ML20195H212

Monthly Operating Repts for Dec 1987

ML20195H212
Person / Time
Site:	Braidwood
Issue date:	12/31/1987
From:	Fitzpatrick E, Peterson M COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
(4957Z), EEF-88-19, NUDOCS 8801190109
Download: ML20195H212 (14)

Text

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-o BRAIDH000 NUCLEAR P0HER STATION UNIT 1 AND UNIT 2 MONTHLY PERFORMANCE REPORT l

COMMONHEALTH EDISON COMPANY NRC DOCKET NO. 050-456, LICENSE NO. NPF-72 NRC DOCKET NO. 050-457, LICENSE NO NPF-75 l

i d ' z+<p (4957z) 8801190109 871231

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I. Monthly Report fer Braidwood Unit 1 A. Summary of Operatina Exoerience The unit entered the month of December at 73% reactor power. Power was increased to 90% on December 3. On December 6, the unit was manually tripped due to plugged condensate pump suction strainers. The unit was re-synchronized to the grid on December 9, and power was increased to 88% by December 12. The power level was raised to 99.5% by December 30, following completion of the 90% testing sequence, and remained there through the end of the month.

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(49572/3)

B. QEERATING DATA REPORT DOCKET NO.: 50-456 UNIT: Braidwood 1 DATE: 01/08/88 COMPILED BY: M. H. Peterson TELEPHONE: (815)458-2801 ext. 2480 OPERATING STATUS

1. Reporting Period: December, 1987 Gross Hours: 744.0

2. Currently Authorized Power Level (MHt): 3411 Design Electrical Rating (MHe-gross): 1175 Design Electrical Rating (MHe-net): 1120 Max Dependable Capacity (MHe-gross).: 1175 Max Dependable Capacity (MHe-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: 744.0 4153.0 4153.0

6. Hours Reactor Critical: _ 694.2 3059.7 .3059.7 __

7. RX Reserve Shutdown Hours: 0.0 0.0 0.0

8. Hours Generator on Line: 679.8 2610.7 2610.7

9. Unit Reserve Shutdown Hours: 0.0 0.0 0.0

10. Gross Thermal Energy (MHH): 1895472 5015674 5015674

11. Gross Elec. Energy (MWH): 646837 _1604604 .1604604

12. Net Elec. Energy (MHH): 615901 1456651 1456651

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: 64.2 1322.3 1322.3

21. Shutdowns Scheduled Over Next 6 Months:

January 1. 1988 - 6 week surveillance outage

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 Commercial Operation 03/26/88 (4957z/4)

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C. &EERAGE DAILY UNIT &lT P0HER LEVEL LOG DOCKET NO.: 50-456 UNIT: Braidwood 1 DATE: 01/08/88 COMPILED 8Y: M. H. Peterson TELEPHONE: (815)458-2801 ext. 2480 HONTH: December, 1987

1. 796 17. 981

2. 811 18. 981

3. 977 19. 945

4. 977 20. 946

5. 989 21. 946

6. 812 22. 945

7. 0 23. 946

8. 0 24, 945  ;

9. 101 _ 25. 943

10. 275 __ 26. 943

11. 667 27. 943

12. __B,71 28. 943

13. 860 29. 1021

14. 960 30. 1125

15. 961 31. 1131

16. 971 INSTRUCTIONS On this form list the average daily unit power level in HWe-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.

I (4957z)

D. UNIT SHUTDOHNS/REDUCTIQNS DOCKET NO.: 50-456 .

UNIT: Braidwood'1 -

DATE: 01/08/88 COMPILED BY: M.:H. Peterson '

TELEPHONE: (815)458-2801 ext. 2480 REPORT PERIOD: December, 1987

_NJ_ DA_IE ILPE HOURS REASON METHOD LER NUMBER SYSTEM COMPONENT CAUSE & CORRECTIVE ACTION TO PREVENT RECURRENCE 13 871206 F 64.2 H 2 87-060 SD STR Plugged strainers on all condensate pumps.

Strainers were removed and cleaned.

SUMMARY

TYPE REASON METH00 SYSTEM & COMPONENT F-Forced A-Equipment Failure 1 - Manual Exhibit F & H S-Scheduled B-Maint or Test 2 - Manual Scram Instructions for Preparation of C-Refueling 3 - Auto Scram Data Entry Sheet D-Regulatory Restriction 4 - Continued Licensee Event Report E-Operator Training & License Examination 5 - Reduced Load (LER) File (NUREG-1022)

F-Administration 9 - Other G-Oper Error H-Other r

g:-

E. UNIOUE REPORTING REOUIREMENTS -

1. Safety / Relief valve operations. ,

,l 1

VALVES NO & TYPE PLANT DESCRIPTION DAIE ACTUATED ACTUATION CONDITION OF E.'ENT

. None

2. Licensee generated changes to ODCM.

None i

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F. LICENSEE EVENT REPORTS The following is a tabular summary of all Licensee Event Reports submitted during the reporting period, December 1 through December 31, 1987. This information is provided pursuant to the reportable occorrence reporting requirements as set forth in 10 CFR 50.73.

