ML20136G722

Monthly Operating Rept for Feb 1997 for Davis-Besse Nuclear Station Unit 1

ML20136G722
Person / Time
Site:	Davis Besse
Issue date:	02/28/1997
From:	Lash J, Matranga E TOLEDO EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
KB-97-0041, KB-97-41, NUDOCS 9703180163
Download: ML20136G722 (6)

Text

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%mm EDISON A Centerior Energy Company March 11,1997 EOO M KB-97-0041 Document Control Desk U. S. Nuclear Regulatory Commission j Washington, D. C. 20555 Ladies and Gentlemen:

Monthly Operating Report, February 1997 Davis-Besse Nuclear Power Station Unit I

! Enclosed is a copy of the Monthly Operating Report for Davis-Besse Nuclear Power Station Unit I for the month of February 1997.

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

l Very truly yours, i

e O x

. es H. Lash i

Plant Manager Davis-Besse Nuclear Power Station ECM/ljk 1

I Enclosure /

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cc: A. B. Beach y NRC Region III Administrator / $

A. G. Hansen NRC Project Manager S. Stasek NRC Senior Resident Inspector 9703180163 970220 PDR ADOCK 05000346

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• AVERAGE DAILY UNIT POWER LEVEL ,

DOCKET NO. 50-0346 UNIT Davis-Besse Unit 1 DATE March 3,1997 COMPLETED BY Eugene C. Matranga TELEPHONE 419/321-8369 l

MONTH February,1997 i

AVERAGE DAILY POWER LEVEL AVERAGE DAILY POWER LEVEL  !

DAY (MWe-Net) DAY (MWe-Net) I i

1 884 15 888 2 878 16 884 3 885 17 880 4 883 18 878 l 5 ,

895 19 877 6 886 20 884 1

7 886 21 873 l

8 886 22 880 1

9 886 23 879 1

10 885 24 881 11 884 25 886 12 512 26 881 13 669 27 880 14 879 28 882

^

OPERATING DATA REPORT

. DOCKET NO 50-0346 DATE March 3,1997 COMPLETED BY Euaene C. Matranca TELEPHONE 419/321-8369

1. Unit Name: Davis-Besse Unit 1 Notes

2. Reportina Period February,1997

3. Licensed Thermal Power (MWt) 2772

4. Nameplate Ratina (Gross MWe) 925 l S. Desian Electrical Ratina (Net MWe) 906

6. Maximum Dependable Capacity (Gross MWe) 917

7. Maximum Dependable Capacity (Net MWe) 873

8. If Chanaes Occur in Capacity Ratinas (Items number 3 through 7) since last report, give reasons:

9. Power Level To Which Restricted, If Any (Net MWe): l

10. Reasons For Restrictions, if Any (Net MWe):

This Month Yr-to-Date Cumulative

11. Hours In Reporting Period 672.00 1,416.00 162,913.00

12. Number Of Hours Reactor Was Critical 672.00 1,416.00 107,611.97

13. Reactor Reserve Shutdown Hours 0.00 0.00 5,532.00

14. Hours Generator On-Line 666.26 1,410.26 10.5,313.76

15. Unit Reserve Shutdown Hours 0.00 0.00 1,732.50

16. Gross Thermal Energy Generated (MWH) 1,817,498 3,878,336 274,457,181

17. Gross Electrical Energy Generated (MWH) 609,612 1,301,528 89,231,605

18. Net Electrical Energy Generated (MWH) 579,386 1,237,507 84,280,701

19. Unit Service Factor 99.15 99.59 64.64

20. Unit Availability Factor 99.15 99.59 65.71

21. Unit Capacity Factor (Using MDC Net) 98.76 100.11 59.26

22. Unit Capacity Factor (Using DER Net) 95.16 96.46 57.10

23. Unit Forced Outage Rate 0.85 0.40 17.09

24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each): A 27 day shutdown is beina considered for late April to replace RCP 2-2 motor due to increasina 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 CRITICAllTY INITIAL ELECTRICITY COMMERCIAL OPERATION

2 .

OPERATIO'NAL

SUMMARY

February 1997 i

i Reactor power was maintained at approximately 100 percent full power

.l until 0033 hours3.819444e-4 days <br />0.00917 hours <br />5.456349e-5 weeks <br />1.25565e-5 months <br /> on February 2,1997, when a manual power reduction was

initiated to perform turbine valve testing and control rod exercising.

Reactor power was reduced to approximately 92 percent full power by 0125 l hours, and control valve and stop valve testing and control rod exercising

, was conducted. At the completion of testing at 0325 hours0.00376 days <br />0.0903 hours <br />5.373677e-4 weeks <br />1.236625e-4 months <br />, power was

! gradually increased to approximately 100 percent full power, which was

achieved at 0450 hours0.00521 days <br />0.125 hours <br />7.440476e-4 weeks <br />1.71225e-4 months <br />.

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Reactor power was maintained at approximately 100 percent full power

[ until 1521 hours0.0176 days <br />0.423 hours <br />0.00251 weeks <br />5.787405e-4 months <br /> on February 12,1997, when a Plant Shutdown was

! commenced because ofidentification that strict compliance with i surveillance testing requirements for the Decay Heat Valve Pit were not j met. At 1905, cooldown of the reactor coolant system was commenced. The j . Main Turbine was manually tripped at 2002.

b At 2005, oral notification of enforcement discretion was received which no

!' longer necessitated a plant shutdown. Reactor power was stabilized at approximately 10 percent full power and the cooldown terminated by 2039.

d

' Reactor coolant system heatup was commenced at 2050 and Reactor power l slowly raised to approximately 20 percent full power. The Main Turbine  ;

i was synchronized with the grid at 0146 on February 13,1997.

Reactor power slowly increased until 0522 when the power increase was i

stopped at approximately 45 percent full power for recalibration of nuclear instrumentation. The recalibration was complete at 1000 hours0.0116 days <br />0.278 hours <br />0.00165 weeks <br />3.805e-4 months <br /> and the

power increase was resumed.

At 1654 hours0.0191 days <br />0.459 hours <br />0.00273 weeks <br />6.29347e-4 months <br /> on February 13,1997, the power increase was stopped at approximately 90 percent full power for recalibration of nuclear instrumentation. The recalibration was complete at 1954 hours0.0226 days <br />0.543 hours <br />0.00323 weeks <br />7.43497e-4 months <br /> and the i power increase was resumed. I' 1

i

Tlie power increase was completed at 2172 hours0.0251 days <br />0.603 hours <br />0.00359 weeks <br />8.26446e-4 months <br /> at approximately 100 percent full power.

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

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

UNIT NAME Davis-Besse #1 ,

DATE March 3,1997-Report Month February,1997 COMPLETED BY E. C. Matranga .

TELEPHONE (419) 321-8369 o.d No. Date

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g j[5$ Licensee Event 5*e gg

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Action to Re # #

F $E y gs to o @O Prevent Recurrence Q

1 97-02-12 F 5.7 D 9 97-005 BP XXXXXX Plant shutdown initiated after identifying conservatively that the plant was not within literal compliance of Technical Specifications.

Notificaton of enforcement discretion recieved from NRR Technical Specification change initiated.

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 4

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 1 - Same Source H-Other (Explain)

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

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