ML20062N825

Monthly Operating Repts for Dec 1993 for Byron Nuclear Station

ML20062N825
Person / Time
Site:	Byron
Issue date:	12/31/1993
From:	Colglazier R, Schwartz G COMMONWEALTH EDISON CO.
To:	NRC, NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
BYRON-94-0014, BYRON-94-14, NUDOCS 9401240097
Download: ML20062N825 (14)

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i Commonwa lth Edicon

' v3 Byron Nuclear Station *

, .O' 4450 North German Church Road  !

Byron, Illinois 61010 l

4 January 10, 1994 ,

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l LTR: BYRON 94-0014  ;

FILE: 2.7.200 (1.10.0101) i F

Director, Office of Management Information and Program Control ,

United States Nuclear Regulatory Commission Washington, D.C. 20555 ATTN: Document Control Desk I

I Gentlemen: .:

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Enclosed for your information ir the Monthly Performance Report  ;

covering Byron Nuclear Power Station for the period December 1 through December 31, 1993.

i Sincerely, P

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BYRON NUCLEAR POWER STATION ,

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UNIT 1 AND UNIT 2 MONTHLY PERFORMANCE REPORT

~6 COMMONWEALTH EDISON COMPANY l B

NRC DOCKET NO. 050-454 NRC DOCKET NO. 050-455 t

LICENSE NO. NPF-37 LICENSE NO. NPF-66 'i

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(992 BMM/WPF/011294 /2) .,

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'I . Monthly Report for Byron UNIT 1 for the month of December 1993 A. Summary of Operatina ExDerience for Unit 1 The Unit began this reporting period in Mode 1 '(Power Operations) .

The power level varied due to load following requirements.

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b B.* OPERATIFIG DATA REPORT I DOCKET NO.: 050-454 UNIT: Byron One DATE: 01/10/94 COMPILED BY: R. Colglazier TELEPHONE: (815)234-5441 x2282 OPERATING STATUS

1. Reporting Period: December, 1993. Gross Hours: 744

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 Ievel to Which Restricted (If Any) None l 4. Reasons for Restriction (If Any): N/A THIS MONTH YR TO DATE CUMUIATIVE*

5. Report Period Hrs. 744 8,760 72,697

6. Rx Critical Hours 744 7,152.2 60,810.5

7. Rx Reserve Shutdown Hours 0 0 38

8. Hours Generator on Line 744 7,105.1 60,132.1

9. Unit Reserve Shutdown Hours 0 0 0

• 10. Gross Thermal Energy (MOI) 2,471,430 22,604,808 183,061,099  !

11. Gross Elec. Energy (MWH) 850,821 7,716,957 61,818,545

17. Het Elec. Energy (MWH) 814,017 7,357,469 58,563,335

13. Reactor Service Factor 100 81.65 83.65

14. Reactor Availability Factor 100 81.65 83.70

15. Unit Service Factor 100 81.11 82.72

16. Unit Availability Factor 100 81.11 82.72

17. Unit Capacity Factor (MDC net) 99.01 76.01 72.90

18. Unit Capacity Factor (DER net) 97.69 74.99 71.93

19. Unit Forced Outage Mrs. 0 94.8 1,498.2 20 Unit Forced Outage Rate 0 1.32 2.43

21. Shutdowns Scheduled Over Next 6 Months: 0 0 0

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/WPF/011194 /4 )

arest resident , dairy and livectock) was used to update Appendix F tables.

Joint Frequency Distribution Tables were added for reference to Appendix F.

Fevised Curie limits for radioactivity in unprotected tanks.

3. Indications of failed fuel.

No. Fuel Reliability Indicator: FR1 = 0 pCi/CC y'

$m 4 i

(992 BMM/WPF/011194 /7)

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• F. LYCEfj{SEE EVENT REPORTS (UNIT 1) i The following.is a tabular summary of all Licensee Event Reporto for Byron Nuclear Power Station,' Unit ON , occurring during the reporting period,_  !

December 1, 1993 through December 31 1993. This information is provided l pursuant to the reportable occurrence reporting requireme:2ts as set forth in  :

10CFR 50.73.

Occurrence  ;

Licensee Event Rgoort Number D3.j;.g

_ Title of Occurrence ~!

i 93-004 12-08-93 Potential Inoperability of the.

Auxiliary Feedwater Switchover: l due to Inadequate Design Change, e

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(9928MM/WPF/011194 /8)

I II. Alnthly Pecort for Byron UNIT 2 for the month of December 1993 A. Su.w.ary of Operatinct Experience for Unit 2 The Unit began this reporting period in Mode 1 (Power Operations).

