ML20206D996

Monthly Operating Rept for Mar 1986

ML20206D996
Person / Time
Site:	Cook
Issue date:	03/31/1986
From:	Climer, Will Smith, Svensson B INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
NUDOCS 8606230037
Download: ML20206D996 (7)

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N.R.C. OPERATING DATA REPORT DOCKET NO. 50-316 DATE 4/1/86 COMPLETED BY CLIMER TELEPHONE 616-465-5901 OPERATING STATUS

1. Unit Name D. C. Cook Unit 2 -----------=-- ----

2. Reporting Period MAR 86 : notes

3. Licensed Thermal Power (MWt) 3411 :  :

4. Name Plate Rating (Gross MWe) 1133 :

5. Design Electrical Rating (Net MWe) 1100 :

6. Maximum Dependable Capacity (GROSS MWe) 1100 :  :

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 744.0 2160.0 72288.0

12. No. of Hrs. Reactor Was Critical O.0 1352.6 50381.4 -

13. Reactor Reserve Shutdown Hours 0.0 0.0 0.0

14. Hours Generator on Line 0.0 1272.5 49126.1

15. Unit Reserve Shutdown Hours O.0 0.0 0.0

16. Gross Therm. Energy Gen. (MWH) O 3404597 154675207

17. Gross Elect. Energy Gen. (MWH) 0 1097780 50784370

18. Net Elect. Energy Gen. (MWH) 0 1053472 48954840

19. Unit Service Factor 0.0 58.9 70.4

20. Unit Availability Factor 0.0 58.9 70.4

21. Unit Capacity Factor (MDC Net) 0.0 46.0 66.2

22. Unit Capacity Factor (DER Net) 0.0 44.3 64.7

23. Unit Forced Outage Rate 0.0 9.9 15.7

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

-. = - -

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

SHUT DOWN FOR REFUELING. ESTIMATED STARTUP JUNE 1, 1986

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

Forcast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION 8606230037 860331 .

PDR ADOCK 05000316 R PDR LE3M

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AVERAGE DAILY POWER LEVEL (MWe-Net)

DOCKET NO. 50-316 UNIT TWO' DATE 4/1/86 COMPLETED BY CLIMER TELEPHONE 616-465-5901 MONTH MAR 86

! AVERAGE DAILY AVERAGE DAILY DAY POWER LEVEL DAY POWER LEVEL 1 0 17 O l 2 0 18 0 1 3 0 19 0 4 0 20 0 5 0 21 0 6 O 22 0 I  ;

7 O 23 0 8 0 24 0 9 O 25 0 10 0 26 0 .

_ 11 0 27 0 12 0 28 O 13 0 29 O 14 0 30 0 15 0 31 0 16 O J

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IMHJKE I NO. 50-316 UNITSiltlillOWNS ANilNIWI.H HlillifrIlONS UNil NAME D.C. Cook, Unit 2 .

HAIE 4-8-86 UPMPI Ellip ley B.A. Svensson March, 1986 HI POH I MONilg 1EI.I PilONE 616/465-5901 SHEET 1 of 1 u

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172 860228 s 744 B&C 1 N.A. ZZ ZZZZZZ The Unit was removed from service on 860228 for Cycle 5-6 Refueling Outage. In addition to the refuel-ing activities, major maintenance work includes steam generator eddy current testing, control rod guide tube split pin replacement, re-placement of the main feedpump tur-bine condensers, replacement of 4

PCB oil cooled transformers and re-placement of vital instrument bus inverters. The estimated return to

service date is June 1, 1986.

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Docket No.: 50-316 Unit Names D.C. Cook Unit 2 l

Completed By: A. S. Puplis Telephone: (616) 465-5901

! Date: April 7, 1986

, Page: 1 of 1 MONTHLY OPERATING ACTIVITIES - MARCH, 1986 l

• 8 HIGHLIGHTS:

1, The reporting period began with the reactor in Mode 3 and the j Reactor Coolant System (RCS) temperature at 510*F prior to cooling down to Mode 5. The reporting period ended with the i reactor in Mode 6.

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SUMMARY

03-01-86 At 0243, a RCS depressurization was started.

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At 0325, an RCS cooldown to 335*F was started.

At 0560, NRC notification was made regarding an inoper-

able Turbine Driven Auxiliary Feed Pump.

