ML20197D071
| ML20197D071 | |
| Person / Time | |
|---|---|
| Site: | Byron  |
| Issue date: | 02/28/1986 |
| From: | Langan J, Querio R COMMONWEALTH EDISON CO. |
| To: | NRC OFFICE OF ADMINISTRATION (ADM), NRC OFFICE OF RESOURCE MANAGEMENT (ORM) |
| References | |
| BYRON-86-0226, BYRON-86-226, NUDOCS 8605140119 | |
| Download: ML20197D071 (8) | |
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BYRON NUCLEAR POWER STATION UNIT 1 MONTHLY PERFORMANCE REPORT 1
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COMMONWEALTH EDISON COMPANY i
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j NRC DOCKET NO. 050-454 i
i LICENSE NO. NPF-37 l
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B605140119 860228 PDR ADOCK 05000454 PDR 3
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Monthly,R: port fcr Byron Unit 1 A.
Summary of Operating Experience tor Unit 1 The Unit was on line for approximately 58% of the month.
It began February at reduced power level due to condenser waterbox cleaning continuing from the previous month.
The Unit reached 98% power on February 4 and remained at power until February 17.
On the 17th the Reactor tripped due to a Main Generator / Turbine trip. The Main Generator / Turbine trip resulted from a transformer phase imbalance caused by icing on the transmission lines.
The Unit went into a scheduled outage following the trip and remained in the outage-through the end of the reporting period.
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OPERAT"*3 DATA REPORT LOCKET NO.: 050-454 UHIT: Byron One DATE: 3/12/86 COMPILED BY:
J.E. Langan i
TELEPHONE:
(815)234-5441 x2825 OPERATING STATUS 1.
Reporting Period: February 1986. Gross Hours:
672 2.
Currently Authorized Power Level (MWt): 3411 Design Electrical Rating: 1175 (MWe-gross)
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Design Electrical Rating: 1120 (MWe-net)
Max Dependable Capacity (MWe-net): NOT DETERMINED 3.
Power Level to Which Restricted (If Any): 1152 (MWe-gross) 4.
Reasons for R_es'triction (If Any): Not meeting minimum requirement on split feedwater flow.
THIS MONTH YR TO DATE CUMULATIVE
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Report Period Hrs.
672 1416 3985 6.
Rx Critical Hours 392.2 1103.7 3096.2 r
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Rx Reserve Shutdown Hours 0
21.7 37.8 8.
Hours Generator on Line 392.2 1063.3 2255.7 9.
Unit Reserve Shutdown Hours 0
0 0
- 10. Gross Thermal Energy (MWH) 1211423 3241070 6580262
- 11. Gross Elec. Energy (MWH) 409118 1076886 2165476
- 12. Net Elec. Energy (MWH) 303390 1012424 2025322
- 13. Reactor Service Factor 58.4 77.9 77.7
- 14. Reactor Availability Factor 58.4 79.5 78.6
- 15. Unit Service Factor 58.4 75.1 56.6
- 16. Unit Availability Factor 58.4 75.1 56.6
- 17. Unit Capacity Factor (MDC net)
N/A N/A N/A
- 18. Unit Capacity Factor (DER net) 50.9 63.8 45.4
- 19. Unit Forced Outage Hrs.
29.8 102.7 205.3
- 20. Unit Forced Outage Rate 7.1 8.8 8.3
- 21. Shutdowns Scheduled Over Next 6 Months: None.
- 22. If Shutdown at End of Report Period, Estimated Date of Startup: March 4, 1986
- 23. Units in Test Status (Prior to Conunercial Operation): None
- Note - The cumulative numbers do not reflect power generated prior to commercial service.
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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.
050-454 UNIT: Byron One DATE: 3/12/86 COMPILED BY:
J.E. Langan TELEPHONE:
(815)234-5441 x2825 MONTH: February, 1986 DAY AVERAGE DAILY POWER LEVEL (MWe-Net) 1.
493 MW 17.
341 MW 2.
495 MW 18.
O MN 3.
954 MW 19.
O MW 4.
102_0 MW 20.
O MW 5.
1071 MW 21.
O MW 6.
1071 MW 22.
O MW 7.
1072 MW 23.
'0_ MW 8.
1070 MW 24.
O MW 9.
1063 W 25.
O MW 10.
1062 MW 26.
O MW 11.
1061 MW 27.
O MW 12.
1070 MW 28.
O MW 13.
1071 MW 14.
1069 MW 15.
1063 MW 16.
1071 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 not electrical rating of the unit there may be occasions when the daily average power level exceeds the 100% line (or 1
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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1 eeeeeeeeeeeeeeeeeeeeeeeeee Report Period February, 1986 UNIT SHUTDOWNS / REDUCTIONS BYRON eenee. ***eeeeeeeeeeeeee.
No.
Date Type Hours Reason Method LER Number System ramtvwu nt Cause & Corrective Action to Prevent Recurrence 5) 86/01/31 S
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4 N/A KE COND
- Condenser Waterbox cleaning continued from previous month.
6) 86/02/17 F
29.8 H*
3 86-08 EZ XPT
- Generator / Turbine / Reactor Trip due to Main Transformer phase imbalance caused by Transmission Tower icing.
7) 86/02/18 S
250.0 B 9**
N/A N/A N/A
- Decision made to enter the planned outage which was originally scheduled for 5/15/86.
o - External Cause 00 - Scheduled outage began after Rx Trip.
cocccome***eese j
o Summary 17 days of power operations, one unplanned Rx trip, and 11 days of scheduled outage.
occocene.......
TYPE Reason Method System & rn=panant 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)
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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)
None l
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LICENSEE EVENT REPORTS The following is a tabular sumary of all Licensee Event Reports for Byron Nuclear Power Station, Unit One, submitted during the reporting period, February 1 through February 28, 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 85-070-01 2-6-86 Failure of the IB Residual Heat
Removal Pump Due to High Vibration.
86-001-00 2-7-86 Reactor Trip During Reactor Trip Breaker Surveillance Due to an Inadequate Temporary Procedure.
86-002-00 2-18-86 Control Room Ventilation Actuation Due to Radiation Monitor OPR31J Iodine Channel Spike.
86-003-00 2-21-86 Reactor Trip Due to DC Grounds Which Caused a Main Steam Isolation Valve Closure.
86-004-00 2-24-86 Auto-Start of Auxiliary Building Charcoal Booster Fan Due to Failed Relay.
86-005-00 2-24-86 Station Blowdown Radiation Monitor Inoperable and Technical Specification Action Not Taken Due to Personnel Error.
(0625M/62M)
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March 12, 1986 LTR:
BYRON 86-0226 File:
2.7.200 Director, Office of Managemend Information and Program Control j
United States Nuclear Regulatory Comission I
Washington, D.C.
20555 ATTN:
Document Control Desk s
i Gentlemen:
Enclosed for your information is the Monthly Performance Report covering Byron 1
Nuclear Power, Station for the period February 1 through February 28,-1986, i
l Very truly yours, 1
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Station Manager Byron Nuclear Power Station 4
REQ /JEL/lr i
Enclosures i
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cc:
J.G. Keppler, NRC, Region III j
NRC Resident Inspector Byron Gary Wright, Ill. Dept. of Nuclear Safety i
D.P. Galle, CECO l
T. J. Maiman i
D.L. Farrar, CBCo l
Nuclear Fuel Services, PWR Plant Support G. R. Benson, Revenue Requirements INPO Records Center Thermal Group, Tech Staff Byron Station j
Nuclear Group, Tech Staff Byron Station J. Langan L. Olshan - USNRC i
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