ML20082F948

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Monthly Operating Rept for Jul 1991 for Davis-Besse Nuclear Power Station Unit 1
ML20082F948
Person / Time
Site: Davis Besse Cleveland Electric icon.png
Issue date: 07/31/1991
From: Bradley Davis, Storz L
TOLEDO EDISON CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
KB91-0821, KB91-821, NUDOCS 9108160135
Download: ML20082F948 (6)
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TOL E DO EDISON A ( entem, ( ,, rw f :m;,tr y E OtLON PL AT A 3[10 MADGON Auf NUE 1OL 1110. Out0 43G'2-0T1 August 9, 1991 KB91-0821 Docket No. 50-346 License No. NPF-3 U, S. Nuclear Regulatory Commission Document Control Desk -

Washington, D.C. 205S5 Gentlemen:

Monthly Operating Report, July, 1991 Davis-Besse Nuclear Power Station Unit 1 Enclosed are ten copies of the Monthly Operating Report for Davis-Desse Nuclear Power Station Unit No. 1 for the month of July, 1991.

If you have any questions, please contact Bilal Sarsour at (419) 321-7304.

Very truly yours, s/ ,

.j C- )

)[l% .

Louis F. Storz Cfj)/

C Plant Manager Davis-Besse Nuclear Power Station BMS/tld F.nclosures cc: Mr. Paul Byron NRC Resident Inspector Mr. A. Bert Davis Regional Administrator, Region III Mr. J. B. Hopkins NRC Senior Project Manager p

910e16o135 91o731 p'n o m os00s m PDR

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1 AVER AGE D ALLY UNil POWER LEVEL l

DOCKET NO, __50-347 UNIT D3VI"~8 88" #I DATE A"E""I '

COMPLE1ED liY Dilrry DayIs 1ELEPil0NE (419)321-7370 MONTil "IY' DAY AVER AGE D AILY POWER LEVEL DAY AVER AGE D AILY POWER LEVEL (MWe Net) (MWe Net) 876 870 g

2 868 lg 876 3 867 39 857 4

870 20 5 870 21 000 - - - -

6 864 yy G 7

860 822 33 g 871 ,4 837 9 870 25 _

10 876 26 818 ll 873 ,, 818 g 875 ,g 801 g3 874 789

_ 39 14 876 30 ._

15 -

85 3, 770 16 872 INSTRUCTIONS On this format, hst the average daily unit power level m MWe Net for each day in the reporting month. C.un;iute to the nearest whole megawatt.

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OPER ATING DATA REPORT DOCKET No 50-347 DATE Aucust _9_ 1991 COMPL ETED BY Rnrry Dnvia TELEPil0NE //10)321-7370 OPERATING ST ATUS

1. Unit Narre: Davis-Besse Ill Note $
2. Reporting Penod: July, 1991 2772
3. Lucenwd Thermal Power (MWt):
4. Nameplate Rating (Gron MWe t 925
5. Design Electrical Rating (Net MWeI: 906
6. Maximum Dependable Capacity (Gron Mhel: 918
7. Masimum Dependable Capacity (Net MWel: 874
8. If Changes Occur in Capacity Ratings (items Number 3 Through 7)Since Last Report. Gise Reasons:

The end of fuel cycle coastdown began on July 20, 1991. Fron this point on, reactor power wilThe lowered a t /2 rate 01 JA approKlmately cVery 3 days.

9. Power Lesel To Which Restricted. lf Any (Net MWer
10. Reascns For Restrictions.lf Any:

This Month Yr. to Date Cumuhtise

11. Hours in Reporting Period 744.0 5,087.0 113,976
12. Number Of 11ours Reactor Was Critical 744.0 5.087.0 64.208.2
13. Reactor Resene Shutdown llours 0.0 0.0 5,393.7

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14. Hours Generator On Line 744,0 5,087.0 62.156.3
15. Unit Resene Shutdown Hours 0.0 0.0 1,732.5
16. Gross Thermal Energy Generated (MWH) 2,007,149 13,942,270 152.068,757
17. Gron Electrical Energy Generated (MWHI 664,9 1 ,,, 4,646,684 50,376,701 ,
18. Net Electrical Energy Generated (MWH) 632.534 4.421.232 47.369.860
19. Unit Senice Factor 100.0 100.0 54.5_
20. Unit Asailability Factor _

100.0 100.0 55.7

21. Unit Capacity Factor (Using MDC Net) 97 3 99.4 47.6
22. Unit Capacity Factor (Using DER Net) 93.9 95.9 45.9
23. Unit Forced Outage Rate 0.0 0.0 25.6
24. Shutdowns Scheduled Oser Next 6 Months tT)pe. Date, and Duration of Eacht.

The unit will be shutdown on August 30, 1991, to perform scheduled maintenance and refueling outage.

25. If Shut Down At End Of Report Period. Estimated Date of Startup:
26. Units in Test Status (Prior o Commercial Operation): Forecas: Achiesed INITI A L CRITICA LITY INITI A L ELECTRICITY COMMERCI AL OPER ATION pm ? )

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oocarr re. 50-347 tarIT NAME Dawns-Gesse il smrt A,mune 9. 1991 .

CCHrt1TED ST Bilal Sarsour mEroar mars July, 1991 rErzeuanE (sin 321-nse

~  %. cause a cer ective c - ~ License

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m. pert e jj pu {" Prevent a.currene.

8 N/A N/A N/A N/A As part of end of cycle coastdown, 2 91-07-20 S H reactor power will be reduced at a rate of 3 percent approxiraately every 3 days.

Method: Exhibit G - Instructions for Preparation of Data F: Forced Beason:

5: Sche <ialed A-Equipment rallure (Empletal 1-Mans.a1 Entry Sheets for Licensee Event Peport tIIR) 8-Maintenance or Test 2-Manual Scram Fate OduPIG-0161 )

c-Refueling 3-Automatic Scram D-Pegulatory Restriction 4 4cntinuation from E-operator Training & I.icense Examination Previous Month Exhibit 1 - Same Source F-Meinis t r ative 5-Ioad Reduction

  • Report challenges to Power operated Relief' valves G-operational Error (Explain) 9HXher (Emplain) (PCRVs) and Pressuriser Code Safety Valves (PCSvs)

H-other (Emplain)

I

i Operational Summary July, 1991 Reactor power was maintained at approximately 100 percent until 0843 hours0.00976 days <br />0.234 hours <br />0.00139 weeks <br />3.207615e-4 months <br /> on July 17, 1991, when reactor power was ieduced to 95 percent. This power reduction was a result of Number 3 circulating Vater Pump Dischatge Isolation Valve throttling shut, due to a vorker accidentally pressing against the valve's control switch. The valve was immediately returned to its normal position and, subsequently, reactor power was returned to 100 percent by 0910 houts on July 17, 1991.

The end of fuel cycle coastdown began at 1800 hours0.0208 days <br />0.5 hours <br />0.00298 weeks <br />6.849e-4 months <br /> on July 20, 1991. From this time on, teactot power vill be reduced at a rate of 3 petcent approxi-mately every 3 days until the plant is shutdown on August 30, 1991.

9 RETUELING INFORMATION Date: July 1991

1. Name of facility: Davis-Besse tinit 1
2. Scheduled date for next refueling outage? September 1991
3. The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pool, and (c) the new fuel storage areas.

(a) 177 (b) 328 (c) 0

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

Present: 735 Increased size by: approximately 900 by 1994 is under review

5. The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity.

Date: 1996 - assuming ability to unload the entire core into the spent fuel pool is maintained

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