ML20070S131

Monthly Operating Repts for Apr 1994 for Byron Nuclear Power Station Units 1 & 2

ML20070S131
Person / Time
Site:	Byron
Issue date:	04/30/1994
From:	Colglazier R, Schwartz G COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
BYRON-94-0181, BYRON-94-181, NUDOCS 9405230223
Download: ML20070S131 (14)

Text

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. . / R ) Byron Nuclear Station

, is C ' 7 4450 North German. Church Road (j/ Byron, Illinois 61010 May 11, 1994 LTR: BYRON 94-0181 FILE: 2.7.200 (1,10.0101)

Director, Office of Management Information and Program Control United States Nuclear Regulatory Commission Washington, D.C. 20555 ATTN: Document Control Desk Gentlemen:

Enclosed for your information is the Monthly Performance Report covering Byron Nuclear Powcr Station for the period April 1 through April 30, 1994.

SAncerely, f l s

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G. K. Schwartz Station Manager Byron Nuclear Power Station GKS/RC/ng cc:

1 J.B. Martin, NRC, Region III NRC Resident Inspector Byron IL Dept. of Nuclear Safety l Nuclear Licensing Manager j Nuclear Fuel Services, PWR Plant Support l D.R. Eggett, Station Nuclear Engineering l INPO Records Center

! J.B. Hickman - USNRC l

F. Yost - Utility Data Institute, Inc.

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! 9405230223 940430 .

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4 BYRON NUCLEAR POWER STATION UNIT 1 AND UNIT 2 MONTHLY PERFORMANCE REPORT COMMONWEALTH EDISON COMPANY NRC DOCKET NO. 050-454 NRC DOCKET NO. 050-455 LICENSE NO. NPF-37 LICENSE NO. NPF-66 l

l (9928MM/051194 /2 )

f j4 I. Monthly Reoort for Byron UNIT 1 for the month of Aoril 1994 i

• A. Summary of Ooeratino Exoerience for Unit 1 The Unit began this reporting period in Mode 1 (Power Operations) .

I i The power level varied due to load following requirements, i

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(9928MM/051194 /3)

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4 B: OPERATING DATA REPORT DOCKET NO.. 050-454 UNIT: Byron One DATE: 05/11/94 l COMPILED BY: R. Colglazier TELEPHONE: (815)234-5441 x2282 OPERATING STATUS

1. Reporting Period: April, 1994. Gross Hours: 719

2. Currently Authorized Power Level: 3411 (MWt)

Design Electrical Rating: 1175 (MWe-gross)

Design Electrical Rating: 1120 (MWe-net)

Max Dependable Capacity: 1105 (MWe-net)

3. Power Level to Which Restricted (If Any): None 4 Reasons for Restriction (If Any) : N/A THIS MONTH YR TO DATE CUMULATIVE *

! 5. Report Period Mrs. 719 2879 75,576 l

l 6. Rx Critical Hours 719 2879 63,689.5

7. Rx Reserve Shutdown Hours 0 0 38

8. Hours Generator on Line 719 2879 63,011.1

9. Unit Reserve Shutdown Hours 0 0 0

• 10. Gross Thermal Energy (MWH) 2,392,629 9,655,446 192,716,545

11. Gross Elec. Energy (MWH) 831,587 3,318,907 65,137,452

12. Net Elec, Energy (MWH) 796,030 3,174,689 61,738,024

13. Reactor Service Factor 100 100 84.27

14. Reactor Aval) ability Factor 100 100 84.32

15. Unit Service Factor 100 100 83.37

16. Unit Availability Factor 100 100 83.37

17. Unit Capacity Factor (MDC net) 100.19 99.79 73.93

18. Unit Capacity Factor (DER net) 98.85 98.46 72.94

19. Unit Forced Outage Hrs. 0 0 1,498.2

20. Unit Forced Outage Rate 0 0 2.32

21. Shutdowns Scheduled Over Next 6 Months: 1

22. If Shutdown at End of Report Period, Estimated Date of Startup: None

23. Units in Test Status (Prior to Commercial Operation) : None

• Note - The cumulative numbers do not reflect power generated prior to commercial service.

