ML20206J217

Monthly Operating Rept for Mar 1987

ML20206J217
Person / Time
Site:	Braidwood
Issue date:	03/31/1987
From:	Fitzpatrick E, Peacock B COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
(4957Z), EEF-87-557, NUDOCS 8704160045
Download: ML20206J217 (8)

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1BRAIDWOOD NUCLEAR POWER STATIONi UNIT l' MONTHLY PERFORMANCE REPORT COMMONWEALTH EDISON COMPANY NRC DOCKET.'IO. 050-456 LICENSE NO. NPF-59 s

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B704160045 DR 870331 ADOCK 05000456 >

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B.: ' OPERATING DATA REPORT DOCKET NO. 50-436 UNIT: Braidwood 1 DATE: 04/10/87 COMPILED BY: B. M. Peacock TELEPHONE: (815)458-2801 ext. 2480 OPERATING STATUS

1. Reporting Period: March,1 1987 Gross Hours: N/A

~2. Currently Authorized Power Level _(MWt): . 'O Design Electrical Re. ting (MWe-gross): '1175 Design Electrical Rating (MWe-net): 1120 Max Dependable Capacity (MWe-gross): 0 Max Dependable Capacity.(MWe-net): 0

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'3. Power level to'which restricted (If Any): 0 (MWe-gross)

4. . Reasons for restriction (If Any)': Low power testing license.has not been received yet.

THIS MONTH .YR TO DATE CUMULATIVE'.

5. Report period Hours: N/A -- --

6. Hours Reactor Critical: N/A -- --

7. ~RX Reserve Shutdown Hours: N/A -- --

8. Hours Generator on Line: N/A -- --

9. Unit Reserve Shutdown Hours: N/A -- --

10. Gross Thermal Energy (MWH): N/A -- --

11. Gross Elec. Energy (MWH): N/A -- --

12. Net Elec. Energy (MWH): N/A -- --

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

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

15. Unit Service Factor: 'N/A- -- --

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

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

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

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

20. Unit Forced Outage Hours: N/A -- --

21. Shutdowns Scheduled Over Next 6 Months:

22. If Shutdown at End of Report Period, )

-Estimated Date of Startup-l

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

FORECAST ACHIEVED 1 Initial Criticality 05/11/87 Initial Electricity 06/19/87 CommerciaJ' Operation 09/04/87' (4957z)

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'C. AVERAGE DAILY UNIT NET POWER LEVEL LOG DOCKET NO.: 50-456' F iUNIT: Braidwood 1 DATE: 04/10/87 COMPILED BY: B.'M. Peacock TELEPHCNE: -(815)458-2801 ext. 2480' MONTH: March, 1987

1. N/A 17. N/A-

-2. N/A 18. _, N/A- ,

3. -N/A~ '19. _

N/A

4. N/A 20. N/A 5 .' N/A 21. N/A

6. N/A 22. N/A

7. N/A- 23.- N/A

8. N/A 24. N/A

9. N/A 25. N/A:

10. N/A 26. N/A-

11. N/A 27. N/A

12. N/A 28. -N/A

13. N/A 29. N/A

14. N/A 30. N/A '

15. N/A 31. 'N/A

16. N/A INSTRUCTIONS On this form list the average daily unit power level.in MWe-Net for each j 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*4 line (or the restricted power level line). In-such cases the average ' daily unit power output sheet should be-footnoted to explain the apparent anorr.aly.

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l-D. UNIT SIIUTDOWNS/ REDUCTIONS. DOCKET NO.: 50-456-UNIT: Braidwood 1-l' DATE: 04/10/87 COMPILED BY: B. M.. Peacock TELEPilONE: (815)458-2801 ext. 2480 t

L REPORT PERIOD: March, 1987

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No DATE TYPE IIOURS REASON METIIOD LER NUMBER. SYSTEM COMPONENT CAUSE & CORRECTIVE ACTION TO PREVENT RECURRENCE.

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N/A PRECRITICAL PERIOD f*<

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o'S U'M M A R Y

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REASON METIIOD ' SYSTEM & COMPONENT

F-Forced' A-Equipment Failure Maint or Test 1 - Method Exhibit F & II .

S-Sche'duled C-Refueling 2 - Manual Scram' Instructions for Preparation.of D-Regulatory Restriction 3 - Auto Scram Data. Entry Sheet:

E-Operator Training & License Examination 4 - Continued . Licensee Event. Report ,

F-Administration 5 - Reduced Load (LER) File (NUREG-0161)

.G-Oper Error- 9 - Other , ,.

II-Other l'

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• E. UNIQUE REPORTING' REQUIREMENTS , ..

1. Safety / Relief valve operations.

VALVES .NO.& TYPE PLANT DESCRIPTION" DATE ACTUATED ACTUATION CONDITION OF EVENT None s

2. Licensee generated changes to ODCM.

None s

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F. LICENSEE EVENT REPORTS ~

The following is a tabular.summaqr of all Licensee Event Reports

' submitted during .the reporting period, March 1, through March 31, 1987.

This:information is provided pursuant to the reportable occurrence

. reporting requirements as set forth'in 10 CFR 50.73.

Licensee Event- Report Report Number Date Title of Occurrence 1 -

87-010-00~ 03/07/87 ' Inadvertent Icss of power to instrument bus 111 resulting in a reactor trip due to personnel error.

4 87-012-00 03/18/87 Fire detection zone'lD-8 inoperable due to unauthorized removal of a-detector.-

87-013-00 03/12/87 Manual reactor-trip due to

-inadequate procedure.

87-014-00 03/24/87 Failure' t'o maintain an operable

airlock door closed'while testing an inoperable door due to judgement

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error by licensed supervisory

personnel.

87-015-00 03/25/87 Manual reactor trip due to deficient: procedure as a result of E

rod misalignment during testing.

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- I; l Monthly Report for Braidwood Unit 1 A. Summary of Operating Experience On March'2,-1987 the unit entered Mode;3 and remained .in-Mode 3-throughout'.the month. Pre-operational .. testing continued.

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7 'N . Commonwealth Edison -

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) Braidwood Nuclear Power Station

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\ r Braceville. Illinois 80407

' \ / : Telephone 815/458-2801 1 i

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l EEF/87-557-File: AGNC-14 April-10, 1987 Director, Office of Resource Management United States Nuclear Regulatory Commission Washington, D.C. -20555 ATTN: Docurret Control Desk 4

Gentlemen: l l

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

Very truly yours, i

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E. E. Fi atrick Station Manager Braidwood Nuclear Power Station l

I EEF/RCB/ jab (4957=)

Attachments cc: J. G. Keppler, NRC, Region III-NRC Resident Inspector Braidwood Gary Wright, Ill. Dept. of Nuclear Safety D. P. Galle T. J. Maiman D. L. Farrar Nuclear Fuel Services, PWR Plant Support L. Anastasia, Station Nuclear Engineering INPO Records Center Performance Monitoring Group, Tech Staff Braidwood Station .

Nuclear Group, Tech Staff Braidwood Station. gj J. Stevens - USNRC / fk P. L. Barnes /

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