ML20045B198

Monthly Operating Rept for May 1993 for Dbnps,Unit 1.W/ 930608 Ltr

ML20045B198
Person / Time
Site:	Davis Besse
Issue date:	05/31/1993
From:	Bradley Davis, Storz L TOLEDO EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
KB93-0515, KB93-515, NUDOCS 9306160403
Download: ML20045B198 (5)

Text

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'1 TOLEDD - I l

%sm EDISON A Centenot Energy Company l

EDISON PLAZA $

300 MADISON AVENUE TOLEDO OHIO 43652-0001 June 8, 1993 .;

KB93-0515 Docket No. 50-346 License No. NPF-3 -:

I U.S. Nuclear Regulatory Commission Document Control Desk Vashington, D.C. 20555 ,

Gentlemen:

• Monthly Operating Report May 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 May 1993. ,

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

Very truly yours,

,~ 'I (ouisF. Storz Plant Manager Davis-Besse Nuclear Power Station  ;

-l BFD/tld Enclosures ec: Mr. J. B. Hopkins '

NRC Senior Project Manager -

Mr. J. B. Martin Region III Administrator Mr. S. Stasek  ;

NRC Senior Resident Inspector i

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/ 8 9306160403 930532 6 /LJ[/ W f PDR ADDCK 0500 R

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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO 50-0346  :

UNIT Davis-Besse Unit 1 l DATE June B, 1993  ;

COMPLETED BY BARRY DAVIS-TELEPHONE 419-321-7370 -

HONTH MAY 1993 AVERAGE DAILY POWER LEVEL AVERAGE DAILY POWER LEVEL  ;

DAY (MWe-Net) DAY (MWe-Net) i I

1 339 17 880 2 464 18 879

• 3 488 19 881 4 749 20 407  ?

5 840 21 240 ,

6 868 22 879 7 876 23 872 8 877 24 857 >

9 868 25 877 10 874 26 877 11 871 27 872 12 871 28 966 13 883 29 882 14 876 30 879  !

15 871 31 879 16 881 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. ,

(9/77) -

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L OPERATING DATA REPORT 00CKET NO _

DATE ,M, M_8_,_f993

_J,u_n_e_

C0MPLETED BY . Asp;Il_ Day,,1s TELEPHONE _{4 Lgl_11L-7370 OPERATING STATUS

1. Unit Name: Davis-Besse Unit 1 l Notes l ,

2. Reporting Period.......................MAY 1993 l l

3. Licensed Thermal Power (NWt)............. 2772 l l

4. Nameplate Rating (Gross MWe)............. 925 l l. ,

5. Design Electrical Rating (Net MWe)....... 906 l l

6. Maximum Dependable Capacity (Gross MWe).. 921 l l 3

7. Maximum Dependable capacity (Net NWe).... 877 l l

0. If Changes occur in Capacity Ratings l____________________________l (Items 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 Cumulative

11. Hours In Reporting Period.............. 744.00 3623.00 130056.00

12. Number Of Hours Reactor Was Critical... 724.40 2192.20 77127.20

13. Reactor Reserve Shutdown Hours........ 0.00 0.00 5532.00

14. Hours Generator on-Line................ 718.50 2143.90 74919.30

15. Unit Reserve Shutdown Hours............ 0.00 0.00 1732.50

16. Gross Thermal Energy Generated (MWH)... 1882742 5284984 185964107

17. Gross Electrical Energy Generated (MWH) 620242 s770690 61703003

18. Net Electrical Energy Generated (MWH).. 588603 1676130 58119103

19. Unit Service Factor.................... 96.57 59.17 57.61

20. Unit Availability Factor............... 96.57 59.17 58.94

21. Unit Capacity Factor (using MDC Net)... 90.21 52.75 50.96

22. Unit capacity Factor (Using DER Net)... 87.32 51.06 49.32

23. Unit Forced Outage Rate................ 3.43 1.18 22.43

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 SHUTDOVNS AND POVER REDUCTIONS DOCKET NO.: 50-346 UNIT NAME: Davis-Besse 91.

DATE: June 8, 1993 Completed by: Barry Davis Report Month M3Y 1993 Telephone: (419)321-7370 l

m i o-) u censee t'8 ca" " ' c*cti'*

h 7 Event $

0 Action to

-to i 33 g- 3 2= Re,o,t ,  : 0 g .rev.,t R. _ r.nce e3{- v 4 93-05-20 F 25.5 A 3 93-003 JA N/A Integrated Control System (ICS) fuse cap failure within the ICS T-ave circuit. Replaced fuse cap.