Licensee Event Reoort ReDort Number QAlg Title of Occurrence 87-058-00 12/04/87 Two trains of control room ventilation declared inoperable due to incorrect design change.

! 87-059-00 12/04/87 Missed surveillance due to lost data sheet.

87-060-00 12/24/87 Manual reactor trip due to plugged condensate pump suction strainers.

87-062-00 12/23/87 Unit 1 ESF actuation due to ESF signal generated from Unit 2.

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II. Monthly Report for Braidwood Unit 2 A. Summary of Ooeratina Experience Braidwood Station Unit 0 received its low power operating .

license on December 18. The first fuel assembly was "

installed in the reactor vessel on December 21 and fuel loading operations were completed on December 27.

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(4957z)

. . - - - - , . . . . . . -. . - - - - - . -_ _. -- - . - --. J

B. OPERATING DATA REPORT DOCKET NO.: 50-457 UNIT: Braidwood 2 DATE: 01/08/88 COMPILED BY: H. H. Peterson TELEPHONE: (815)458-2801 ext. 2480 OPERATING STATUS

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

2. Currently Authorized Power Level (HHt): 0 Design Electrical Rating (HHe-gross): 1175 Design Electrical Rating (MHe-net): 1120 Max Dependable Capacity (MHe-gross): 0 Hax Dependable Capacity (HHe-net): 0

3. Power level to which restricted (If Any): 5%

4. Reasons for restriction (If Any): Terms of Braidwood Station's Facility Operating License.

THIS MONTH YR TO DATE CUMULATIVE

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

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

7. RX Reserve Shutdown Hours: W/A -- --

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

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

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

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

12. Net Elec. Energy (HHH): 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 Honths:

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

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

FORECAST ACHIEVED Initial Criticality 02/29/88 Initial Electricity 03/28/88 Commercial Operation 07/25/88 (4957z/10)

C. 6VERAGE DAILY UNIT NET P0HER LEVEL LOG DOCKET NO.: 50-457 UNIT: Braidwood 2 DATE: 01/08/88 ,

, COMPILED BY: H. H. Peterson TELEPHONE: (815)458-2801 ext. 2480 HONTH: December, 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 r

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 HHe-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.

T (4957z/11)

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D. UNIT SHUTDOWNS / REDUCTIONS DOCKET NO.: 50-457 UNIT: Braidwood 2-

• DATE: 01/08/88 -

00MPILED BY: M. H. Peterson ~

TELEPHONE: (815)458-2801 ext. 2480 REPORT PERIOD: December, 1987

~

No DAIE IIPJ. HOURS REASON METHOD LER NUMBER SYSTEM COMPONENT CAUSE & CORRECTIVE ACTION TO PREVENT RECURRENCE N/A Precritical Period

SUMMARY

TYPE REASON METHOD SYSTEM & COMPONENT F-Forced A-Equipment Failure 1 - Manual Exni'uit F & H S-Scheduled B-Maint or Test 2 - Manual Scram Instructions for Praparation of C-Refueling 3 - Auto Scram Data Entry Sheei D-Regulatory Restriction 4 - Continued Licensee Event Report E-Operator Training & License Examination 5 - Reduced Load (LER) File (NUREG-1022)

F-Administration 9 - Other G-Oper Error H-Other

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E. U!i100E REPORTING REOUIREMENTS - UNIT _2 , .

1. Safety / Relief valve operations.

VALVES NO & TYPE PLANT DESCRIPTION DALE ACTUATED 8CT_U/U91 Q)NDITION OF EVENT None

2. Licensee generated changes to 00CM.

None

_ - , , - - - - . . , , . . . . , - , - , , . _ - . . . . ... .m -. .- . .-. . _.,. . _ , ,----- , . ._...._.I

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, .- l F. LICENSEE EVENT REPORTS - UNIT 2 The following it a tabular summary of all Licensee Event Reports ,

submitted during the reporting period, December 1 through- l Dacember 31, 1987. This information is provided pursuant to the  ;

reportable occurrence reporting requirements as set forth in 10 CFR 50.73.

. 1 L

Licensee Event Reoort Report Number- QA11 Title of Occurrence ,

None i

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\ .) Braldwood Ba v11 e inoisNucl2r 60407 Pow:r Stc. tion

\ Telephone 815/458-28o1 EEF/88-19

' January 8, 1988 Director, Office of Resource Management United States Nuclear Regulatory Commission Washington 0.C. 20555 ATTN: Document Control Desk Gentlemen:

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

Very truly yours, E. E. Fi 2 patrick Station Manager Braidwood Nuclear Power Station EEF/RCB/mje (49572)

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, PWR Plant Support L. Anastasia, Station Nuclear Engineering i 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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