ML20045B193

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Monthly Operating Repts for May 1993 for Braidwood Nuclear Power Station,Units 1 & 2.W/930610 Ltr
ML20045B193
Person / Time
Site: Braidwood  Constellation icon.png
Issue date: 05/31/1993
From: Kofron K, Stanczak P
COMMONWEALTH EDISON CO.
To:
NRC, NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
BW-93-0197, BW-93-197, NUDOCS 9306160397
Download: ML20045B193 (14)
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Text

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CN Comm:nwnith Editan

'[ ~ \ . Braidwood Nuclear Power Station

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V f} Route #1, Braceville, Box B4 Illinois Telephone 815/45L -

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June 10, 1993  ;

BW/93-0197 ,

Director, Office of Resource Management United States Nuclear Regulatory Commission )

Washington, D.C. 20555 Attn: Document Control Desk

Dear Sir:

Enclosed for your information is the Monthly Performance Report covering Braidwood Nuclear Power Station for the ,

period May 1 through May 31, 1993.

. Kofro Station Manager Braidwood Station KLK/JL/dla o:corresp/zcbw93 Attachments cc: A. B. Davis, NRC, Region III '

R. R. Assa, USNRC Ill Dept of Nuclear Safety NRC Resident Inspector, Braidwood i INPO Records Center D. L. Farrar, Nucl Reg Serv Mgr J. A. Bauer, Nucl Licensing Admin D. R. Eggett, Nucl Eng Dept S. M. Berg, Site V.P., Braidwood Nuc1 Fuel Serv, PWR Plant Support Results Engineering Group, Tech Staff, Braidwood 1 Nuclear Group, Tech Staff, Braidwood l

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i 9306160397 930531 $

gDR. ADOCK 0500 6 l l

. , .. BRAIDWOOD NUCLEAR POWER STATION UNIT.1 AND UNIT 2 MONTHLY PERFORMANCE REPORT Commonwealth Edison Company NRC DOCKET NO. 050-456, LICENSE NO. NPF-72 NRC DOCKET NO. 050-457, LICENSE NO. NPF-77 f

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'i i . MONTHLY REPORT FOR BRAIDWOOD UNIT 1- l

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A. Summary of Ooeratina Exnerience  !

t Braidwood Unit 1 entered the month of May 1993 at approximately 100% capable, but operated at reduced load as requested by the load dispatcher. The Unit operated routinely until May 29 when it was taken -

off line to perform chemistry testing of the steam generators. The Unit I went back on line May 30.

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l B. OPERATING DATA REPORT DATE NO: 50-456 UNIT: BRAIDWOOD 1 DATE: 06/10/93 COMPILED BY: P. STANCZAK TELEPHONE: (815)458-2801 ,

EXT.2486 h

OPERATING STATUS

1. REPORTING PERIOD: MAY 1993 GROSS HOURS: 744
2. CURRENTLY AUTHORIZED POWER LEVEL (MWt): 3411 i DESIGN ELECTRICAL RATING (MWe-GROSS): 1175 ,

DESIGN ELECTRICAL RATING (MWe-NET): 1120 MAX DEPENDABLE CAPACITY (MWe-GROSS): 1175 l MAX DEPENDABLE CAPACITY (MWe-NET): 1120

3. POWER LEVEL TO WHICH RESTRICTED (IF ANY): NONE i
4. REASONS FOR RESTRICTION (IF ANY): NONE THIS MONTH YR TO DATE . CUMULATIVE {
5. REPORT PERIOD MOURS: 744.0 3623.0 42416.0
6. HOURS REACTOR CRITICAL: 716.0 3435.3 32952.5
7. RX RESERVE SHUTDOWN HOURS: 0.0 0.0 0.0
8. HOURS GENERATOR ON LINE: 702.6 3415.1 32390.8
9. UNIT RESERVE SHUTDOWN HOURS: 0.0 0.0 0.0 -
10. GROSS THERMAL ENERGY (MWHt): 2139318.0 11024522.0 97926162.0
11. GROSS ELECT ENERGY (MWH): 738445.0 3844611.0 33633259.0
12. NET ELECT ENERGY (MWH): 708679.0 3705945.0 32155640.0
13. REACTOR SERVICE FACTOR: 96.2 94.8 77.7-
14. REACTOR AVAILABILITY FACTOR: 96.2 94.8 -77.7 >
15. UNIT SERVICE FACTOR: 94.4 94.3 76.4 ,
16. UNIT AVAILABILITY FACTOR: 94.4 94.3 76.4
17. UNIT CAPACITY FACTOR (MDC NET): 85.0 91.3 67.7
18. UNIT CAPACITY FACTOR (DER NET): 85.0 91.3 67.7.
19. UNIT FORCED OUTAGE RATE: 0.0 4.6 9.5
20. UNIT FORCED OUTAGE HOURS: 0.0 166.5 3402.8

