ML20094L104
| ML20094L104 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 10/31/1995 |
| From: | Wolf G, Jeffery Wood TOLEDO EDISON CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| KB-92-0202, KB-92-202, NUDOCS 9511200051 | |
| Download: ML20094L104 (5) | |
Text
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e, TOLEDO
% IEE)lEBC)fW EDISON Pu2A 300 MADISON AVENUE TOLEDO OHIO 43652-0001 November 15, 1995 KB-95-0202 1
Docket No. 50-346 l
I License No. NPF-3 U.S. Nuclear Regulatory Commission Document Control Desk Vashington, D.C.
20555 Gentlemen:
Monthly Operating Report, October, 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 October, 1995.
If you have any questions, please contact G. M. Volf at (419) 321-8114.
Very truly yours, Jo n K. Vood Plant Manager Davis-Besse Nuclear Power Station GMV/dmc Enclosures cc:
L. L. Gundrum NRC Project Manager H. J. Miller Region III Administrator S. Stasek NRC Senior Resident Inspector, Stop 4030
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I 9511200051 951031 I
PDR ADDCK 05000346 I
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4 AVERAGE DAILY UNIT POWER LEVEL i
DOCKET NO. 50-0346
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UNIT Davis-Besse Unit 1 DATE Nov. 2,1995 COMPLETED BY _ Gerald M. Wolf TELEPHONE 419/321-8114 MONTH October,1995 AVERAGE DAILY POWER LEVEL AVERAGE DAILY POWER LEVEL DAY (MWe-Net)
DAY (MWe-Net) 1 875 17 882 2
879 18 879 3
878 19 877 4
880 20 879 5
877 21 883 6
879 22 882
~
882 23 879 7
8 875 24 881 9
881 25 882 10 880 26 882 11 879 27 880 4
12 876 28 882 13 875 29
___ 880 14 880 30 884_
15 883 31 883 16 884 i
1 OPERATING DATA REPORT DOCKET NO 50-0346 DATE Nov. 2,1995 COMPLETED BY [GeraidLWojf_~
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TELEPHONE 419/321-8114 _
OPERATING STATUS
- 1. Unit Name: Davis-Besse Unit 1 Notes 2 Reporting P.eriod _
_ 2772 October,1995 3._L.icen_s_ed Ther_ mal. Power _(M.Wt) _
4._ Nameplate Rating (Gro_ss MWe) _
925
- 5. Design Electrical Rating (Net _MWe) 906 6._ Maximu_rn. Dependable _Capa. city _(Gross MWe)___
915 7.__ Maxi. um_Dep_endable Capacity.(Net MWe)_
871 m
8._lf C_hanges Occur in_ Cap _acity. Ratings (ltems 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 Cun:ulative
- 11. Hours in Reporting Period 745.00 7,296.00 151,249.00
- 12. Number Of Hours Reactor Was Critical 745.00 7,296.00 97,241.77
- 13. Reactor Reserve Shutdown Hours 0.00 0.00 5,532.00
- 14. Hours Generator On-Line 745.00 7,296.00 94,986.90 i
- 15. Unit Reserve Shutdown Hours 0.00 0.00 1,732.50
- 16. Gross Thermal Energy Generated (MWH) 2,063,699 20,111,569 246,207,642
- 17. Gross Electrical Energy Generated (MWH) 687,879 6,713,368 79,784,856
- 18. Net Electrical Energy Generated (MWH) 654,649 6,387,323 75,298,691
- 19. Unit Service Factor 100.00 100.00 62.80
- 20. Unit Availability Factor 100.00 100.00 63.95
- 21. Unit Capacity Factor (Using MDC Net) 100.89 100.51 57.if.
