <br />0.421 hours <br />0.00251 weeks <br />5.772185e-4 months <br /> the Unit was removed ,

from service for turbine overspeed testing. The Unit was returned to service at 1850 hours0.0214 days <br />0.514 hours <br />0.00306 weeks <br />7.03925e-4 months <br /> the same day.

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INN:KEI NO. 50-315' - .

IINST SlHilllOWNS ANilrowl:H NElllfrilONS IINITNAME D.C. Cook - Unit 1 IBA1E 12-6-85 COMPI ETEll hy B.A. Svensson November, 1985 NI FOlll HinN HI 1EI.EPllONE 616/465-5901 PAGE 2 of 2 .

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due to a reactor trip.

248 851125 F 121.3 B 3 Latdr ZZ ZZZZZZ A reactor trip occurred from 78% re-actor power due to a negative rate trip. The trip resulted from one power range channel's bistable being

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in the tripped position for surveil-lance testing and a spurious signal on a second power range channel while taking detector current read-ings for quadrant power tilt deter-mination. During a containment in-spection after the reactor trip, a-leak was discovered on No. 12 R.C.

Pump casing flange. To repair the ,

leak, the RCS had to be cooled down and' drained to half-loop. The Unit remained shut down in Mode 5 at the end of the month.

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.. Dockst No.: 50-315 Unit N me =D.C. Cook Unit 1 Completed By: D. A. Bruck Telephone: (616) 465-5901 Date: December 9, 1985 Page: 1 of 3 MONTHLY OPERATING ACTIVITIES - NOVEMBER, 1985 HIGHLIGHTS:

The reporting period began with the reactor' coolant system in Mode 3 and 536*F temperature.

The low power physics testing began on 11-13-85 with the reactor being critical for the first time in Cycle IX at 1605 hours0.0186 days <br />0.446 hours <br />0.00265 weeks <br />6.107025e-4 months <br />. The low power physics testing was completed at 2300 hours0.0266 days <br />0.639 hours <br />0.0038 weeks <br />8.7515e-4 months <br /> on 11-15-85 and the generator was paralleled to the grid at 2206 on 11-16-85.

On 11-17-85, the unit was removed from service to perform turbine overspeed testing. The unit was returned to service the same-day.

On 11-20-85, reactor power was increased to 48%. On 11-24-85, reactor power was increased to 68%. On ll-25-85, a reactor power increase to 80% began. A reactor trip occurred from 78% due to an inadvertant negative rate trip.

On 11-26-85, a reactor coolant system cooldown was started to repair leaks on the No. 12 reactor coolant pump flange. Mode 4 was entered on 11-26-85 and Mode 5 was entered on 11-27-85.

The reporting period ended with the reactor coolant system in Mode 5, cold shutdown.

Gross electrical generation for the month of November was 86,040 MWH.

SUMMARY

11-04-85 At 1631, an inadvertant source range reactor trip, while in Mode 3 occurred while performing surveillance tests.

11-06-85 At 0251, the Turbine Driven Auxiliary Feed Pump failed to start for surveillance testing due to erratic governor control.

11-09-85 At 0548, the Turbine Driven Auxiliary Feed Pump was declared operable.

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> 'UnitLNemes D.C. Cook-Unite 11 Completed By: D. A. Bruck

Telephone: (616)1465-5901-Date: December 9, 1985 Page:~ 2 of 3-

11-12-85 At 0230, a' turbine trip-occurred while in Mode 3,fdue to Hi-Hi steam generator ~ level.

At 1024, an inadvertantiESF actuation from highLateam line flow coincident with Lo-Lo Tave occurred which resulted infa safety injection actuation and' steam;line +

isolation. The cause was simultaneous surveillance testing of high steam line flow channels requiring bistables to be tripped and an auxiliary feedwater ,

system test adding _ water to the steam generators, resulting in RCS cooldown to the Lo-Lo Tave value, 11-13-85 At'1605, the reactor-became critical for the first time in Cycle IX.

11-14-85 At 0915, a power' increase began,; stabilizing at 2% at 1150. "

11-15-85 At 2300, low power physics testing was completed.

11-16-85 At 1300, a power increase began and the reactor entered ,

Mode 1 at 1320.

At 1426, the main turbine was rolled.

At 1540, the main turbine experienced high vibration and a shutdown was begun.

At 1555, the main turbine tripped on high vibration.

At 2000, a power increase began and the reactor entered Mode 1 at 2018.

At 2050, the main turbine was rolled.

At 2206, the generator was paralleled to the grid.

11-17-85 At 0150, the power increase stopped at 30%.

At 0210, a unit shutdown was begun <per Tech. Spec.

3.0.3 due to MFC-110'and MFC-111 being inoperable.

At 0436, MFC-110 was declared operable and a power increase began, stabilizing at'29% at 0720. .

