ML20115C743

Monthly Operating Rept for Mar 1985

ML20115C743
Person / Time
Site:	Byron
Issue date:	03/31/1985
From:	Querio R, Toney J COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF ADMINISTRATION (ADM), NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
BYRON-85-0499, BYRON-85-499, NUDOCS 8504180541
Download: ML20115C743 (8)

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BYRON NUCLEAR POWER STATION UNIT 1 MONTHLY PERFORMANCE REPORT COMMONWEALTH EDISON COMPANY NRC DOCKET NO. 050-454 LICENSE NO. NPF-37 r

8504180541 850331 7 PDR ADOCK 05000454 s R PDR '

61(L (0625M) l

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,I.; Monthly __Riport for Byron Unit l' A. Sununary of Operating Experience for Unit 1 During this reporting period, Byron Station's Unit 1 continued in the Startup Testing Program, and achieved significant objectives toward

. Commercial Operations. ,.

'The Unit 1 testing activities were highlighted by the performance of the " Loss of Offsite Power". test, and the " Unit Shutdown from Outside the Control Room" test.

Byron Station's Unit l'starte'd this reporting period in a hot-standby

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condition. On March 1, at 0613 hours0.00709 days <br />0.17 hours <br />0.00101 weeks <br />2.332465e-4 months <br />, the reactor was taken-critical. At 2131 hours0.0247 days <br />0.592 hours <br />0.00352 weeks <br />8.108455e-4 months <br />, initial synchronization of the main-generator to the grid was achieved. A Reactor Trip on Turbine Trip occurred at 2136 hours0.0247 days <br />0.593 hours <br />0.00353 weeks <br />8.12748e-4 months <br /> due to Turbine Control (DEHC) failure to pick tqp electrical load.

On March 2, at 0651 hours0.00753 days <br />0.181 hours <br />0.00108 weeks <br />2.477055e-4 months <br />, the Unit 1 reactor achieved criticality, and the generator was synchronized to the grid at.1440 hours0.0167 days <br />0.4 hours <br />0.00238 weeks <br />5.4792e-4 months <br />. The reactor maintained criticality until March 4, at 2011 hours0.0233 days <br />0.559 hours <br />0.00333 weeks <br />7.651855e-4 months <br />, when a Turbine Trip initiated a Reactor Trip during a turbine valve surveillance.

On March 5, during reactor startup at 0126 hours0.00146 days <br />0.035 hours <br />2.083333e-4 weeks <br />4.7943e-5 months <br />, a Reactor Trip resulted from a personnel error. At 1108 hours0.0128 days <br />0.308 hours <br />0.00183 weeks <br />4.21594e-4 months <br /> the reactor was taken critical and remained critical until March 8 at 1004 hours0.0116 days <br />0.279 hours <br />0.00166 weeks <br />3.82022e-4 months <br /> when a

. Reactor Trip was initiated due to a low-low steam generator level.

On_ March 9, at-0120 hours, the reactor. achieved criticality and

-remained critical until.2100 hours0.0243 days <br />0.583 hours <br />0.00347 weeks <br />7.9905e-4 months <br /> at which time the reactor was tripped for the purpose of testing.

On March 12, at 0413 hours0.00478 days <br />0.115 hours <br />6.828704e-4 weeks <br />1.571465e-4 months <br />,1the reactor was taken critical and remained critical until March 14, at 2102 hours0.0243 days <br />0.584 hours <br />0.00348 weeks <br />7.99811e-4 months <br />, when a Reactor Trip was initiated due to " Loss of Offsite Power" testing. At 2153 hours0.0249 days <br />0.598 hours <br />0.00356 weeks <br />8.192165e-4 months <br /> Safety Injection was initiated due to low steam'line pressure. At 2209 hours0.0256 days <br />0.614 hours <br />0.00365 weeks <br />8.405245e-4 months <br />, an " Unusual Event" was declared due to the failure of two main steam isolation, valves (MSIV's) to close on a Safety Injection signal. This unusual event was terminated at 2312 hours0.0268 days <br />0.642 hours <br />0.00382 weeks <br />8.79716e-4 months <br />.

On March 19, at 2253 hours0.0261 days <br />0.626 hours <br />0.00373 weeks <br />8.572665e-4 months <br />, an inadvertent manual Safety Injection was initiated during MSIV testing. .

On March 29, at 1703 hours0.0197 days <br />0.473 hours <br />0.00282 weeks <br />6.479915e-4 months <br />, the reactor was taken critical and remained critical until 2357-hours when a Reactor Trip was initiated due to a power range high negative rate trip signal caused by multiple rod drops.

On March 30, at 2127, the reactor was taken critical and remained critical through the end of this' reporting period.

