ML20063Q101

Monthly Operating Rept for Jul 1990 for Davis-Besse Nuclear Power Station

ML20063Q101
Person / Time
Site:	Davis Besse
Issue date:	07/31/1990
From:	Sarsour B, Storz L TOLEDO EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
KB90-0502, KB90-502, NUDOCS 9008170250
Download: ML20063Q101 (6)

Text

. . .

4 am Eoo -180N EDISON PLAZA ~

300 MADISON AVENUE '

- TGLEDO. OHIO 43652 o001

, r August 13, 1990 KB90-0502 4 Docket No. 50-346' License No. NPP-3 Document Control DtJk

~U. S. Nuclear Regulatory Commission _,

7920 Norfolk Avenue

, Bethesda, MD -20555 Gentlemen Monthly Operating Report, July 1990 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 July 1990.

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

Very truly yours,

, ./ g fjen 7 8 Louis F. Storz Plant Manager i Davis-Besse Nuclear Power Station BMS/ tid Enclosures l cci Mr. A. Bert Davis Regional Administrator, Region-III Mr. Paul-Byron NRC Resident Inspector-

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Mr. M. D. Lynch NRC Senior Project Manager }

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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO, 50-346 UNIT Davis-Besse il [

August 13, 1990 DATE

~ COMPLETED BY. Bilal Sarsour - 'l TELEPHONE- (419)321-7384-1 l

MONTH July, 1990 DAY AVERAGE DAILY POWER LEVEL DAY. AVER AGE DAILY POWER LEVEL (Mbe Net) ( MWe-Net )

1 0 872-g7

-)

2 0 867 g

3 0 862 39 4 16 856 20 5 204 873-  !

33 6 297 ,, 867 7 ano 885 23 ,

8 600 885 24  ;

9 804 885 25 j 10 641 s885 26 f 11 840 ,, 884 j 12 R41 s 832 1.1 875 ,9 -873-14 875 875 1 30 15 877 880.

3 16 873 INSTRUCTIONS I On this format. list the average daily unit power inelin MWe. Net for each day in the reportine month. Compute o the nearest whole megawmt, '

1 pil7" ) -)

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1 OPERATING DATA REPORT , -

DOCKET NO. _ 50-346

. DATE Aucust- 13' 1990 .

COMPLETED liY Bilal Sarsour TELEPilONE (4191321-7384 ,

OPERATING STATUS

1. , Unit Name: Davis-Besse #1 N

2. Reporting Period: July, 1990 3 Licensed Thermal Power (MWt): 2779 4, Nameplate Rating (Gross MWep 925

5. Deign Electrical Rating (Net MWep 906 6 Maximum Dependable Capacity (Gross MWep 918 --

7, Maximum Dependable Capacity (Net MWeh 874 i S. If Changes Occur in Capacity Ratings (Itears Number 3 Through 7) Since Last Report, Give Reasons:

' 9. Power Lesel To Which Restricted. lf Any (Net MWen

10. Reasons For Restrictions,if Any:

i This Month - Yr. to.Date Cumulatise -

II. Flours in Reporting Period 744.0- 5,087.0 105,216

12. Number Of flours Reactor Was Critical -

714 0 1 149 R 55 647 6'

13. Reactor R sene Shutdown Hours O'. 0 0.0 5.393.7 .;

644.2 '

14. Hours Generator On Line . 1.253.0 53.453.4

15. Unit Resene Shutdown Hours 0.0 '0.0 1.732.5 l

16. Gross Thermal Energy GenerateJ IMWH) 1_619 250 1.949.57s 1?Ri?06.40s

17. Gross Electrical Energy Generated (MWH). 539 2 2%_.-. '1.076.223- 42.426.524

18. . Net Electrical Energy Generated (MWh) 508.281 1.017.021 39.804,179

19. Unit Service Factor 86.6 24.6 50.8

20. Unit A5allability Factor 86.6 24.6 s2.5 r

21. Unit Capacity Factor iUsing MDC Net) 78.2 22.9 43.3~

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22. Unit Capacity Factor IUsing DER Net) 75:4  ?? 1 al' R 23 Unit Forced Outage Rate 0.0 21.2 28.6-

24. Shutdowns Scheduled Oser Next 6 Months (Type, Date,and Duration of Eacht:

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

26. Units in Test Status (Prior to Commercial Operationn Forecast Achiesed i

3 INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIA L OPER A TION i (4/77)

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INIT SIFJrDOWitS AtED POWEP REDUCTIcetS DOONT 140.56-346 tBEIT EUWE Davis-8 esse ti- *

• DATE 'Aimiser it,.1990 CCNTIITED BY Silal Sarsour mEPomT rEurrs July, 1990 TElzPuoi4E (41,5 321-73se  !

n g _ c. Y ea

• Licensee #

• Cause & Corrective o a C TUe C U w j .g No. Date "h e

$':n$ $

e K

• sc Event

, o C u Action to

• • u Prevent securrence j j jg poport 9 8

6 90-07-01 S 99.8 C 4 NA NA- NA The outage was extended longer than anticipated to complete planned and scheduled work.

