ML20236Q164

Monthly Operating Rept for Oct 1987

ML20236Q164
Person / Time
Site:	Braidwood
Issue date:	10/31/1987
From:	Fitzpatrick E, Peacock B COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
(4957Z), EEF-87-1716, NUDOCS 8711190219
Download: ML20236Q164 (8)

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l BRAIDH000 NUCLEAR P0HER STATION UNIT 1 MONTHLY PERFORMANCE REPORT COMMONWEALTH EDISON COMPANY NRC DOCKET NO. 050-456 LICENSE NO. NPF-72

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I.- Monthly Report for Braidwood Unit 1 3 A. Summary of Operatina Experience The unit entered the month of October at 49% reactor  ;

power. On October 2, the power level was reduced to 30% '

for four (4) days of power ascension testing. An unplanned reactor trip took' place on October 9 during turbine valve surveillance testing. Control rods were manually inserted on October 15 shortly after returning to l criticality due to a rod position indication problem. .The.

unit. was 're-synchronized to the grid on October 16. On-October 26, reactor power was increased to 75%. Reactor power was reduced to 60% on October 30 due to stator .

cooling concerns and remained there through the end of the '

month. ,

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1 B. OPERATING DATA REPORT DOCKET NO.: 50-456 UNIT: Braidwood 1 DATE: 11/10/87 COMPILED BY: B. M. Peacock TELEPHONE: (815)458-2801 ext. 2480 OPERATING STATUS

1. Reporting Period: October, 1987 Gross Hours: 745.0 i

2. Currently Authorized Power Level (HWt): 3411 Design Electrical Rating (HWe-gross): 1175 Design Electrical Rating (HWe-net): 1120 Max Dependable Capacity (MWe-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 HONTH YR TO DATE CUMULATIVE

5. Report period Hours: 745.0 2689.0 2689.0

6. Hours Reactor Critical: 585.6 1645.5 1645.5

7. RX Reserve Shutdown Hours: 0.0 0.0 0.0

8. Hours Generator on Line: 570.8 1235.6 1235.6

9. Unit Reserve Shutdown Hours: 0.0 0.0 0.0

10. Gross Thermal Energy (HWH): 933567 1619440 1619440

11. Gross Elec. Energy (MHH): 297984 461103 461103 _

12. Net Elec. Energy (MWH): 268464 374656 374656

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

14. Reactor Availability Factor: N/A 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: 174.1 1258.1 1258.1

21. Shutdowns Scheduled Over Next 6 Months:

November 16, 1987 - I day maintenance outage Dgcember 19. 1987 - 6 week surveillance outaae

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

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

FORECAST ACHIEVED Initial Criticality 05/23/87 05/29/87 Initial Electricity 07/11/87 07/12/87 3 Commercial Operation 02/22/88 (49572)

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

UNIT: Braidwood 1 ' l DATE: 11/10/87 'I COMPILED BY: B. M. Peacock TELEPHONE: (815)458-2801 ext. 2480 MONTH: October, 1987

1. 479 17. 222

2. '436 18. 163

3. 259 19. 235

4. 280' 20. 276

5. 270 21. 470

6. 341 22. 501

7. 472 23. 489

8. 503 24. 554

9. 360 25. 593

10. 0 26. 598

11. 0 27. 770

12. 0 28. 824

13. 0 29. 823

14. 0 30. 800

15. 0 31, 651

16. O INSTRUCTIONS >

On this form list the average daily unit power level in MHe-Net for each day in the reporting month. Compute to the nearest whole megawatt.

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 100% 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, October 1 through October 31, 1987. This information is provided pursuant to the i reportable occurrence' reporting requirements as set forth in.10 CFR 50.73.-

Licensee Event Reoort Report Numbet_' Dgift Title of Occurrence 87-045-00, -10/07/87 Axial' flux difference surveillance-not initiated'when process computer was rebooted due to y misinterpretation.

87-046-00 10/07/87 Increase in.RCS cooldown rate causing lo'lo steam generator level i

and . auto start of the 18 diesel l< . driven aux-feed pump.

87-047-00 10/16/87 Missed diesel generator surveillance.

~87-048-00 10/07/87 Loss of'offsite power _due to inadvertent deluge' system actuation resulting from a mispositioned valve.  !

87-049-00 10/05/87 Exceeded analysis frequency on' waste gas' oxygen analysis.-

87-050-00 10/14/87 Reactor trip due to deluge system discharge.

87-051-00 10/14/87 Control room ventilation switchover due to spurious noise on channel ORE-PR033B.

87-052-00 10/19/87 Reactor trip while synchronizing to the grid.

87-053-00 10/14/87 Containment isolation from loss of power to 1RT-AR011.

i 87-055-00 10/20/87 Spurious containment isolation signals caused by radiation detector 1RT-AR012 failure.

(; 056-00 10/30/87 Control roorn ventilation shift to emergency makeup mode due to a failure of radiation moinitor OPR333 pressure switch. ,

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Commonwrith Edison >

Br:ldwood Nucl:Ir Pow:r StItion Route #1. Box 84 Braceville, Illinois 6o407 Telephone B15/458-2801 4

EEF/87-1716 November 10, 1987-Director, Office of Resource Management United States Nuclear Regulatory Commission Hashington, D.C. 20555 ATTN: Document Control Desk Gentlemen:

Enclosed for your information is the Monthly Performance Report covering Braidwood Nuclear Power Station for the period October 1 through October 31, 1987.

Very truly yours,

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E. E. Fi patrick Station Manager Braidwood Nuclear Power Station.

EEF/RCB/mjv i (4957z)

Attachments .

1 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. Anastasia, Station Nuclear Engineering INP0 Records Center Performance Monitoring Group, Tech Staff Braidwood Station Nuclear Group, Tech Staff Braidwood Station S. Sands - USNRC P. L. Barnes

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