ML20066D842

Monthly Operating Rept for Dec 1990 for Davis-Besse Nuclear Power Station Unit 1

ML20066D842
Person / Time
Site:	Davis Besse
Issue date:	12/31/1990
From:	Sarsour B, Storz L TOLEDO EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
KB91-0003, KB91-3, NUDOCS 9101160272
Download: ML20066D842 (6)

Text

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TOLEDO EDISON j

= A Centenor Energy Company EDISON PLAZA -

300 MADtSON AVENUE TOLEDO, OHIO 436524)O01.

January 11, 1991 KB91-0003 j

Docket No. 50-346 I

License No. NPF-3 Document Control Desk j

U. S. Nuclear Regulatory Commission j

7920 Norfolk Avenue Bethesda, HD 20555 Gentlemen:

Monthly: Operating Report, December 1990 Davis-Besse Nuclear Pover Station Unit i Enclosed are ten copies of.the Monthly Operating Report for Davis-Besse i

Nuclear Power Station Unit No. 1 for the mont.h of December 1990.-

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

Very truly yours, t'cch y

Louis F. Storz

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Plant Manager

-Davis-Besse Nuclear Power Station BHS/ tid

-Enclosures-cci Hr. A. Bert Davis l

Regional Administrator, Region III Hr.-Paul Byron-NRC Resident Inspector Hr.- H. D. Lynch NRC. Senior Project Manager

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9101160272 901230

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PDR ADOCK 05000346 R-PDR

.l AVER AGE DAILY UNIT POWER LEVEL -

DOCKET NO, 50-346 Davis-Besse #1 S'IT DATE' January 11, 1991 COMPLETED BY lillal Snrsour TELEPHONE (4I9)32I'7300 MONTH December. 1990 DAY AVER AGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL (MWe Net 1 (MWe Neti 880 876 g7 2

885 I

33 882 3

881 882 g9 4

882 881 20 884 878 5

g 883 879 6

33 7

885 33 882-g 882 881 74 883 9

881 3

i 10 882 26 880 1;

881 877 g3 881 877

,3 290 874 33

,9 14 0

873

.30 28 878 15 3,

745 16 INSTRUCTIONS On this format.hst the aserage daily unit power leselin MWe Net for each das in the reporting inonth. ( oinnute to the nearest whole megawat' pu-i

OPERATING DATA REPORT 50-346 DOCKET NO.

DATE January - 11, 1991 CONIPLETED BY Bilal Sarsour TELEPil0NE (419)321-7384 OPER ATING STATUS

1. Unit Name:

Davda-Besse #1 N0'e5

2. Reporting Period:

December, 1990

3. Licensed Thermal Power thlWt):

2772 4 Nameplate Rating (Gnm AlWe):

925

5. Design Electrical Rating (Net hlW:):

906

6. Slaximum Dependable Capacity (Gross blWe):

910 870 N1atimum Dependable capacity (Net SIWE):

if Changes occur in Capacity Ratings (items Number 3 Through 7)Since Last Report.Give Reawns:

h

9. Power Lesel To Which Restricted,1f Any (Net AlWe):

10. Reamns For Restrictions. lf Any:

This hionth Yr. to.Date Cumulative

11. flours in Reporting Period 744.0 8,760.0 108,889-

12. Number Of flours Reactor Was Critical 694.8 4,966.6 59,121.2

13. Reactor Reserve Shutdown ilours 0.0 0.0 5,393.7

14. Ilours Generator 0n.Line 666.9 4,868.9 57,069.3

15. Unit Resene Shutdown flours 0.0 0.0 1.732.5 t

Iti Grou Thermal Energy Generated (AlWil) 1,881,412 13.162,565 138,126,485 17 Gnm Electrical Energy Generated (N!Wil) 627,9 L _,

4,379,716 45,730,017 lb. Net Electrical Energy Generated (SlWil) 595.144 4.161.470 42.948.628

19. Unit Service Factor 92.3 55.6 52.4

20. Unit Asailability Factor 92.3 55.6 54.0 21 Unit Capacity Factor (Using NIDC Net) 91.5 54.4-

22. Unit Capacity Factor (Using DER Net) 88.3 52.4 45.1 43 1

23. Unit Forced Outage Rate 7.7 7.5 27.3

24. Shutdowns Scheduled Over Next 6 Slonths(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 Io Commercial Operation)

Forecast Achiesed INITI AL CRITICALITY INITIA L ELECTRICITY CONINlERCIAL OPER ATION (9/77 )

UNIT SMLTEDWNS AND FDWER NCSS DocErr No. 50-346 UNIT MAME Davis-Besse el tmTE January 11, 1991 COMPIETED ST Bilal Sarsour REmRT - December, 1990 TE11PPONE (419) 321-7384 I

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Date 4 -=

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Prevent Recurre,ce 8

8 90-12-13 F

57.1 A

3 90-016 AA BRK The Reactor Protection System (RPS) tripped the reactor on low RCS pressure after the group 7 rods dropped in the core.

(See Operational Summary for further details).

j F: Forced Reason:

' Method:

Exhibit G ~ Instructions for Preparation of Data S: Scheduled A-Equipment Failure (Explain) 1-Manual Entry Sheets for Licwnsee Event Report (IIR)

S-Maintenance or Test 2-Manual Scram File (NUREG-0161)

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

• Report challenges to Power operated Bellsf valves 9 ether (Explain)

(PORVs) and Pressuriter Code Safety valves (PCSTs)

G-operational Error (Explain) s H-other (Explain)

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Operational Summary December,1990 e

Reactor power was maintained at approximately 100% full power until 0844 hours0.00977 days <br />0.234 hours <br />0.0014 weeks <br />3.21142e-4 months <br /> on December 13, 1990 when a reactor trip occurred. The Reactor Protection System (RPS) tripped the reactor on lov Reactor Coolant System (RCS) pressure after the group 7 rods (except Rod 7-1) dropped in the core.

Rod 7-1 dropped into the core < tring the reactor trip.

The reactor was critical at 0823 hours0.00953 days <br />0.229 hours <br />0.00136 weeks <br />3.131515e-4 months <br /> on December 15, 1990 and the turbine generator was synchronized on line at 1748 hours0.0202 days <br />0.486 hours <br />0.00289 weeks <br />6.65114e-4 months <br /> on December 15, 1990.

Reactor power was slowly increased to approximately 100% full power at 2000 hours0.0231 days <br />0.556 hours <br />0.00331 weeks <br />7.61e-4 months <br /> on December 16, 1990, and maintained at this power level for the rest of the month.

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REFUELING INFORMATION Date December 1990 j

1.

Name of facility:

Davis-Desse 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.ptesent 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 teviev 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 sp~ent~~

fuel pool is maintained i

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