At 0628, the RCS was placed in Mode 4.

03-02-86 At 1655, the RCS was placed in Mode 5.

i At 2200, No. 3 Boric Acid Transfer Pump was declared

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inoperable because of tripping on thermal overloads.

! 03-11-86 At 1305, inadvertant reactor trip signals were

! generated while removing a power range nuclear ,

i instrumentation drawer for cleaning due to a short circuit in the drawer.

1 l 03-19-86 At 1818, the reactor was place in Mode 6, Refueling.

03-25-86 At 2025, an Engineered Safety Feature Train B Safety

Injection actuation was received. The inadvertant j actuation was due to a personnel error while 1 troubleshooting the turbine impulse-pressure interlock (permissive).

s 03-27-86 At 0006, the reactor vessel closure head was lifted and placed on its storage stand.

At 2227, the upper reactor internals were removed, j 03-28-86 At 0418, the reactor vessel head was placed on the i reactor vessel to permit draining the refueling cavity j to repair the refueling cavity water seals.

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, DOCKET NO. 50 - 316 I

UNIT NAME D. C. Cook - Unit No. 2 DATE 4-8-86 COMPLETED BY B. A. Svensson TELEPHONE (616) 465-5901 PAGE 1 of 2 MAJOR SAFETY-RELATED MAINTENANCE MARCH, 1986 M-1 CCW-245-72 and CCW-246-72, Component Cooling Water Check Valves in piping to Containment Penetrations CPN-3 and CPN-4, exhibited leakage in excess of B&C and IST guidelines. . Valve seats were cleaned and lapped and the valves retested satisfactorily.

M-2 Flex conduit on IM0-911, Refueling Water Storage Tank to Charging Pump Suction Header Isolation was crushed. Conduit was replaced and IMO-911 tested satisfactorily.

i M-3 Valve Number CCR-440 in Component Cooling Water Return Line from

] Containment Penetration Cooling Coils was leaking by in excess l of seat leak test guidelines. Valve was repaired and tested satisfactorily.

M-4 MRV-231 and MRV-232, Dump Valves for #3 Main Steam Stop Valves had seat leakage. Replaced internals in both valves. Both valves were tested and returned to service.

C&I-1 XCR-103, Control Air to Containment Isolation Valve ASCO Solenoid Valve would not close and air continues to vent off the exhaust port of the ASCO Solenoid Valve when control switch is turned to closed position. The ASCO Solenoid Valve was rebuilt and XS0-103, Proper Valve Operation was verified.

C&I-2 ECR-32, Containment Isolation Valve for ERS-2300 failed to close completely when valve was cycled for ISI stroke time.

i The Valve Stem was found binding on packing gland. Adjusted packing gland and verified that valve stroked correctly.

C&I-3 The ASCO Solenoid Valves for Containment Isolation Valves CCR-440,

, WCR-921, WCR-948, WCR-958 and WCR-954 have failed to a position where they continuously bleed off control air. The ASCO Solenoid Valves were rebuilt and correct valve stroke verified.

C&I-4 WCR-951, would not open when control switch was turned to open.

The ASCO Solenoid Valve, XS0-951, was rebuilt and proper valve operation was verified.

t C&I-5 ECR-31, containment Isolation Valve for ERS-2300 failed to close

)- completely during performance of Type C leak rate test. The ASCO Solenoid Valve was stuck and was both venting and supplying air to ECR-31. The ASCO Solenoid Valve, XS0-31 was rebuilt and proper valve stroke was verified.

DOCKET NO. 50 - 316 '

UNIT NAME D. C. Cook - Unit No. 2 DATE 4-8-86 COMPLETED BY B. A. Svensson TELEPHONE (616) 465-5901 PAGE 2 of 2 MAJOR SAFETY-RELATED MAINTENANCE MARCH, 1986 C&I-6 ASCO Solenoid Valve, XS0-921 for containment Isolation Valve, WCR-921 leaks through. Rebuilt ASCO Solenoid Valve, XS0-921 and verified that WCR-921 operated correctly.

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• g meresen ystent INOMNA &_MMMAN ELKMC10WAM Donald C. Cook Nuclear Plant P.O. Box 458, Brdgman, Michgan 49106 April 8, 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 March, 1986 is submitted.

Sincerely, k' hl 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 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 M

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