ML20246B234

Monthly Operating Rept for Jul 1989 for Davis-Besse Nuclear Power Station,Unit 1

ML20246B234
Person / Time
Site:	Davis Besse
Issue date:	07/31/1989
From:	Sarsour B, Storz L TOLEDO EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
KB89-00416, KB89-416, NUDOCS 8908230287
Download: ML20246B234 (6)

Text

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%ms EDISON EDISON PLAZA 303 MADISON AVENUE TOLEDO OHIO 43652-0001

' August 14, 1989 KB89-00416 Docket No. 50-346 p.-

License No. NPF-3 Document Control Desk U. S. Nuclear Regulatory Commission 7920 Norfolk Avenue Bethesda, MD 20555 Gentlemen Monthly Operating Report, July, 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.'l-for the month of July, 1989.

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

Very truly yours, 4

Louis F. Storz Plant Manager Davis-Besse Nuclear Power Station BMS/mjb Enclosures cc - Mr. A. Bert Davis Regional Administrator, Region III Mr. Paul Byron NRC Resident Inspector Mr. T. V. Vambach NRC Senior Project Manager

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[ DOCKET NO. 50-346 UNIT Davis-Besse #1 -

.DATE August 14, 1989 COMPLETED BY lilal Sarsour 1i 1 TELEPHONE -(419)321-7384 MONTH July, 1989 ll DAY AVERAGE DAILYPOWER LEVEL- ' DAY ' AVERAGE DAILY POWER LEVEL -

- (MWe-Net) LWwe Net)

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15 879 3I 877 16 877

-f! INSTRUCTIONS On tLu format,hst the aserage daily t,nir power level in uwe.Nei for each da3 in the repornny in.inth. C..inpu

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OPERATING DATA REPORT DOCKET NO. 50-346 DATE Aucust 14 1989 COMPLETED BY R11n1 sarnour TELEPHONE (419)321-7384 OPERATING STATUS i

1. Unit Name: Davis-Besse Unit //1 Notes

2. Reporting Period: July, 1989

3. LicensedThermalPower(MWt): 2772

4. Nameplate Rating (Gross MWe): 925

5. Design Electrical Rating (Net MWe): 906

6. Maximum Dependable Capacity (Gross MWe): 918

7. Maximuin Dependable Capacity (Net MWe): 874

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

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

10. Reasons For Restrictions.If Any:

This Month Yr.-to-Date Cumulative

11. Hours in Reporting Period 744.0 5,087.0 -96,456.0

12. Number Of Hours Reactor Was Critical 744.0 4,874.1 50.481.6

13. Reactor Reserve Shutdown Hours 0.0 89.0 5,393.7

14. Hours Generator On.Line 744.0 4,833.6 40.527.4

15. Unit Reserve Shutdown Hours 0.0 0.0 1.732.5

16. Gross Thermal Energy Generated (MWH) 2,031,765 13,046,141 114,915,530 .

17. Gross Electrical Energy Generated (MWH) 673,713 _ 4.356.009 37,997,193

18. Net Electrical Energy Generated (MWH) 440,870 4.131.858 35,596,910

19. Unit Service Factor 100.0 95.0 50.3

20. Unit Availability Factor 100.0 95.0 52.1

21. Unit Capacity Factor (Using MDC Net) 98.6 92.9 42.2__

22. Unit Capacity Factor (Using DER Net) 95.I 89.7 40.7

23. Unit Forced Outage Rate 0.0 3.2 30.3

24. Shutdowns Scheduled Over Next 6 Months (Type. Date.cnd 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 INITIAL ELECTR CII Y COMMERCIAL OPER ATION (4/77)

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SUMMARY

l o July, 1989 i .i Reactor power was maintained 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 July 2, 1989, when a manual power reduction to approximately 85% vas initiated to perform turbine valve testing.

After completion of the turbine testing, reactor power was slowly. increased to l

approximately 100% full power which was attained at 0700 hours0.0081 days <br />0.194 hours <br />0.00116 weeks <br />2.6635e-4 months <br /> on l 4 ' July 2, 1989.

Reactor power was maintained at approximately 100% full power until 0136 hours0.00157 days <br />0.0378 hours <br />2.248677e-4 weeks <br />5.1748e-5 months <br /> on July 9, 1989, when a manual power reduction to approximately 95% vas initiated to perform turbine valve testing.

Reactor power vss slowly increased following the turbine valve testing to approximately 100% full power which was attained at 0500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br /> on July 9, 1989.

Reactor power was maintained at approximately 100% full power until 1217 hours0.0141 days <br />0.338 hours <br />0.00201 weeks <br />4.630685e-4 months <br /> on July 10, 1989, when power was reduced to approximately 98% due to a high condenser pressure caused by the high circulating vater temperature. The high circulating water temperature was attributed to hot and humid weather conditions. Reactor power was maintained at approximately 98% until 2400 hours0.0278 days <br />0.667 hours <br />0.00397 weeks <br />9.132e-4 months <br /> on July 10, 1989, when reactor power was slowly increased to approximately 100% full power which was attained on 0100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> on July 11, 1989 Reactor power was maintained at 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 23, 1989, when a manual power reduction to approximately 92% vas initiated to perform turbine valve testing and control rod drive exercise testing. An engineering evaluation is in progress to change the frequency of main turbine testing. A single monthly power reduction to accomplish control rod exercise testing and turbine valve testing is anticipated.

After completion of the control rod drive exercise testing, reactor power was slowly increased to approximately 100% vhich was attained at 0700 hours0.0081 days <br />0.194 hours <br />0.00116 weeks <br />2.6635e-4 months <br /> on July 23, 1989, and maintained at this power level until 0912 hours0.0106 days <br />0.253 hours <br />0.00151 weeks <br />3.47016e-4 months <br /> on July _23, 1989, when a manual power reduction to approximately 50% was initiated due to a dropped control rod (rod 7-5), caused by a blovn fuse on phase "CC" in the transfer switch for rod 7-5. The fuse blev as a result of an over current condition. The fuse was replaced and reactor power was slowly increased to approximately.100% full power which was attained at 1000 hours0.0116 days <br />0.278 hours <br />0.00165 weeks <br />3.805e-4 months <br /> on July 24, 1989, and maintained at this power level for the rest of the month.

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REFUELING INFORMATION Date: July 1989

1. Name of facility: Davis-Besse Unit 1

2. Scheduled dat? for next refueling outage? F,ebruary 1990

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

4. Will 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)?

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 _

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&W Owners Group.

5. Scheduled date(s) for submitting proposed licensing action and supporting information: For Section 2, January, 1990.

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. Sixty Batch Reload 3.38% enriched.

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

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: approximately 900 by 1993 is planned

9. 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

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