ML20237J360

Monthly Operating Rept for Jul 1987

ML20237J360
Person / Time
Site:	Braidwood
Issue date:	07/31/1987
From:	Fitzpatrick E, Peacock B COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
(4957Z-90Z), EEF-87-1151, NUDOCS 8708180119
Download: ML20237J360 (8)

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l BRAIDWOOD NUCLEAR POWER STATION UNIT 1 MONTHLY PERFORMANCE REPORT COMMONWEALTH EDIS0N COMPANY  ;

NRC DOCKET NO. 050-456 LICENSE NO. NPF-72 8708100119 870731 PDR ADOCK 05000456 R PDR (4957z/90z)

, LL. Monthly Report for Braidwood Unit 1 A. Summary of Ooeratina Exoerience The unit entered the month of July in' Mode 2. On July 1, the unit was shutdown due to rod control problems. Mode 2

was reentered on July 3. On-July.5, a manual reactor trip-was initiated'after an inadvertent. opening of the control

' rod drive motor generator breakers caused the control rods to de-energize and insert into the core. . Mode 2~was re-entered on July 7. Initial synchronization to the grid took place on July 12 and turbine power was increased to

.approximately 10%. . On July 15, a planned turbine trip was

-undertaken as part of testing. On July 19, a normal unit shutdown and cooldown was initiated.to repair the 1B diesel generator and to perform other maintenance activities. Mode 2 was-re-entered on July 30. The unit

.was again synchronized to the grid on July 31 and remained at 6% turbine power through the end of the month.

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B. OPERATING DATA REPORT DOCKET NO.: 50-456 UNIT: Braidwood 1 DATE: 08/10/87 COMPILED BY: B. M. Peacock TELEPHONE: (815)458-2801 ext. 2480 i

OPERATING STATUS

1. Reporting Period: July, 1987 Gross Hours: 480.0

2. Currently Authorized Power Level (MWt): 3411  ;

Design Electrical Rating (MWe-gross): 1175 l Design Electrical Rating (MWe-net): 1120 Max Dependable Capacity (MHe-gross): 1175 Max Dependable Capacity (MWe-net): 1120

3. Power level to which restricted (If Any): None

4. Reasons for restriction (If Any): None THIS MONTH YR TO DATE CUMULATIVE

5. Report period Hours: 480.0 480.0 480.0

6. Hours Reactor Critical: 225.4 225.4 225.4

7. RX Reserve Shutdown Hours: 0.0 0.0 0.0

8. Hours Generator on Line: 74.2 74.2 74.2

9. Unit Reserve Shutdown Hours: 0.0 0.0 0.0

10. Gross Thermal Energy (MWH): 64085 64085 64085

11. Gross Elec. Energy (MHH): 7185 .J185 7185

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12. Net Elec. Energy (MWH): 0.0 0.0 0.0

13. Reactor Service Factor: N/A N/A N/A

14. Reactor Availability Factor: NUL_ N/A N/A

15. Unit Service Factor: N/A __ N/A N/A

16. Unit Availability Factor: N/A N/A N/A

17. Unit Capacity Factor (MDC net): N/A N/A N/A

18. Unit Capacity Factor (DER net): N/A N/A N/A

19. Unit Forced Outage Rate: N/A N/A N/A

20. Unit Forced Outage Hours: 405.8 405.8 405.8

21. Shutdowns Scheduled Over Next 6 Months:

22. If Shutdown at End of Report Period, Estimated Date of Startup: _

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23. Units in Test Status (Prior to )

Commercial Operation): l

, FORECAST ACHIEVED Initial Criticality 05/23/87 05/29/87 l Initial Electricity 07/11/87 07/12/87 i Commercial Operation 09/26/87 I l

(4957z/902)

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. C. AVERAGE DAILY UNIT NET POWER LEVEL LOG DOCKET NO.: 50-456 UNIT: Braidwood 1.

l DATE: 08/10/87.

. COMPILED BY: B. M. Peacock TELEPHONE: (815)458-2801 ext. 2480

' MONTH: July, 1987 l- 1. N/A 17. 0 2 ~. N/A 18. 0

3. N/A 19. 0 l 4. N/A 20, 0

5. N/A 21. O _

6. N/A' 22. O _

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7. N/A 23. O _

8. N/A 24. 0

9. N/A 25. 0

10. N/A 26. 0

11. N/A 27. 0-

12. 0 28. 0

13. 79 29. 0 14, 67 30. 0

15. 0 31. 21

16. O l INSTRUCTIONS On this form list the average daily unit power level in MWe-Net for each day in the reporting month. Compute to the nearest whole megawatt. l These figures will be used to plot a graph for each reporting month.

Note that when maximum dependable capacity is used for the net electrical rating of the unit there may be occasions when the daily average power level exceeds the 1001. line (or the restricted power level line). In such cases the average daily unit power output sheet should be footnoted to explain the apparent anomaly.

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. F. LICENSEE EVENT REPORTS The following is a tabular summary of all Licensee Event Reports submitted during the reporting period, July 1 through July 31, 1987.

This information is. provided pursuant to the reportable occurrence

' reporting requirements as set forth in 10 CFR 50.73.

Licersee Event Report Report Number Daig Title of Occurrence 87-025-00 07/01/87 Inadvertent opening of main steam isolation valve during maintenance activities due to procedural error.

87-025-01 07/29/87 Inadvertent opening of main steam isolation valve during maintenance activities due to procedural error.

87-027-00 07/01/87 Reactor trip signal generated during solid state protection system logic testing due to a procedural deficiency.

87-029-00 07/14/87 Missed technical specification surveillance due to procedural-deficiency.

87-031-00 07/02/87 Control room ventilation shift to ,

the emergency makeup mode as a '

result of spurious actuation of a radiation monitor due to inadvertent radio operation.

87-032-00 07/22/87 Manual reactor trip due to loose connections and bad fuses in a rod control disconnect switch cabinet.

87-033-00 07/29/87 Control room ventilation system inoperable due to inadvertent de-energized damper.

87-034-00 07/29/87 Analysis frequency exceeded due to data storage limitations in the counting room computer.

87-036-00 07/29/87 Missed circulation water blowdown composite sample due to inadequate procedure.

(4957z/90z)

/. N Commonw:cith Edis:n I

) Braidwood Nuclear Pow r Stition

'! m I, Routa C1, Box 84

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' / Braceville, Illinois 60407 N / Telephone 815/458-2801 l

EEF/87-1151 August 10, 1987 i

Director, Office of Resource Management United States Nuclear Regulatory Commission Washington, D.C. 20555 ATTN: Document Control Desk j Gentlemen: l Enclosed for your information is the Monthly Performance Report covering Braidwood Nuclear Power Station for the period July 1 through July 31, 1987. j Very truly yours, E. E. Fitzpa[ trick Station Manager  !

Braidwood Nuclear Power Station EEF/RCB/mjv (49572) l I

i Attachments cc: A. B. Davis, NRC, Region III NRC Resident Inspector Braidwood Gary Wright, Ill. Dept. of Nuclear Safety T. J. Maiman K. L. Graesser L. D. Butterfield  !

Nuclear Fuel Services, PHR Plant Support l L. Anastasia, Station Nuclear Engineering  ;

INPO Records Center  :

Performance Monitoring Group, Tech Staff Braidwood Station Nuclear Group, Tech Staff Braidwood Station J. Stevens - USNRC P. L. Barnes .

(4957z/90z)  !

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