ML20134E261
| ML20134E261 | |
| Person / Time | |
|---|---|
| Site: | Byron  |
| Issue date: | 07/31/1985 |
| From: | Langan J, Querio R COMMONWEALTH EDISON CO. |
| To: | NRC OFFICE OF ADMINISTRATION (ADM), NRC OFFICE OF RESOURCE MANAGEMENT (ORM) |
| References | |
| (0625M), (625M), BYRON-85-1124, NUDOCS 8508200112 | |
| Download: ML20134E261 (8) | |
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BYRON NUCLEAR PONER STATION UNIT 1 MONTHLY PERFORMANCE REPORT COMMONWEALTH EDISON COMPMlY NRC DOCKET NO. 050-454 LICENSE NO. NPF-37 i
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8508200112 850731ADOCK 05000454 PDR PDR R
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Monthly Report f r Byron Unit 1 A.
Summary of Operating Experience for Unit 1 Byron Station's Unit 1 continued to achieve significant objectives towards finishing the startup program.
The Unit began this reporting period in a planned maintenance outage.
Startup after the outage began on July 7th. On July 8th the Turbine was manually tripped due to a decreasing Reactor Coolant temperature caused by a misaligned Control Rod. A Reactor Trip resulted from the Turbine Trip. The Unit was taken critical on July 9th and brought to 98% Power.
On July 12th the Reactor tripped while executing the 50% Load Rejection Startup Test. A Reactor Coolant overtemperature condition was the cause of the trip. In the process of returning to power, on July 13th, the Reactor tripped from a high negative flux rate. This occurred when a group of Control Rods dropped coincident with a lightning strike.
The Unit remained shutdown until July 23rd to investigate and repair problems resulting from the lightning strike. The Unit was returned to 98% Power on July 24th. The 100% Power Reactor Trip Startup Test was executed on July 27th. The Unit remained shutdown through the end of the reporting period for repairs.
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B.
OPERATING DATA REPORT DOCKET NO.: 050-454 UNIT: Byron One DATE: 8/12/85 COMPILED BY:
J.E. Langan TELEPHONE:
(815)234-5441 x2825 OPERATING STATUS 1.
Reporting Period: July 1985 Gross Hours in Reporting Period:
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): 1175 (We-gross) 4.
Reasons for Restriction (If Any): START UP TESTING PROGRAM THIS MONTH YR TO DATE CUMULATIVE 5.
Number of Hours Reactor was Critical 213.5 2714.8 2714.8 6.
Reactor Reserve Shutdown Hours 0
0 0
7.
Hours Generator on Line 201.4 2123.0 2123.0 8.
Unit Reserve Shutdown Hours 0
0 0
9.
Gross Thermal Energy Generated (MWH) 568273 3942521 3942521
- 10. Gross Elec. Energy Generated (MWH) 187804 1217753 1217753
- 11. Net Elec. Energy Generated (MWH) 162297 1065987 1065987
- 12. Reactor Service Factor 0
0 0
- 13. Reactor Availability Factor 0
0 0
- 14. Unit Service Factor 0
0 0
- 15. Unit Availability Factor 0
0 0
- 16. Unit Capacity Factor (Using MDC) 0 0
0
- 17. Unit Capacity Factor (Using Design MWe) 0 0
0
- 18. Unit Forced Outage Rate 0
0 0
- 19. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each) N/A
- 20. If Shutdown at End of Report Period, Estimated Date of Startup: August 2,1985
- 21. Units in Test Status (Prior to Consnercial Operation): Unit 1 FORECAST ACHIEVED Initial Criticality 1-25-85 2-2-85 Initial Electricity 3-1-85 Commercial Operation (0625M)
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C.
AVERAGE DAILY UNIT POEfER LEVEL DOCKET NO.: 050-454 UNIT: Byron One DATE:
8/12/85 COMPILED BY:
J.E. Langan TELEPHONE:
(815)234-5441 x2825 MONTH: July, 1985 1.
O MW 17.
O MW 2.
O MW 18.
O MW 3.
O MW 19.
O MW 4.
O MW 20.
O MW 5.
O MW 21.
O MW 6.
O MW 22.
O MW 7.
O MW 23.
191 MW 8.
O MW 24.
735 MW 9.
718 MW 25.
1067 MW 10.
1078 MW 26.
1076 MW 11.
1080 MW 27.
880 MW 12.
495 MW 28.
O MW 13.
O MW 29.
O MW 14.
O MW 30.
O MW l
15.
O MW 31.
O MW 16.
O 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 output sheet should be footnoted to explain the apparent anomaly.
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R port Period July 1985 UNIT SHUTDOWNS / REDUCTIONS BYRON
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No.
Date T
LER Number System C m ent Cause & Corrective Action to Prevent Recurrence m Hours Reason Method
- 20) 7/1/85 S
168.9 A 4
Continued scheduled outage from 6/27/85.
- 21) 7/8/85 F
14.1 A
2 A manual turbine trip was initiated at 8% Reactor Power due to misalignment of control rod P-8.
A reactor trip resulted.
- 22) 7/12/85 F
10.7 B
3 The reactor tripped during performance of the 50% load rejection test.
- 23) 7/13/85 F
211.3 A 3
The reactor tripped due to high negative flux rate which was caused by lightning.
- 24) 7/27/85 S
100.0 B 2
100% Reactor Trip Startup Test.
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Summary A
Byron 1 is continuing in its 100% Power Test Sequence.
coccome********
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)
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E.
UNIQUE REPORTING REQUIRDENTS 1.
Safety / Relief valve operations for Unit One.
VALVES NO & TYPE PLANT DESCRIPTION DATE ACTUATED ACTUATION CONDITION OF EVENT Rx trip during 7/12/85 Pressurizer 1
50% Load Valve relieved Pcwor Rejection Reactor Coolant Operated Test S 2335 psig.
Relief Valve (0625M)
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LICENSEE EVENT REPORTS The following is a tabular susmary of all licensee event reports for Byron Nuclear Power Station, Unit One, submitted during the reporting period, July 1 through July 31, 1985. 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 84-001-01 7-31-85 Failure of Security to Patrol Fire Watch for Penetration Seals.
84-002-01 7-31-85 Failure to Complete Data Entry on a Shift Surveillance of the Residual Heat Removal System.
84-007-01 7-31-85 Sampling Missed for Vent Stacks for ICOAR on IRE-PR028 and 2RE-PR028 84-015-01 7-31-85 Failure To Take Samples Required by Technical Specifications.
84-027-02 7-25-85 Failure of MSIV to close on MS Isolation Signal.
85-060-00 7-16-85 RNST Temperature above 100*F.
85-061-00 7-24-85 Reactor Trip.
85-006-00 7-25-85 Unit 1 Containment Ventilation Isolation.
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k August 12, 1985 LTR:
BYRON 85-1124 File:
2.7.200 Director, Office of Management Infor: nation 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 July 1 through July 31, 1985.
Very truly yours, mg
./ fpaua R. E. Querio Station Superintendent Byron Nuclear Power Station REQ /JEL/bg Enclosure 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 G. R. Benson, Revenue Requirements INPO Records Center Thermal Group, Tech Staff Byron Station Nuclear Group, Tech Staff Byron Station J. Langan (0625M)