ML20140H044

Monthly Operating Rept for May 1997 for Davis-Besse Nuclear Power Station Unit 1

ML20140H044
Person / Time
Site:	Davis Besse
Issue date:	05/31/1997
From:	Lash J, Matranga E TOLEDO EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
KB-97-0090, KB-97-90, NUDOCS 9706180021
Download: ML20140H044 (5)

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TOLEDO

%m EDICON A Centerior Energy Company 1

Davis-Besse Nuclear Power Staten 5501 North State Floute 2 Oak Harbor. OH 43449-9760 June 12,1997 KB-97-0090 l

Document Control Desk l

U. S. Nuclear Regulatory Commission l

' Washington, D. C. 20555 l

l Ladies and Gentlemen:

Monthly Operating Report, May 1997 l

Davis-Besse Nuclear Power Station Unit 1 l

Enclosed is a copy of the Monthly Operating Report for the Davis-Besse Nuclear Power Station for the month of May 1997.

l If you have any questions, please contact E. C. Matranga at (419) 321-8369.

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l Very truly yours, 3M.skbN f

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James II. Lash Plant Manager Davis-Besse Nuclear Power Station f/

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ECM/ljk Enclosure -

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A. B. Beack

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l NRC Reg: m III Administrator

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q A. G. Hansen i

NRC Project Manager S. Stasek

$ r' D,0 NRC Senior Residdnt Inspector 9706190021 970531 ~..

!hl PDR ADOCK 05000346' R

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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-0346 i

UNIT Davis-Besse Unit 1 DATE June 2,1997 COMPLETED BY Eugene C. Matranga TELEPHONE 419/321-8369 MONTH May,199/

l AVERAGE DAILY POWER LEVEL AVERAGE DAILY POWER LEVEL l

DAY (MWe-Net)

DAY (MWe-Net) i 1

876 16 0

)

l 2

879 17 0

3 878 18 0

l 4

453 19 0

1 l

5 0

20 0

l 6

0 21 0

1 7

0 22 0

1

)

8 0

23 0

I 9

0 24 0

10 0

25 0

11 0

26 0

l l

12 0

27 0

i' 13 0

28 46 14 0

29 849 1

15 0

30 877

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OPERATING DATA REPORT DOCKET NO 50-0346 DATE June 2,1997 l

COMPLETED BY Eucene C. Matranca TELEPHONE 419/321-8369 OPERATING STATUS l

1. Unit Name: Davis-Besse Unit 1 Notes l

2. Reportina Period May,1997

3. Licensed Thermal Power (MWt) 2772

4. Nameplate Ratina (Gross MWe) 925

5. Desian Electrical Ratina (Net MWe) 906 i

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6. Maximum Dependable Capacity (Gross MWe) 917 l

7. Maximum Dependable Capacity (Net MWe) 873

8. If Chances Occurin Capacity Ratinas i

j (Items number 3 through 7) since last report, give reasons:

9. Power Level To Which Restricted, If Any (Net MWe):

10. Reasons For Restrictions, if Any (Net MWe):

i This Month Yr-to-Date Cumulative

11. Hours In Reporting Period 744.00 3,623.00 165,120.00

12. Number Of Hours Reactor Was Critical 220.18 3,099.18 109,295.15

13. Reactor Reserve Shutdown Hours 0.00 0.00 5,532.00 l

14. Hours Generator On-Line 174.06 3,047.32 106,950.82

15. Unit Reserve Shutdown Hours 0.00 0.00 1,732.50

16. Gross Thermal Energy Generated (MWH) 467,439 8,395,202 278,974,047

17. Gross Electrical Energy Generated (MWH) 146,281 2,801,708 90,731,785

18. Net Electrical Energy Generated (MWH) 138,030 2,663,283 85,706,477

19. Unit Service Factor 23.40 84.11 64.77

20. Unit Availability Factor 23.40 84.11 65.82

21. Unit Capacity Factor (Using MDC Net) 21.25 84.20 59.46

22. Unit Capacity Factor (Using DER Net) 20.48 81.14 57.29

23. Unit Forced Outage Rate 76.60 15.89 17.24

24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):

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25. If Shut Down At End Of Report Period, Estimated Date of Startup:

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26. Units In Test Status (Prior to Commercial Operation):

