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Monthly Operating Rept for Jul 1994 for Davis-Besse Nuclear Power Station Unit 1
	ML20072E047
Person / Time
Site:	Davis Besse
Issue date:	07/31/1994
From:	Wolf G, Jeffery Wood; TOLEDO EDISON CO.
To:	; NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
	KB-94-1564, NUDOCS 9408220088
	Download: ML20072E047 (5)
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%mm EDISON A Centerior Ene#y conyany 0E G O 1 65 000) autust 12. 1994 KB-94-1564 Docket No. 50-346 License No. NPF-3 U.S. Nuclear Regulatory Commission Document Contr01 Desk Vashington, D.C.

20555 Gentlemen Monthly Operating Report, July 1994 Davis-Besse Nuclear Power Station Unit 1 Enclosed are ten copies of the Monthly Operating Report for Davls-Besse Nuclear Power Station Unit No.1 for the month of July 1994.

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

Very truly yours,

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,G John ['.Vood Plant Manager Davis-Besse Nuclear Power Station GHV/dmc Enclosures cc L. L. Gundrum NRC Senior Project Manager J. B. Hartin Region III Administrator S. Stasek NRC Senior Resident Inspector j 0,[) O O R g

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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50 -0346 UNIT Davis-Besse Unit 1 DATE August 2,1994 COMPLETED BY GERRY M. WOLF TELEPHONE 419-321 -8114 MONTH JULY 1994 l

l AVERAGE DAILY POWER LEVEL AVERAGE DAILY POWER LEVEL DAY (MWe-Net)

DAY (MWe-Net) 1 866 17 849 2

864 18 864 3

867 19 864 4

866 20 857 5

858 21 860 1

6 857 22 862 7

858 23 865 8

859 24 863 9

862 25 865 10 869 _

26 867 11 869 27 833 12 862 28 567 13 863 29 866 14 864 30 866 15 862 31 867 16 866

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OPERATING DATAREPORT l

DOCKET NO 50 -0346 DATE 8-2-94 COMPLETEDBY GERRYWOLF TELEPHONE 419 -321 -8114 OPERATING STATUS L Unit Name: Davis-Besse Unit 1 Notes

2. Reporting Period JULY,1994

3. Ucensed Thermal Power (MWt) 2772 E

4 Nameplate RatingfGross MWe) 925 I

5. Design ElectricalRating (Net MWe) 906 i

6. Maximum DependableCapacity (Gross MWe) 913 l

7. Maximum Dependable Capacity (Net MWe) 868 l

8. If Changes Occurin Capacity Ratings l

(Items number 3 through 7) since last report, give reasons:

l 1

l

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

I

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

(

)

i This Month Yr-to-Date Cumulative

11. Hours in Reporting Period 744.00 5,087.00 140,280.00

12. Number Of Hours Reactor Was Critical 744.00

'5,087.00 87,327.45

13. Reactor Reserve Shutdown Hours 0.00 0.00 5,532.00

14. Hours Generator On-Line 744 CJ 5,087.00 85,110.73

15. Unit Reserve Shutdown Hours 0.00 0.00 1,732.50

16. Gross Thg mal Energy Generated (MWH) 2,035,092 14,048,052 219,819,821

17. Gross Electrical Energy Generated (MWH) 667,491 4,648,088 70,988,109

18. Net Electrical Energy Generated (MWH)

_19. Unit Service Factor 634,201 4,419,631 66,946,001 100.00 100.00 60.67

20. Unit Availability Fat: tor 100.00 100.00 61.91

21. Unit Capacity Factor (Using MDC Net) 98.21 100.09 54.98 l.

22. UNt Capacity Factor (Using DER Net) 94.09 95.90 52.67 l

23. Unit Forced Outage Rate 0.00 0.04 20.32

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

Scheduled maintenance and refueling outage - October 1,1994, q

Planned duration - 49 days.

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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 GRITICALITY INITIAL ELECTRICITY l

COMMERCIALOPERATION I

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UNIT SHUTDOVNS AND POVER REDUCTIONS.-

DOCKET NO.:

50-346 w

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. UNIT NAME:

Davis-Besse #1

@* J DATE:

August 3.

