ML20214C051
| ML20214C051 | |
| Person / Time | |
|---|---|
| Site: | Byron  |
| Issue date: | 01/31/1986 |
| From: | Langan J, Querio R COMMONWEALTH EDISON CO. |
| To: | NRC OFFICE OF ADMINISTRATION (ADM), NRC OFFICE OF RESOURCE MANAGEMENT (ORM) |
| References | |
| BYRON-86-0116, BYRON-86-116, NUDOCS 8602200737 | |
| Download: ML20214C051 (8) | |
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4 BYRON NUCLEAR POWER STATION UNIT 1 MONTHLY PERFORMANCE REPORT COMMONWEALTH EDISON COMPANY NRC DOCKEI NO. 050-454 LICENSE NO. NPF-37 h
(0625M/62M) 8602200737 860131
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PDR ADOCK 05000454
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Monthly Report for Byron Unit 1 A.
Summary of Operating Experience for Unit 1 The Unit was on line for 90% of this reporting period. On January 6th the power level restriction of 92%, due to excessive Steam Generator Moisture carryover, was lifted. Currently a power level restriction of 98% is in effect due to excessive Feedwater flow to the 1A Steam Generator lower nozzle.
There were two unplanned reactor trips this month and two forced power reductions. On January 16th the Reactor was tripped by an inadvertent opening of B train Reactor Trip Breaker during a Trip Breaker surveillance. On January 29th the Reacter was tripped from a low Steam Generator level signal caused by a sudden closure of the 1A Main Steam Isolation Valve. This closure was caused by a circuit failure in the valve's eli;ctionics. On January 13th power was reduced to compensate for a Circulating Water pump trip and, on January 17th the Unit was taken off-line briefly to investigate unusual noises in the condenser.
On January 31st the Unit was reduced to approximately 40% power to facilitate a scheduled condenser waterbox cleaning.
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B.
OPERATING DATA REPORT DOCKET NO.:
050-454 UNIT: Byron One DATE: 2/07/86 COMPILED BY:
J.E. Langan TELEPHONE:
(815)234-5441 x2825 OPERATING STATUS 1.
Reporting Period: January 1986. Gross Hours: 744 2.
Currently Authorized Power Level (MWt): 3411 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): 1152 (MWe-gross) 4.
Reasons for Restriction (If Any): Not meeting minimum requirement on split feedwater flow.
THIS MONTH YR TO DATE CUMULATIVE
- 5.
Report Period Hrs.
744 744 3313 6.
Rx Critical Hours 711.5 711.5 1992.5 7.
Rx Reserve Shutdown Hours 21.7 21.7 37.8 8.
Hours Generator on Line 671.1 671.1 1863.5 9.
Unit Reserve Shutdown Hours 0
0 0
- 10. Gross Thermal Energy (MWH) 2029647 2029647 5368839 11,, Gross Elec. r.4ergy (MWH) 667768 667768 1756358
- 12. Net Elec. Energy (MWH) 629034 629034 1641932
- 13. Reactor Service Factor 95.6 95.6 60.1
- 14. Reactor Availability Factor 98.5 98.5 61.3
- 15. Unit Service Factor 90.2 90.2 56.2
- 16. Unit Availability Factor 90.3 90.2 56.2
- 17. Unit Capacity Factor (MDC net)
N/A N/A N/A
- 18. Unit Capacity Factor (DER net) 75.5 75.5 44.3
- 19. Unit Forced Outage Hrs.
72.9 72.9 175.5
- 20. Unit Forced Outage Rate 9.8 9.8 8.6
- 21. Shutdowns Scheduled Over Next 6 Months: Scheduled outage planned for May 15, 1986. The duration of the outage will be 2 weeks.
- 22. If Shutdown at End of Report Period, Estimated Date of Startup: N/A
- 23. Units in Test Status (Prior to Commercial Operation): None
- Note - The cumulative numbers do not reflect power generated prior to commercial service.
j (0625M/62M)
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C.
AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.:
050-454 UNIT: Byron One DATE:
2/07/86 COMPILED BY:
J.E. Langan TELEPHONE:
(815)234-5441 x2825 MONTH: January, 1986 DAY AVERAGE DAILY POWER LEVEL (MWe-Net) 1.
