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Monthly Operating Rept for Dec 1991 for Davis-Besse Nuclear Power Station,Unit 1
	ML20091K162
Person / Time
Site:	Davis Besse
Issue date:	12/31/1991
From:	Sarsour B, Storz L; TOLEDO EDISON CO.
To:	; NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
	KB92-0079, KB92-79, NUDOCS 9201220313
	Download: ML20091K162 (6)
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F TOL EDO EDISON A Corderror Energy Longwy EO! SON PLAZA 300 MADtSON AVENUE TOL000. OHto 43652 0001 Jitnuary 10, 1992 KB92-0079 Docket NoE 50-346 License'No. NPF-3 Document-Control De'sk U.S.-Nuclear Regulatory Commission

=7920 Norfolk Avenue

- Be thesda,-_ HD -20814 Gentlemen:

-Monthly: Operating Report,' December, 1991-

- Davis-Besse Nuclear ~ Power Station Unit 1 Enclosed are-te'n copies;of'the Monthly Operating Report ~for Davis-Besse

. Nuclear Power'..btation Unit No.-I for-the month of December, 1991.

-If you;have.any. questions, please contact Bilal Sarsour at (419) 321-7384.

Very truly yours,.

3}bk Louis. Storz f

. Planti Manager Davis-Besse Nuclear-Power Station BHS/ tid:

Enclosures-cci :Mr.cA.iBert Davis Regional-Administrator, Region III

l. Mr. J.: B. Hopkins -

NRC Senior Project Hanager i

-Mr. Villiam Levis NRC Resident: Inspector

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AVERAGE D AILY UNIT POWER LEVEL DOCKET NO, 50-346 UNIT Davis-Besse #1 DATE lanuary 10. 1992 COMPLETED liY Bilal Sarsour TELEPHONE (419)321-7384 MONTil December, 1991--

DAY AVER AGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL (MWe Net) iMWe. Net i I

877 7

885 2

879-

-lg 886 3

881 887 39 4

879 20 887 3

880 885 21 325 885 6

22 7

0 23 885 0

886 g

3 9

0 25 885 10 0

885 26 361 885 g,_

g 12 732 28 885 13 871 884 29 855 880 14 -

30 886 886 15 3,

886 16

' INSTRUCTIONS On this format, hst the average daily unit power lesel in MWe Net for each day in the reporting month. Compute to the nearest whole mepwart.

pH77)

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l OPERATING DATA REPOPT DOCKET NO, 346 DATE danuary 10, 1992 COMPLETED BY Bflal Sarsour TELEPHONE (419)321-7384 OPERATING ST ATUS i

1. Unit Name:

Dads-Besse h H Notes

2. Reporting Period:

De c ernb e r. 1991

3. Licenwd Thermal Power (MWt1:

2772

4. Nameplate Rating (Gross MWe):

925 906 S. Design Electrical Rating (Net MWe).

6. Maximum Dependable Capacity (Gross M$"r 418

7. Ma.simum Dependable Capacity (Net MWei-874

8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report. Gise Reasons:

9. Power Level To Which Restricted,1f Any(Net MWe):

10. Reasons For Restrictions.lf Any:

This Month Yr..to.Dat e Cumulatne

11. Hours in Reporting Period.

744.0 8,760.0 117,649

12. Number Gf Hours Reactor Was Critical 630.5 7,054.6 66,175.8

13. Reactor Reserve Shutdown Hours 113.5 113.5 5,507.2

14. Hours Generator On Line 613.7 6,963.8 64,033.I

15. Unit Reserve Shutdown Hours 0.0 0.0-1,732.5

- 16. Gross Thermal Energy Generated (M WH) 1,681,828 18,482,806 156,609,293

17. Gross Electrical Energy Generated (MWH) 562,258

-6,163,360 51.893.377-

18. Net Electrical Energy Cenerated (MWH) 530,063 5,843,860 48,792,488

19. Unit Service Factor 82.5 79.5 54,4

20. U sit Asailability Factor 82.5 79.5 55.9

21. Unit Capacity Factor (Using MDC Net) 81.5 76.3 47.5

22. Unit Capacity Factor (Using DER Net) 78.6 73.6 45.8-

23. Unit Forced Outage Rate 17.5 2.1 25.2 24.' Shutdowns Scheduled Oser Next 6 Months iType. Date, and Duration of Each t.

