ML20247M045

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

ML20247M045
Person / Time
Site:	Davis Besse
Issue date:	08/31/1989
From:	Sarsour B TOLEDO EDISON CO.
To:
Shared Package
ML20247L978	List: ML20247L974 ML20247M045 ML20247M051
References
NUDOCS 8909250120
Download: ML20247M045 (5)

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AVERAGE DAtLY' UNIT POWER LEVEL

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September 15, 1981

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DATE COMPLE1TD BY Bilal Sarsour TELEPHONE (419) 321-7384 MONnt August,'1989 DAY AVERAGE DAILY POWER LEVEL -

DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1 871 37 876 2

869 33 857 3

866 g9 875 4

861 20 853 5

866 21 870 6

869 22 869 7

880 23 871 8.

878 24 872 5

9 864 25 873 10 874 26 878

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873 27 852

-12 872 28 868 13 872 869

,79 14 857 30 872 15 868

'3, 875 1

16 872 I

INSTRUCTIONS On this format, hst the aserage daily t. net power levelin MWe-Net for each day in the reportin,e nionth C.u the nearest whole rnegawaii.

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. OPERATING DATA REPORT i

'i DOCKET NO.

50-346 l

DATE September 15, 1989.j COMPLETED BY Bilal Sarsour TELEPHONE (419) 321-7384 OPERATING STATUS

1. Unit Name:

Davis-Besse Unit #1 Notes

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2. Reporting Period:

August, 1989 l

3. Licensed Thennal 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:

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 5,831.0 97,200.0

12. Number Of Hours Reactor Was Critical 744.0 5,618.1 51.225.6

13. Reactor Reserve Shutdown Hours 0.0 89.0 5.393.7

14. Hours Generato On-Line 744.0 5,577.6 49,271.4

15. Unit Reserve Shutdown Hours 0.0 0.0 1,732.5 l

16. Gmss Thermal Energy Generated (MWH) 2,052,389 15,098,530 116,967,919

17. Gross Electrical Energy Generated (MWH) 679,436 5,035,445 38,676,629

18. Net Electrical Energy Generated (MWH) 646,612 4,778,470 36,243,522

19. Unit Scavice Factor 100.0 95.7 50.7

20. Unit Availability Factor 100.0 95.7 52.5

21. Unit Capacity Factor (Using MDC Net) 99.4 93.8 42.7

22. Unit Capacity Factor (Using DER Net) 95.9 90.5 41.2

23. Unit Forced Outage Rate 0.0 2,8 29.9

24. Shutdowns Scheduled Over Next 6 Months (Type. Date, and Duration of Each):

Refueling - Start February 1, 1990 - 18 weeks - End June 5, 1990

25. If 3 hut Down At End Of Report Period. Estimated Date of Startup:

26. Units in Test Status (Prior to Commercial Operation):

Forecast Achiesed INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION N/77 )

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OPERATIONAL'

SUMMARY

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August, 1989-f

i A; M Reactor power vas

naintained at approximately 100% until 1132. hours on

' August 8, 1989, when' power was reduced to approximately 97% due to Control Rod 3

Drive (CRD) speed circuit failure during a selected rod movement.

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Rea'ctor power was slovly increased to'approximately 100% full power which was attained at 1500 hours0.0174 days <br />0.417 hours <br />0.00248 weeks <br />5.7075e-4 months <br /> on August 8, 1989. Reactor power was maintained at this power level until 0105 hours0.00122 days <br />0.0292 hours <br />1.736111e-4 weeks <br />3.99525e-5 months <br /> on August 9, 1989, when a manual power reduction to approximately 91% was initiated due to lov load demand.

Reactor' power was slowly increased to approximately 100% full power which was attained at 0600 hours0.00694 days <br />0.167 hours <br />9.920635e-4 weeks <br />2.283e-4 months <br /> on August 9, 1989, and maintained at this power level until 0929 hours0.0108 days <br />0.258 hours <br />0.00154 weeks <br />3.534845e-4 months <br /> on August 12, 1989, when a manual power reduction to approximately 98% was initiated to repair control Rod Drive (CRD) logic.

After the completion of the CRD logic repair, reactor power was slowly increased to approximately 100% at 1000 hours0.0116 days <br />0.278 hours <br />0.00165 weeks <br />3.805e-4 months <br /> on August 12, 1989.

. Reactor power was maintained at.approximately 100% full power until 1350 hours0.0156 days <br />0.375 hours <br />0.00223 weeks <br />5.13675e-4 months <br /> on August 14, 1989, when a manual power reduction to approximately 90% vas initiated due to low service water pump 1-1 discharge pressure. Turbine Plant secondary heat loads were shifted from service water to circulating vater cooling, and power was decreased ~to reduce the. heat load in the turbine secondaries.

At 1830 hours0.0212 days <br />0.508 hours <br />0.00303 weeks <br />6.96315e-4 months <br />.on August 14, 1989, a' reactor power escalation to approximately 100% full power began. Reactor power was slowly increased to approximately 100% full power at 2100 hours0.0243 days <br />0.583 hours <br />0.00347 weeks <br />7.9905e-4 months <br /> on August 14, 1989, and maintained at this power level until 1425 hours0.0165 days <br />0.396 hours <br />0.00236 weeks <br />5.422125e-4 months <br /> on August 18, 1989, when reactor power was reduced to approximately 88% due to a feedvater transient. This transient occurred while performing Integrated Control System (ICS) tuning of the Steam Generator outlet differential temperature controller (ATc). There were no safety concerns identified in this transient.

In addition, no RPS, SFAS, or SFRCS parameters approached their trip values during the transient. However, the event was significant because of the loss of a relatively large electrical load (approximately 70 HVe). The unit was stabilized at approximately 92%,

and reactor power was restored to approximately 100% full power by 2030 hours0.0235 days <br />0.564 hours <br />0.00336 weeks <br />7.72415e-4 months <br /> on August 18, 1989.

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 August 20, 1989, when a manual power reduction to approximately 85%

vas initiated to perform turbine valve testing and CRD exercise testing.

After completion of turbine valve testing and CRD testing, reactor power was slowly increased to approximately 100% full power which was attained at 0807 hours0.00934 days <br />0.224 hours <br />0.00133 weeks <br />3.070635e-4 months <br /> on August 20, 1989.

Reactor power was maintained at this power level until 0100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> on August 27, 1989, when power was reduced to approximately 95% to perform turbine valve testing.

After completion of turbine valve testing, reactor power was slowly increased to approximately 100% power which was attained at 1405 hours0.0163 days <br />0.39 hours <br />0.00232 weeks <br />5.346025e-4 months <br /> on August 27, 1989, and maintained at this power level for the rest of the month.

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%f REFUELING INFORMATION Date: August 1989 1.

Name of facility: Davis-Besse Unit I r

2..

Scheduled date for next refueling outage? February 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 will 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, lover 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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