ML20100R701

Monthly Operating Rept for Mar 1992 for Davis-Besse Nuclear Power Station Unit 1

ML20100R701
Person / Time
Site:	Davis Besse
Issue date:	03/31/1992
From:	Sarsour B TOLEDO EDISON CO.
To:
Shared Package
ML20100R691	List: ML20100R689 ML20100R701 ML20100R713
References
NUDOCS 9204170082
Download: ML20100R701 (5)

Text

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A\\ ER AGE D AILY L: Nil P0hER LEVEL DOCKET NO.

50-336 Davis-Besse (!!

L' Nil D ATE April 13, 1992 CO\\tPLEll D itY hilal Sarspur TELEP110NE ( 419) 321-738 <.

m ai, 1992 st0NTil DAY AVER AGE D AILY POhER LEVEL.

DAY AVER AGE (MILY POhER LEVEL t\\the Net t t \\th e-Net p 0

888 y

p 3

887 7

gg 889 3

790 ig 007 80 4

20 883 891 3

882 887 6

3 883 891 7

73 884 887 g

74 885 888 9

g 888 10 887 26 890 887

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gj 77 889 890 37 73 889 888 g3 y,

891 80 g4 30 8M M

15 3,

886 16 INSlRUC110NS On this format.hst the aserne dady umt powet lese! m \\1We-Net for each day in th-repomng m. nth. Omnpute to the nearest whole megawatt cor7; 9204170092 920413 PDR ADOCK 05000346 R

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l OPER ATLNG DATA REPORT DOCKL1NO 50-146 0WE iwIll_D I992 R11n1 S3fMOu CON 1PLET ED liY (419) 321 -7 38 A' TELEPHONL OPERATING STATUS lblVIS-BPSSC lln i t #1 N"

1. Urut Name; Mm b, 1992

2. Reporting Period:

2772

3. Licensed Thermal Power t%1her 925

4. Nameplate Rating (Grou Slhe-906

5. Design Electrical Rating (Net Slwet 921

6. Stasimum Dependable Capacity (Gross Nlwer 877

7. Stasimum Dependable Capadty (Net Mher

5. If Changes Occur in Capacity Ratings (Items Numb <3 3 Through 7) Since Last Report Gise Reasont

9. Power Lesel To hhich Restricted. If Any (Net Mher

10. Reasons For Restrictions. If Any :

This Month Yr to-Date Comulathe 744.0 2,184.0 119,833_

11. Hours in Reporting Period

12. Number Of Hours Reactor Was Critical 719.2 2.159.2 68.335.0 24.8 24.8 5,532.0

13. Reactor Reserve Shutdown Hours 702.3 2,142.3 66.175.4

14. Hours Generator On-Line

15. Unit Resene Shut.down Hours 0.0 0.0 1.732.5

16. Grou Thermal Exrgy Generated (MWH) 1,930,643 5,917,666 16? 526.9L 648,250 1,989.784 53,883d61-17 Gross Electrical Energy Generated (MWH)

15. Net Electrical Energy Generated (MWH) 615,000 1,892.058_

50.684.54(.

94.4 98.1 55.2

19. Unit Senice Factor 94.4 9M.1 56.7

20. Unit Asailability Factor 94.3 98.8 48.2 21 Unit Capacity Factor (Using MDC Net) 91,2 95.6 46.7

22. Unit Capacity Factor (Using DER Net) 5.6 1.9 24.6

23. Unit Forced Outage Rate

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 (Pnor to Commeretal Operationr Forecast Achiesed INITIA L CRITIC ALITY INITI A L. ELECTRICITY COMMERCI AL OPER AllON pum )

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P UNIT $3ftfrDOWitS A!7D IUWER PEIPJCTIOftS30-346

-m, UtsIT NAME Davis-Besse el Int April 13. 1992 COMPIETED BY tilal Sarsour psPerr texrne March, 1992 TEtzrnanc (419 p 321-73e4 r

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32-03-01 F

10.4 11 5

NA NA NA Power reduction to approximately 6 percent to take the turbine-generator off line to allow contain-ment entry for Containment Air Coolers cleaning and to perform containment walkdown and inspection for leaks.

2 42-03-01 F

31.3 H

3 92-002 SB PCV The reactor tripped by the i

i Anticipatory Reactor Trip System (ARTS) following a turbine trip.

'See Operational Summary for further details.

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• Exhibit G - Instrw;tsons for Preparation of Data F: Tsreed Peason:

Nthod:

S: Scheduled A-Equirment railure (Explain) 1-m nual Entry Sheets for Licensee Event Report (IIR)

B--mte:tecance or Test 2-s nual Scram File t'? MEG-0161 )

c-Refueling 3-Automatic Scram D-Regulatory Restriction 4-continuation from E-operator Training & License Examination Previous Month Exhib A I - Same Source F-Administrative 5-Ioad Reductson

• Report challenges to Power Operated Relief valves G-Operational Error (Explain) 9-other (Emplain)

(PORVsl and Pressuriger CwSe Safety valves (PCSvs)

H-other (Explain) l l

Operational Summary March, 1992 Reactor power reduction to approximately 6 percent continued.

A manual power reduction to 6 percent was initiated to take the turbine-generator off line to l

allow containment entty for Containment Air Coolets (CACs) cleaning and inspection for the source of a small Reactor Coolant System (RCS) leak that was causing boron deposits on the Containment Air Coolers.

The turbine-generator was taken off line at 0326 hours0.00377 days <br />0.0906 hours <br />5.390212e-4 weeks <br />1.24043e-4 months <br /> on March 1, 1992.

At 1157 hours0.0134 days <br />0.321 hours <br />0.00191 weeks <br />4.402385e-4 months <br /> on March 1, 1992, and after the completion of Containment Air Coolers cleaning, reactor power was slovly increased and the turbine-generator I

was synchronized on line at 1348 hours0.0156 days <br />0.374 hours <br />0.00223 weeks <br />5.12914e-4 months <br /> on March 1, 1992.

At 1500 hours0.0174 days <br />0.417 hours <br />0.00248 weeks <br />5.7075e-4 months <br /> on March 1, 1992, while the unit was at approximately 40 percent

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of full power, a reactor trip occurred. The reactot tripped by the Anticipatory Reactor Trip System (ARTS) following a turbine trip. The turbine trip vas due to actuation of the exhaust hood temperature trip circuit when Maintenance - I&C personnel vere checking the condition of the vacuum pressure switches at a junction box local to the turbine.

It has been determined that a meter test lead came into contact with the wrong terminal point, vhich then actuated the turbine exhaust hood high temperature trip for the main turbine.

The reactor was critical at 1530 hours0.0177 days <br />0.425 hours <br />0.00253 weeks <br />5.82165e-4 months <br /> on March 2, 1992, and the turbine-generator was synchronized on line at 2221 hours0.0257 days <br />0.617 hours <br />0.00367 weeks <br />8.450905e-4 months <br /> on March 2, 1992.

Reactor power was slovly increased to approximately 100 percent, which was achieved at 0625 hours0.00723 days <br />0.174 hours <br />0.00103 weeks <br />2.378125e-4 months <br /> on Mar ch 3, 1992, and maintained at this power level for the rest of the month-M

REFUELING'INFORMATION-Date March 1992 1.

Name of facility:. Davis-Besse Unit 1 f

2' Scheduled date-for:next' refueling outage? March 1993 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.

1.a) 177 (b) 393 (c) 0 j

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

Present:

735 5.

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

Date:

1994 - assuming ability to unload the entire core into the spent fuel pool is maintained b

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