ML20087H306

Monthly Operating Rept for Jul 1995 for Davis-Besse Nuclear Power Station Unit 1

ML20087H306
Person / Time
Site:	Davis Besse
Issue date:	07/31/1995
From:	Wolf G, Jeffery Wood TOLEDO EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
KB-95-0121, KB-95-121, NUDOCS 9508180010
Download: ML20087H306 (5)

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TOLEDO EDISON A Centerior Energy Cornpany E

1 August 14, 1995 KB-95-0121 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, 1995 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, 1995.

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

Very truly yours, John K. Wood i

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

L. L. Gundrum NRC Project Manager H. J. Hiller Region III Administrator f

S. Stasek

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NRC Senior Resident Inspector, Stop 4030 e

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AVERAGE DAILY UNIT POWER LEVEL

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DOCKET NO.

50-0346 UNIT Davis-Besse Unit 1 l

DATE August 2,1995 COMPLETED BY Gerald M. Wolf 7

TELEPHONE 419/321-8114

. MONTH July,1995 AVERAGE DAILY POWER LEVEL AVERAGE DAILY POWER LEVEL DAY (MWe-Net)

DAY (MWe-Net) l 1

878 17 871 2

881 18 863 3

879 19 875 4

872 20 873 5

868 21 874 3

6 870 22 872 7

876 23 872 8

880 24 873 9

844 25 873 10 876 26 872 11 875 27 871 12 874 28 867 13 865 29 870 l

14 863 30 873 15 863 31 871 16 869

OPERATING DATA REPORT 1

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• DOCKET NO 50-0346 DATE August 2,1995 COMPLETED BY Gerald M. Wolf TELEPHONE 419/321-8114 OPERATING STATUS

1. Unit Name: Davis-Besse Unit 1 Notes

2. Reporting Period July,1995

3. Licensed Thermal Power (MWt) 2772

4. Nameplate Rating (Gross MWe) 925

5. Design Electrical Rating (Net MWe) 906

6. Maximum Dependable Capacity (Gross MWe) 913

7. Maximum Dep_endable Capacity (Net MWe) 868

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 5,087.00 149,040.00

12. Number Of Hourt Reactor Was Critical 744.00 5,087.00 95,032.77

13. Reactor Reserve Shutdown Hours 0.00 0.00 5,532.00

14. Hours Generator On-Line 744.00 5,087.00 92,777.90

15. Unit Reserve Shutdown Hours 0.00 0.00 1,732.50

16. Gross Thermal Energy Generated (MWH) 2,058,376 13,995,650 _240,091,723

17. Gross Electrical Energy Generated (MWH) 681,329 4,682,633 77,754,122

18. Net Electrical Energy Generated (MWH) 648,101 4,455,161 73,366,530

19. Unit Service Factor 100.00 100.00 62.25

20. Unit Availability Factor 100.00 100.00 63.41

21. Unit Capacity Factor (Using MDC Net) 100.36 100.90 56.71

22. Unit Capacity Factor (Using DER Net) 96.15 96.67 54.33

23. Unit Forced Outage Rate 0.00 0.00 18.95

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 l

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SUMMARY

July 1995 Reactor power was maintained at approximately 100 percent full power until 0000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> on July 9,1995, when a manual power reduction was initiated to perform control valve testing. Power was manually reduced to approximately 94 percent full power by 0015 hours1.736111e-4 days <br />0.00417 hours <br />2.480159e-5 weeks <br />5.7075e-6 months <br />, and the testing was conducted. At the completion of testing at 0035 hours4.050926e-4 days <br />0.00972 hours <br />5.787037e-5 weeks <br />1.33175e-5 months <br />, reactor power was j

reduced at the request of the load dispatcher. The power reduction was stopped at 0045 hours5.208333e-4 days <br />0.0125 hours <br />7.440476e-5 weeks <br />1.71225e-5 months <br /> with reactor power at approximately 90 percent full l

power. At 0830 hours0.00961 days <br />0.231 hours <br />0.00137 weeks <br />3.15815e-4 months <br />, reactor power was gradually increased to l

approximately 100 percent full power, which was achieved at 1000 hours0.0116 days <br />0.278 hours <br />0.00165 weeks <br />3.805e-4 months <br />.

Reactor power was maintained at approximately 100 percent full power until 0439 hours0.00508 days <br />0.122 hours <br />7.258598e-4 weeks <br />1.670395e-4 months <br /> on July 18, when a manual power reduction was initiated to perform maintenance on high pressure feedwater heater 1-4 normal j

drain valve. Power was manually reduced to approximately 93 percent full power by 0600 hours0.00694 days <br />0.167 hours <br />9.920635e-4 weeks <br />2.283e-4 months <br />, and the valve was isolated. At the completion of maintenance at 0818 hours0.00947 days <br />0.227 hours <br />0.00135 weeks <br />3.11249e-4 months <br />, reactor power was gradually increased to approximately 100 percent full power, which was achieved at 0924 hours0.0107 days <br />0.257 hours <br />0.00153 weeks <br />3.51582e-4 months <br />.

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

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