ML20246P930

Monthly Operating Rept for June 1989 for Davis-Besse Nuclear Power Station

ML20246P930
Person / Time
Site:	Davis Besse
Issue date:	06/30/1989
From:	Sarsour B, Storz L TOLEDO EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
KB89-00362, KB89-362, NUDOCS 8907200369
Download: ML20246P930 (6)

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TOLEDO EDISON 5

EDISON PLAZA L

' 300 MADISON AVENUE p

TOLEDO. OHIO 43652-0001

~ July 12,'1989

'KB89-00362 Docket No. 50-346

' License No. NPF-3 Document-Control Desk U. S..' Nuclear Regulatory Commission 7920 Norfolk Avenue Bethesda, MD 20555 Gentlemen:

Monthly Operating Report, June, 1989 Davis-Besse Nuclear Power Station Unit 1 e

' Enclosed are ten copies of the Monthly Operating Report for Davis-Besse Nuclear Power. Station Unit No.1 for-the inonth of June,1989.

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

~Very truly yours, l

pu Louis F. Storz Plant Manager Davis-Besse Nuclear Power Station BMS/mjb En61osures cc:

Mr. A. Bert Davis Regional Administrator, Region III l

Mr. Paul Byron NRC Resident Inspector

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Mr. T. V. Vambach NRC Senior Project Manager A

8907200369-890630 r>.

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' AVERAGE DAILY UNIT POWER LEVEL -

DOCKET NO.

50-346

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. UNIT Davin-Besse #1 DATE July 12, 1989 COMPLETED BY Bilal Sarsour TELEPHONE (419)321-7384.

MON 1H June, 1989 DAY

. AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(gwe. Net) 1-812 17 880 2

873 18 871 3'

874 i 19 877 4

877 20 877 5

881 21 877 6

878 22 873 7

874 23 871" 8

874 24 871

.cN' 9

876 25 863 a

10 881 26 867 878 11 071 27 070 12 875 28 13 879 880

,29 14 880 30 880 IS 878 3,

16 880 INSTRUCTIONS On this format.hst the aserage dail) 4. nit power level in MWe Net for each da) in the repornne in.inth.Ge the nearest whole rnegawan, I

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OPERATING DATA REPORT DOCKET NO. 50-346-DATE July 12. 1989 COMPLETED BY Bilal..jlar.gour TELEPHONE (419)321-7384 OPERATING STATUS

1. Unit Name:

Davis-Besse Unit #1 N tes

2. Reporting Period:

' June, 1989

3. Licensed Thermal Power (MWt):

2772

4. Nameplate Rating (Gross MWe):

925

5. Design Electrical Rating (Net MWe):

906

6. Maximum Dependable Capacity (Gross MWe):

918

7. Maximum Dependable Capacity (Net MWe):

874

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

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9. Power Level To Whth Restricted,If Any (Net MWe):

10. Reasons For Restrictions,if Any:

This Month Yr.-to Date Cumulative k

11. Hours in Reporting Period 720 4,343 95,712

12. Number Of Hours Reactor Was Critical 720 4.130.1 49.737.6

13. Reactor Reserve Shutdown Hours 0.0 89.0

-5,393.7 l

14. Hours Geneistor On4.ine 720 4,089.6 47,783.4

15. Unit Reserve Shutdown Hours 0.0 0.0 1.732.5

16. Gross Thermal Energy Generated (MWH) 1,983,865 11.014.376 112,883,765

17. Gross Electrical Energy Generated (MWH) 661,549 3,682,296 37,323,480

18. Net Electrical Energy Generated (MWH) 629,149 3,490,988 34,956,040 l

19. Unit Service Factor 100 94.2 49.9 _

20. Unit Availability Factor 100 94.2 51.7 l

21. Unit Cap: city Factor (Using MDC Net) 99.9 92.0 41.8

22. Unit Capacity Factor (Using DER Net) 96.4 88.7 40.3

23. Unit Forced Outage Rate 0.0 3.7 30 6

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 (l'rior to Commercial Operation):

Forecast Achiesed INITIA L CRITICA LITY INITIAL ELECTRICITY COMMERCIA L OPER ATION I

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OPERATIONAL

SUMMARY

June, 1989 l

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Reactor power was maintained at approximately 100% full power until 0130 hours0.0015 days <br />0.0361 hours <br />2.149471e-4 weeks <br />4.9465e-5 months <br />

.on June 11, 1989, when a manual power reduction to approximately 94% vas initiated to perform turbine valve testing. After completion of the turbine valve testing, reactor power was slowly increased to approximately 100% full power which was attained at 0315 hours0.00365 days <br />0.0875 hours <br />5.208333e-4 weeks <br />1.198575e-4 months <br /> on June 11, 1989.

Reactor power was maintained at approximately 100% full power until 0115 hours0.00133 days <br />0.0319 hours <br />1.901455e-4 weeks <br />4.37575e-5 months <br /> j

on June 18, 1989, when a manual power reduction to approximately 94% vas initiated to perform turbine valve testing.

Reactor power was slowly increased following the turbine valve testing to approximately 100% full power which was attained at 0415 hours0.0048 days <br />0.115 hours <br />6.861772e-4 weeks <br />1.579075e-4 months <br /> on June 18, 1989.

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Reactor power was maintainad at approximately 100% full power until 0200 hours0.00231 days <br />0.0556 hours <br />3.306878e-4 weeks <br />7.61e-5 months <br /> on June 25, 1989, when a manual power reduction to approximately 93% vas initiated to perform Control Rod Drive (CRD) exercise ; testing and turbine valve testing.

After completion of dRD testing and turbine valve testing, reactor power was slowly increased to approximately 100% full power and maintained at this power level for the rest of the month.

7 l

, a REFUELING INFORMATION Date: June 1989 l.

Name of facility: Davis-Besse Unit 1 2.

Scheduled date for next refueling outage? February 1990 3.

Scheduled date for restart from current refueling: June 1990 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 answer 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)?

1 Ans: A license amendment request to remove cycle-specific values from Section 3 of the Technical Specifications was submitted to the NRC on June 16, 1989, based on Generic Letter 88-16.

Assuming approval of

i this submittal by November 1989, no Cycle 7 Technical Specification changes are expected for Section 3 of the Technical Specifications.

Cycle-specific changes to Section 2 of Technical Specifications vill likely be made. This depends on the date of approval of a document on criteria and methodology, which is presently under development by the B&V Owners Group.

I 5.

Scheduled date(s) for submitting proposed licensing action and supporting information:

For Section 2, January, 1990.

{

i 6.

Important licensing considerations associated with refueling, e.g.,

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

i a.

Sixty Batch Reload 3.38% enriched instead of 60 Batch Reload.

b.

New fuel design Mark B8A (Reconstitutable, removable upper end fitting, Zircaloy grid spacer, debris resistant lover end cap, lover prepressurization, and annealed guide tubes.

7.

The number of fuel assemblies (a) in the core and (b) in the spent i

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 m-~~----__---__--_---_---_

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