5 93-05-24 F 0 A 5 N/A N/A N/A Reactor power manually reduced to approximately 76%. The TPCW High Level Cooling Water Tank (HLCWT)

Inlet Valve, CW620, failed closed.

Valve CW620 was isolated and HLCWT level restored to normal.

See Operational Summary or LER for further details.

F: Forced Reason: Method: Eahabit G - Instructions for Preparation of Data 3: scheduled A-Equipment Failure (Emplain) 1-Manual Entry Sheets for I.icensee Event Report iter)

B-Maintenance or Test 2-Manual Scram File (NUPIG-0161) c-Refueling 3-Automatic Scram D-Regulatory Restriction 4-continuation from E-opetator Traintng & Laconse Examination Previous Month Exhibit I - Same Source F-Administ r ative 5-toed Reduction

• Report challenges to Power Operated Relief Valves G-operational Error (Eaplain) 9-Other-(Emplain) (PORVs) and Pressurizer code Safety valves IPC5vs)

M-other (Eaplain)

Operational Summary  ;

May 1993  ;

t The plant ramp up in power continued. Reactor power was slowly increased to f approximately 55 percent of full power at 1920 hours0.0222 days <br />0.533 hours <br />0.00317 weeks <br />7.3056e-4 months <br /> on May 1, 1993. Reactor power was held at 55 percent until the completion of physics testing. Physics testing was completed at 1630 hours0.0189 days <br />0.453 hours <br />0.0027 weeks <br />6.20215e-4 months <br /> on May 3, 1993. '

The power ramp up continued to approximately 90 percent reactor power at 0938 hours0.0109 days <br />0.261 hours <br />0.00155 weeks <br />3.56909e-4 months <br />  !

on May 4, 1993. Reactor power was held at 90 percent for fuel conditioning.

After the completion of fuel conditioning, reactor power was slowly increased to approximately 97 percent at 1909 hours0.0221 days <br />0.53 hours <br />0.00316 weeks <br />7.263745e-4 months <br /> on May 4, 1993. Physics testing finished at s 1955 hours0.0226 days <br />0.543 hours <br />0.00323 weeks <br />7.438775e-4 months <br /> on May 5, 1993.

i Reactor power was slowly increased to approximately 100 percent full power at '

2343 hours0.0271 days <br />0.651 hours <br />0.00387 weeks <br />8.915115e-4 months <br /> on May 5, 1993.

At 1138 hours0.0132 days <br />0.316 hours <br />0.00188 weeks <br />4.33009e-4 months <br /> on May 20, 1993, while the unit was at approximately 100 percent.of ,

full power, a reactor trip occurred. The automatic plant trip was due to high l Reactor Coolant System (RCS) pressure initiated as a result of an Integrated Control System (ICS) fuse cap failure within its T-ave circuit. The fuse cap vas replaced and other fuse holders were checked for problems. l The reactor was critical at 0714 hours0.00826 days <br />0.198 hours <br />0.00118 weeks <br />2.71677e-4 months <br /> on May 21, 1993, and the turbine was synchronized on line at 1308 hours0.0151 days <br />0.363 hours <br />0.00216 weeks <br />4.97694e-4 months <br /> on May 21, 1993. Reactor power reached approximately 100 percent at 2231 hours0.0258 days <br />0.62 hours <br />0.00369 weeks <br />8.488955e-4 months <br /> on May 21, 1993. j The plant continued to operate at 100 percent reactor power until 1221 hours0.0141 days <br />0.339 hours <br />0.00202 weeks <br />4.645905e-4 months <br /> on May 24, 1993, when a manual power reduction to approximately 76 percent was done. '

The power reduction was necessary due to low level in the Turbine Plant Cooling ,

Vater (TPCV) Bigh Level Cooling Vater Tank (HLCVT). The TPCV'HLCVT Inlet Valve,  ;

CV620, failed closed because of a broken control air supply line to CV620. ' Valve CV620 was isolated.and the level in the HLCVT vas restored to its. normal operating ,

level. l l

AT 1246 hours0.0144 days <br />0.346 hours <br />0.00206 weeks <br />4.74103e-4 months <br /> on May 24, 1993, reactor power was slowly increased to approximately  ;

100 percent at 1409 hours0.0163 days <br />0.391 hours <br />0.00233 weeks <br />5.361245e-4 months <br /> on May 24, 1993. 1 I

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

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