(9928MM/051194 /4)

C. AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.. 050-454 UNIT: Byron One DATE: 05/11/94 COMPILED BY: R. Colglazier TELEPHONE: (815)234-5441 x2282 MONTH: April, 1994 DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

1. 1102 MW 16. 1116 MW

2. 1104 MW 17. 1112 MW

3. 1116 MW 18, 1079 MW

4. 1105 MW 19. 1099 MW e

5. 1115 MW 20. 1105 MW

6. 1113 MW 21, 1120 MW

7. 1118 MW 22. 1121 MW

8. 1109 MW 23, 1110 MW

9. 1104 MW 24. 1097 MW

10. 1110 MW 25. 1090 MW

11. 1053 MW 26. 1088 MW

12. 1114 MW 27. 1110 MW

13. 1114 MW 28. 1118 MW

14. 1109 MW 29. 1118 MW

15. 1110 MW 30. 1122 MW 31.

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 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.

(9928MM/051194 /5)

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• BYRON

• Report Period April, 1994 UNIT SHUTDOWNS / REDUCTIONS (UNIT 1) **************************

No. Date Tvoe Hours Reason Method LER Number System Comoonent Cause & Corrective Action to Prevent Recurrence NO SHUTDOWNS OR MAJOR REDUCTIONS FOR UNIT ONE l

• Summary

• TYPE Reason Method System & Component F-Forced A-Equip Failure F-Admin 1-Manual Exhibit F & H S-Sched B-Maint or Test G-Oper Error 2-Manual Scram Instructions for C-Refueling H-Other 3-Auto Scram Preparation of D-Regulatory Restriction 4-Continued Data Entry Sheet E-Operator Training 5-Reduced Load Licensee Event Report

& License Examination 9-Other (LER) File (NUREG-0161)

(9928MM/051194 /6)

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]L UNIOUR REPORTING REOUIREMENTS (UNIT 1) for the month of Acril 1994

1. Safety / Relief valve operations for Unit One.

VALVES NO & TYPE PLANT DESCRIPTION DATE ACTUATED ACTUATION CONDITION OF EVEN]

None l

2. Licensee generated changes to ODCM. .

None

3. Indications of failed fuel.

No. Fuel Reliability Indicator: FRI = 4.2 E-6 pCi/CC l

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t f F. LICENSEE EVENT REPORTS (UNIT 1) l

( The fol'owing l is a tabular summary of all Licensee Event Reports for j Byron Nuclear Power Station, Unit One, occurring during the reporting period, April 1, 1994 through April 30, 1994. This information is provided pursuant to the reportable occurrence reporting requirements as set forth in 10CFR 50.73.

Occurrence Licensee Event Report Number Date Title of Occurrence 454: 94-003 03/14/94 LER 94-003 Auxiliary Feedwater Isolation Valve Exposure to Potentially Harsh Environment due to Flood Seal Removal 454: 94-004 04/23/94 LER 94-004 Missed Tech Spec Surveillance For OC Gas Decay Tank.

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. l II. Monthly Reoort for Byron UNIT 2 for the month of April 1994 A. Summarv of Operatinct Experience fcr Unit 2 The Unit began this reporting period in Mode 1 (Power Operations),

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B. OPEPATING DATA REPORT DOCKET NO.- 050-455 UNIT: Byron Two DATE: 05/11/94 COMPILED BY: R. Colglazier TELEPHONE: (815)234-5441 x2282 OPERATING STATUS

1. Reporting Period: April, 1994. Oross Hours: 719

2. Currently Authorized Power Level: 3411 (MWt)

Design Electrical Rating: 1175 (MWe-gross)

Design Electrical Rating: 1120 (MWe-net)

Max Dependable Capacity: 1105 (MWe-net)

