ML20149K771

Monthly Operating Rept for Jan 1996 for Davis-Besse Nuclear Power Station.W/Undated Ltr

ML20149K771
Person / Time
Site:	Davis Besse
Issue date:	01/31/1996
From:	Wolf G, Jeffery Wood TOLEDO EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
KB-96-00044, KB-96-44, NUDOCS 9602220150
Download: ML20149K771 (5)

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TOLEDO

%es EDISON A Centerior Energy Corrpany AD ON AVENUE TOLEDO. OHIO 43652OOO1 KB-96 00044 Docket No. 50-346 License No. NPF-3 U.S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555 Gentlemen:

Monthly Operating Report, January 1996 Davis-Besse Nuclear Power Station Unit 1 Enclosed is a copy of the Monthly Operating Report for Davis-Besse Nuclear Power Station Unit No. 1 for the month of January 1996.

If you have any questions, please contact G. M. Wolf at (419) 321-8114.

Very truly yours, J n K. Wood Plant Manager Davis-Besse Nuclear Power Station GMW/dmc Enclosures cc: L. L. Gundrum NRC Project Manager H. J. Miller Region III Administrator S. Stasek NRC Senior Resident Inspector, Stop 4030 noou 9602220150 960131 )

PDR ADOCK 05000346 hL, g R PDR i a

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, ,, AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-0346 UNIT Davis-Besse Unit 1 DATE Feb.1,1996 COMPLETED BY Gerald M. Wolf TELEPHONE 419/321-8114 MONTH January,1996 AVERAGE DAILY POWER LEVEL AVERAGE DAILY POWER LEVEL DAY (MWe-Net) DAY (MWe-Net) j 1 886 17 881 i

2 .__

884 18 880 3 _

884 19 884 4 885 20 884 5 885 21 881 6 884 22 881 7 _.

885 23 881 8 884 24 883 9 883 25 885 10 _

885 26 883 11 885 27 884 12 885 28 885 13 884 29 887 14 884 30 884 15 885 31 884 16 884

OPERATING DATA REPORT DOCKET NO _50-0_346_ _ __

DATE Feb.1,1996 ~

COMPLETED BY -~ Gerald sl. VToif TELEPHONE 419/321-8114 OPERATING STATUS

1. Unit Name: Davis-Besse Unit 1 Notes

2. _ Reporting Period January,1996

3. Lige.nsed Therma.1 Power _(MWt) _2772 4, Narneplate Ra. ting (Gross M_We) _

_ _ _ _925 5._ Design Electrical Rating (Net MWe)_ _. . _906

6. Maximu_m_ Dependable _.Capag_ity (Gross.MWe)_ 915 < ,,

7._Maxirnum Dependable _C_apacity_(N_et_MWe) 871 8._lf Changes Ocgur.in Capacity Ratings my (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 744.00 744.00 153,457.00

12. Number Of Hours Reactor Was Critical 744.00 744.00 99,449.77

13. Reactor Reserve Shutdown Hours 0.00 0.00 5,532.00

14. Hours Generator On-Line 744.00 744.00 97,194.90

15. Unit Reserve Shutdown Hours 0.00 0.00 1,732.50

16. Gross Thermal Energy Generated (MWH) 2,061,037 2,061,037 252,298,946

17. Gross Electrical Energy Generated (MWH) 691,162 691,162 81,825,264

18. Net Electrical Energy Generated (MWH) 657,617 657,617 77,239,558

19. Unit Service Factor 100.00 100.00 63.34

20. Unit Availability Factor 100.00 100.00 64.47

21. Unit Capacity Factor (Using MDC Net) 101.48 101.48 57.79

22. Unit Capacity Factor (Using DER Net) 97.56 97.56 55.56

23. Unit Forced Outage Rate 0.00 0.00 18.25

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

.._ Scheduled _ maintenance and refueling outage - April 8,1996. Planned duration - 39 days. _

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 l

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OPERATIONAL

SUMMARY

January 1996 Reactor power was maintained at approximately 100 percent full power until 0129 hours0.00149 days <br />0.0358 hours <br />2.132936e-4 weeks <br />4.90845e-5 months <br /> on January 21,1996, when a manual power reduction was initiated to perform turbine control valve testing. Reactor power was reduced to approximately 93 percent full power by 0156 hours0.00181 days <br />0.0433 hours <br />2.579365e-4 weeks <br />5.9358e-5 months <br />, and control valve testing was conducted. At the completion of testing at 0254 hours0.00294 days <br />0.0706 hours <br />4.199735e-4 weeks <br />9.6647e-5 months <br />, power gradually increased to approximately 100 percent full power, which was achieved at 0331 hours0.00383 days <br />0.0919 hours <br />5.472884e-4 weeks <br />1.259455e-4 months <br />.

Reactor power was maintained at approximately 100 percent full power until 1142 hours0.0132 days <br />0.317 hours <br />0.00189 weeks <br />4.34531e-4 months <br /> on January 22,1996, when a manual power reduction was initiated to perform maintenance on Circulating Water Pump 4 motor breaker. The pump was stopped at i155 hours, and the power reduction stopped at approximately 99 percent full power at 1200 hours0.0139 days <br />0.333 hours <br />0.00198 weeks <br />4.566e-4 months <br />. Since there was no appreciable effect on the plant from stopping the pump, at 1218 hours0.0141 days <br />0.338 hours <br />0.00201 weeks <br />4.63449e-4 months <br />, a e anual power increase was initiated. The pump breaker was replaced, and the pump was restarted at 1228 hours0.0142 days <br />0.341 hours <br />0.00203 weeks <br />4.67254e-4 months <br />. The power increase was completed at 1245 hours0.0144 days <br />0.346 hours <br />0.00206 weeks <br />4.737225e-4 months <br /> at approximately 100 percent full power.

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

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4 s UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.: 50-346 $

UNITNAME: Davis-Besse #1 DATE: February 1.1996" Completed by: G. M. Wolf -

Report Month January 1996 Telephone: (419) 321-8114 4-n 80 e

gy m .E co Licensee E 'o g Cause & Corrective g gg g 3gy Event 3i [" =j Action to No. Date E--  !; - o

• is' g c xU m =u QO 2 $

Report #

Prevent Recurrence Q-No Significant Shutdowns or Power Reductions I 2 3 #

F: Forced Reason: Method: Exhibit G - Instructions for Preparation of Data S: Scheduled A-Equipment Failure (Explain) 1-Manual Entry Sheets for Licensee Event Report (LER)

B-Maintenance or Test 2-Manual Scram File (NUREG-0161)

C-Refueling 3-Automatic Scram D-Regulatory Restriction 4-Continuation from 5 '

E-Operator Training & License Examination Previous Month Exhibit I- Same Source F-Administrative 5-Load Reduction

• Report challanges to Power Operated Relief Valves G-Operational Error (Explain) 9-Other (Explain) (PORVs) and Pressurizer Code Safety Valves (PCSVs)

H-Other (Explain)

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