ML20012C223

Monthly Operating Rept for Feb 1990 for Davis-Besse Nuclear Power Station,Unit 1.W/900313 Ltr

ML20012C223
Person / Time
Site:	Davis Besse
Issue date:	02/28/1990
From:	Sarsour B, Storz L TOLEDO EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
KB90-0119, KB90-119, NUDOCS 9003200330
Download: ML20012C223 (6)

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TOLEDO EDISON f DISON PLAZA 300 MADISON AVENUE TOLEDO, OH10 43052 0001 March 13, 1990 KB90-0119 Docket No. 50-346 License No. NPF-3 Document-Conttol Desk U. S. Nuclear Regulatory Commission 7920 Norfolk Avenue Bethesda, MD 20555 Gentlemen Monthly Operating Report, February 1990 Davis-Besse Nuclear Power Station Unit 1 Enclosed are' ten copies of the Monthly Operating Report for Davis-Besse l Nuclear Power Station Unit No.-1 for the month'of February 1990.

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.During review of the NRC's " Licensed Operating Reactors Status Summary Report" (NUREG-0020/Vol. 13, No. 11/ November 1989), Toledo Edison noted several errors in the. data for the Davis-Besse Nuclear Power Station. These errors appear to 2 have been propagated from a typographical error in the Gross Thermal Energy l (Item 17). The figure listed in Item 17 for the month is 2,507,046. Davis-  !

-Besse records indicate that the correct figure is 2,057,046. This error vas- i found to have affected the year-to-date and cumulative figures for Gross a Thermal Energy, as well as, the year-to-date Unit Capacity Factor (MDC) listed. '

in Item 22.-

~ Toledo Edison requests that those corrections be made, and that they be reflected in future issuances of the " Licensed Operating Reactors Status Summary Report."

If you have any questions, please contact Bilal Sarsour at (419) 321-7384. 1 Very truly yours, Gk > i 0 k Louis F. Storz l Plant Manager . 1 Davis-Besse Nuclear Power Station j BMS/mj b Enclosures 9003200330 900228' 3 PDR ADOCK 05000346 ..q

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I ,tj ,, AVERAGE D AILY UNIT POWER LEVEL -

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DOCKET NO. 50-346 .

UNIT Davis-Besse #1 DATE Mnrch 11. 1990 COMPLETED BY Bilal sarsour TELEPHONE 419-321-7384 MONTH February 1990 DAY AVERAGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL (MWe Net) (MWe-Net) 1 0 17 0 2 0 gg 0 3 0 g9 0 4 0 20 0 5 0 ;g 0 6 0- 22 0

-7 0 0 23 8 0 2.g 0 9 0 0 25 10 0 26 0 1I O O 27 . _ _ .

I2 0 28 0 13 0 29 I4 0 30 15 0 y; ,,,

16 0

' INSTRUCTIONS On this format list the average daily unit power levelin MWe Net for each day in the reporting month. Compute to the nearest whole megawatt.

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5 OPERATING DATA REPORT DOCKET NO. 50-346 DATE mvr-h I '4 . 1990 COMPLETED By Bilal Saisour TELEPHONE 419-321-7384 OPERATING STATUS  ;

1. Unit Nai - - ,

Davis-Ilmse Unit #1 Notes

2. Report!{h "'Druary

- 1990

3. Licensed i; . , J 2772

<r (MWt):

4. Nameplate Rating (Gross MWe): 925

5. Design Electrical Rating (Net MWe): 906

6. Maximum Dependable Capacity (Gross MWe): 918 1

7. Maximum Dependable Capacity (Net MWe): 874

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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:

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i This Month Yr. to Date Cumulative l

11. Hours in Reporting Period 672.0u 1,416.0 101,545.0 ,

12. Number of Hours Reactor Was Critical 0.0 608.8 54.763.4_ {

13. Reactor Reserve Shutdown Hours 0.0 0.0 5.393.7  !

14, Hours Generator On Line 0.0 608.8 52,809,2 I

15. Unit Reserve Shutdown Hours 0.0 0.0 1,732.5

16. Gross Thermal Energy Generated (MWH) 0.0 1.603,325 126.567,245

17. Gross Electrical Energy Generated (MWH) 0.0 _ _ _ , _ ,

536,477 41,886,778 j l~ 18. Net Electrical Energy Generated (MWH) 0.0 508,740 39,295,898 i

19. Unit Service Factor 0.0 43.0 52.0 j

20. Unit Availability Factor 0.0 43.0 53.7 '

21. Unit Capacity Factor (Using MDC Net) 0.0 41.1 44.3 1 , 22. Unit Capacity Factor (Using DER Net) 0.0 39.7 42.7  ;

1 23. Unit Forced Outage Rate 0.0 18.2 28.6 L 24. Shutdowns Scheduled Oser Next 6 Months (Type.Date,and Duration of Each):

25. If Shut Down At End Of Report Period. Estimated Date of Startup: June 5, 1990

26. Units in Test Status (Prior to Commercial Operationi: Forecast Achiesed l

INITIA L CRITICALITY l

INITI AL ELECTRICITY COMMERCIAL OPER ATION W/771

m - m - ProucrIon S \ - E * :-

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. texr nove: o.vt.-e omrt March 13. 1990 CCMP12TED BY Bilal'Serecer REPORT roren, February 1990 TErzenion E 919) 321-m

, e-AE n I gf r.ieens*e

[ cause a corrective No. o.co g

8. 2 lUe Event j

,1 I Action to 5-=

g _g g gjg .moport e gu Prevent Recurrence 8 . ~ .

2 90-02-01 S 672 C 9 NA NA 'NA The refueling outage was entered following the reactor trip on January 26, 1990, to perform scheduled maintenance and refuel-ing work.

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I #p.ason: 3 r: Forced Method: *En hibit G - Instructions for Preparation of Data S: Scheduled A-Equipment Failure (Explain) 1-Manual Entry Sheets for Licensee Event Report (IER) 8-Maintenance or Test 2-Manual Scram File (frJPJ:G-0161)

,c-Refueling 3-Automatic Scram l D-Regulatory Restriction 440ntinuation from 1 E-operator Training & t.icense Examination '

Previous Month Enhibit I - Some Source l

F-Administrative S-tead Reduction

• Report challenges to Power Operated Relief valves G-operational Error (Explain) 9-other (Explain) (PORVs) and Pressuriser code Safety Valves (PCSvs)

N-other (Explain) l g y e #tri'* w e y 9 "y g '+ - y, w. y p_ m_,m*us.-.W*

.,' , REFUELING INFORMATION Date: February 1990

1. Name of facility: Davis-Besse Unit 1

2. Scheduled date for next refueling outage? September 1991

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 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)?

Anst 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, and was approved in January 1990. No Cycle 7 Technical Specification changes to the Technical Specification, except for Bases changes, vill be submitted.

5. Scheduled date(s) for submitting proposed licensing action and supporting information: Changes to the bases were submitted on February 2, 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) 328 (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 1994 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 l

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