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I F: Forced Reason: ' Method: Exhibit G - Instructions for Preparation of Data 2: Schedtaled - A-Equipment Failure (Explain) 1+anual Entry Sheets for Licensee Event Report (1st)

' B-Maintenance or Test 2-Manual Scram File (fEustEG-0161) c-Refueling 3-Automatic Scram

.D-megulatory mestriction 4-continuation from E-Operator Training & License Examination Previous Month ' Exhibit I - Same Source F-Administrative 5-load medaction Wrt challenges to Power Operated Relief Talves G-operational Error (Emplain) 9-Other (Emplain) (POR7s) and Pressuriser Code Safety Talves (PC5Vs)

II-<rther (Explain)

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-. .u . _ ._ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ . _ _ _ . . _ _ _ _ , _ _ _ _ _ . . _ _

. o Operational Summary Ji'ly 1990 Zero Power Physics Testing began on Juna 30, 1990, and the reactor was deborated to criticality at 1001 hours0.0116 days <br />0.278 hours <br />0.00166 weeks <br />3.808805e-4 months <br /> on July 1, 1990. Zero Power Physics Testing was completed at 1000 hours0.0116 days <br />0.278 hours <br />0.00165 weeks <br />3.805e-4 months <br /> on July 3, 1990.

The turbine-generator was synchronized at 0349 hours0.00404 days <br />0.0969 hours <br />5.770503e-4 weeks <br />1.327945e-4 months <br /> on July 5, 1990, marking the completion of the unit outage which began on January 26, 1990.

Reactor power was slowly increased to approximately 40% of full power which ,

was attained at 1500 hours0.0174 days <br />0.417 hours <br />0.00248 weeks <br />5.7075e-4 months <br /> on July 5, 1990. Physics testing at 40% of full power was completed on July 7, 1990.

Reactor power escalation continued. Reactor power was increased to approximately 75% of full power, which was achieved at 1300 hours0.015 days <br />0.361 hours <br />0.00215 weeks <br />4.9465e-4 months <br /> on July 8, 1990. It was maintained at this power level for core power distribution and hot channel factor testing until 1600 hours0.0185 days <br />0.444 hours <br />0.00265 weeks <br />6.088e-4 months <br /> on July 8, 1990, when reactor -

power was slowly increased to approximately 96% full power, which was attained at 1700 hours0.0197 days <br />0.472 hours <br />0.00281 weeks <br />6.4685e-4 months <br /> on July 9, 1990. Physics testing at 96% of full power was completed on July 11, 1990.

Reactor power was slowly increased to approximately 100% full power at 0515 hours0.00596 days <br />0.143 hours <br />8.515212e-4 weeks <br />1.959575e-4 months <br /> on July 13, 1990, and maintained at this power level until 2100 hours0.0243 days <br />0.583 hours <br />0.00347 weeks <br />7.9905e-4 months <br /> on July 20, 1990, when a manual power reduction to approximately 85% of full power was initiated due to a drop in condenser vacuum. Condenser vacuum returned to normal at 2206 hours0.0255 days <br />0.613 hours <br />0.00365 weeks <br />8.39383e-4 months <br /> on J91y 20, 1990, and reactor power was slowly increased to approximately 100% full power, which was achieved at 0230 hours0.00266 days <br />0.0639 hours <br />3.80291e-4 weeks <br />8.7515e-5 months <br /> on July 21, 1990.

l Reactor power was maintained at approximately 100% full power until 0100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br />

! on July ?"., 1990, when a manual power reduction to approximately 85% of full power was initiated for control rod drive exercise testing, turbine control valve testing, and stop valve testing.

After the completion of stop valve testing, reactor power was slowly increased to approximately 100%, which was attained at 0800 hours0.00926 days <br />0.222 hours <br />0.00132 weeks <br />3.044e-4 months <br /> on July 22,- 1990, i

Reactor power was maintained at this power level until 0317 hours0.00367 days <br />0.0881 hours <br />5.241402e-4 weeks <br />1.206185e-4 months <br /> on July 27, l 1990 when reactor power was reduced to approximately 90% of full-power as a j precaution to insure adequate vacuum due to a loss of Circulating Vater Pump 1-3 which resulted from a motor failurc.

l l At 1918 hours0.0222 days <br />0.533 hours <br />0.00317 weeks <br />7.29799e-4 months <br /> on July 28, 1990, reactot power was slowly increased to approximately 100% full power which was achieved at 2000 hours0.0231 days <br />0.556 hours <br />0.00331 weeks <br />7.61e-4 months <br /> on July 28, l 1990, and maintained at this power. level for the rest of the month.

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, REFUELING INFORMATION Date: July 1990'

-1. Name of facility: Davis-Besse Unit 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 i

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