ML20096E047

Monthly Operating Rept for April 1992 for Davis-Besse Unit 1

ML20096E047
Person / Time
Site:	Davis Besse
Issue date:	04/30/1992
From:	Sarsour B, Storz L TOLEDO EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
KB92-0276, KB92-276, NUDOCS 9205190040
Download: ML20096E047 (5)

Text

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TOLEDO

% EDISON A Centsv (noegy C<n.pany C DiSON Pt.AZA LV10 MADISON AVENUE lottno osio4xmaxo May 12, 1992 ItD92-0276 Dockef No. 50-346 License No. NPF-3 U.S. Nuclear Regulatory Commission Document Conttol Desk Vashington, D.C. 20555 4

Gentlemen -

Honthly Operatiag Report, April. 1992

• Davis-Desso Nuclear Power Station Unit Enclosed are ten copies of the Honthly Operating'l<eport for Davis-Desse-Nuclear Power Station Unit No. 1 for the month of April, 1992.

The refueling information has been deleted from this report since it is not required by the NRC Regulatory Guide 1.16. <

If you have any questions, please contact lillal Satuour at (419) 321-7384.

V cy truly yours, 1

L

., g (Q -

1.ouis F. S(orz Plant Managt Davis-Besse Nuclear Power Station BMS/ tid Enclosures cc Mr. A. Bert Davis RegionalAdministrator,Rchion111 Hr. J. B. Ilopkins NRC Senior Project Manager

.Hr. Villiam Levis.

NRC Senior Resident Inspector y .f e

1 190011 9205190040 920430

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( AVER AGE DAILY UNil PohER LEVEL DOCKETNO.

p3gg Davis-Besse #1 D ATE Flay 12.1992 004tPLETL D hy hilal Sarsour TELEPflONE - 1 321-7384

\t0NT11 April, 1992 DAY AVER AGE D AILY PohER LEVEL DAY AVER AGE D AILY PohER LEVEL (Mbe Netn (\lhe Neti 888 g, 885 3 889_ Jg 887 3 891 885 39 ,

4 887 20 g 851

• y; 880 6 885 ,.. 885 7 884 884 33 ,

8 886 882

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9 009 06

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10 889 00I 26 gi 883 887 37 12 886 886

,8 13 009 29 .

g4 890 00 30 15 888 3; _,,.

16 881

• Based on the average of 23 hours2.662037e-4 days <br />0.00639 hours <br />3.80291e-5 weeks <br />8.7515e-6 months <br /> generation due to titae change.

INSTRUCTIONS On this format.hst the aserage daily unit powei level in MWe Net for each day in the reporting month. Cmnpute to the nearest whole megawatt, (4I 71 i

. _ _ . _ . - . _ _ - _ . - - . .. - - - - - _ .=. _ _ _ _ _ . - - .-

O!LRAllNG DATA REPOR1 DOCKET NO $0-346 DAll Mav 12. 1992 COMPLE1ED ily Ililal Sarsour I[LEPilONL (419(321-7384 OPf RATING ST ATUS

1. Urut N,ame' Davis-Besse Unit lil Note: '

2. Reporting Period: April. 1992 2772

3. Licenwd T hermal h wer (MWt): ,

925

4. Nameplate Rating (Cross MWe): ,,

5. Design Liectrical Rating (Net MWe1: 906

6. Maximum Dependable Capacity (Gross MWe): -

921 877

7. Matimum Dependable Capacity (Net MWel:

h. If Changes occurin Capacity Ratino(Itt-ms Number 3 Through 7)Since Last Report,Glic Renwns:

9. Power Leiel To Whict. nntricted,if Any (Net MWe1: ,_

10. Reasons For Restrictions,if Any: ,,, _

This Month Yr. to Date Cumulatise

11. Ilours in Reporting Period 719.0 2,903.0 120.55_2 ,

[ 12. Number of Hours Reactor Was Critical 719.0 2.878.2 (,9 , n u 0

13. Reactor Resene Shutdown flours 0.0 2 4 ._8_,_ 5,532.9 14, llours Generator On Line 719.d 2,861.3 66,894.4

15. Unit Rewne Shutdown lleurs 0.0 0.0 1,732.5

16. Gross Thermal Energy Generated (MWH) l*991.848 _ 7,909,514 164,518,807

17. Gross Electrical Energy Generated (MWH) Dh81 743 2.658,527 54,551,904

18. Net Electrical Energy Generated (MWil) 636,764 2,528,822 51,321,310

19. Unit Senire Factor 100.0 ,

98.6 ,

5 5 . 5' '

20. Unit Assilability Factor 100.0 98.6 5 6. 9 _.

21. Unit Capacity Factor (Using MDC Net) 101.0 ,

99.3 48.5 ,

22. Unit Capacity Factor IUsing DER Net) 97.8 96.1 47.0

23. Unit Forced Outage Rate 0.0 1.4 24.4

24. SHtdowns Scheduled Oier Nest 6 Months (Type Date,and Duratwn of Each):

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

26. Units in Test Status lPrior to Commercial Operation)- Forecast Achiesed l

l INITI AL CRITICALITY INITI AL ELECTRICITY COMMERCIAL OPER ATION I

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i Operational Summary April, 1992 Iteactor pover was maintained at approximately 100 percent full power until 0102 hours0.00118 days <br />0.0283 hours <br />1.686508e-4 weeks <br />3.8811e-5 months <br /> on April 26, 1992, when a manual power reduction to apprm:is.ately 91 percent was initiated to perform Main Turbine Valve _ testing and Control Rod Drive Exercise testing. g After completion of the Hain Turbine Valve testing and Control Rod Drive testing, reactor power was slowly increased to approximately 100 percent it'll power, which was achieved at 0500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br /> on April 26, 1992, and maintained at this power level for the rest of the month.

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