ML20099H549

Monthly Operating Rept for Jul 1992 for DBNPS Unit 1.W/

ML20099H549
Person / Time
Site:	Davis Besse
Issue date:	07/31/1992
From:	Sarsour B, Storz L TOLEDO EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
KB92-1883, NUDOCS 9208190085
Download: ML20099H549 (5)

Text

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TOLEDO EDISON A Co dener ( Nagy Cptpry CDtSON Pt A7A 300 MADi5ON AVE Nt>E Tott DO. OHIO 43f62 0001 August 10, 1992 KD92-1883 Docket No. 50-346 License No. NPF-3 U.S. Nuclear Regulatory Commission Document Control Desk Vashington, D.C. 20555 Gentlemen Monthly Operating Report, July, 1992 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 July, 1992.

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

Very_truly yours,

[ D tu Louis (F. Storz Plant Manager Davis-Besse Nuclear Power Station BHS/ tid Enclosures cc: Mr. A. Bert Davis Regional-Administrator, Region III Hr. J. B. Hopkins NRC Senior Project Manager Mr. Villiam Levis NRC Senior Resident Inspector 9208190085 920731 PDR .ADOCK 05000346 R PDR

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AVER AGE D ALLY UNil POhER LEVrl DOCKET NO. _ 50-346 UNIT Davis-Besse #1 DATE A.ygust 10, 1992 CO\tPLETED BY Bilal Sarsour TELLP110NE 119)321-7384 MONT11 July. 1992 DAY AVER AGE DAILY P0hER LEVEL DAY (Mhe NetI AVER AGE D\lLY P0hER LEVEL r

(MWe NetI g 876 j- _ 871 2 _

873 18 _. 873 3 -

19 869 4 __ 876 20 868 5 __.

873 21 _ 880 6 881 22 877 7 -

23 875 8 _. 870 24 876 9 863 25 _

874 10 _. 871 26 868

!! 871 27 _

872 i *s 868 --

s 874 J3 872 29 869 14 867 30 _

875 15 875 31 __

873 16 872 ~~

INSTRUCTIONS On thb whole the nearest format.hst megawait, the average dady unit power le5elin A!We-Net for .

each da) in the report u e to (9/773

OPERATING DATA REPORT DOCKET NO. 50-346 DA1E August. 10, 1992 COMPLETED itY Bilal Sarsour TELEPilONE (61 0 '11-7384 OPER AllNG STAl US Davis-Besse Unit #1 Notes

1. Unit Name:

2. Reporting Period: July, 1992

3. Licensed 1 hermal Power (MWt):

2772

4. Nameplate Rating (Gross MWe): 925

5. Design Electrical Rating (Net MWe): 906

6. Maximum Dependable Capacity (Gross MWe): 921-  ;

7. Masimum Dependable Capacity (Net MWe): 877 S. If Changes Occur in Capadty Ratings (Items Number 3 Through 71Since Last Report,6ise Renons:

9. Power Lesel To Which Restricted. lf Any (Net MWe): .

10. Reasons For Restrictions,if Any:

This Month Yr. to Date Cumulative

11. Hours in Reporting Period 744.0 5,111.0 122,760

12. Number Of Hours Reactor Was Critical 744.0 5,086.2 71,262

' 13. Reactor Reserve Shutdown flours - 0.0 24.8 5.532.0

14. Ilours Generator On-Line 744.0 5,069.3 69,102.4

15. Unit Resene Shutdown flours 0.0 , , , , .

0.0 .1,732.5 2,060,372 13,938,281 170,547,;' i

16. Gross Thermal Energy Generated (MWil)

17. Gross Electrical Energy Generated (MWH) 682,035 4.661,081 56,554,438 649,118 4,434.554 53,227.042

18. Net Electrical Energy Generated (MWH)

19. Unit Senice factor. 100.0 99.2 56.3 20.' Unit Asailability Factor 100.0- 99.2 57.7 21.' Unit Capacity Factor (Using MDC Net) 99.5 98,9 49,4

22. Unit Capacity Factor (Using DER Net) . 96.3 ,

95.8 47.9

23.l Unit Forced Outage Rate 0.0 0.82 23.8 ,  ;

24, Shutdowns Scheduled Oser Nest 6 Months (Type, Date,and Duration of Eachl

c _

i.

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

26. Units 11 Test Status (Prior to Commercial Operation k Forecast Achiesed INITIA L CRITICALITY INITIAL ELECTRICITY COMM ERCI A L OPER ATION top 7 )

,.-,s- . .. . _ . . . . _ . . . _. .. ~ _ . , - . , . _ _ _ , _ _ _ _ . _ . _ _ . _ , . . .

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tmIt - no rowsm aEcuerzens tocxrr no. __50-346 ,

1RrIT RAPE Davis-Basse el ~

tare August 10, 1992 COMP 11TED BY Silal Sarseur .

EEpour rarn July, 1992 TErzenant vers 321-73s4 "o

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Cause & Corrective e:a

- - = e e u no.  ; g Event sotton to ro t. . e  ; g g=  ; jj ; .

poport s gu rrevent m.currence No significant sh'Itdowns or-power reductio 1s .

i 2

e--A F; Forced Beeson: Method: Exhibit G - Instructions for Preparation of Data 5: Scheduled A-Draipment Failure (Explain) 1-Manual Entry Sheets for Licensee Event Report tIIR)

B-Maintmance or Test 2-Manual scram File (NUPIG-0161)

C-Refueling 3-Automatic Scram D-Regulatory Restriction 4-Continuation from E @ rator Training & License Examination Previous Pkrath Exhibit I - Same Source F-Administrative FLoad Reduction *Repert challengee to Power Operated Relief Valv.s G operational Error (Explain) 9-other (Explaint (POEva) and Pressurizer Code Safety valves (PCsvst H-Other (Esplein)

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Operational Summary July, 1992

' Reactor power was maintained at approximately 100 percent full pover until

0102 hours on July 19, 1992, when a manual power reduction to approximately 92 percent-was. initiated to perform mairi turbine valve testing and control rod drive exercise testing.

After. completion of main turbine valve testing and control rod drive testing, reactor power was slowly increased to approximately 100 percent full power, which was achieved at 0340 hours0.00394 days <br />0.0944 hours <br />5.621693e-4 weeks <br />1.2937e-4 months <br /> on July 19, 1992, and maintained at tMs '

power level for'the rest of the month.

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