ML20213H074

Monthly Operating Rept for Oct 1986

ML20213H074
Person / Time
Site:	Byron
Issue date:	10/31/1986
From:	Dandrea P, Querio R COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF ADMINISTRATION (ADM), NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
BRYON-86-1393, NUDOCS 8611190072
Download: ML20213H074 (8)

Text

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L BYRON NUCLEAR POWER STATION UNIT 1 MONTHLY PERFORMANCE REPORT i

COMMONWEALTH EDISON COMPANY NRC DOCKET NO. 050-454 LICENSE NO. NPF-37 f

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8611190072 861031

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Monthly Report for Byron Unit 1 A.

Summary of Operating Experience for Unit 1 The Unit began this reporting period on October 1 in Hot Standby.

The Unit 1 Reactor was taken critical on October 2 at 0609 hours0.00705 days <br />0.169 hours <br />0.00101 weeks <br />2.317245e-4 months <br />. At 0650 hours0.00752 days <br />0.181 hours <br />0.00107 weeks <br />2.47325e-4 months <br /> a " Rod Control Urgent Failure" alarm was received causing operators to enter a Limiting Condition of operation. At 1150 hours0.0133 days <br />0.319 hours <br />0.0019 weeks <br />4.37575e-4 months <br /> on October 2, the reactor was manually tripped. A faulty circuit card in the Rod Drive power cabinet was later determined to be the problem and was replaced.

The Reactor was again taken critical on October 2 at 2149 hours0.0249 days <br />0.597 hours <br />0.00355 weeks <br />8.176945e-4 months <br /> and the generator was synchronized to the grid on October 3 at 0103 hours0.00119 days <br />0.0286 hours <br />1.703042e-4 weeks <br />3.91915e-5 months <br />.

On October 10, reactor power was decreased to 70% to allow isolation of the IC condenser waterbox for cleaning. The unit was returned to 93% power on October 13, 1986.

On October 28, reactor power was decreased to 71% to allow isolation of the 1A waterbox for repairs. The unit returned to 93% power on October 31, and remained at that level for the remainder of the reporting period.

The Hot Leg Temperature Reduction Program to prevent stress corrosion J

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 administratively evaluated as to its continuance.

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OPERATING DATA REPORT DOCKET NO.:

050-454 UNIT: Byron One-DATE:

11/10/86 COMPILED BY:

P. H. Dandrea TELEPHONE:

(815)234-5441 x2341 OPERATING STATUS 1.

Reporting Period: ' October 1986. Gross Hours: 745 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): 1105 (MWe-gross) 4.

Reasons for Restriction (If Any): Reduction of Hot Leg Temperature for Prinwry Water Stress Corrosion Cracking Concerns.

THIS MONTH YR TO DATE CUMULATIVE

• 5.

Report Period Hrs.

745 7296 9865

6. 'Rx Critical Hours 704.9 6359.9 8349.4 7.

Rx Reserve Shutdown Hours 0

21.7 37.8 8.

Hours Generator on Line 696 6297.3 7489.7 9.

Unit Reserve Shutdown Hours 0

0 0

10. Gross Thermal Energy (MWH) 2018377 18613229

'21952421

11. Gross Elec. Energy (MWH) 678578 6291503

.7380093

12. Net Elec. Energy (MWH) 639377 5931859 6944757

13. Reactor Service Factor 94.6 87.2 84.6

14. Reactor Availability Factor 94.6 87.4 85.0

15. Unit Service Factor 93.4 86.3 75.9

16. Unit Availability Factor 93.4 86.3 75.9

17. Unit Capacity Factor (MDC net)

N/A N/A N/A

18. Unit Capacity Factor (DER net) 76.6 72.6 62.9

19. Unit Forced Outage Hrs.

49 674.4 777

20. Unit Forced Outage Rate 6.6 9.7 9.4

21. Shutdowns Scheduled Over Next 6 Months: Scheduled refueling outage to start 2/13/87

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.

(0625M/62M)

7 C.

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.:

050-454 UNIT: Byron One DATE:

11/10/86 COMPILED BY:

P. H. Dandrea TELEPHONE:

(815)234-5441 x2341 MONTH: October, 1986 DAY AVERAGE DAILY POWER LEVEL (MWe-Net) 1.

O MW 17.

1025 MW 2.

O MW 18.

1024 MW 3.

482 MW 19.

1025 MW 4.

805 MW 20.

1021 Mti 5.

876 MW 21.

991 MW 6.

986 MW 22.

975 MW 7.

1025 MW 23.

1014 MW 8.

1024 MW 24.

1021 MW 9.

1015 MW 25.

1011 MW 10.

756 MW 26.

930 MW 11.

754 MW 27.

910 MW 12.

753 MW 28.

749 MW 13.

980 MW 29.

749 MW 14.

1021 MW 30.

748 MW 15.

1021 MW 31.

953 MW 16.

1019 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.

(0625M/62M)

Rzport Period October, 1986 UNIT SHUTDOWNS / REDUCTIONS BYRON

• • • • • • • • • • • • • • • • • • a****a**

No.

Date Type Hours Reason Method LER Number System Component Cause & Corrective Action to Prevent Recurrence 12) 9/30/86 F

39 H

3 Continued outage from last month.

13) 10/2/86 F

10 A

2 Faulty Circuit Card in Rod Drive Power Cabinet. The circuit card was replaced.

14) 10/10/86 F

0 A

5 Reduced power to isolate 1C waterbox for cleaning.

15) 10/28/86 F

0 A

5 Reduced power to isolate lA waterbox for repair.

.b" ene************

The Unit was in an outage at the beginning of the reporting period and experienced one reactor trip and Summary two power reductions. The unit operated at 93% power for much of the reporting period and was operating at 93% power at the end of the reporting period.

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)

(0625M/0062M)

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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)

No 3.

Indications of failed fuel.

(Y/N)

Yes. Iodine spikes during power changes indicate failed fuel. Judging from the extent of the spikes it is estimated that there are four to eight failed rodlets.

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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, October 1 through October 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 Occurrence 84-010-01 10-16-86 Boron Dilution Protection System Blocked Indication 84-019-01 10-16-86 Boron Dilution Protection Actuation 84-031-01 10-10-86 Boron Dilution Protection Actuation 86-007-01 10-16-86 Auto Start of Train "B" Control Room Ventilation Makeup Fan Due to Radiation Monitor Noise Spikes 86-012-01 10-16-86 Rod Position Indication Surveillance Not Performed Within Required Periodicity Due to Personnel Error j

86-026-00 10-16-86 Control Room Ventilation Actuation Due to Lightning Induced Voltage Transient 86-027-00 10-28-86 Reactor Trip Due to Damaged Test Cable Caused by Personnel Error 86-028-00 10-29-86 Manual Reacto,r Trip Due to Rod Drop Caused bi Faulty Circuit Cards I

(0625M/62M)

30 - Y39' November 10, 1986 LTR:

BYRON 86-1393 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 October 1 through October 31, 1986.

Very truly yours,

• ' N R. E. Querio Station Manager l

Byron Nuclear Power Station REQ /PHD/bb cc:

J.G. Keppler, NRC, Region III NRC Resident Inspector Byron Gary Wright, Ill. Dept. of Nuclear Safety D.P. Galle T. J. Maiman 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 v

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