ML20211C319
| ML20211C319 | |
| Person / Time | |
|---|---|
| Site: | Byron  |
| Issue date: | 09/30/1986 |
| From: | Dandrea P, Querio R COMMONWEALTH EDISON CO. |
| To: | NRC OFFICE OF ADMINISTRATION (ADM), NRC OFFICE OF RESOURCE MANAGEMENT (ORM) |
| References | |
| BYRON-86-1270, NUDOCS 8610210324 | |
| Download: ML20211C319 (8) | |
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7 BYRON NUCLEAR POWER STATION UNIT 1 MONTHLY PERFORMANCE REPORT l
COMMONWEALTH EDISON COMPANY t
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NRC DOCKET NO. 050-454 LICENSE NO. NPF-37 i
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8610210324 860930 PDR ADOCK 05000454 R
PDR i
i (0625M/62M)
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I.
Monthly Report for Byron Unit 1 I
A.
Summary of Operating Experience for Unit 1 The Unit began this reporting period on September 1 in a critical mode, and continued plant operation at 93% power until September 21 when the reactor power was reduce ( to 30% to facilitate the repair of a circulating water tube leak on the IB waterbox. The Unit began its return to full power on September 22 and reached 93% power on September 23.
The Unit continued to operate at 93% power until September 30 when a reactor trip occurred due to the damaging of a cable by contractor personnel in an ESP cabinet. The Unit remained in Hot Standby at the end of this reporting period.
The Hot Leg Temperature. Reduction Program to prevent stress corrosion cracking of the Steam Generator U-tubes is still in affect. The 6%
derating to 94% power based on safety analysis will continue through the end of the Unit 1 fuel cycle where upon it will be administrative 1y evaluated as to its continuance.
N.
e N
(0625M/62M)
B.
OPERATING DATA REPORT DOCKET NO.:
050-454 UNIT: Byron One DATE:
10/10/86 COMPILED BY:
P. H. Dandrea TELEPHONE:
(815)234-5441 1
x2341 OPERATING STATUS 1.
Reporting Period: September 1986. Gross Hours:
720 2.
Currently Authorized Power Level (MWt): 3411 i
Design Electrical Rating: 1175 (MWe-gross)
Design Electrical Rating: 1120 (MWe-net)
Max Dependable Capacity (MWe-net): NOT DETERMINED 3.
Power Level to Which Restricted (If Any): 1105 (MWe-gross) 4.
Reasons for Restriction (If Any): Reduction of Hot Leg Temperature for Primary Water Stress Corrosion Cracking Concerns.
l THIS MONTH YR TO DATE CUMULATIVE
- l 5.
Report Period Hrs.
720 6551 9120 6.
Rx Critical Hours 705.2 5652 7644.5 7.
Rx Reserve Shutdown Hours 0
21.7 37.8 8.
Hours Generator on Line 705.2 5601.3 6793.7 9.
Unit Reserve Shutdown Hours 0
0 0
- 10. Gross Thermal Energy (MWH) 2168895 16594852 19934044
- 11. Gross Elec. Energy (MWH) 731860 5612925 6701515
- 12. Net Elec. Energy (501) 693364 5292482 6305380
- 13. Reactor Service Factor 97.9 86.3 83.8
- 14. Reactor Availability Factor 97.9 86.6 84.2
- 15. Unit Service Factor 97.9 85.5 74.5
- 16. Unit Availability Factor 97.9 85.5 74.5
- 17. Unit Capacity Factor (MDC net)
N/A N/A N/A
{
- 18. Unit Capacity Factor (DER net) 86.0 72.1 61.7
- 19. Unit Forced Outage Hrs.
14.8 625.4 728
- 20. Unit Forced Outage Rate 2
10.0 9.7
- 21. Shutdowns Scheduled Over Next 6 Months: Scheduled refueling outage to start 2/15/87
- 22. If Shutdown at End of Report Period, Estimated Date of Startup: 10/3/86
- 23. Units in Test Status (Prior to Commercial Operation): None
- Note - The cumulative numbers do not reflect power generated prior to commercial service.
