ML20237K351

Monthly Operating Rept for Apr 1987

ML20237K351
Person / Time
Site:	Cook
Issue date:	04/30/1987
From:	Climer, Will Smith, St Amand J INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	NRC
References
NUDOCS 8708190214
Download: ML20237K351 (8)

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• N.R.C. OPERATING DATA REPORT 1% "

DOCKET NO. 50-316 DATE 5/4/87 s COMPLETED BY CLIMER V TELEPHONE 616-465-5901 OPERATING STATUS

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

2. Reporting Period APRIL 87 inotes l

3. Licensed Thermal Power (MWt) 3411 l l

4. Name Plate Rating (Gross MWe) 1133 l l

5. 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-

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This Mo. Yr. to Date Cumm.

11. Hours in Reporting Period 719.0 2879.0 81767.0

12. No. of Hrs. Reactor Was Critical 230.6 1718.7 5630S.0

13. Reactor Reserve Shutdown Hours 0.0 0.0 0.0

14. Hours Generator on Line 233.5 1711.9 54955.2

15. Unit Reserve Shutdown Hours 0.0 0.0 0.0

16. Gross Therm. Energy Can. (MWH) 456573 4431550 170122753

17. Gross Elect. Energy Gen. (MWH) 143540 1468280 55686320

18. Net Elect. Energy Gen. (MWH) 135020 1405078 53639914

19. Unit Service Factor 32.5 59.5 69.3

20. Unit Availability Factor 32.5 59.5 69.3

21. Unit Capacity Factor (MDC Net) 17.7 46.0 63.8

22. Unit Capacity Factor (DER Net) 17.1 44.4 62.3

23. Unit Forced Outage Rate 67.5 40.5 15.8

24. Shutdowns Scheduled over Next Six Months (Type,Date,and 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 j i 1 I l l 1 l l 8708190214 870430 1 gDR ADOCK0500pgg6 bF _ ]

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i , DOCKET NO: 50-316 UNIT NAME: D.C. Cook Unit 2 COMPLETED BY: 'J. L. St. Amand TELEPHONE: (616) 465-5901 DATE: May 8,1987 PAGE: 1 of 2 MONTHLY OPERATING ACTIVITIES - APRIL 1987 HIGHLIGHTS The reporting period began with the unit in Mode 5 at half-loop, after being shutdown due to increasing primary to secondary leakrates. After plugging several steam generator tubes, the unit start-up was delayed by control rod malfunctions. A connector on the reactor head was repaired and the unit successfully restarted, reaching the 80% administrative limit imposed to minimize steam generator tube leaks on 4-29 87. The reporting period ended with the unit in Mode 1 at 80% power. Gross Electrical Generation for the month of April was 143,540 MWH.

SUMMARY

4-1-87 The unit was in Mode 5, with the reactor coolant system at half-loop. 4-8-87 2130 - Started filling and venting the reactor coolant system. 4-12-87 1426 - Completed filling and venting. 2142 - Reactor coolant system oxygen within specifications; began heat-up for mode change. 2303 - Mode 4 entered. 4330 - Started steam generator crevice flushing. 4-15-87 0355 - Completed crevice flushing. 2337 - Mode 3 entered. 4-17-87 0220 - Began pulling shutdown banks. 0259 - All shutdown banks out. 4-18-87 0125 - Reactor start-up commenced; began pulling rods. 0138 - Stopped pulling rods; rod H-10 in bank A indicating 154 steps, remaining rods at 228 steps. 0611 - Control bank A rods on bottom. 4-20-87 1856 - Reactor start-up commenced. 4-21-87 0023 - Reactor is critical.

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) ;;:' ' ' 0631 - Turbine paralleled. j h 0655 - Reactor at 20% power. 3 0715 - Reactor at 25% power. 0852 - Began increasing power at 3%/ hour. 1216 - Holding at 33% power for steam generator chemistry and boric acid soak. 4-25-87 1137 - Segan power increase to 48% at 3%/ hour. 1721 - Chemistry for 48% power level 0K, increasing to 80% at 3%/ hour. 2030 - Holding at 56% power due to >2% (2.06) difference between N-42, power range instrumentation; indication and thermal power program. ) 2155 - N-42 coarse gain adjusted, ir. creasing to 80% power at 3%/ hour. 4-26-87 0512 - Holding at 78% power to adjust nuclear instrumentation, then increasing to just under 80% until chemistry approved for >80%. 4-29-87 0930 - Began increasing power-to 80.5%. 0955 - Holding at E0.5% power. The reporting period ended with the unit in Mode 1 at 80% power. 1 i j

DOCKET NO. 50-316 UNIT NAME D. C. Cook - Unit No. 2 DATE May 7, 1987 COMPLETED BY J. L. St. Amand TELEPHONE (616) 465-5901 PAGE 1 of 2 MAJOR SAFETY-RELATED MAINTENANCE APRIL, 1987 M-1 Removed an object from the #22 steam generator hotleg found lodged in the row 3 column 5 tube. The object was determined to be a tube plug missing from the row 40 column 39 tube. Repaired both tubes, prior to returning to service. M-2 A total of 110 steam generator tubes were plugged following eddy current inspection of all steam generators. Repairs were required due to high primary - secondary leakrates experienced prior to shutdown. 1 M-3 Upon opening the #21, #22, and #23 steam generators for inspection, I the primary manway bolt holes.were found damaged. The damage was  ; repaired by helicoiling affected bolt holes and replacing studs. l l M-4 During testing, the #2 hydrogen recombiner was found to have the #5 ) heater bank incorrectly wired. The heater was rewired correctly and l verified to be operating acceptably before returning to service. M-5 Several component cooling water pipe weld cracks were repaired after being identified by ISI hydro testing.  ; M-6 The pressurizer pressure relief valves, NRV-153 and NRV-152 were , found leaking. The valves were repaired and returned to service. I&C-1 A steamflow/feedflow mismatch alarm was received for steam generator

             #22 with flow indications reading near zero. A defective amplifier

! in feedwater flow transmitter FFC-220 was replaced, calibrated, and proper flow indication verified. j

18C-2 The #21 steam generator high-high level channel II trip and low-low channel II trip bistable was found to be defective. The bistable was replaced, calibrated, and tested before returning to service. I&C-3 One of 3 reactor Coolant system loop 2 flow indications was reading 3% different than the other two. The I/I repeater for NFP-221 was found to be drifting and unable to maintain calibration. The repeater was replaced, calibrated, and verified to operate correctly ' before returning to service. l i l i i

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l r, d~?# l f.^n ca - Th (_s;;L waisnApicmasyjacisc_couenyy DONALD C. COOK NUCLEAR PLANT P.O. Box 458, Bridgman, Michigan 49106 l (616) 465-5901 May 8, 1987 l Director, Office Of Management Information and Program Control U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Gentlemen: l Pursuant to the requirements of Donald C. Cook Nuclear Plant Unit 2 Technical Specification 6.9.1.10, the attached Monthly Operating Report for the Month of i April, 1987 is submitted. Sincerely, LA).Cn W - W. G. Smith, Jr. Plant Manager WGS/jd i cc: J. E. Dolan i 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 INPO Records Center ANI Nuclear Engineering Department T. R. Stephens NRC Region III B. L. Jorgensen S L. Hall D. A. Timberlake r}' \ x j}}