ML20045H039

Monthly Operating Rept for June 1993 for Dbnps,Unit 1.W/

ML20045H039
Person / Time
Site:	Davis Besse
Issue date:	06/30/1993
From:	Bradley Davis, Jeffery Wood TOLEDO EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
KB93-0605, KB93-605, NUDOCS 9307160274
Download: ML20045H039 (5)

Text

,

i f

TOLEDO EDISON A Centerior Energy Company i DS 4 AVENUE TOLEDO. OHIO ' 1652-0001 July 9, 1993 KB93-0605 Docket No. 50-346 License No. NPF-3 U.S. Nuclear Regulatory Commission Document Control Desk Washington, D.C.

20555 Gentlemen:

Monthly Operating Report June 1993 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 June 1993.

If you have any questions, please contact Barry Davis at (419) 321-7370.

Very truly yours,

/

Jo i K. Vood Plant Manager Davis-Besse Nuclear Power. Station BFD/ tid Enclosures cc:

.Hr. J. B. Ilopkins NRC Senior Project Manager Mr. J. B. Martin Region III Administrator Mr. S. Stasek NRC Senior Resident Inspector J

f,'

-9307160274 930630 4

ggM1 (

PDR ADOCK 05000346 j_

n eon un

~

.. ~

t AVERAGE. DAILY UNIT' POWER LEVEL DOCKET NO 50-0346 UNIT Davis-Besse Unit 1 DATE 7/01/93

.l COMPLETED BY BARRY DAVIS.

TELEPHONE 419-321-7370 MONTH JUNE 1993 F

AVERAGE DAILY. POWER LEVEL AVERAGE DAILY POWER LEVEL

' +

DAY (MWe-Net)

DAY (MWe-Net) 5 1

879 17 872 2

880 18 867 3

885 19 869 4

879 20 863 5

879 21 871 6

878 22 871 7

877 23 872 8

871 24 869 9

868 25 864 10 872 26 868 11 874 27 867 12 874 28 870 13 875 29 873 14 869 30 873 l

15 875 16 880 INSTRUCTIONS on this format, list the average daily unit power level in MWe-Net-for each day in the reporting month. Compute to the nearest whole megawatt.

q 3

l

- ~.

~.

OPERATING DATA REEORP D00TP NO 50-346 DATE 7/01/93 COMPIETED BY Barry Davis l

TILEPHONE x7370 OPERATING STATUS 1.

Unit Name: Davis-Besse Unit 1 Notes 2.

Reporting Period....................... JUNE 1993 3.

Licensed Thennal Power (MYt)............. 2772 4.

Nameplate Rating (Gross Mie)............. 925 5.

Design Electrical Rating (Net M9c)....... 906 6.

Maximum Dependable Capacity (Gross Mie).. 913*

7.

Maxinr.t Dependable Capacity (Net M4e).... 868*

8.

If dianges Occur in Capacity Ratings (Items number 3 through 7) since last report, give reasons:

• As a result of an eight hour maximum dependable capacity test performed following the Eighth Refueling Outage.

9.

Power Invel To Which Restricted, If Any (Net Mie):

10. Reasons For Restrictions, If Any (Net MWe):

This Month ~Yr-to-Date Cumulative

11. Hours In Reporting Period..............

720.00 4343.00 130776.00-

12. Number Of Hours Reactor Was Critical...

720.00 2912.20

.77847.20

13. Reactor Reserve Shutdown Hours.........

0.00 0.00 5532.00

14. Hours Generator On-Line................

720.00 2863.90 75639.30

15. Unit Reserve Shutdown Hours............

0.00 0.00 1732.50

16. Gross 'Ihennal Energy Generated (M4H)...

1994509 7279494 187958617

17. Gross Electrical Energy Generated (MWH) 660966 2431656 62363969

18. Net Electrical Energy Generated (M4H)..

628433 2304563 58747536.

19. Unit Service Factor....................

100.00 65.94 57.84

20. Unit Availability Factor...............

100.00 65.94 59.16

21. Unit Capacity Factor (Using MDC Net)...

100.56 61.13 51.75

22. Unit Capacity Factor (Using DER Net)...

96.34 58.57 49.58

23. Unit Forced Outage Rate................

0.00 0.88 22.27

24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Ead1):

25. If Shut Down At End Of Report Period, Estimated Date of Startup:

26. Units In 'Ibst Status (Prior to Commercial Operation):

Forecast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION I

l

e f

UNIT SHUTDOVNS AND POVER REDUCTIONS DOCKET NO.:

50-346 "

UNIT NAME:

Davis-Besse il DATE:

July 1. 1993 Completed by: Barry Davis June 1993 Report Month Telephone:

(419)321-7370 "u.

o c --

~,

g Licensee yg Caus. s Correctiv.

o f

$l

[

]3j

!'4 EO Action to Event ut, -

3 yg R. port.

ga

[

rr..nt..cu,, enc.

a No significant shutdowns or power reductions.

a F: Forced Reason:

Method:

Exhibit G - Instructions for Freparation of Data 3

S: Scheduled A-Equipment Failure (Explain) 1-Manual Entry Sheets for Licensee Event Report (IIR)

B-Maintenance or Test 2-Manual Scram File (NUPIG-0161) j C-Refueling 3-Automatic Scram

.D-Regulatory Restriction 4-Continuation from E-operator Training & License Examination Previous Nnth Exhibit I - Same Source -

F-Administrative 5-Imad Reduction

• Report challenges to Power operated Relief Valves c @ rational Error (Explain) 9-other (Explain)

(FORVs) and Pressurizer Code Safety valves (PCSys)

N or (Explaint t

____ _.. - ~. -

Operational Summary June 1993 Reactor power was maintained at approximately 100 percent full power until 0200 hours0.00231 days <br />0.0556 hours <br />3.306878e-4 weeks <br />7.61e-5 months <br /> on June 20, 1993, when a manual power reduction to approximately 92 percent power was initiated to perform main turbine valve testing and control l

rod drive (CRD) testing.

After completion of main turbine valve testing and CRD exercise testing, reactor power was slowly increased to approximately 100 percent full power, which was achieved at 0548 hours0.00634 days <br />0.152 hours <br />9.060847e-4 weeks <br />2.08514e-4 months <br /> on June 20, 1993.

Reactor power was maintained at this power level for the rest of the month.

i l

't }

t 4

t l

l f

• e

--m r.* -,

i.--a w-

- - - -. +

-o

---v~

m

.--re.,

w