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, Dock;t No.: 50-315 Unit N:me: D.C. Cook Unit 1 Completed.By: D. A. Bruck Telephone: (616) 465-5901 Date: December 9, 1985 Page: 3 of 3 11-17-85 At 1250, a reactor power decrease to perform turbine overspeed testing began.

At 1415, an inadvertant Engineered Safety Features actuation occurred due to high alarms on containment radiation monitors 1401 and 1409.

At 1517, the generator was disconnected from the grid to perform turbine overspeed testing.

At 1532, the turbine tripped on high vibration.

At 1850, the generator was paralleled with the grid and power was stabilized at 29% at 0100.

11-20-85 At 1900, the Turbine Driven Auxiliary ree:1 Pump was declared inoperable due to governor oil leaking.

At 2245, a power increase began, stabilizing at 48% at 0534.

11-23-85 At 1312, the Turbine Driven Auxiliary Feed Pump was declared operable.

11-24-85 At 0006, a power increase began, stabilizing at 68% at 0924.

11-25-85 At 1850, a power increase to 80% began.

At 2243, with reactor power at 78%, the reactor tripped due to a negative rate trip. The trip resulted from one NIS power range channel's bistables being in the tripped position for surveillance testing and a spurious signal on a second power range channel while taking detector current readings for quadrant power tilt determination. A At 2300, the Turbine Driven Auxiliary Feed Pump was declared inoperable due to a broken control air line to the speed controller.

11-26-85 At 1623, a cooldown of the re' actor coolant system was started, entering Mode 4 at 2220.

11-27-85 At 1854, the reactor coolant system entered Mode 5.

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DOCKET'NO. 150 - 315 UNIT NAME D. C. Cook - Unit'No. 1~.

DATE 6 COMPLETED BY .B. A. Svensson-TELEPHONE. (616) 465-5901 3 PAGE 1 of 1 l

MAJOR SAFETY-RELATED MAINTENANCE

-1 NOVEMBER, 1985 M-1 Reactor trip bypass breaker "B" would not close when racked into the test position. The fuse block. stabs were found to be spread open. The gap between the stabs was closed and the fuse block-reinstalled. The breaker now operates properly.

! M-2 Turbine Driven _ Auxiliary Feed Pump Trip and Throttle Valve was leaking by. Replaced internals and bonnet. Valve tested okay l after repsirs.

M-3 Found water in oil supply for Turbine Driven Auxiliary Feed Pump l governor. Removed governor, drained and flushed system. New governor was installed temporarily. Old governor was repaired by manufacturer and reinstalled on November 23, 1985.

C&I-l NIS, source range channel N-31, was reading erratic. Found source range preamplifier bad. Replaced source range preamplifier with new preamplifier. Performed' source range calibration and surveil-lance test and declared N-31 operable.

l C&I-2 Reactor coolant wide range Thot on loop 2 has a large deviation l compared to the other three loops.

Found R/I NTR-220, I/I NTR-120A and recorder out of calibration.

Recalibrated R/I, I/I and recorder. I/I NTR-120 could not be calibrated and had to be replaced. Loop 2 now agrees.with the other three loops.

C&I-3 Loop 1 wide range That is reading 20*F higher than the other three channels.

i Found R/I NIR-110 to be out of calibration high. Recalibrated the I/I. The four channels now agree with each other.

C&I-4 NPP-152, pressurizer pressure indication channel 11 is reading 35 to 40 psig lower than the other two channels.

Transmitter was found to be out of specification and could not be brought within specifications. Replaced with new transmitter; recalibrated and returned to service.

C&I-5 Steam generator #1 steam flow indication channels MFC-110 and 111 I were exhibiting low readings. The square root extractor for MFC-110 was replaced and MFC-lll's transmitter was recalibrated to restore correct flow indication to the channels.

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Donald C. Cc3 Nucteer Plant P.o. Som 450, Bridgman. Mchgen 49106 i

Jecccher 6, 1985 i Director, Office Of Managemt.nt Information and Program Control U. S. Nuclear Regulatory Commission Washington, D. C. 205'55 Gentlemen:

Pursuant to the requirements of Donald'C. Cook Nuclear Plant Unit 1 Technical Specification 6.9.1.6, the attached Monthly Operating Report for the Month of November, 1985 is submitted.

Sircerely, t

W. G.

Yh' dth, Jr.

Plant rianager WGS:ab

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Attachments l

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x cc: J. E. Dolan 9 \

M. P. Alexich '-

R. W. Jurgensen NRC Region III B. L. Jorgensen R. O. Bruggee

, R. C. Callen y SS. J. Hierzwa

• F. S. VanPelt, Jr.

P. D. Rennix ,

D. R. Hahn Z. Cordero J. J. Markowsky J. F. Stietzel PNSRC File INPO Records Center-ANI Nuclear Engineering Department

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