(9928MM/n'PF/011194 /9)

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• i B. OPEPATING DATA REPOPJ -[

DOCKET NO.: 050-455 l UNIT: Byron Two -l DATE: 01/10/94 )

COMPILED.BY: R. Colglazier ,

TELEPHONE: (815)234-5441 j x2282 -

OPERATING STATUS ,

1. Reporting Period: Decente r, 1993. Gross Hours: 744 l 1

2. Currently Authorized Power Level: 3411 (MWt) ,

Design Electrical Rating: 1175 (MWe-gross) ,

Design Electrical Rating: 1120 (MWe-net) l Max Dependable Capacity: 1105 (MWe-net) ,

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

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4. Reasons for Restriction (If Any). N/A i THIS MONTH YR TO DATE CUMULATIVE * ~

S. Report Period Hrs. 744 8,760 55,801  !

6. Rx Critical Hours 744 7,470.3 47,805.9

7. Rx Reserve Shutdown Hours 0 0 0 l

8. Hours Generator on-Line 744 7,400.3 47,205.6 ,

9 Unit Reserve Shutdown Hours 0 0 0 l

10. Gross Thermal Energy (MWH) 2,454,116 23,321,470 136,071,927  ;

11. Gross Elec. Energy (MWH) 846,460 7,967,336 46,183,274  !

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12. Net Elec. Energy (MWH) 809,984 7,622,468 43,783,227

13. Reactor Service Factor 100 85.28 85.67 14 Reactor Availability Factor 100 85.28 85.67

15. Unit Service Factor 100 84.48 84,60

16. Unit Availability Factor 100 84.48 84.60

17. Uns* Capacity Factor (MDC net) 98.52 78.75 71.01

18. Unit Capacity Factor (DER net) 97.20 77.69 70.06

19. Unit Forced Outage Hrs. 0 74.9 1,318.9

20. Unit Forced Outage Rate 0 1.00 2.72 21., Shutdowns Scheduled Over Next 6 Months: 0 0 0

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

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

• Note - The cumulative numbers do not ref1 ct power generated prior to commercial service.

(9928MM/WPF/011194 /10)

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. . . J, , .t C. AVERAGE DAJJ,Y UNIT POWER LEVEL j

DOCKET NO.: 050-455 UNIT: Byron Two )

DATE: 01/10/94 ,

COMPILED BY: R. Colglazier l TELEPHONE: _ (815)234-5441 l x2282 -f MONTH: December, 1993 l DAY AVERAGE DAILY POWER LEVEL f (MWe-Net)

1. 1104 MW 16. 1112 MW l i

2, 1079 MW 17. 1110 MW l 6

3. 1106 MW 18. 1084 MW i

4. 1098 MW 19. 783 MW  !

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5. 1082 MW ?u. 1102 MW l t

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6. 1096 MW 21. 1117 MW l

1102 MW

7. 22. 1116 MW B. 1098 MW 23. 1101 MW

9. 1089 MW 24, 1087 MW  !

'10. IQ14 MW 25, 1070 MW j

11. 1108 MW 26. 1099 MW .j

12. 1110 MW 27 1100 MW <' .

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1101 MW 28. 1098 MW

14. 1102 MW 29. '1096 MW

15. 1105 MW 30. 1103 MW

31. 1080 MW i

INSTRUCTIONS 1 On this form list the average daily unit power level in MWe-Net for each day i 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 j 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 c (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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'(9928MM/WPF/011194 /11) j a

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Report Period December, 1993 UNIT SHITI' DOWNS / REDUCTIONS

• BYRON *

(UNIT 2) **************************

No. Date Type HQurs Reason Method LER Number System Comnonent Cause & Corrective Action To Prevent Recurrence.

6. 12/19/93 S 16 A 5 FW Valve Reduced Load For Planned Maint. on 2FWOO9C.

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• Summary

• TYPE' Reason Method System & Comconent

'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-Othe3. (LER) File'(NUREG-0161)

(992'8MM/WPF/011194 /12)

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-E. UNIQpE REPORTING PEOUIREMENTS (UfgT 2) for the month of December 1993 I

1. Safety / Relief valve operations for Unit Ter..

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VALVES PLANT DESCRIPTION p_Alg ACTUATED ACTUATION CONDITION OF EVEfrr  !

l None i

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2. Licensee generated changes to ODCM.

The Offsite Dose Calculation Manual (CDCM) was revised effective  !

January 1, 1994. This revision addressed changes to support the new 10CFR20 implementation. These major changes include-Whole body dose factors are now calculated using 2 cm depth as opposed to 5 cm.

Restricted Area Boundaries here bcen revised and are included in Appendix F. [

The Land Use Census (e.g. nearest resident, dairy and livestock) was  !

used to update Appendix F tables.

• Joint Frequency Distribution Tables were added for reference to '

Appendix F. .

Revised Curie limits for radioactivity in unprotected tanks.

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3. Indications of failed fuel, f

i No. Fuel Reliability Indicator: FRI = 2.4 E-5 yCi/CC  !

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4' 4 e F. LICENSEE EVENT PEPORTS (UNIT 2)  ;

The following !.s a_ tabular summary of all L_icensee Event Reports for Byron Nuclear Power Station, Unit Two, occurring during the reporting period,- ,

December 1, 1993 through December 31, 1993. This infonnation is provided  !

pursuant to the reportable occurrence reporting requirements as set forth in ,

10CFR 50.73.  !

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E Occurrence Licensee Event Reoort Number Date Title of Occurrence None l

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E (9928MM/WPF/011194 /14)

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