Forecast Achieved INITIAL CRITICAllTY INITIAL ELECTRICITY i

COMMERCIAL OPERATION J

W

OPERATIONAL

SUMMARY

May 1997 Reactor power was maintained at approximately 100 percent full power until 0008 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> on May 4,1997, when a manual power reduction was initiated to perform turbine valve testing. Reactor power was reduced to approximately 92 percent full power by 0033 hours3.819444e-4 days <br />0.00917 hours <br />5.456349e-5 weeks <br />1.25565e-5 months <br />, and control valve and stop valve testing were conducted. At the completion of testing at 0117 hours0.00135 days <br />0.0325 hours <br />1.934524e-4 weeks <br />4.45185e-5 months <br />, power was gradually increased to approximately 100 percent full power, which was achieved at 0205 hours0.00237 days <br />0.0569 hours <br />3.38955e-4 weeks <br />7.80025e-5 months <br />.

At 1731 hours0.02 days <br />0.481 hours <br />0.00286 weeks <br />6.586455e-4 months <br /> on May 4,1997, a spurious deluge system activation occurred on the Main Transformer resulting in an automatic reactor trip 4 i

minutes later. The plant was maintained in Mode 3 while various inspections and maintenance were performed.

1 On May 7,1997, a decision was made to replace the Main Transformer and i

preparations are made to enter Mode 5. The cooldown was completed on May 9,1997.

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A plant heatup was commenced at 0538 hours0.00623 days <br />0.149 hours <br />8.895503e-4 weeks <br />2.04709e-4 months <br /> on May 19,1997 and the reactor achieved criticality at 1324 hours0.0153 days <br />0.368 hours <br />0.00219 weeks <br />5.03782e-4 months <br /> on May 26,1997.

L At 0940 hours0.0109 days <br />0.261 hours <br />0.00155 weeks <br />3.5767e-4 months <br /> on May 28,1997, power was increased to approximately 20 percent full power and the Main Turbine was synchronized to the grid at l

1132 hours0.0131 days <br />0.314 hours <br />0.00187 weeks <br />4.30726e-4 months <br />. Power w., increased until 0212 hours0.00245 days <br />0.0589 hours <br />3.505291e-4 weeks <br />8.0666e-5 months <br /> on May 29,1997 when power was held at approximately 80 percent full power for nuclear instrumentation calibration. Nuclear instrumentation calibration was completed at 0405 hours0.00469 days <br />0.113 hours <br />6.696429e-4 weeks <br />1.541025e-4 months <br /> and the power ascension was resumed. The power increase was stopped at 0633 hours0.00733 days <br />0.176 hours <br />0.00105 weeks <br />2.408565e-4 months <br /> at approximately 97 percent full power

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for nuclear instrumentation calibration. Nuclear instrumentation calibration was completed at 0847 hours0.0098 days <br />0.235 hours <br />0.0014 weeks <br />3.222835e-4 months <br /> and the power ascension was resumed. At 1014 hours0.0117 days <br />0.282 hours <br />0.00168 weeks <br />3.85827e-4 months <br />,100 percent full power was achieved.

. Reactor power was maintained at approximately 100 percent full power for the remainder of the month.

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UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.

50-346 UNIT NAME Davis-Besse #1

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DATE June 2,1997 Report Month May.1997 COMPLETED BY E. C. Matranga l

TELEPHONE (419) 321-8369 i

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E E" b Cause & Corrective b

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No Date 8.

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Action to l

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Prevent Recurrence 8

2 97-05-04 F

569.9 A

3 97-010 IC T;S Plant trip occurred after receipt of a fire alarm on the Main transformer and activation of the Deluge Fire t

Protec3on System.

A temperature switch falsely indicated a high temperature condition and activated the Deluge System. 4 of 168 nozzles were not optimally aimed and may have contributed to causing a i

flashover which in tum caused the reactor trip.

The Main Transformer and its re?ated temperature sensors were replaced. Similar transformer sensors were checked. Nozzles not optimally aimed were realigned.

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1 2

3 4

F: Forced Reason:

Method:

Exhibit G-Instructions S: Scheduled A-Equipment Failure (Explain) 1-Manual for Preparation of Data B-Maintenance or Test 2-Manual Scram Entry Sheets for Licensee C-Refueling 3-Automatic Scram Event Report (LER) File (NUREG-D-Regulatory Restriction 4-Continuation from 0161)

E-OperatorTraining & License Examination Previous Month F-Administrative 5-Load Reduction 5

G-Operational Error (Explain) 9-Other (Explain)

Exhibit 1 - Same Source H-Other (Explain)

• Report challenges to Power Operated Relief Valves (PORVs) and Pressurizer Code Safety Valves (PCSVs) t

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