ML20236C055

Monthly Operating Rept for Feb 1989 for Davis-Besse

ML20236C055
Person / Time
Site:	Davis Besse
Issue date:	02/28/1989
From:	Sarsour B, Storz L TOLEDO EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
KB89-00152, KB89-152, NUDOCS 8903210466
Download: ML20236C055 (6)

Text

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s og AVERAGE DAILY UNIT POWER LEVEL :

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DOCKET NO.'

50-346 UNIT Davis-Besse #1 DATE 3-15-89 COMPLETED BY Bilal Sarsour TELEPHONE (419) 321-7384 -

MONTH.

-February 1989 DAY AVER AGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL ~

(M We-Net) -

(MWe-Net)

I'

'882 882 37-2 880' 18 882 3

882 19 880 4

883 20 881 5

886 21 881 6

885 22 880 885 7-23 880 8

885 883 24 9

886 25 879 10 886 26 880 11 886 27 882 12 886 28 872 13 844 9

866 14 30 15

'873 3,

.16 882 I

INSTRUCTIONS On.this format, list the average daily unit power levelin MWe Net for each day in the reporting inonth. Compute to the nearest whole megawait, i

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OPERATING DATA REPORT f

DOCKET NO.- '50-346 l

DATE 3-15-89 COMPLETED BY Bilal Sarsour TELEPHONE -(419} 321-7384 OPERATING STATUS

1. Unit Name:

Davis-Besse Unit #1 Notes h

' 2. Reporting Period:

February 1989

3. Licensed Thermal Power (MWt):

2772 L

4. Nameplate Rating (Gross MWe):

925

(-

S. Design Electrical Rating (Net MWe):

906 j

6. Maximum Dependable Capacity (Gross MWe):

904

7. Maximum Dependable Capacity (Net MWe):

860

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

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

10. Reasons For Restrictions. If Any:

This Month

. Yr to Date Cumulative 1

11. Hours in Reporting Period 672.0 1,416.0

92,785'

12. Number Of Hours Reactor Was Critical 672.0 1,292.1 46.899.6 s

13. Reactor Reserve Shutdown Hours 0.0 0.0 5.304.7

14. Hours Generator On Line -

672.0 1,283.1 44.976.9

15. Unit Reserve Shutdown Hours.

0.0 0.0 1,732.5

16. Gross Thermal Energy Generated (MWH) 1,854.135 3.522.657 105,392,046

17. Gross Electrical Energy Generated (MWH) 621,560 1,179,556 34.820.740

18. Net Electrical Energy Generated (MWH)

'591,477 1,117,496 32,582,548

19. Unit Setvice Factor 100.0 90.6 48.5

20. Unit Availability Factor 100.0 90.6 50.3

21. Unit Capacity Factor (Using MDC Net)

• 102.3 91.8 40.8

22. Unit Capacity Factor (Using DER Net) 97.1 87.1 38,8

23. Unit Forced Outage Rate 0.0

'9.4 31,9

24. Shutdowns Scheduled Over Next 6 Months (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 to Commercial Operation):

Forecast Achieved

{

INITIAL CRITICALITY INITIA L ELECTRICITY COMMERCIA L OPERATION

• Capacity Factor is >100% because the last cycle's MDC is being utilized. A new MDC is planned to be determined in March of 1989.

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OPERATIONAL

SUMMARY

FE9RUARY 1989 a

-l Reactor power was maintained'at approximately 100% full power until 0010 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> on February-12, 1989, when power was reduced to approximately 85% to perform turbine valve testing and to repair moisture separator second stage drain tank steam leak. A gasket in the second stage reheat steam drain tank #2 manvay cover failed, which allowed steam to escape.

After completion of the turbine valve testing and when repair to MSR drain j

tank was not possible, reactor power was slowly increased with MSR second stage isolated.- We then attained approximately 100% at 1200 hours0.0139 days <br />0.333 hours <br />0.00198 weeks <br />4.566e-4 months <br /> on February 15, 1989.

Reactor power was maintained at approximately 100% until 1105 hours0.0128 days <br />0.307 hours <br />0.00183 weeks <br />4.204525e-4 months <br /> on February 28, 1989, when a manual power reduction to approximately 93% was initiated to perform control rod drive exercise testing.

Reactor power was slowly increased following the control rod drive exercise testing to 100% 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 February 28, 1989.

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D REFUELING.INFORMATION Date:

February 1989 i

1.

Name of fac'ility:L Davis-Besse Unit 1 2.

Scheduled date for next refueling outage?' February 1990 3.

Scheduled date for restart from current refueling: N/A 4.

Vill' refueling or' resumption.of operation'thereafter require a technical specification change or other license amendment? If-answer is yes','what in general vill these be? If ansver is no, has:the reload fuel design and core configuration been reviewed by your Plant Safety Review Committee to determine whether any unreviewed safety questions are associated with the core reload (Ref. 10 CFR Section 50.59)?

Ans - The Reload Report requires standard reload fuel design Technical Specifications changes (2. Safety Limits and Limiting Safety System Settings, 3/4.1 Reactivity Control Systems, 3/4.2 Power Distribution Limits and 3/4.4 Reactor Coolant System.)

i 5.

Scheduled date(s) for submitting proposed licensing action and supporting information: Received Amendment from NRC October 3, 1988' 6.- Important licensing considerations associated with refueling, e.g.,

new or different fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures.

a.

The highly absorbing silver-indium-cadmium axial power shaping rods were replaced with reduced absorbing inconel rods.

b.

The discrete neutron sources were removed from the core and not replaced.

c.

The physics testing has been reduced in scope.

i 7.

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) 268 (c) 0 8.

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:

0 (zero) 9.

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

Date:

1995 - assuming ability to unload the entire core into the spent fuel pool is maintained

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TOLEDO' EDISON EDISON PULZA GOO MADISON AVENUE TOLEDO, OHIO 43652-0001 March 13, 1989 KB89-00152 Docket tio. 50-346 License No. NPF-3 Document Control Desk U. S. Nuclear Regulatory Commission l

7920 Norfolk Avenue i

Bethesda, MD 20555 Gentlemen:

Monthly Operating Report, February, 1989 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 February, 1989.

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

Very truly yours,

~49

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Louis F. Storz General Manager - Davis-Besse Plant BMS/mjb Enclosures cc:

Mr. A. Bert Davis Regional Administrator, Region III Hr. Paul Byron NRC Resident Inspector Mr. T. V. Vambach NRC Senior Project Manager i

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