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

26. Units in Test Status (Prior to Commerem Operationt Forecast Achiesed IN'T!A L CRITICA LITY INITIA L ELECTRICITY CO\\tMERCIAL OPER ATION (u m,

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mrr SwTINES AND M REDUCTIORS

.50-346 DoCxrT m.

tRrIT NAME Davis-Besse el DnTE January 10, 1992*

COMP 11TED BY Bila! Sareour PZPORT NMDI December, 1991 rE12PiosE (4ts) 321-73s4

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91-007 EK SCO The turbine-generator was taken 3

i off line due to exceeding the 72 I

hour. time limit for Emergency Diesel Generator (EDG) inoperability per Technical Specification 3.8.1.1.

See Operational Summary for further details.

F: Forced Reason:

Method:

Exhibit G - Instructions for Preparation of Data S: Scheduled A-Equig'eent Failure (Explain) 1-Manual Entry Sheets for 1.icensee Event Report 112R)

B-M.sintenance or Tect 2-Marmal Scram File (NUREG-0161)

C-Refueling 3-Automatic Scras D-Regulatory Restriction 4-Continuation from E-operator Training & License Examination Previous Month Exhibit 1 - Same Source F-Administrative 5-toad Reduction

Peport challerges to Power Ogerated Relief Valves M stational Error (Explaini 9-4ther (Explain?

(PORVs) and Pressur1rer Code Safety Valves (PCSVs)

H e lmr (Explaial

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Operational Summary December, 1991 1

Reactor power was maintained at approximately 100 percent full power until 0805 hours0.00932 days 0.224 hours 0.00133 weeks 3.063025e-4 months on December 6, 1991, when a manual power reduction was initiated to take the turbine off line. The turbine-vas taken-off line at 1034 hours0.012 days 0.287 hours 0.00171 weeks 3.93437e-4 months on December 6, 1991, and the reactor was shutdown to comply with Technical Specification 3.8.1.1, which requires both Emergency Diesel Generators (EDG) to;be operable while at power.

EDG Number 2 vas declared inoperable on December 3, 1991, when the speed switch failed.

The reactor was critical at 0430 Sours on December 11, 1991, and the Turbine -

Generator was synchronized on line at 2057 hours0.0238 days 0.571 hours 0.0034 weeks 7.826885e-4 months on December 11, 1991.

Reactor power-was slovly increased to approximately 75 percent of full power,

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which was Schieved at 0400 haurs on December 12, 1991. Reactor power was I

maintained at this power level for approximately four hours for conditioning of the fuel.

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I Reactor power escalation continued.

Reactor power was slowly i crimiel to approximately 100 percent full power, which was achieved at approxima ely 1700 hours0.0197 days 0.472 hours 0.00281 weeks 6.4685e-4 months on December 12, 1991, and maintained at this power-lavel until 1859 hours0.0215 days 0.516 hours 0.00307 weeks 7.073495e-4 months on December 13, 1991, when a manual power reduction to approxi-mately 95 percent vas initiated to isolate Feedvater Heater 1-4 in order to s

repair a steam leak on instrument line, c

After the completion of-Feedvater Heater 1-4 steam leak repair, reactor power was slowly increased-to approximately 100 percent full power, which was achieved at 1418 hours0.0164 days 0.394 hours 0.00234 weeks 5.39549e-4 months on December 14, 1991. Reactor power was maintained at u

100 percent for the retaainder of the month.

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REFUELING INFORMATION Date December 1991 1.

Name of facility:

Davis-Besse Unit 1 2.

Scheduled date for.next refueling outage? Harch 1993 3.

The number of fuel assemblica (a) in the core and (b) in the srent fuel storage pool, and (c) the new fuel storage areas.

(a) 177 (b) 393 (c) 0 4.

The present licensed spent fuel pool storage' capacity and the size of any increasa in licensed storage capacity that has been requested-or is planned, in number of fuel assemblies.

Present:

735 Increased size by:

approxiaately 900 by 1994 is under re';iew 5.

The projected date of the last refueling that can be discharged to the spent fuel.nool assuming the present license' capacity.

Date:

1996 - assuming ability to unload the entire core into the spent fuel oool is maintained l

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ML20091K162

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