ML20133G016

Monthly Operating Rept for Dec 1996 for Davis-Besse Nuclear Power Station,Unit 1

ML20133G016
Person / Time
Site:	Davis Besse
Issue date:	12/31/1996
From:	Lash J, Matranga E TOLEDO EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
KB-97-0029, KB-97-29, NUDOCS 9701150100
Download: ML20133G016 (5)

Text

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W TOLEDO EDISON A Centerior Energy Company January 13,1997 Z^

ggsgNggoN AVENUE TOLEOO. OHIO 43652-0001 KB-97-0029 i

1 Document Control Desk U. S. Nuclear Regulatory Commission Washington, D. C. 20555 j

1 Ladies and Gentlemen:

Monthly Operating Report, December 1996 Davis-Besse Nuclear Power Station Unit 1 Enclosed is a copy of the Monthly Operating Report for Davis-Besse Nuclear Power Station Unit 1 for the month of December 1996.

a If you have any questions, please contact E. C. Matranga at (419) 321-8369.

Very truly yours, i

1 James H. Lash

Plant Manager Davis-Besse Nuclear Power Station ECM/ljk Enclosure cc: A. B. Beach / ,

NRC Region III Administrator i

A. G. Hansen NRC Project Manager S. Stasek NRC Senior Resident Inspector 9701150100 961231 PDR ADOCK 05000346 R PDR

i t

AVERAGE DAILY UNIT POWER LEVEL

(

DOCKET NO. 50-0346 l UNIT Davis-Besse Unit 1 :

DATE January 2,1997 COMPLETED BY Eugene C. Matranga TELEPHONE 419/321-8369 )

l MONTH December,1996 l AVERAGE DAILY POWER LEVEL AVERAGE DAILY POWER LEVEL DAY (MWe-Net) DAY (MWe-Net) 1 874 17 885 2 887 18 886 3 887 19 886 l l

4 887 20 886 5 886 21 885 6 886 22 885 7 886 23 883 8 882 24 865 9 890 25 886 10 887 26 886 11 . 886 27 885 12 886 28 884 13 886 29 885 14 886 30 885 15 885 31 886 16 886

i . .

OPERATING DATA REPORT DOCKET NO 50-0346 DATE January 2.1997 COMPLETED BY Euaene C. Matranca TELEPHONE 419/321-8369 OPERATING STATUS

, 1. Unit Name: Davis-Besse Unit 1 Notes

2. Reportina Period December,1996

3. Licensed Thermal Power (MWt) 2772

4. Nameplate Ratina (Gross MWe) 925

5. Desian Electrical Ratina (Net MWe) 906

6. Maximum Dependable Capacity (Gross MWe) 917

7. Maximum Deoendable Capacity (Net MWe) 873

8. If Chanaes Occurin Capacity Ratinas (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 8,784.00 161,497.00

12. Number Of Hours Reactor Was Critical 744.00 7,490.20 106,195.97

13. Reactor Reserve Shutdown Hours 0.00 0.00 5,532.00

14. Hours Generator On-Line 744.00 7,452.60 103,903.50

15. Unit Reserve Shutdown Hours 0.00 0.00 1,732.50

16. Gross Thermal Energy Generated (MWH) 2,058,376 20,340,936 270,578,845

17. Gross Electrical Energy Generated (MWH) 691,655 6,795,976 87,930,077

18. Net Electrical Energy Generated (MWH) 658,212 6,461,254 83,043,194

19. Unit Service Factor 100.00 84.84 64.34

20. Unit Availability Factor 100.00 84.84 65.41

21. Unit Capacity Factor (Using MDC Net) 101.34 84.26 58.90

22. Unit Capacity Factor (Using DER Net) 97.65 81.19 56.76

23. Unit Forced Outage Rate 0.00 0.00 17.28

24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each): A 23 day shutdown is beina considered for late May to replace RCP 2-2 motor due to increasinn thrust bearina temperatures.

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

a-OPERATIONAL

SUMMARY

December 1996 Reactor power was maintained at approximately 100 percent full power until 0230 hours0.00266 days <br />0.0639 hours <br />3.80291e-4 weeks <br />8.7515e-5 months <br /> on December 1,1996, when a manual power reduction was initiated at the request of the load dispatcher. Reactor power was reduced to approximately 94 percent full power by 0301 hours0.00348 days <br />0.0836 hours <br />4.976852e-4 weeks <br />1.145305e-4 months <br />. At 0700 hours0.0081 days <br />0.194 hours <br />0.00116 weeks <br />2.6635e-4 months <br />, power was gradually increased to approximately 100 percent full power, which was achieved at 0750 hours0.00868 days <br />0.208 hours <br />0.00124 weeks <br />2.85375e-4 months <br />.

Reactor power was maintained at approximately 100 percent full power until 0008 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> on December 8,1996, when a manual power reduction was again initiated to perform turbine valve testing and control rod exercising.

Reactor power was reduced to approximately 92 percent full power by 0048 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, and control valve and stop valve testing and control rod exercising was conducted. At the completion of testing at 0141 hours0.00163 days <br />0.0392 hours <br />2.331349e-4 weeks <br />5.36505e-5 months <br />, power was gradually increased to approximately 100 percent full power, which was achieved at 0233 hours0.0027 days <br />0.0647 hours <br />3.852513e-4 weeks <br />8.86565e-5 months <br />.

Reactor power was maintained at approximately 100 percent full power until 0110 hours0.00127 days <br />0.0306 hours <br />1.818783e-4 weeks <br />4.1855e-5 months <br /> on December 24,1996, when a manual power reduction was again initiated at the request of the load dispatcher. Reactor power was reduced to approximately 90 percent full power by 0210 hours0.00243 days <br />0.0583 hours <br />3.472222e-4 weeks <br />7.9905e-5 months <br />. At 0635 hours0.00735 days <br />0.176 hours <br />0.00105 weeks <br />2.416175e-4 months <br />, power was gradually increased to approximately 100 percent full power, which was achieved at 0804 hours0.00931 days <br />0.223 hours <br />0.00133 weeks <br />3.05922e-4 months <br />.

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

I i

l

UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-346 ,

UNIT NAME Davi:-Besse 01 DATE January 2,1997 ,

Report Month December.1996 COMPLETED BY E. C. Matranga 'l TELEPHONE (419) 321-8369 a

c. oe E, e Cause & Corrective

'e @y y ] y' g Licensee Event SS k$j Action to h [

I j f Report # yj Prevent Recurrence O

No Significant Shutdowns Or Power Reductions.

1 2 3 4 F: Forced Reason: Method: Exhibit G-Instructions S: Scheduled A-Equipment Failure (Explain) 1-Manual for Preparation of Data B-Maintenance or Test 2-Manual Scram Entry Sheets for Licensee C-Refueling 3-Automatic Scram Event Report (LER) File (NUREG-D-Regulatory Restriction 4-Continuation from 0161)

E-Operator Training & License Examination Previous Month F-Administrative 5-Load Reduction 5 G-Operational Error (Explain) 9-Other (Explain) Exhibit I- Same Source H-Other (Explain)

• Report challanges to Power Operated Relief Valves (PORVs) and Pressurizer Code Safety Valves (PCSVs)

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