Text

Monthly Operating Rept for June 1996 for Davis-Besse Nuclear Station Unit 1
	ML20116E016
Person / Time
Site:	Davis Besse
Issue date:	06/30/1996
From:	Lash J, Wolf G; TOLEDO EDISON CO.
To:	; NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
	KB-96-0260, KB-96-260, NUDOCS 9608050044
	Download: ML20116E016 (5)
	v • d • e

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,0 TOLEDO

% EDISON A Centerior Energy Company July 12,1996 e o o "oED'aoot KB-96-0260 Docket No. 50-346 License No. NPF-3 U. S. Nuclear Regulatory Commission Document Control Desk Washington, D. C. 20555 Gentlemen:

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

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

Very truly yours, t[h_ b ca w.

James H. Lash Plant Manager Davis-Besse Nuclear Power Station GMW/ljk Enclosures

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yC. L. Gundrum cc:

NRC Project Manager lV

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H. J. Miller NRC Region III Administrator

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S. Stasek NRC Senior Resident Inspector, Stop 4030

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960E050044 960630 PDR ADOCK 05000346 k[k R

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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-0346 UNIT Davis-Besse Unit 1 DATE July 1,1996 COMPLETED BY Gerald M. Wolf TELEPHONE 419/321-8114 MONTH June,1996 AVERAGE DAILY POWER LEVEL AVERAGE DAILY POWER LEVEL DAY (MWe-Net)

DAY (MWe-Net) 1 0

16 872 97 17 871 2

3 435 18 871 4

430 19 869 5

796 20 871 6

871 21 871 j

7 870 22 868 8

875 23 877 9

873 24 869 10 871 25 878 11 872 26 877 12 872 27 874 i

13 868 28 869 14 870 29 865 15 871 30 865

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OPERATING DATA REPORT DOCKET NO 50-0346 DATE July 1,1996 COMPLETED BY Gerald M. Wolf OPERATING STATUS

1. Unit Name: Davis-Besse Unit i Notes

2. Reporting Period June,1996

3. Licensed Thermal Power (MWt) 2772

4. Namepla_te Rating (Gross MWe) 925

5. Design Electrical Rating (Net MWe) 906

6. Maximum Dependable Capacity _(Gross MWe) 915

7. Maximum Dependable Capacity (Net MWe) 871

8. If Changes Occur in Capacjty Ratings (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 720.00 4,367.00 157,080.00

12. Number Of Hours Reactor Was Critical 715.23 3,073.20 101,778.97

13. Reactor Reserve Shutdown Hours 0.00 0.00 5,532.00

14. Hours Generator On-Line 682.62 3,035.60 99,486.50

15. Unit Reserve Shutdown Hours 0.00 0.00 1,732.50

16. Gross Thermal Energy Generated (MWH) 1,810,520 8,118,039 258,355,948

17. Gross Electrical Energy Generated (MWH) 595,207 2,587,967 83,843,529

18. Net Electrical Energy Generated (MWH) 563,520 2,457,548 79,150,027

19. Unit Service Factor 94.81 69.51 63.33

20. Unit Availability Factor 94.81 69.51 64.44

21. Unit Capacity Factor (Using MDC Net) 89.86 64.61 57.85

22. Unit Capacity Factor (Using DER Net) 86.39 62.11 55.62

23. Unit Forced Outage Rate 0.00 0.00 17.91

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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OPERATIONAL

SUMMARY

l June,1996 l:

The reactor achieved criticality at 0446 hours0.00516 days 0.124 hours 7.374339e-4 weeks 1.69703e-4 months on June 1,1996. Reactor power was then slowly increased to approximately 20 percent full power. This power level was maintained while the Main Turbine was synchronized to the grid at 1323 hours0.0153 days 0.368 hours 0.00219 weeks 5.034015e-4 months on June 2, marking the completion of j

the Tenth Refueling Outage which began April 8,1996.

Reactor power was then slowly increased until 1557 hours0.018 days 0.433 hours 0.00257 weeks 5.924385e-4 months on June 2, when the power increase was stopped at approximately 25 percent full power because a control rod drive asymmetric rod alarm was received. At 1656 hours0.0192 days 0.46 hours 0.00274 weeks 6.30108e-4 months a faulty switch was repaired to clear the alarm, and the power l

increase was reinitiated.

Reactor power was slowly increased to approximately 64 percent power at 0801 hours0.00927 days 0.223 hours 0.00132 weeks 3.047805e-4 months on June 3 l

for reactor physics testing. Reactor power was then reduced to approximately 55 percent at 0845 hours0.00978 days 0.235 hours 0.0014 weeks 3.215225e-4 months to control condenser vacuum as part of reactor physics testing. Reactor power was held at approximately 55 percent until reactor physics testing was complete at 1530 hours0.0177 days 0.425 hours 0.00253 weeks 5.82165e-4 months on June 3, 1996.

Reactor power was slowly increased until 0423 hours0.0049 days 0.118 hours 6.994048e-4 weeks 1.609515e-4 months on June 5, when the power increase was stopped at approximately 83 percent full power to perform main turbinc stop valve testing. The testing was complete at 0444 hours0.00514 days 0.123 hours 7.34127e-4 weeks 1.68942e-4 months , and the power increase was resumed.

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At 0712 hours0.00824 days 0.198 hours 0.00118 weeks 2.70916e-4 months on June 5, the power increase was stopped at approximately 90 percent full power for recalibration of nuclear instrumentation. The recalibration was complete at 1145 hours0.0133 days 0.318 hours 0.00189 weeks 4.356725e-4 months , and the power increase was resumed.

At 1416 hours0.0164 days 0.393 hours 0.00234 weeks 5.38788e-4 months on June 5, the power increase was stopped at approximately 93 percent full power for main turbine control valve and combined intermediate valve testing. During testing the group j

7 control rods reached their out limit while attempting to place the turbine first stage pressure feedback into service, so power was reduced to 90 percent full power to insert group 7 to the required position. The power increase was resumed at 1430 hours0.0166 days 0.397 hours 0.00236 weeks 5.44115e-4 months , and then stopped again at 1632 hours0.0189 days 0.453 hours 0.0027 weeks 6.20976e-4 months at approximately 94 pement full power to perform turbine valve testing.

At the completion of turbine valve testing at 1728 hours0.02 days 0.48 hours 0.00286 weeks 6.57504e-4 months on June 5, reactor power was slowly increased to approximately 100 percent full power, which was attained at 1920 hours0.0222 days 0.533 hours 0.00317 weeks 7.3056e-4 months on June 5.

Reactor power remained at 100 percent full power for the rest of the month.

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A-UNIT SIIUTDOWNS AND POWER REDUCTIONS DOCKET NO.:

50-346 UNIT NAME: Davis-Besse #I DATE:

July 1.1996 4

Completed by:

G. M. Wolf Report Month June 1996 Telephone:

(419) 321-8114

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s Licensee Cause & Corrective w

f "t:

Event 4

Action to No.

Date E--

ti o

tgc xU EO Q =*

2 Report #

m j

Prevent Recurrence C

2 96-04-08 S

37.4 C

1 N/A N/A N/A Turbine-Generator taken off-line to (cont.)

perform scheduled maintenance and refueling outage.

I

'F: Forced Reason:

Method:

Exhibit G - Instructions for Preparation of Data 2

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

E-Operator Training & License Examination Previous Month Exhibit 1 - 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) a

ML20116E016

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