ML20098A265

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

ML20098A265
Person / Time
Site:	Davis Besse
Issue date:	08/31/1995
From:	Wolf G, Jeffery Wood TOLEDO EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
KB-95-00175, KB-95-175, NUDOCS 9509220280
Download: ML20098A265 (6)

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%sm EDISON A Centerior Energy Cornpany 0EOo 1

September 18, 1995 KB-95-00175 Docket No. 50-346 License No. NPF-3 U.S. Nuclear Regulatory Commission Document Control Desk Vashington, D.C.

20555 Gentlemen:

Monthly Operating Report, August, 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 August, 1995.

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

Very truly yours, O

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- h John K. Vood Plant Manager Davis-Besse Nuclear Power Station GMV/dmc Enclosures cc:

L. L. Gundrum NRC Project Manager H. J. Ailler Region III Administrator S. Stasek NRC Senior Resident Inspector, Stop 4030 nan -

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PDR ADOCK 05000346 I

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i AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-0346 UNIT Davis-Besse Unit 1___

DATE Sept. 5,1995 COMPLETED BY Gerald M. Wolf TELEPHONE 419/321-8114 MONTH August,1995 AVERAGE DAILY POWER LEVEL AVERAGE DAILY POWER LEVEL DAY (MWe-Net)

DAY (MWe-Net) 1 869 17 869 2

871 18 866 3

868 19 869 4

869 20 866 872 21 868 5

6 825 22 871 7

871 23 872 871 8

873 24 872 9

871 25 10 870 26 870 11 865 27 867 12 866 28 872 13 864 29 871 14 863 30 870 15 865 31 865 16 866 i

OPERATING DATA REPORT DOCKET NO _50-0346 DATE _ Sept. 5,199_5__

COMPLETED BY Gerald M. Wolf TELEPHONE 419/321-8114 OPERATING STATUS

1. Unit Name: Davis-Besse Unit 1 Notes August,1995 2,_Regorting Perio.d_

2772 3 Licensed _ Thermal _ Power (M_Wt)

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4. Na_mept. ate Rating (Gross MWe)_ _

925

5. Design Electrical Rating (Net MWe) 906 6_ Maximum Dependable Capacity _(Gross.MWe) 913 7._ Maximum Dependable Capacity _(Net MWe) 868

8. If Changes Occur in Capacity Ra. tings (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 5,831.00 149,784.00

12. Number Of Hours Reactor Was Critical 744.00 5,831.00 95,776.77

13. Reactor Reserve Shutdown Hours 0.00 0.00 5,532.00

14. Hours Generator On-Line 744.00 5,831.00 93,521.90

15. Unit Reserve Shutdown Hours 0.00 0.00 1,732.50

16. Gross Thermal Energy Generated (MWH) 2,057,711 16,053,361 242,149,434

17. Gross Electrical Energy Generated (MWH) 678,545 5,361,179 78,432,667

18. Net Electrical Energy Generated (MWH) 645,302 5,100,463 74,011,832

19. Unit Service Factor 100.00 100.00 62.44

20. Unit Availability Factor 100.00 100.00 63.59

21. Unit Capacity Factor (Using MDC Net) 99.92 100.77 56.93

22. Unit Capacity Factor (Using DER Net) 95.73 96.55 54.54

23. Unit Forced Outage Rate 0.00 0.00 18.83

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

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1 OPERATIONAL

SUMMARY

August 1995 Reactor power was maintained at approximately 100 percent full power until 2330 hours0.027 days <br />0.647 hours <br />0.00385 weeks <br />8.86565e-4 months <br /> on August 5,1995, when a manual power reduction was initiated to perform control valve testing, stop valve testing, and control rod drive exercising. Reactor power was manually reduced to approximately 93 percent full power by 2358 hours0.0273 days <br />0.655 hours <br />0.0039 weeks <br />8.97219e-4 months <br />, and control valve testing was conducted.

The power reduction resumed when control valve testing was completed at 0042 hours4.861111e-4 days <br />0.0117 hours <br />6.944444e-5 weeks <br />1.5981e-5 months <br /> on August 6. Reactor power was manually reduced to approximately 85 percent full power by 0115 hours0.00133 days <br />0.0319 hours <br />1.901455e-4 weeks <br />4.37575e-5 months <br />, and stop valve testing and control rod drive exercising was conducted. At the completion of testing at 0224 hours0.00259 days <br />0.0622 hours <br />3.703704e-4 weeks <br />8.5232e-5 months <br />, power was held at approximately 85 percent full power at the request of the load dispatcher. At 0813 hours0.00941 days <br />0.226 hours <br />0.00134 weeks <br />3.093465e-4 months <br />, reactor power was gradually increased to approximately 100 percent full power, which was achieved at 0942 hours0.0109 days <br />0.262 hours <br />0.00156 weeks <br />3.58431e-4 months <br />. Reactor power was maintained at approximately 100 percent full power for the rest of the month.

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UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO'.:

50-346 UNIT NAME: Davis-Besse'#1 -

. DATE:

Seotember 5.1995

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Completed by: ' G. M. Wolf -

Report Month.

August 1995 Telephone:

(419) 321-8114 gy Licensee Cause & Corrective y

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]hj Event i-j

' Action to No. ~

- Date N

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. Report #

6 Prevent Recurrence m

No Significant Shutdowns or Power Reductions i

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4 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-l E-Operator Training & License Examination Previous Month

. Exhibit I-Same Source F-Administrative 5-Load Reduction

• Report challanges to Power Operated Relief Valves l-G-Operational Error (Explain) 9-Other (Explain).

(PORVs and Pressurizer Code Safety Valves (PCSVs) -

H-Other (Explain)

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' September 18, 1995-KB-95-0175-

' bec LZ. A. Clayton, OEPA

. R. E.' Donnellon, Manager - Plant: Engineering L J.

L~. Galecki, Public Affairs, Stop 850 F. Heizer, PUC0 R.fS. Hula,' Bulk Power Operations, IND 212'

.J. H. Lash, Manager - DB Operations.

Je Long, Babcock & Wilcox D. M. McConahay, Stop 1056 V. T.10'Connor, Manager ~- Regulatory Affairs, Stop 3065 L. Sharp, Public Relations -'Stop 850-V. K. Shav, IND 411 D..J. Stephenson, CNRB Administrator, Stop 3030 F. L. Svanger, Supervisor - Nuclear Safety Analysis,.Stop 3105' J. Vitellos, Board Secretary J. K.-Wood, Plant Manager, Stop 2101 D. R. Vuokko, Supervisor - Nuclear Regulatory Affairs,- Stop 3065 F. Yost, Director of Research, Utility Data Institute, Inc.

.American Nuclear' Insurers INPO Records Center-d d

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