1994 Completed by:

G. M. Wolf Report Month J"lY 1994 Telephone:

(419)321-8114 Y

o, tic.n..e g4 c m e a corrective o

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Action to

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03 94-07-27 F

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5 N/A N/A N/A Unscheduled power reduction for repair of steam leak at root weld of FW21.

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~ F: Forced Reason:

I Method:

rwhihit G - Instructions for Preparation of Data S: Scheduled A-Equipment Failure (Explain) 1 +.anual.

Entry sheets for Licensee Event Report (IZR)

IHtaintenance or Test 2+.anual scram File trJREG-0161)

C-Refueling 3-Automatic Scram

D-Regulatory Restrictica

(<ontinuation f rom E-operator Training & I.icense Examination

- Previous Month ruhihit 1 - Same Source F4dministrative 5-Ioad Reduction

Report challenges to Power Operated Relief Valves G-operational Error (Explain) 9-other (Explain)

(PORVs) and Pressuriser code Safety valves (PC5 Val a-other (Explain)

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OPERATIONAL

SUMMARY

Reactor power was maintained at approximately 100 percent full power until 2347 hours0.0272 days 0.652 hours 0.00388 weeks 8.930335e-4 months on July 1

16, 1994, when a manual power reduction was initiated to perform combined intercept valve testing, control valve testing, control rod drive testing, and main turbine stop valve testing.

Power was manually reduced to approximately 92 percent, at which point control rod drive, control valve, and combined intercept valve testing were performed. Manual power reduction resumed at 0141 hours0.00163 days 0.0392 hours 2.331349e-4 weeks 5.36505e-5 months on July 17, 1994, for main turbine stop valve testing. Power was manually reduced to approximately 85 percent full power. After testing completion, at 0252 hours0.00292 days 0.07 hours 4.166667e-4 weeks 9.5886e-5 months , reactor power was gradually increased to approximately 100 percent full power, which was achieved at 0600 hours0.00694 days 0.167 hours 9.920635e-4 weeks 2.283e-4 months on July 17, 1994. Reactor power was maintained at this level until July 27,1994.

A manual power reduction at a rate of 5 percent per hour commenced at 1800 hours0.0208 days 0.5 hours 0.00298 weeks 6.849e-4 months on July 27, 1994, following the detection of a steam leak at the root weld of feedwater valve FW21.

Reactor power was manually decreased to approximately 55 percent full power, which was achieved at 0255 hours0.00295 days 0.0708 hours 4.21627e-4 weeks 9.70275e-5 months on July 28,1994. Reactor power remained at this level until a power increase to 60 percent was initiated at 0325 hours0.00376 days 0.0903 hours 5.373677e-4 weeks 1.236625e-4 months and completed at 0527 hours0.0061 days 0.146 hours 8.713624e-4 weeks 2.005235e-4 months on July 28, 1994. At 0939 hours0.0109 days 0.261 hours 0.00155 weeks 3.572895e-4 months , Main Feed Pump Turbine #2 was tripped. Reactor power remained at approximately 60 percent until 1158 hours0.0134 days 0.322 hours 0.00191 weeks 4.40619e-4 months on July 28,1994. At this time, a gradual power increase to a goal of 65 percent full power was initiated. The power increase was completed at 1255 hours0.0145 days 0.349 hours 0.00208 weeks 4.775275e-4 months on July 28,1994. At 1836 hours0.0213 days 0.51 hours 0.00304 weeks 6.98598e-4 months , July 28,1994, following the repair of FW21, Main Feed Pump Turbine #2 was reset in preparation for start-up. The Main Feed Pump Turbine #2 was returned to full auto at 1938 hours0.0224 days 0.538 hours 0.0032 weeks 7.37409e-4 months on July 28,1994. A gradual reactor power increase to 100 percent commenced at 1946 hours0.0225 days 0.541 hours 0.00322 weeks 7.40453e-4 months on July 28,1994, reaching 100 percent full power at 0022 hours2.546296e-4 days 0.00611 hours 3.637566e-5 weeks 8.371e-6 months on July 29,1994. Reactor power remained at this level for the remainder of the month.

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ML20072E047

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