ML20245A290

Monthly Operating Rept for May 1989 for Davis Besse Unit 1

ML20245A290
Person / Time
Site:	Davis Besse
Issue date:	05/31/1989
From:	Sarsour B, Storz L TOLEDO EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
KB89-00331, KB89-331, NUDOCS 8906210190
Download: ML20245A290 (6)

Text

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s

. 1 TOLEDO EDISON '

o

i EDIGON PLAZA JOO MADISON AVENUE '

TOLEDO. OHIO 43652-0001

~I 1

- June 15, 1989

')

KB89-00331 L

Docket No. 50-346 License No.'NPF-3

'I Document Control Desk 1

U. S. Nuclear Regulatory Commission 7920 Norfolk Avenue i

Bethesda, MD.

20555 i

Gentlemen:

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

)

Enclosed are ten copies of the Monthly Operating Report for Davis-Besse j

Nuclear Power Station Unit No. 1 for the month of May, 1989.

]

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

Very truly yours, f

gfcup Louis F. Storz

~

'I I

Plant Manager

- Davis-Besse Nuclear Power Station BMS/mj b Enclosures

.,l l

cc Mr. A. Bert Davis i

Regional Administrator, Region III l

Mr. 1aul Byron l

NRC Resident Inspector-

i l

Mr. T. V. Watabach NRC Senior Project Manager a

utve 8906210190 090531

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PDR ADOCK 0500 6

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m_________

_-_-_m_m___u_.___.___.2__

AVERAGE DAILY UNIT POWER LEVEL.

DOCKET NO.-

50-346-UNIT Davis-Besse #1- >

DATE June 15.-1989.

COMPLETED BY Bila1'Sarsour I

TELEPHONE '(419) 321-7384 L l

l i

MONTH May, 1989 DAY AVERAGE DAILY POWER LEVEL DAY

. AVERAGE DAILY POWER LEVEL '

(MWe-Net)

(MWe-Net) i 884' g7 882 2

885 gg.

883 3

887 19 877 4

884

- 20 876-5 883 21 879 6

888 22 877 7

854 23 880 8

883 24 878

[

9 880 25 878 10 886 26' 773-31 884 27 128 12 881 28 432-13 883 29.

797 14 884 30 821 15 885 3:

112 16 884 INSTRUCTIONS On this format. list the average daily unit power level in MWe-Net for each day iri the reporting month. Cornpute the nearest whole ruegawatt.

W/77) 4

OPERATING DATA REPORT DOCKET NO. 50-346 DATE June 15. 1989 COMPLETED BY Bilal Sarsour TELEPIIONE (419) 321-7384 OPERATING STATUS

1. Unit Name:

. Davis-Besse Unit #1 Notes

2. Reporting Period:

May, 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 Octur 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 3,623 94,992

12. Number Of Hours Reactor Was Critical 728.8 3,410.1 49,017.6

13. Reactor Reserve Shutdown Hours 15.2 89.0 5,393.7

14. Hours Generator Op-Line 709.4 3,369.6 47.063.4

15. Unit Reserve Shutdown Houn 0.0 0.0 1,732.5

16. Gmss Thermal Energy Generated (MWH) 1,878,751 9,030,511 110,899,900

17. Gross Electrical Energy Generated (MWH) 626,036 3,020,747 36,661,931

18. Net Electrical Energy Generated (MWH) 593,428 2.861.839 34.326.891

19. Unit Service Factor 95.3 93.0 49.5

20. Unit Availability Factor 95.3 93.0 51.4

21. Unit Capacity Factor (Using MDC Net) 91.3 90.4 41.3

22. Unit Capacity Factor (Using DER Net) 88.0 87.2 39.9

23. Unit Forced Outage Rate 3.4 4.5 30.9

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

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

26. Units in Test Status (Prior 1o Commercial Operation):

Forecast Achieved INITIA L CRITICALITY INITIAL ELECTRICITY CONIM ERCIA L OPER ATION (4/77 )

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L Operational Summary i

May, 1989 Reactor power was maintained at approximately 100% full power until 0100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> on May 7, 1989, when a manual power reduction was initiated to approximately 82% to perform Control Rod Drive (CRD) exercise testing.

l After the completion of the CRD exercise testing, reactor power was slowly increased to approximately 100% at 0900 hours0.0104 days <br />0.25 hours <br />0.00149 weeks <br />3.4245e-4 months <br /> on May 7, 1989.

