ML20081D899
| ML20081D899 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse |
| Issue date: | 02/28/1995 |
| From: | Wolf D, Jeffery Wood TOLEDO EDISON CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| KB-95-0054, KB-95-54, NUDOCS 9503210063 | |
| Download: ML20081D899 (5) | |
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TOLEDO EDISON A Centerior Energy company EDO O 1
March 14, 1995 KB-95-0054 Docket No. 50-346 k
License No. NPF-3 U.S. Nuclear Regulatory Commission Document Control Desk Washington, D.C.
20555 Gentlemen:
Monthly Operating Report, February, 1995 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 February, 1995.
If you have any questions, please contact G. H. Volf at (419) 321-8114.
Very trt:ly yours,
& hd u.
John K. Vood Plant Manager Davis-Besse Nuclear Power Station GMW/dmc Enclosures cc:
L. L. Gundrum NRC Project Manager J. B. Martin Region III Administrator S. Stasek NRC Senior Resident Inspector, Stop 4030 9503210063 950228 PDR ADOCK 05000346
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AVERAGE DAILY UNIT POWER LEVEL 4
DOCKET NO. '50-0346 UNIT Davis-Besse Unit 1 DATE 01 - 95 COMPLETED BY GERALD WOLF TELEPHONE 419 - 321 - 8114 MONTH FEBRUARY 1995 AVERAGE DAILY POWER LEVEL AVERAGE DAILY POWER LEVEL DAY (MWe-Net)
DAY (MWe-Net) 1 889 15 887 2
887 16 889 3
890 17 890 4
889 18 889 5
890 19 888 6
889 20 888 7
889 21 888 8
888 22 888 9
889 23 888 10 888 24 890 11 890 25 888 12 889 26 872 13 889 27 889 14 890 28 889
4 OPEP,ATING DATA REPORT DOCKET NO. 50-0346 DATE March 2,1995 COMPLETED BY Gerald Wolf TELEPHONE 419 - 321 - 8114-OPERATING STATUS
- 1. Unit Name: Davis-Besse Unit 1
- 2. Reporting Period FEBRUARY 1995 Notes
- 3. Ucensed 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 5 IfChanges Occur in Capacty Ratings (items number ? c ough 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 Report N Nriod 672.00 1,416.00 145,369.00
- 12. Number Of Hours R'6 actor Was Cntical 672.00 1,416.00 91,361,77
- 13. Reactor Reserve Shutdown Hours 0.00 0.00 5,532.00
- 14. Hours Generator On-Une 672.00 1,416.00 89,106.90
- 15. Unit Reserve Shutdown Hours 0.00 0.00 1,732.50
- 16. Gross Thermal Energy Generated (MWH) 1,860,438 3,920,145 230,016,218 H. nross Electrical Energy Generated (MWH) 627,131 1,319,219 74,390,707
- 18., set Electrical Energy Generated (MWH) 596,841 1,255,421 70,166,790
- 19. Unitllervice Factor 100.00 100.00 61.30
- 20. Unit Availability Factor 100.00 100.00 62.M
- 21. Unit Capacity Factor (Using MDC Net) 102.32 102.14 55.61
- 22. Unit Capacity Factor (Using DER Net) 98.03 97.86 53.28
- 23. Unit Forced Outage Rate 0.00 0.00 19.58 243hutdowns 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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'4.3 UNIT' SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.:
50-346 ~
- 3 ~.,
UNIT NAAE: - Davis-Besse #1 DATE:.
March 2.1995 Completed by:
G. M. Wolf Report Month February 1995 Telephone:
.(419)321-1114 _,
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Cause & Corrective l
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Action to g1 No.
Date p-g 3g9 P y" gu eu d
Prevent Recurrence
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No Significant Shutdowns or -
Power Reductions 4
4 1
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 o.,ual Scram
_ File (NUREG-0161)
C-Refueling 3-Automatic Scram D-Regulatory Restriction 4-Continuation from.
5-i 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 Ermr(Explain)
- 9-Other (Explain)
(PORVs and Pressurizer Code Safety Valves (PCSVs) '
H-Other (Explain)
o ye f, a
OPERATIONAL
SUMMARY
February 1995 l
Reactor. power was maintained at approximately 100 ' percent full power l
until 2338 hours0.0271 days <br />0.649 hours <br />0.00387 weeks <br />8.89609e-4 months <br /> on February 25,1995,.when a manual power redu'ction was-1 initiated to perform stop valve testing, control' valve testing, and control rod.
drive exercising. Power was' manually reduced to approximately 95 percent full power by 0016 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> on February 25,1995, and control valve testing was performed. Reactor power was then reduced to approximately 85 '
percent full power, which was attained at 0211 hours0.00244 days <br />0.0586 hours <br />3.488757e-4 weeks <br />8.02855e-5 months <br />.. At this point stop valve testing and control rod drive exercising was performed. Reactor power was reduced to approximately 82 percent as a result of control rod drive exercising. ' At 0305 hours0.00353 days <br />0.0847 hours <br />5.042989e-4 weeks <br />1.160525e-4 months <br />, reactor power was gradually increased to :
approximately 100 percent full power, which was achieved at 0520 hours0.00602 days <br />0.144 hours <br />8.597884e-4 weeks <br />1.9786e-4 months <br />.
Reactor power was' maintained at approximately 100 percent full power for.
the rest of the month, i
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