ML20085E505

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Monthly Operating Rept for May 1995 for Davis-Besse Nuclear Power Station
ML20085E505
Person / Time
Site: Davis Besse Cleveland Electric icon.png
Issue date: 05/31/1995
From: Wolf G, Jeffery Wood
TOLEDO EDISON CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
KB-95-0111, KB-95-111, NUDOCS 9506160558
Download: ML20085E505 (5)


Text

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6 TOLEDO

%mm EDISON EDISON PLAZA 300 MADISON AVENUE TOLEDO. OHIO 436520001 June 13, 1995 KB-95-0111 ,

Docket No. 50-346 License No. NPF-3 U.S. Nuclear Regulatory Commission Document Control Desk Vashington, D.C. 20555 Gentlemen:

Monthly Operating Report, May, 1995 s Davis-Besse Nuclear Power Station' Unit 1 Enclosed are ten copies of the Monthly Operating Report for Davis-Besse [

Nuclear Power Station Unit No. 1 for the month of May, 1995. "

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

y ry truly yours,

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M $ .

John K. Vood Plant Manager Davis-Besse Nuclear Power Station GMV/dmc Enclosures cc: L. L. Gundrum NRC Project Manager J. B. Martin Region III Administrator S. Stasek NRC Senior Resident Inspector, Stop 4030 9506160558 950531 PDR ADOCK 05000346 R PDR ,

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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-0346 UNIT Davis-Besse Unit 1 DATE 6 95 COMPLETED BY Gerald M. Wolf TELEPHONE 419/321 - 8114 MONTH MAY 1995 AVERAGE DAILY POWER LEVEL AVERAGE DAILY POWER LEVEL- j DAY- (MWe-Net) DAY (MWe-Net) 1 884 17 877 2 885 18 888 3 885 19 882 4 884 20 881 5 884 21 878 6 888 22 884 7 885 23 879 8 886 24 882 9 884 25 884 10 881 26 884  :

11 884 27 883 12 885 28 875  ;

13 848 29 882 l

14 391 30 882 15 880 31 878 16 880

OPERATING DATA REPORT DOCKET NO 50 -0346 DATE June 1,1995 ,

COMPLETED BY Gerald M. Wolf I TELEPHONE 419/321-8114 OPERATING STATUS

1. Unit Name: Davis-Besse Unit 1 Notes
2. Reporting Period May 1995 l
3. Licensed Thermal Power (MWt) 2772  !
4. Nameplate Rating (Gross MWe) 925
5. Design Electrical Rating (Net MWe) 906
6. Maximum Dependable Capacity (Gross MWe) 913
7. Maximum Dependable Capacity (Net MWe) 868 B. If Changes Occurin Capacity 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 744.00 3,623.00 147,576.00 ,
12. Number Of Hours Reactor Was Critical 744.00 3,623.00 93,568.77 l
13. Reactor Reserve Shutdown Hours 0.00 0.00 5,532.00
14. Hours Generator On-Line 744.00 3,623.00 91,313.90
15. Unit Reserve Shutdown Hours 0.00 0.00 1,732.50
16. Gross Thermal Energy Generated (MWH) 2,024,224 9,943,430 236,039,503
17. Gross Electrical Energy Generated (MWH) 677,082 3,339,192 76,410,681
18. Ne+ Electrical Energy Generated (MWH) 643,953 3,177,093 72,088,462
19. Unit Service Factor 100.00 100.00 61.88 l

.o i mit Availability Factor 100.00 100.00 63.05 l

21. Unit Capacity Factor (Using MDC Net) 99.72 101.03 56.28
22. Unit Capacity Factor (Using DER Net) 95.53 96.79 53.92
23. Unit Forced Outage Rate 0.00 0.00 19.20
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

UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO : 50-346 '

UNIT NAh1E: Davis-Besse #1 DATE: June 1.1995 Completed by: G. hl. Wolf '.

Report hionth hlav 1995 Telephone: L419) 321-8114

, g, Licensee g Cause & Corrective 57 e s .E e E% Eg g 'sy j j s :g Event y7 g7 Action to No. Date i-pg y 3 -j e e 6 Report # #

u gu Prevent Recurrence C

2 95-5-13 F N/A B 5 N/A N/A N/A Power reduction to approximately 20 percent to add oil to reactor coolant pump 2-1 motor thrust bearing i 2 3 4 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 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)

H-Other (Explain)

OPERATIONAL

SUMMARY

May 1995 Reactor power was maintained at approximately 100 percent full power until 1915 hours0.0222 days <br />0.532 hours <br />0.00317 weeks <br />7.286575e-4 months <br /> on May 13,1995, when a manual power reduction was initiated to reduce containment radiation levels to support a containment entry. Power was gradually reduced to approximately 20 percent full power by 0810 hours0.00938 days <br />0.225 hours <br />0.00134 weeks <br />3.08205e-4 months <br /> on May 14, and personnel entered containment to add oil to reactor coolant pump 2-1 motor thrust bearing. Once work in containment was complete at 1215 hours0.0141 days <br />0.338 hours <br />0.00201 weeks <br />4.623075e-4 months <br />, a manual power ascension was initiated. Four pauses were made in the power ascension to perform testing:

from 1951 hours0.0226 days <br />0.542 hours <br />0.00323 weeks <br />7.423555e-4 months <br /> to 2019 hours0.0234 days <br />0.561 hours <br />0.00334 weeks <br />7.682295e-4 months <br />, reactor power was held at approximately 81 percent to test turbine stop valves 3 and 4, from 2031 hours0.0235 days <br />0.564 hours <br />0.00336 weeks <br />7.727955e-4 months <br /> to 2l00 hours, reactor power was held at approximately 85 percent to test turbine stop valves 1 and 2, from 2159 hours0.025 days <br />0.6 hours <br />0.00357 weeks <br />8.214995e-4 months <br /> to 2227 hours0.0258 days <br />0.619 hours <br />0.00368 weeks <br />8.473735e-4 months <br />, reactor power was held at approximately 95 percent to perform main turbine control valve testing, from 2350 hours0.0272 days <br />0.653 hours <br />0.00389 weeks <br />8.94175e-4 months <br /> to 0025 hours2.893519e-4 days <br />0.00694 hours <br />4.133598e-5 weeks <br />9.5125e-6 months <br /> on May 15, reactor power was held at approximately 97 percent to perform control rod drive exercising.

The power ascension was completed on May 15 at 0052 hours6.018519e-4 days <br />0.0144 hours <br />8.597884e-5 weeks <br />1.9786e-5 months <br /> at approximately 100 percent full power. Reactor power was maintained at approximately 100 percent until 0235 hours0.00272 days <br />0.0653 hours <br />3.885582e-4 weeks <br />8.94175e-5 months <br /> on May 21, when a manual power reduction to 90 percent was initiated at the request of the System Dispatcher. This power reduction was stopped at 0300 hours0.00347 days <br />0.0833 hours <br />4.960317e-4 weeks <br />1.1415e-4 months <br /> at approximately 97 percent full power due to a problem with a group 8 control rod (APSR) module. Reactor power was maintained at approximately 97 percent until 0745 hours0.00862 days <br />0.207 hours <br />0.00123 weeks <br />2.834725e-4 months <br />, when a manual power ascension was initiated at the request of the System Dispatcher. Reactor power  ;

reached approximately 100 percent full power at 0845 hours0.00978 days <br />0.235 hours <br />0.0014 weeks <br />3.215225e-4 months <br />, and was i maintained at approximately 100 percent full power for the rest of t! l month.  !

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