ML20057A720
| ML20057A720 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 08/31/1993 |
| From: | Bradley Davis, Jeffery Wood TOLEDO EDISON CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| KB93-0855, KB93-855, NUDOCS 9309150211 | |
| Download: ML20057A720 (5) | |
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TOLEDO I
EDISON 1
Acont nm En-gy canpany 30 AD S N AVENUE TOL.EDO. OHIO 436524001 j
l September 14, 1993 l
KB93-0855 Docket No. 50-346 i
License No. NPF-3 j
U.S. Nuclear Regulatory Commission Document Control Desk l
Vashington, D.C.
20555 q
Gentlemen:
l Monthly Operating Report August 1993 Davis-Besse Nuclear Power Station Unit 1 i
Enclosed are ten copies of the Monthly Operating Report for Davis-Besse j
Nuclear Power Station Unit No. 1 for the month of August 1993.
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If you have any questions, please contact Valt Flippin'at (419) 321-8300.
Very truly yours, J
Jo K. Vood Plant Manager Davis-Besse Nuclear Power Station WNF/ tid Enclosures cc:
Mr. J. B. Hopkins i
NRC Senior Project Manager Mr. J. B. Martin Region III Administrator Mr. S. Stasek.
NRC Senior Resident Inspector 4
'f 1 c: ~ n o Q :
9309150211 930831' I
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PDR ADDCK 05000346 - s%
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AVERAGE DAT6Y INIT POWER IIVEL DOCKET NO 50-0346 unT Davis-Besse Unit i DATE 09-01-93 OTELEI'ED BY BARRY DAVIS TELEPHONE 419-321-7370 K NIH AUGUSI' 1993 AVERAGE DAIIX PCMER LEVEL AVERAGE DAILY POWER IIVEL DAY
(!5t 12t)
DAY (15t-Ikt) 1 870 17 866 2
868 18 866 3
870 19 865 4
872 20 867 5
876 21 872 6
876 22 872 7
875 23 869 8
873 24 861 9
872 25 864-10 870 26 863 11 868 27 859 12 867 28 866 13 867 29 868' 14 865 30 864 15 850 31
-867 16 865 INSIRUCI' IONS On this format, list the average daily unit power level in MWe-Net far each day in the reporting month, carapute to the nearert whole negawatt.-
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OPERATING DATA REFORT J
1 DOCKET NO 50-0346 L
IETE 09-01-93 EIPLEIID BY BARRY DAVIS j
TELEPHONE 419-321-7370 l
1 OPERATHIG STATUS i
1.
Unit Nare: Davis-Besse Unit 1 Notes 2.
Reporting Period....................... AUGUST 1993 3.
Licensed Therral Power (Et)............. 2772 1
4.
Naneplate Rating (Gross We)............. 925 5.
Design Electrical Rating, (Net We)....... 906 G.
Maxinn Dependable Capacity (Gross IMe).. 913 7.
Maximn Dependable Capacity (Net We)... 868 8.
If Changes Occur in Capacity Ratings (Items number 3 through 7) since last 19;vd, give reasons:
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9.
Power icvel To Which Restricted, If Any (Net We):
- 10. Reasons For Restrictions, If Any (Net We):
I 7his Month Yr-to-Date Cumulative
- 11. Hours In Reporting Period..............
744.00 5831.00 127921.00
- 12. Number Of Hours Reactor Was Critical...
744.00 4400.20 76423.00 i
- 13. Reactor Reserve Shutdown Hours.........
0.00 0.00 5532.00
- 14. Hours Generator On-Line................
744.00 4351.90 74263.40 l
- 15. Unit Reserve Shutdown Hours............
0.00 0.00 1732.50 16.' Gross 7herinal Energy Generated (15E)...
2060372 11390924 184739992 3
- 17. Gross Electrical Energy Generated (ISE) 678859 3789268 61285445
- 18. Net Electrical Energy Generated (IGE)..
645463 3595412 57729974 1
- 19. Unit Service Factor....................
100.00 74.63 58.05
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- 20. Unit Availability Factor...............
100.00 74.63 59.41 l
- 21. Unit Capacity Factor (Using MDC Net)...
99.95 71.04 51.99 i
- 22. Unit Capacity Factor (Using DER Net)...
95.76 68.06 49.81
- 23. Unit Forced Outage Rate................
0.00 0.58 22.59 i
j
- 24. Shutdowns Scheduled over Next 6 Months (Type, Date, and Duration of Each):
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- 25. If Shut Down At Erd Of Report Period, Estirated Date of Startup:
- 26. Units In 7bst Status (Prior to Comnercial Operation):
Forrv xt Achieved INITIAL CRITICALTIY INITIAL ELELTRICITY i
03EERCIAL OPERATIOt!
UNIT SHUTD0VNS AND POWER REDUCTIONS DOCKET No.:
50-346 UNIT NAME:
Davis-Besse #_1 DATE:
9/1/9'3 Completed by:
Barry Davis Report Month August 1993 Telephone:
(419)321-7370
[
Cause & Corrective e
$f h
- g s-A Event eo l
Date aig Prevent mecurr.nc.
ge a
e e
No significant sh atdowns or powet reductions.
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- Exhibit G - Instructions for Preparation of Data F: Forced Reason:
Method:
S: Sche <hiled A-Equipment Failure (Explain) 1-Manual Entry Sheets for I.icensee Event Report (IIR)
B-Maintenance or Test 2-Manual Scram File (NUREG-0161)
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C-Refueling 3-Automatic Scram Il F Regulatory Restriction 4-<ontinuation from E-operator Training & License Examination Previous Month Ethibit I - Same Source F-Administrative 5-toad Reduction
- Report challenges to Power Operated Relief Valves G-operational Error (Explain) 9-Other (Explain)
(IORVsl and Pressuriser Code Safety Valves (PcSVs)
H-Other {Explaini
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j Operational Summary
]
August 1993 i
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Reactor power was maintained at approximately 100 percent full power until l
1 0100 on August 15, 1993, when a manual power reduction to approximately 85 percent l
1 was initiated to perform main turbine valve testing and control rod drive (CRD) l j
testing.
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j After completion of main turbine control valve testing, stop valve testing, and CRD f
exercise testing, reactor power was slowly increased to approximately 100 percent l
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full power, which was achieved at 0528 on August 15, 1993.
Reactor power was j
maintained at this power level for the rest of the month.
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