973 MW 17.
47 MW 2.
982 MW 19.
517 MW 4.
1059 MW 20.
1032 MW 5.
1038 MW 21.
1060 MW 6.
1027 MW 22.
1051 MW 7.
1021 MW 23.
1056 MW 8.
1008 MW 24.
1062 MW 9.
1014 MW 25.
1066 MW 10.
1028 MW 26.
1044 MW 11.
1026 MW 27.
1046 MW 12.
1008 MW 28.
1041 MW 13.
832 MW 29.
O MW 14.
979 MW 30.
351 MW 15.
1036 MW 31.
629 MW 16, 223 MW INSTC K:TIONS On this form list the average daily unit power level in MWe-Net for each day in the rcporting 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.
(0625M/62M)
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R: port Period January, 1986 UNIT SHUTDOWNS / REDUCTIONS BYRON enneme***enemennene ******
No.
Date Type Hours Reason Method LER Number System Component Cause & Corrective Action to Prevent Recurrence 1) 86/01/13 F
0 A
5 N/A KE P
- Reduced load due to IB CW pump trip. Pump tripped due to loss of excitation current.
2) 86/01/16 F
13.9 B 3
86-01 JG BKR
- Turbine / Reactor trip resulted during the performance of the B Train Reactor Trip Breaker Surveillance. The cause was attributed to poor cabinet labeling and procedure error.
3) 86/01/17 F
33.4 B 1
N/A KE COND
- The unit was taken off-line to allow for condenser inspection, because of an unusual noise heard coming from the C zone of the condenser.
4) 86/01/2?
F 25.6 A 3
86-03 SB RLY
- Sudden closure of the 1A MSIV caused low level in the 1A S/G, resulting in a reactor trip. The closing relay was energized as a result of ground problems.
5) 86/01/31 S
0 B
5 N/A KE COND
- Reduced load to allow for condenser waterbox cleaning.
1 oone***ne******
The Unit had two unplanned trips, two forced reductions, and one planned reduction.
Summary d
emoce*****e****
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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 Sheat E-Operator Training 5-Reduced Load Licensee Fevent Report j
& License Examination 9-Other (LER) Fila (NUREG-0161) l (0625M)
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E.
UNIQUE REPORTING REQUIREMENTS 1.
Safety / Relief valve operations for Unit One.
VALVES NO & TYPE PLANT
. DESCRIPTION DATE ACTUATED ACTUATION CONDITION OF EVENT None f
l (0625M/62M) 1
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F.
LICENSEE EVENT REPORTS 4
The following is a tabular summary of all licensee event reports for Byron Nuclear Power Station, Unit One, submitted during the reporting period, January 1 through January 31, 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 Occurronce 85-096-00 1-3-86 Incorrect Containment Pressure Loops Utilized to Fulfill Post Accident Monitoring Requirements Due to Misinterpretation.
85-097-00 1-3-86 Inadvertent Safety Injection During Surveillance Testing Due to Ma1 positioned Switch.
85-098-00 1-6-86 Actuation of Main Control Room Ventilation System Due to De-energization of the Associated Rad Monitors.
85-099-00 1-6-86 Actuation of the Main Control Room Ventilation System Due to the Spiking of the Iodine Channel of the OPR31J Rad Monitor.
85-100-00 1-6-86 Construction Equipment Blocking Fire Door in Open Position.
85-101-00 1-16-86 Reactor Trip Due to High Steam Generator Level During Testing.
85-102-00 1-16-86 Missed ISI Surveillance Due to Outage Procedure Deficiency.
(0625M/62M)
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-s February 7, 1986 LTR:
BYRON 86-0116 File:
2.7.200 Director, Office of Management Information and Program Control United States Nuclear Regulatory Commission Washi.qton, 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 January 1 through January 31, 1986.
Very truly yours,
'fAhLc R. E. Querio Station Manager Byron Nuclear Power Station REQ /JEL/bb Enclosures cc:
J.G. Keppler, NRC, Region III NRC Resident Inspector Byron Gary Wright, Ill. Dept. of Nuclear Safety D.P. Galle, CECO T. J. Maiman D.L. Farrar, CECO Nuclear Fuel Services, PWR Plant Support G. R. Benson, Revenue Requirements INPO Records Center Thermal Group, Tech Staff Byron Station Nuclear Group, Tech Staff Byron Station J. Lancan L. Olsham - USNRC
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