ML20094L104

Monthly Operating Rept for Oct 1995 for Davis-Besse Nuclear Power Station Unit 1

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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-  % IEE)lEBC)fW EDISON Pu2A 300 MADISON AVENUE TOLEDO OHIO 43652-0001 November 15, 1995 KB-95-0202 1

l Docket No. 50-346 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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9511200051 951031 ft I 1

I PDR ADDCK 05000346 I R PDR

4 AVERAGE DAILY UNIT POWER LEVEL i l

l DOCKET NO. 50-0346 )

UNIT Davis-Besse Unit 1 l

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

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7 _,__

882 23 _ _ _

879 8 875 24 881 9 881 25 882 10 880 26 882 4 11 879 27 880 12 876 28 882 13 875 29 _ ___ 880 14 _

880 30 _ 884_ ___

15 _ _ . _

883 __

31 883 _

16 _

884 i

. 1 OPERATING DATA REPORT 1

. DOCKET NO 50-0346 . . _

DATE Nov. 2,1995

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COMPLETED BY [GeraidLWojf_~ j TELEPHONE 419/321-8114 _

OPERATING STATUS

1. Unit Name: Davis-Besse Unit 1 Notes 2 Reporting P.eriod _ _

October,1995 3._L.icen_s_ed Ther_ mal . Power _(M.Wt) _ _ 2772 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. m um_Dep_endable Capacity.(Net MWe)_ 871 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): __ _

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This Month Yr-to-Date Cun:ulative  ;

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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 8O e

gy o .E =

Licensee E 'o g Cause & Corrective Event e =o k ig g .g g y gi g, 7 Action to xv ytgc g No. Date E.-  ;; - o m E u oO e Report # Prevent Recurrence o 6 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 1

was then gradually increased to approximately 100 percent full power,  !

i i which was achieved at 0340 hours0.00394 days <br />0.0944 hours <br />5.621693e-4 weeks <br />1.2937e-4 months <br />.

4  :

Reactor power was maintained at approximately 100 percent full power i

[ 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 l g

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 />, 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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