ML20063A726

Monthly Operating Rept for Dec 1993 for DBNPS Unit 1

ML20063A726
Person / Time
Site:	Davis Besse
Issue date:	12/31/1993
From:	Koch S, Jeffery Wood TOLEDO EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
KB94-0001, KB94-1, NUDOCS 9401260309
Download: ML20063A726 (6)

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TOLEDO

%s EDISON A Centenor Energy Company EDISON PLAZA 300 MADISON AVENUE TOLEDO. OHIO 43652-0001 l

January 13, 1994 KB94-0001

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Docket No. 50-346 l

License No. NPF-3 i

U.S. Nuclear Regulatory Commission I

Document Control Desk Vashington, D.C.

20555 l

Gentlemen:

i Monthly Operating Report, December 1993 Davis-Besse Nuclear Power Station Unit 1 Enclosed are ten copies of the Monthly Operating Report for Davis-Besse-Nuclear Power Station Unit No. 1 for the month of December 1993.

If you have any questions, please contact S. D. Koch at (419) 321-7791.

Very truly yours,

,t u

Je n K. Vood

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Plant Manager Davis-Besse Nuclear Power Station SDK/dmc Enclosures cc:

Mr. R. J. Stransky NRC Senior Project Manager Mr. J. B. Martin Region III Administrator 4

Mr. S. Stasek NRC Senior Resident Inspector i

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9401260309 931231 5

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AVERAGE DAILY GTIT PCHER LEVEL D00TP 10 50-0346 GIIT Davis-Besse Unit 1 DATE 1/04/94 00MPIEfED BY STEVE KOQi TELEPHONE 419-321-7791 W.tml DECEMBER 1993 AVERAGE DAILY ECWER LEVEL AVERAGE DAILY POWER LEVEL DAY (MWe-Net)

DAY (Mie-Net) 1 877 17 877 2

878 18 576 3

878 19 844 4

878 20 877 5

878 21 877 6

877 22 877 7

879 23 880 8

879 24 880 9

879 25 878 10 879 26 879 11 879 27 880 12 879 28 879 13 879 29 879 14 879 30 879 15 879 31 879 16 878 INSIEUCTIQiS On this format, list the average daily unit power level in MWe-Net for each day in the reporting month. Ctxtpute to the nearest whole megawatt.

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OPERATING DATA REPORT DOCKET NO 50-0346 DATE 1-4-94 COMPLETED BY STEVE KOCH TELEPHONE 419-321-7791 OPERATING STATUS 1.

Unit Names Davis-Besse Unit 1 Notes 2.

Reporting Period..................... DECEMBER 1993 3.

Licensed Thermal Power (MWt).............

2772 4.

Nameplate Rating (Gross MWe)............. 925 5.

Design Electrical Rating (Net MWe).......

906 e

6.

Maximum Dependable Capacity (Gross MWe).. 921 7.

Maximum Dependable capacity (Net MWe).... 877 8.

If Changes occur in capacity Ratings (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):

This Month Yr-to-Date Cumulative

11. Hours In Reporting Period..............

744.00 8760.00 135193.00

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12. Number Of Hours Reactor Was Critical...

744.00 7305.45 82240.45

13. Reactor Reserve Shutdown Hours.........

0.00 0.00 5532.00

14. Hours Generator On-Line................

744.00 7248.33 80023.73

15. Unit Reserve Shutdown Hours............

0.00 0.00 1732.50

16. Gross Thermal Energy Generated (MWH)...

2039083 19283806 199962929

17. Gross Electrical Energy Generated (MWH) 678844 6407708 66340021

18. Net Electrical Energy Generated (MWH)..

645465.

6083397 62526370

19. Unit Service Factor....................

100.00 82.74 59.19

20. Unit Availability Factor...............

100.00 82.74 60.47

21. Unit Capacity Factor (Using MDC Net)...

98.92 79.18 52.74

22. Unit Capacity Factor (Using DER Net)...

95.76 76.65 51.05

23. Unit Forced Outage Rate................

0.00 0.79 21.33

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

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

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

Forecast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION

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lRIIT SHUTDOVNS AND POVER REDUCTIONS a

DOCKET No..

50-346

. UNIT NAME:

Davis-Besse #1 DATE:

Completed by: Steve Koch Report Month Deccaber 1993 Telephone:

(419)321-7791

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No.

Date t "4 3u Ev.nt 3

3 Action to Report g "O

A j g-Prevent Recurrence

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93-12-1E S

0 B

5 N/A N/A N/A Planned power reduction to approxi-mately 65 percent to plug leaking Main Condenser tubes and clean water boxes for Circulating Water Loop 1 and control valve testing.

10 93-12-22 F

0 A

5 93-09 VI TBG An Unusual Event was declared.

The plant entered Technical Speci-fication 3.0.3 when both Control Room Emergency Ventilation System (EVS) trains were inoperable.

A leaking tube run was repaired to return one train of Control Room EVS to operable status, thus exiting the T.S. and the Emergency Classification.

P: Forced Reason:

' Exhibit G - Instructions for Preparation of Data Method:

s: scheduled A-Equipment Failure (Explain) 1-Manuel B-Maintenance or Test Entr-* Sheets f or t.icensee Event Report (IIR) 2-Manual Scram File (NUPIG-C161)

C-Refueling 3-Automatic Scram D-Regulatory Restriction 4-<ontinuation from E-Operator Training'& License Examination Previous Month

' Exhibit I - Same Source F-Administrative 5-toad Beduction G 4perational Error (Explain)

• Report challenges to Power Operated Relief Valves 9-Other (Emplain)

(PCRVs) and Pressuriser Code Safety Valves (PCSVs)

H4ther (Explain)

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OPERATIONAL

SUMMARY

December 1993 Reactor power was maintained at approximately 100 percent full power until 0000 on December 18, 1993, when a planned power reduction to approximately 65 percent was initiated to perform the following activities:

a) Clean Main Condenser water boxes b) Locate and repair Main Condenser tube leaks c) Perform control valve testing Following the testing and repairs, reactor power was returned to approximately 100 percent power at 0445 hours0.00515 days <br />0.124 hours <br />7.357804e-4 weeks <br />1.693225e-4 months <br /> on December 19, 1993. On December 22, 1993, at 1245 hours0.0144 days <br />0.346 hours <br />0.00206 weeks <br />4.737225e-4 months <br />, the plant entered Technical Specification (TS) 3.0.3 due to both trains of the Control Room Emergency Ventilation System (CREVS) being declared inorerable. An Unusual Event was declared and a power reduction to approximately 98 percent power was initiated. A leaking tubing line on the CREVS #1 compressor was repaired and the train declared operable. At 1357 hours0.0157 days <br />0.377 hours <br />0.00224 weeks <br />5.163385e-4 months <br /> on December 22, 1993, TS 3.0.3 and the Unusual Event were exited. At 1422 hours0.0165 days <br />0.395 hours <br />0.00235 weeks <br />5.41071e-4 months <br /> reactor power was restored to approximately 100 percent. This power level was maintained for the remainder of the month.

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