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21. SHUTDOWN SCHEDULED OVER NEXT 6 MONTHS N/A
22. IF SHUTDOWN AT END OF REPORTING PERIOD, ESTIMATED DATE OF STARTUP N/A 1

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j C. AVERAGE DAILY UNIT NET POWER LEVEL LOG ,

DOCKET NO: 50-456 UNIT: BRAIDWOOD 1 DATE: 06/10/93 COMPILED BY: P. STANCZAK TELEPHONE: (815)458-2801 EXT.2486 .

MONTH: MAY 1993  ;

i

1. 789 ___
16. 892
2. 751 17. 1063
3. 1027 18. *1132
4. 1104 19. *1131
5. 1098 20. 1042 e
6. 1036 21. 1099
7. 1038 22. 1081
8. 1113 23. 972 ,
9. 978 24. 1105
10. *1130 25. 1092
11. *1126 26. 1103
12. 1111 27. 1094
13. 1050 28. 1008 l
14. 1029 29. 7 '
15. 1078 30, 18 ,
31. 215 -

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. The=e figures will be used to  ;

plot a graph f or 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.

  • Due to condenser efficiency.

3 D. UNIT SHUTDOWNS / REDUCTIONS .

DOCKET NO: 50-456 -

UNIT: BRAIDWOOD 1 DATE: 06/10/93 ^

COMPILED BY: P.STANCZAK TELEPHONE: (815) 458-2801 EXT.2486

' REPORT PERIOD: MAY 1993 CAUSE & CORRECTIVE ACTION TO

' NO. DATE TYPE HOURS REASON METHOD LER NUMBER SYSTEM COMPONENT PREVENT RECURRENCE 10 930501 S 0.0 H 5 N/A N/A N/A Reduction in load as requested by the Load Dispatcher.

11' 930529 S 41.4 B 1 N/A N/A N/A Unit taken off 1ine for chemistry

' testing of the steam generators.

TYPE REASON METHOD SYSTEM & COMPONENT F-Forced A - Equipment Failure Maint or Test 1 - Method Exhibit F &

' S-Scheduled B - Maint or Test 2 - Manual Scram Instructions for Preparation C - Refueling 3 - Auto Scram of Data Entry Sheet D - Regulatory Restriction 4 - Continued Licensee Event Report

- E - Operator Training & Licensee Examination 5 - Reduced Load (LER) File (NUREG -0161) -

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

- _ _ - . . . . . . ~ _ . . . _ - . ._ _ - -- . . - . , . . . . . . - . . . . ,

4.i.

l E. ' UNIQUE REPORTING REQUIREMENTS - UNIT 1 .

1. SAFETY / RELIEF VALVE OPERATIONS.

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

. --+,w w ew *-rv v wem---w-n w 'e + ~ * ~ - + < - ---ww '*= w **'ww '-*e' " " "

I F. LICENSEE EVENT REPORTS - UNIT 1 ,

The following is a tabular summary of all Licensee Event Reports submitted during the reporting period, May 1 through May 31,1993. This information is provided -

pursuant to the reportable occurrence reporting requirements as set forth in 10 CFR .  ;

50.73.

i LICENSEE EVENT REPORT NUMBER DATE TITLE OF OCCURRENCE None E

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11. MONTHLY REPORT FOR BRAIDWOOD UNIT 2 A, Summarv of Ooeratina Exoerience Braidwood Unit 2 completed its third refueling outage and went.back on:

line on May 2. The Unit operated routinely through the end of the.

month.

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i B. OPERATING DATA REPORT .

DOCKET NO: 50-457 UNIT: BRAIDWOOD 2 DATE: 06/10/93'  ;

COMPILED BY: P. STANCZAK TELEPHONE: (815) 458-2801 EXT.2486  :

OPERATING STATUS

1. REPORTING PERIOD: MAY 1993 GROSS HOURS: 744
2. CURRENTLY AUTHORIZED POWER LEVEL (MWt): 3411 -

DESIGN ELECTRICAL RATING (MWe-GROSS): 1175 DESIGN ELECTRICAL RATING (MWe-NET): 1120 MAX DEPENDABLE CAPACITY (MWe-GROSS): 1175 MAX DEPENDABLE CAPACITY (MWe-NET): 1120  :