3. Power Level to Which Restricted (If Any) : None

4. Reasons for Restriction (If Any) : N/A l

l THIS MONTH YR TO DATE CUMULATIVE

• j 5. Report Period Hrs. 719 2879 58,680

6. Rx Critical Hours 719 2879 50,684.9 7 Rx Reserve Shutdown Hours 0 0 0

8. Hours Generator on Line 719 2879 50,084.6

9. Unit Reserve Shutdown Hours 0 0 0

10. Gross Thermal Energy (MWH) 2,416,032 9,600,042 145,671,969

11. Gross Elec. Energy (MWH) 833,646 3,308,288 49,491,562

12. Net Elec. Energy (MWH) 798,413 3,165,520 46,948,747

13. Reactor Service Factor 100 100 86.38

14. Reactor Availability Factor 100 100 86.38

15. Unit Service Factor 100 100 85.35 l 16. Unit Availability Factor 100 100 85.35

17. Unit Capacity Factor (MDC net) 100.49 99.50 72.41

18. Unit Capacity Factor (DER net) 99.15 98.17 71.44

( 19. Unit Forced Outage Hrs. 0 0 1,343.4

! 20. Unit Forced Outage Rate 0 0 2.61

21. Shutdowns Scheduled Over Next 6 Months: 0

22. If Shutdown at End of Report Period, Date of Startup: None

23. Units in Test Status (Prior to Commercial Operation) ; None i

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• Note - The cumulative numbers do not reflect power generated prior to commercial service.

(9928MM/051194/10) i

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C. AVERAGE DAILY UNIT POWER LEVEL DOCKET NO., 050-455 UNIT: Byron Two i DATE: 05/11/94 l COMPILED BY: R. Colglazier TELEPHONE: (815)234-5441 x2282 MONTH: April, 1994 DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

1. 1112 MW 16. 1121 MW

2. 1107 MW 17. 1121 MW

3. 1116 MW 18. 1110 MW

4. 1111 MW 19. 1119 MW l

5. 1121 MW 20. 1126 MW 6, 1118 MW 21, 1107 MW

7. 1118 MW 22. 1111 MW 8, 1115 MW 23. 1121 MW

9. 1108 MW 24, 1110 MW j 10. 1117 MW 25, 1043 MW

11. 1118 MW 26. 1102 MW

12. 1113 MW 27, 1122 MW

13. 1119 MW 28. 1074 MW

! 14, 1115 MW 29. 1071 MW

15. 1115 MW 30, 1117 MW 31.

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 l 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.

l (9928MM/051194 /11) l

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• BYRON

• Report Period April, 1994 UNIT SHUTDOWNS / REDUCTIONS (UNIT 2) **************************

No. Date Type Hours Reason Method LER Number System Component Cause & Corrective Action To Prevent Recurrence NO SHUTDOWNS OR MAJOR REDUCTIONS FOR UNIT TWO

• Summary

• TYPE Reason Method System & Comnonent F-Forced A-Equip Failure F-Admin 1-Manual Exhibit F&H S-Sched B-Maint or Test G-Oper Error 2-Manual Scram Instructions for C-Refueling H-Other 3-Auto Scram Preparation of D-Regulatory Restriction 4-Continued Data Entry Sheet E-Operator Training 5-Reduced Load Licensee Event Report

& License Examination 9-Other (LER) File (NUREG-0161)

(9928MM/ 051194 /12)

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E. UNIOUE REPORTING REOUIREMENTS (UNIT 2) for the month of Anril 1994 l

1. Safety / Relief valve operations for Unit Two.

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

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2. Licensee generated changes to ODCM. ,

I l None

3. Indications of failed fuel.

No. Fuel Reliability Indicator: FRI = 5.2 E-5 pCi/CC l l l

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! F. LIdENSEE EVENT REPORTS (UNIT 2) 1 e

The following is a tabular summary of all Licensee Event Reports for Byron Nuclear Power Station, Unit Two, occurring during the reporting period, i April 1, 1994 through April 30, 1994. This information is provided pursuant to the reportable occurrence reporting requirements as set forth in 10CFR 50.73.

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! Licensee Event Reoort Number Date Iltle of Occurrence 3

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I (9928MM/051194 /14 ) '

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