ML20064F845
| ML20064F845 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 02/28/1994 |
| From: | Koch S, Jeffery Wood TOLEDO EDISON CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| KB-94-0542, KB-94-542, NUDOCS 9403150465 | |
| Download: ML20064F845 (5) | |
Text
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4 TDLEDO
% EEE)lEiC)rd EDISON PLAZA 300 MADISON AVENUE TOLE DO. OHIO 43652-0001 4
March 10, 1994 KB-94-0542 Docket No. 50-346 License No. NPF-3 1
U.S. Nuclear Regulatory Commission Document Control Desk Vashington, D.C.
20555 Gentlemen:
Monthly Operating Report, February 1994 Davis-Besse Nuclear Power Station Unit 1 Enclosed are ten copies of the Monthly Operating Report for Davis-Besse Nuclear Pover Station Unit No. 1 for the month of February 1994.
If you have any questions, please contact S. D. Koch at (419) 321-7791.
Very truly yours, LL
,h Jo in K. Vood Plant Manager Davis-Besse Nuclear Power Station SDK/dmc Enclosures cc:
Mr. R. J. Stransky NRC Senior Project Manager Mr. J. B. Martin Region III Administrator Mr. S. Stasek l
NRC Senior Resident Inspector 1
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.'s AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-0346 UNIT Davis-Besse Unit 1-DATE 3 94 COMPLETED BY STEVE KOCH TELEPHONE 419-321 -7791 MONTH FEBRUARY 1994 AVERAGE DAILY POWER LEVEL AVERAGE DAILY POWER LEVEL -
I DAY (MWe-Net)
DAY (MWe-Net) j 1
878 17 875 2
877 18 875 3
877 19 874 4
877 20 872 5
877 21 875 6
877 22 874 7-877 23 874 8
877 24 875 9
876 25 875 10 876 26 876 11 875 27 876 12 877 28 876 13 870 14 876 15 871 16 876
1 4
OPERATING DATA REPORT DOCKET NO. 50-0346 DATE 3-01-94 COMPLETED BY STEVE KOCH TELEPHONE 419-321 -7791 OPERATING STATUS
- 1. Unit Name: Davis-Besse Unit 1 i
- 2. Reporting Period...
..._. FEBRUARY 1994 Notes
- 3. Licensed Thermal Power (MWt)......
2772
- 4. Narneplate Ratin0 (Gross MWe)..
_...-. -.92 5 i
- 5. Design Electrical Rating (Net MWe)..
906
- 6. Maximum Dependable Capacity (Gross MWe).........913
- 7. Maximum Dependable Capacity (Net MWe)..
.B68
- 8. If Changes Occur in Capacity Ratin09 (items number 3 through 7) since last report, give reasons:
- 9. Power LevelTo Which Restricted, If Any (Net MWe):
- 10. Reasons For Restrictions, if Any (Not MWo):
This Month Yr-to-Date Cumulative
- 11. Hours in Reporting Period..
672.00 1416.00 136609.00
- 12. Number Of Hours Reactor Was Critical..
672.00 14i6.00 83656.45
- 13. Reactor Reserve Shutdown Hours..
0.00 0.00 5532.00
- 14. Hours Generator On-Line..
672.00 1416.00 81439.73
- 15. Unit Reserve Shutdown Hours......_..
0.00 0 00 1732.50
- 10. Gross Thermal Energy Generated (MWH)..
1,862,119 3,923,156 209,694,925
- 17. Gross Electrical Energy Generated (MWH)..
618,546 1,305,737 67,645,750
- 18. Not Electrical Energy Generated (MWH).
588,198 1,241,780 63,768,150
- 19. Unit Service Factor..
100.00 100.00 59.62
- 20. Unit Availability Factor..
100.00 100.00 60.88
- 21. Unit Capacity Factor (Using MDC Net)..
100.64 101.03 53.78
- 22. Unit Capacity Factor (Using DER Net)..
96.61 96.80 51.52
- 23. Unit Forced Outage Rate..
0.00 0.00 21.04
- 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 SHUTD0'JNS AND PO'JER REDUCTIONS DOCKET NO.:
50-346
. UNIT NAME:
Davis-Besse #1 DATE:
March 2, 1994 Completed by:
- s. D. Koch Report Month February, 1994 Telephone:
(419)321-7791 O
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Prevent moeurrence No significan1 shutde' ens or power reduct icas.
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f: Forced Reason:
Method:
4Exhibit G - Instructions for Preparation of Data S: Scheduled A-Equipment Failure (Explain) 1-Manual Entry *dheets fcr Licensee Event Report (IIR)
B-Maintenance or Test 2-Manual Scram File (trJPIG-0161)
C-Rafueling 3-Automatic Scram D-Regulatory Restrictica 4-Continuation from E-Operator Training & License Examination Previcus Month Exhibit I - Same Source F-Ad:sinistrative 5-Load Redaction
- Report challenges to Power Operated Relief valves G-operational Error (Explain) 9-other IExplain)
.(PcRva) and Pressurizer Code safety Valves (PCSVsl j
H-Other (Explain)
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-OPERATIONAL
SUMMARY
February 1994 Reactor power was maintained at approximately 100 percent full power until 0100 l
hours on February 13, 1994, when a manual power reduction to approximately 94 percent power was initiated to perform main turbine control valve testing and control rod dr-ive exercise testing.
1 After completion of main turbine control valve testing and control rod drive i
exercise testing, reactor power was slowly increased to approximately 100 l
percent full power, which was achieved at 0415 hours0.0048 days <br />0.115 hours <br />6.861772e-4 weeks <br />1.579075e-4 months <br /> on February 13, 1994.
Reactor power was maintained at this power level for the rest of the month.
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