3. POWER LEVEL TO WHICH RESTRICTED (IF ANY): NONE ,

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4. REASONS FOR RESTRICTION (lF ANY): NONE THIS MONTH YR TO DATE _QUMULATIVE i i
5. REPORT PERIOD HOURS: 744.0 3623.0 40498.0
6. HOURS REACTOR CRITICAL: 744.0 2272.9 33435.4 l
7. RX RESERVE SHUTDOWN HOURS: 0.0 0.0 0.0' i
8. HOURS GENERATOR ON LINE: 696.2 -2210.2 33098.0
9. UNIT RESERVE SHUTDOWN HOURS: 0.0 0.0 0.0 '
10. GROSS THERMAL ENERGY (MWHt): 1937581.0- 6517162.7 98529905.7
11. GROSS ELECT ENERGY (MWH): 658946.0 2211113.0 33667834.0
12. NET ELECT ENERGY (MWH): 630385.0 2101762.0 32215798.0 l
13. REACTOR SERVICE FACTOR: 100.0 62.7 82.6
14. REACTOR AVAILABILITY FACTOR: 100.0 62.7 82.6
15. UNIT SERVICE FACTOR: 93.6 61.0 81.7' !
16. UNIT AVAILABILITY FACTOR: 93.6 61.0 81.7-I
17. UNIT CAPACITY FACTOR (MDC NET): 75.7 51.8 71.0
18. UNIT CAPACITY FACTOR (DER tGTi- 75.7 51.8 71.0 ,
19. UNIT FORCED OUTAGE RATE: 0.0 0.0 3.5
20. UNIT FORCED OUTAGE HOURS: 0.0 0.0 1197.3 i
21. SHUTDOWN SCHEDULE OVER NEXT 6 MONTHS: N/A j
22. IF SHUTDOWN AT END OF REPORTING  :

PERIOD, ESTIMATED DATE OF STARTUP: N/A 1

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C. 6_VERAGE DAILY UNIT NET POWER LEVEL LOG DOCKET NO: 50-457 UNIT: BRAIDWOOD 2 DATE: 06/10/93 COMPILED BY: P, STANCZAK

' TELEPHONE: (815)458-2801 EXT.2486 MONTH: MAY 1993

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15 16. 1104

2. -

7 17. 1106

3. 186 18. 1104
4. 242 19. 1103
5. 380 20. 1103
6. 521 21. 1104
7. 519 22. 1109
8. 520 23. 1106
9. 503 24. 1103
10. 770 25. 1103
11. 845 26. 1103
12. 861 27. 1099 <
13. 1098 28. 1102
14. 1110 29, 1090
15. 1105 30. 1084
31. 1091 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. These figures will be used to plot a graph for each reporting month. Note that when maximum dependable capacity.is used for the not 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.

Due to condenser efficiency.

'D. UNIT SHUTDOWNS / REDUCTIONS '

DOCKET NO: 50456 -

UNIT: BRAIDWOOD 2 -

DATE: 06/10/93- '

COMPILED BY: P. STANCZAK TELEPHONE: (815) 458-2801 EXT.2486 REPORT PERIOD: MAY 1993 CAUSE & CORRECTIVE ACTION TO -

NO DATE TYPE HOURS REASON METHOD LER NUMBER SYSTEM COMPONENT PREVENT RECURRENCE 23 930501 S 47.8 C 4 N/A N/A N/A Unit coming out of refueling outage .

A2R03.

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TYPE REASON METHOD SYSTEM & COMPONENT F-Forced A - Equipment Failure Maint or Test 1 - Method Exhibit F & .i S-Scheduled - B - Maint or Test- 2 - Manual Scram Instructions for. Preparation  !

C - Refueling 3 - Auto Scram of Data Entry Sheet-D - Regulatory Restriction 4 - Continued Licensee Event Report -

E - Operator Training & Licensee Examination 5 - Reduced Load (LER) File (NUREG -0161)

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

. E. - UNIQUE REPORTING REOUiREMENTS - UNIT 2 .

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1. -SAFETY / RELIEF VALVE OPERATIONS.

VALVES NO & TYPE PLANT DESCRIPTION DATE ACTUATED ' ACTUATION CONDITION OF EVENT

1 None i

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F. LICENSEE EVENT REPORTS - UNIT 2 -I i

The following is a tabular summary of all Licensee Event Reports submitted dunng - ._

the reporting period, May 1 through May 31,1993. This information is provided pursuant to the reportable occurrence reporting requirements as set forth in 10 CFR 50.73. ,

LICENSEE EVENT ,

REPORT NUMBER DATE TITLE OF OCCURRENCE i

93-002 May 14,1993 Unplanned Engineered Safety :

Feature Actuation Due to Management and Procedural Deficiency.93-003 May 19,1993 Technical Specifications Violated Due to Source Range Reactor Trip 1 Capability Being Blocked.

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