ML20079C120

Monthly Operating Rept for May 1991 for Davis-Besse Nuclear Power Station Unit 1

ML20079C120
Person / Time
Site:	Davis Besse
Issue date:	05/31/1991
From:	Sarsour B, Storz L CENTERIOR ENERGY
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
KB91-0536, KB91-536, NUDOCS 9106180426
Download: ML20079C120 (6)

Text

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TOLEDO EDISON A centefuv i nog, Cun prey LDiSON PLAZA 300 t/ADIDON AVENUE TOLL'DO. OHIO 43052 0001 June 11, 1991 KB91-0536 Docket No. 50-346.

License No. NPF-3 Document Control Desk U. S. Nuclear Regulatory Commission 7920 Norfolk Avenue Bethesda, MD 20555 Gentlemen:

Honthly Operating Report, Hay, 1991 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 May, 1991.

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

Very truly yours, h

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/ 1,ouis F. Storz Plant Manager

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Davis-Besse Nuclear Power Station BHS/tld Enclosures cc:

Mr. Paul Byron NRC Resident Inspector Hr. A. Bert Davis Regional Administrator, Region III Hr. J. B. Hopkins NRC Senior Project Manager fb

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AVER AGE D AILY UNIT P0hER LEVEL DOCKET NO.

50-346 UNIT -Davis-Besse #1 DATE June 11. 1991 COMPLETED !!y Bilal Sarsour TELEPHONE (419)321-7384 MONT11 MdY' 1991 DAY AVER AGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL (Mbe Net)

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884 883 g9 4

885 883 20 5

885 878 6

879 874 7

884 869 33 8

884 873 3

9 883 869 25 10 879 855 26 33 877 869 3

12 871 865

,g 872 862 13 14 871 863 30 15 875 g73 3,

16 869 INSTRUC110NS On this forrnat, hst the aserage daily unit power leselin MWe. Net for each day in the reporting month. Compute io the nearest whole megaw.iit.

(9 /77 )

l OPERAllNG D AT A REPORT DOC KET NO 50-346 D AT E June I C 1991 N

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OPi R \\llNG S14TUS Th. vin-1 esse # 1 Notes

1. Unit Name:

2. Reporting Period:

M4Ya 1991

3. Licenwd thennal Power (Mht t 2772

4. Nameplate Rating (Grou MWe t 925 906

5. Design Electrical Rating (Net MWe0

6. Masimum Dependable Capacity (Gross MWet 418

7. Masimum Dependable Capacity (Net Mhet 870

b. If Changes Occur in Capacity Ratings (Items Number 3 Through 7)Since Last Report,Gise Reasont i

9. Power Lesel To which Restricted.lf Any (Net MWet

10. Reasons For Restrictions,1f Any:

This Month Yr. to Date Cumulative i1. liours in Reporting Period 744.0 3,623.0 112,512

12. Number Of Hours Reactor Was Critical 744.0 3.623.0 62,744.2

13. Reactor Resene Shutdown Hours 0.0 0,0 5.393.7

14. Hours Generator On.Line 744.0 3,623.0 60,692.3

15. Unit Resene Shutdown Hours 0.0 0.0 1,732.5

16. Gross Thermal Energy Generated (MWH) 2,059,042 9.943,275 148,069,760

17. Gross Electrical Energy Generated (MWH) 684,108 3.321.895 49.051.912

18. Net Electrical Energy Generated (MWH) 651.074 3.160.775 46.109.401

19. Unit Senice Factor 100.0 100.0 53,9

20. Unit Asailability Factor 100.0 100.0 55.5

21. Unit Capacity Factor (Using MDC Net) 100.1 99.8 46.9

22. Unit Capacity Factor (Using DER Neti 96.6 96.3 45.2 l

23. Unit Forced Outage Rate 0.0 0.0 26.I

24. Shutdowns Scheduled Oser Nest 6 Months (Type, Date.and Duration of Eacht:

The unit will be shutdown on September 1, 1991, to perform scheduled maintenance and refueling outage.

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

26. Units in Test Status (Prior to Commercial Operation U Forecast Achwsed INITI AL CRITICA LITY INITI A L ELECTRICITY COM%1ERCI AL OPER ATION (9/77) l

TRIT SHUTDCME JJ:D POWER F M CEES w m T reg. 50-34.

UffIT M Davis-Besse 41 rate June 11, 1991 CDMFIITED ST Silal Sarsour REPORT rurar Mav. I991 TEzinosE 4419, 321-73s4 i

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8 No significant s Tutdowns or power reducti ans.

F: Forced Reason:

Method:

Exhibit G - Instructions for Preparation of Data 5: Schecialed A-Equigment Failure (Emplain) 1-Manual Entry Sheets for 1.icensee Event Poport (1D)

IHtaintenance or Test 2-Manual Scram file (NUPEG-0161)

C-Befueling 3-Automatic Scram D-Regulatory Restriction 4-Continuation from E-Operator Training & License Emamanation Previous ?tanth Exhibit I - Same Source T-Administrative 5-Load Reduction

• Report challenges to Power Operated Relief valves I

G-operational Error (Emplaial 9 h r (Esplain)

(10Pvs) and Pressuricer Code Safet} Talves (PC37s)

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Operational Summary Hey, 1991 Reactor power was maintained at approximately 100 percent power until 1319 hours0.0153 days <br />0.366 hours <br />0.00218 weeks <br />5.018795e-4 months <br /> on May 10, 1991, when reactor power ran back to approximately 94 percent power during the performance of DB-M1-03004, Reactor Protection System (RPS)

Channel 4 Functional Testing. The runback was the result of a switch being mispositioned during the test.

After completion of RPS testing, reactor power was increased to approximately 100 percent power, which was achieved at 1600 hours0.0185 days <br />0.444 hours <br />0.00265 weeks <br />6.088e-4 months <br /> on May 10, 1991.

Reactor power was maintained at approximately 100 percent power until 0100 on May 26, 1991, when a manual power reduction to approximately 85 percent power was initiated to perform Control Rod Drive (CRD) testing and main turbine control valves testing.

After completion of main turbine control valves testing, reactor power was slowly increased to approximately 100 percent power, which was achieved at 0530 hours0.00613 days <br />0.147 hours <br />8.763227e-4 weeks <br />2.01665e-4 months <br /> on May 26, 1991, and maintained at this power level for the rest of the month.

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REl'UELING INPORHATION Daten May 1991 1.

Name of facility:

Davis-Ilesse Unit _1 September 1991 2.

Scheduled date for next refueling outage?

e 3.

The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pool, and (c) the new fuel storage areas.

(a) 177 (b) 328 (c) 0 4.

The present licensed spent fuel pool storage capacity and the size of any increase in licensed storage capacity that has been requested or is planned, in number of fuel assemblies.

Present:

735 Increased size by approximately 900 by 1994 is under reviev 5.

The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity.

Date:

1995 - assuming ability to unload the entire core into the spent fuel pool is maintained l

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