Reactor. power was maintained at approximately 100% full power until 0100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> on May 21, 1989, when a manual power reduction to approximately 96% power was i

l initiated to perform CRD exercise testing.

After the completion of the CRD exercise testing, reactor power was slowly increased to approximately 100% at 0400 hours0.00463 days <br />0.111 hours <br />6.613757e-4 weeks <br />1.522e-4 months <br /> on May 21, 1989.

Reactor power was maintained at approximately 100% full pver until 1600 hours0.0185 days <br />0.444 hours <br />0.00265 weeks <br />6.088e-4 months <br /> l

on May 26, 1989, when a planned power reduction was initiated.

Reactor power was reduced to approximately 6% and the turbine generator was taken off line at 1138 hours0.0132 days <br />0.316 hours <br />0.00188 weeks <br />4.33009e-4 months <br /> on May 27, 1989.

During the power reduction, the following are the more significant activities performed:

1)

Added oil to Reactor Coolant Pump 2-2 lover motor bearing.

2)

Eliminated vest D-ring steam leak (SP9B1) by backseating the valve.

3)

Repairs to the Main Feedvater Control Valves (SP6A and SP6B).

4)

Low Pressure Condenser water box was cleaned.

The turbine generator was synchronized on line at 2110 hours0.0244 days <br />0.586 hours <br />0.00349 weeks <br />8.02855e-4 months <br /> on May 27, 1989, and reactor power was slowly increased to 100% full power which was achieved at 1100 hours0.0127 days <br />0.306 hours <br />0.00182 weeks <br />4.1855e-4 months <br /> on May 29, 1989.

Reactor power was maintained at approximately 100% full power until 1415 hours0.0164 days <br />0.393 hours <br />0.00234 weeks <br />5.384075e-4 months <br /> on May 30, 1989, when a reactor trip occurred.

The reactor tripped on an Anticipatory Reactor Trip Signal (ARTS) caused by a trip of the main turbine.

The turbine tripped on low condenser vacuum shortly after the de-energization of two circulating water pumps. The circulating water pumps were de-energized when their breakers tripped on high phase differential current caused by an electrical fault that occurred at a splice in cable feed for a 480V transformer. This transformer is also powered from the e-m 13.8K? bus that powers the tripped circulating water pumps.

After identifying and. correcting the cause of the trip, reactor was taken critical at 0611 hours0.00707 days <br />0.17 hours <br />0.00101 weeks <br />2.324855e-4 months <br /> on May 31, 1989, the turbine generator was synchronized on line at 1520 hours0.0176 days <br />0.422 hours <br />0.00251 weeks <br />5.7836e-4 months <br /> on May 31, 1989, and reactor power was slowly increased to 100% full power.

3

REFUELING INFORMATION Dater May 1989 1.

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 I

4.

Will. refueling or resumption'of operation-thereafter require a 1

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' q

Safety Review Committee to determine whether any unreviewed safety.

l questions are associated with the core reload (Ref. 10 CFR Section

]

50.59)?

1 Ans: A license amendment' request is planned to remove cycle-specific values from Section 3 of the Technical Specifications..This submittal is planned for June 1989 and vill be based on Generic Letter 88-16.

1 Assuming approval of this submittal by November 1989, no Cycle 7 I

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 i

d 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 j

operating procedures.

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 fuel storage pool, and (c) the new fuel storage areas.

l (a) 177 (b) 268 (c) 0 6.

The present licensed spenti uel pool storage capacity and the size of-any f

increase in licensed storage capacity that has been requested or is planned, in number of fuel assemblies.

l Present:

735 Increased size by: 0 (zero) l 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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