(0625M/62M)
C.
AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.: 050-454 UNIT: Byron One DATE:
10/10/86 COMPILED BY:
P. H. Dandrea TELEPHONE:
(815)234-5441 x2341 MONTH: September, 1986 DAY AVERAGE DAILY POWER LEVEL (MWe-Net) 1.
1022 MW 17.
1031 MW 2.
1012 MW 18.
1031 MW 3.
1009 MW 19.
1026 MW 4.
1016 MW 20.
1021 MW 5.
1012 MW 21.
597 MW 6.
1034 MW 23.
958 MW 8.
1029 MW 24.
1020 MW 9.
1023 MW 25.
1014 MW 10.
1014 MW 26.
1012 MW 11.
1015 MW 27.
1016 MW 12.
1024 MW 28.
1016 MW 13.
1027 MW 29.
1015 MW
'14.
1030 MW 16.
1030 MW 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 i
output sheet should be footnoted to explain the apparent anomaly.
(0625M/62M) i
en****ee******eeeemeneene.
R; port Period August, 1986 UNIT SHUTDOWNS / REDUCTIONS BYRON
- e*****************
i No.
Date T_ype Hours Reason Method LER Number System Component Cause & Corrective Action to Prevent Recurrence 11) 9/21/86 F
0 A
5 1B waterbox tube leak. Welded a plug in both ends of the tube which corrected the problem.
l 12) 9/30/86 F
14.49 H 3
Contractor personnel were working in ESF test I
cabinet and damaged a cable causing a plant trip.
l T
5 coceae*********
The Unit operated at 93% power for most of the reporting period. A reduction in power occurred on Summary 9/21/86 for the repair of a waterbox tube leak and a reactor trip occurred on 9/30/86. The Unit is returning to power from Hot Standby following the reactor trip.
TYPE Reason Method System & Component l
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-Contit.ued Data Entry Sheet E-Operator Training 5-Reduced Load Licensee Event Report
& License Examination 9-Other (LER) File (NUREG-0161)
(0625M/0062M) i (0625M/62M) i
e O E.
UNIQUE REPORTING REQUIREMENTS 1.
Safety / Relief valve operations for Unit One.
VALVES NO & TYPE PLANT DESCRIPTION DATE ACTUATED ACTUATION CONDITION OF EVENT None 2.
Licensee generated changes to ODCM.
(Y/N)
No s
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i (0625M/62M)-
F.
LICENSEE EVENT REPORTS The following is a tabular summary of all Licensee Event Reports for Byron Nuclear Power Station, Unit One, submitted during the reporting period, September 1 through September 30, 1986. This information is provided pursuant to the reportable occurrence reporting requirements as set forth in 10CFR 50.73.
Licensee Event Report Number Date Title of Occurrence 86-025 9-23-86 Failure to meet reporting requirements of Technical Specification 3.12.1 due to personnel error.
s D
(0625M/62M)
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October 10, 1986 LTR:
BYRON 86-1270 File:
2.7.200 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 Power Station for the period September 1 through September 30, 1986.
Paul H. Dandrea (extension 2341) has replaced Joseph E. Langan as preparer of this report for the NRC Greybook.
Very truly yours,
/
9
[
the R. E. Querio l
Station Manager Byron Nuclear Power Station REQ /PHD/bb l
cc:
J.G. Keppler, NRC, Region III NRC Resident Inspector Byron Gary Wright, Ill. Dept. of Nuclear Safety D.P. Galle T. J. Malman D.L. Farrar Nuclear Fuel Services, PWR Plant Support L. Anastasia, Station Nuclear Engineering INPO Records Center Thermal Group, Tech Staff Byron Station Nuclear Group, Tech Staff Byron Station L. Olshan - USNRC P. H. Dandrea (0625M/62M)
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