ML20096C797

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

ML20096C797
Person / Time
Site:	Davis Besse
Issue date:	12/31/1995
From:	Wolf G, Jeffery Wood TOLEDO EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
KB-96-00006, KB-96-6, NUDOCS 9601180288
Download: ML20096C797 (5)

Text

_.

TOLEDO

%me EDISON EDISON PLAZA i 300 MADISCN AVENUE 1 TOLEDO, OHIO 43652-0001 January 12, 1996 KB-96-00006 l

Docket No. 50-346 ,

License No. NPF-3 U.S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555 Gentlemen:

Monthly Operating Report, December, 1995 Davis-Besse Nuclear Power Station Unit 1 Enclosed is a copy of the Monthly Operating Report for Davis-Besse Nuclear Power Station Unit No. 1 for the month of December, 1995.

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

Very truly yours, k f M Ge John K. Wood l Plant Manager Davis-Besse Nuclear Power Station 1 GMW/dmc Enclosures cc: L. L. Gundrum NRC Project Manager H. J. Miller Region III Administrator S. Stasek NRC Senior Resident Inspector, Stop 4030 e 180076

• 9601180288 951231 PDR ADOCK 05000346 l R PDR l l

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AVERAGE DAILY UNIT POWER LEVEL 4

4 DOCKET NO. 50-0346 UNIT Davis-Besse Unit 1 DATE Jan.2,1996 COMPLETED BY _ Gerald M. Wolf TELEPHONE 419/321-8114 MONTH December,1995 AVERAGE DAILY POWER LEVEL AVERAGE DAILY POWER LEVEL DAY (MWe-Net) DAY (MWe-Net) 1 881 17 884 2 863 18 883 3 881 19 883 4 883 20 883 5 _

882 21 883 6 883 22 883 7 883 23 507 8 883 24 883 0 883 25 885 10 883 26 886 11 883 27 885 12 883 28 885 .

l 13 882 29 884 l l

14 882 30 884 15 883 31 883 16 884

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OPERATING DATA REPORT. . DOCKET NO 50-0346

DATE _Jan. 2,1996 COMPLETED BY __ Gerald M. Wolf TELEPHONE 419/321-8114 OPERATING STATUS 4

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1. Unit Name: Davis-Besse Unit 1 Notes

_2. Reporting Period . Dec.,1995

3. Licensed Thermal Power (MWt) 2772

4. Namepiste Rating (Gross MWe} _

925

           - 5. Design Electrical Rating (Net MWe)                                            906
             .6. Maximum Dependable CapacityjGross MWe)                                       915
           ..7Jaximum Depeadable Capaci_ty_(Net MWe}

871

8. If Changes Occur in Capacity Ratings j (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 8,760.00 152,713.00

12. Number Of Hours Reactor Was Critical 744.00 8,760.00 98,705.77 ,

13. Reactor Reserve Shutdown Hours 0.00 0.00 5,532.00 1

14. Hours Generator On-Line 744.00 8,760.00. 96,450.90

15. Unit Reserve Shutdown Hours 0.00 0.00 1,732.50

16. Gross Thermal Energy Generated (MWH) 2,035,757 24,141,836 250,237,909

17. Gross Electrical Energy Generated (MWH) 681,338 8,062,614 81,134,102

18. Net Electrical Energy Generated (MWH) 647,674 7,670,572 76,581,940

19. Unit Service Factor 100.00 100.00 63.16

20. Unit Availability Factor 100.00 100.00 64.29 >

21. Unit Capacity Factor (Using MDC Net) 99.95 100.53' 57.57

22. Unit Capacity Factor (Using DER Net) 96.08 96.65 55.35

23. Unit Forced Outage Rate 0.00 0.00 18.37

24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):

Scheduled maintenance and refueling outage - April 8,1996. Planned duration - 39 days.

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

26. Units in Test Status (Prior to Commercial Operation): ,

Forecast Achieved i l INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION . 1

DOCKET NO.: 50-346 b UNIT SHUTDOWNS AND POWER REDUCTIONS

• UNIT NAME: Davis-Besse #1 -

DATE: January 2.19% Completed by: G. M. Wolf , Report Month December 1995 Telephone: (419) 321-8114  ;

                                        ,     g               Licensee                              g                         Cause & Corrective o     8@          c    o .E =

Event E 'o e "o i g ja:g:: y .y g y 3i x0 g, 7 Action to t No. Date o E o E-- Q~

• 2o ;jj c$ Report # m Prevent Recurrence A

6 3 95-12-23 F N/A B 5 N/A N/A N/A Power reduction to approximately 29 percent to check the oillevel of . reactor coolant pump 2-2 motor thrust bearing I 2 # 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 E-Operator Training & License Examination Previous Month , Exhibit I- Same Source F-Administrative 5-Load Reduction

• Report challanges to Power Operated Relief Valves G-Operational Error (Explain) 9-Other (Explain) (PORVs) and Pressurizer Code Safety Valves (PCSVs)

II-Other (Explain)

l OPERATIONAL

SUMMARY

December 1995 Reactor power was maintained at approximately 100 percent full power until 0000 hours on December 2,1995, when a manual power reduction was initiated. Reactor power was reduced to approximately 97 percent full power by 0200 hours to conduct the moderator temperature coefficient testing. At the completion of testing at 2011 hours, power was gradually increased to approximately 100 percent full power, which was achieved at 2120 hours. Reactor power was maintained at approximately 100 percent full power until 0000 hours on December 23, when a power reduction was initiated to reduce containment radiation levels to support a containment entry. Reactor power was manually reduced to approximately 29 percent full power by 0906 hours, and personnel entered containment to check the oil level of reactor coolant pump 2-2 motor thrust bearing. Once work in containment was complete at 1108 hours, a manual power ascension was initiated. Four brief pauses were made during the power ascension: from 1146 to 1205 hours, reactor power was held at approximately 37 percent full power to replace relays in the turbine electro-hydraulic control system, from 1555 to 1622 hours, reactor power was held at approximately 68 percent full power to place the second main feed pump in service, from 1841 to 1905 hours, reactor power was held at approximately 85 percent to perform main turbine stop valve testing, j from 1957 to 2013 hours, reactor power was held at approximately 94 percent to perform main turbine control valve testing. Reactor power reached approximately 100 percent full power at 2120 hours, and was maintained at approximately 100 percent full power for the rest of the month.}}