- 22. Unit Capacity Factor (Using DER Net) 96.99 96.63 54.96
- 23. Unit Forced Outage Rate 0.00 0.00 18.60
- 24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):
_ Scheduled maintenance and_refu.eling outage - April 8,1996. Plan _ned_d_uration - 39 d_ays. __
- 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 NAME: Davis-Besse #1 DATE:
November 2.1995 -
~ Completed by:
G. M. Wolf Report Month October 1995 Telephone:
(419)321-8114 gy Licensee Cause & Corrective g
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.g g y Event gi g, 7 Action to tgc xv E u No.
Date E.-
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Report #
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Prevent Recurrence o
No Significant Shutdowns or Power Reductions l
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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 I - 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)
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OPERATIONAL
SUMMARY
October 1995 i
1 J
i Reactor power was maintained at approximately 100 percent full power until 0001 hours1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> on October 8,1995, when a manual power reduction was initiated to perform turbine control valve testing. Reactor power was manually reduced to approximately 93 percent full power by 0051 hours5.902778e-4 days <br />0.0142 hours <br />8.43254e-5 weeks <br />1.94055e-5 months <br />, l
and control valve testing was conducted. At the completion of testing at
- 0145 hours0.00168 days <br />0.0403 hours <br />2.397487e-4 weeks <br />5.51725e-5 months <br />, power was maintained at approximately 93 percent at the i
request of the load dispatcher until 0243 hours0.00281 days <br />0.0675 hours <br />4.017857e-4 weeks <br />9.24615e-5 months <br />. Power was then gradually increased to approximately 96 percent power by 0300 hours0.00347 days <br />0.0833 hours <br />4.960317e-4 weeks <br />1.1415e-4 months <br />, which was j
maintained at the request of the load dispatcher until 0316 hours0.00366 days <br />0.0878 hours <br />5.224868e-4 weeks <br />1.20238e-4 months <br />. Power l
was then gradually increased to approximately 100 percent full power, 1
i which was achieved at 0340 hours0.00394 days <br />0.0944 hours <br />5.621693e-4 weeks <br />1.2937e-4 months <br />.
i 4
Reactor power was maintained at approximately 100 percent full power i
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until 0201 hours0.00233 days <br />0.0558 hours <br />3.323413e-4 weeks <br />7.64805e-5 months <br /> on October 29,1995, when a manual power reduction was initiated to perform testing. Reactor power was manually reduced to j
approximately 99 percent full power by 0214 hours0.00248 days <br />0.0594 hours <br />3.53836e-4 weeks <br />8.1427e-5 months <br />, and control rod drive exercising was performed. At the completion of control rod drive exercising at 0245 hours0.00284 days <br />0.0681 hours <br />4.050926e-4 weeks <br />9.32225e-5 months <br />, reactor power was manually reduced to approximately 96 percent full power, which was achieved at 0312 hours0.00361 days <br />0.0867 hours <br />5.15873e-4 weeks <br />1.18716e-4 months <br />, l
- and turbine control valve testing was conducted. At the completion of control valve testing at 0349 hours0.00404 days <br />0.0969 hours <br />5.770503e-4 weeks <br />1.327945e-4 months <br />, reactor power was manually reduced to approximately 93 percent full power, which was achieved at 0355 hours0.00411 days <br />0.0986 hours <br />5.869709e-4 weeks <br />1.350775e-4 months <br />, g
and turbine stop valve testing was conducted. At the completion of stop j
valve testing at 0430 hours0.00498 days <br />0.119 hours <br />7.109788e-4 weeks <br />1.63615e-4 months <br />, reactor power was maintained at approximately l
93 percent at the request of the load dispatcher until 0434 hours0.00502 days <br />0.121 hours <br />7.175926e-4 weeks <br />1.65137e-4 months <br />. Power was i
then gradually increased to approximately 100 percent full power, which was achieved at 0550 hours0.00637 days <br />0.153 hours <br />9.093915e-4 weeks <br />2.09275e-4 months <br />. Reactor power was maintained at
- approximately 100 percent full power for the rest of the month.
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