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-B. OPERATING DATA REPORT DOCKET NO.: 050-454-UNIT: Byron One DATE: 4/8/85 COMPILED BY: J.P. Toney TELEPHONE: (815)234-5441 x437 OPERATING STATUS

1. Reporting Period: March 1985 Cross Hours in Reporting Period: 744

2. Currently Authorized. Power Level (MWt): 3411 Design Electrical Rating: 1175 (MWe-gross)

1129 (MWe-net)

3. ~ Power. Level to Which Restricted (If Any): 361 (MWe-net)

4. Reasons for Restriction (If Any): START UP TESTING PROGRAM THIS MONTH YR TO DATE CUMULATIVE

5. Number of Hours Reactor was Critical 258.0 651.4 651.4

6. ' Reactor Reserve Shutdown Hours 0 0 0

7. Hours Generator on Line 160.4 160.4 160.4

8. . Unit Reserve Shutdown Hours 0 0 0

9. Gross Thermal Energy Generated (MWH) 81105 98263 98263 10.-Gross Elec. Energy Generated (MWH) 17060 17060 17060 11'. Net Elec. Energy Generated (MWH) -4154 -4154 -4154

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: N/A

21. Units in Test Status (Prior to Commercial Operation): Unit 1 FORECAST ACHIEVED Initial Criticality 1-25-85 2-2-85 Initial Electricity 3-1-85 Conunercial Operation (0625M)

7 C .' ' AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.: 050-454 UNIT: Byron One DATE: 4/8/85

~ COMPILED BY: J.P. Toney TELEPHONE: (815)234-5441

-x437 MONTH: March, 1985

1. 0 - 17. 0 2.. 12MW 18. 0

3. 2MW~ 19. 0

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-4. 55MW 20. 0

5. 29MW 21. 0

6. 75MW 22. 0

7. 102MW 23. 0 8.- 50MW- 24. 0

9. 75MW . 25. 0

10. 0 26. 0

.11. 0 27. 0

12. 0 28. 0

'13. - 57MW 29. 3MW

14. IllMW ~ 30.' ~0

15. 0 31. 134MW c 16'. 0-

, 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)

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E. UNIT SHUTDOWNS AND POWER kE!Xx7 IONS DOCKET NO.: 050-454

UNIT

Byron One DATE: 4/8/85 COMPILED BY: J.P. Toney TELEPHONE: (815)234-5441

• x437 REPORT MONTH: March, 1985 METHOD OF TYPE SHUTTING DOWN F: FORCED DURATION THE REACTOR OR CORRECTIVE NO. DATE S: SCHEDULED (HOURS) REASON (1) REDUCING POWER ACTIONS / COMMENTS N/A (0625M)

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E. ' UNIQUE REPORTING REQUIREMEIES

1. - Safety / Relief valve operations for Unit One.

VALVES NO & TYPE PLANT DESCRIPTION DATE ACTUATED ACTUATION CONDITION OF EVENT 3/14/85 1RY456 3-AUTO 3 Simulated loss of offsite power i

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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, during the reporting period, March 1 through March 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 84-041-00 3-11-85 UV Detector Failure Prior to License.

85-018-00 '3-1-85 Fire Protection Detectors Documentation Error.

85-020-00 3-16-85 Spurious SI Actuation.

021-00 3-15-85 Failure of an hourly fire watch.

85-022-00~ 3-19-85 Power Range Excore Neutron Detector Failure.

85-023-00 3-19-85 Steamline Low Pressure SI/RX Trip.

85-024-00 3-19-85 Turbine Trip / Reactor Trip during syncronization.

85-025-00 3-25-85 Missed surveillance for Reactor Start-up #7.

85-026-00 3-29-85 1PRllJ Radiation Monitor Inoperable.

85-027-00 3-29-85 Failure of MSIV to close on MS isolation signal.

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/ \ Commonwealth Edison . '

( - / Byron NucisarStation

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_ . sd Byron, Illinois 61010..

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' April 8,-1985 l l

LTR: BYRON 85-0499

. File: 2.7.200 Director, Office of Management Information and Program Control. . .

United States Nuclear Regulatory Com.ission 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 March 1-through March 31, 1985.

Very truly yours,.

bb R. E. Querio

. Station Superintendent Byron Nuclear Power Station REQ /JPT/cib

' Enclosure

.cc: J.G. Keppler, NRC, Region III

'NRC Resident Inspector Byron -

. Gary Wright, Ill.. Dept. of Nuclear Safety D.P. Galle, CECO D.L. Farrar, CECO INPO Records Center

Thermal Group, Tech Staff Byron Station Nuclear Group, Tech Staff Byron Station (0625M)

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