ML20005G488

Monthly Operating Rept for Dec 1989 for Davis-Besse Nuclear Power Station Unit 1.W/900110 Ltr

ML20005G488
Person / Time
Site:	Davis Besse
Issue date:	12/31/1989
From:	Sarsour B, Storz L TOLEDO EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
KB90-00002, KB90-2, NUDOCS 9001190229
Download: ML20005G488 (6)

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EDISON PLAZA 300 MADISON AVENUE TOLEDO. OHIO 43652-OOO1

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t' January;10C1990

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a k,, ' Docket.No. 50-346

' License ' No. ; NPF '

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, Document-Control Desk ,

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• Gentlemen:

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Monthly Operating Report,. December 1989 Davis-Besse Nuclear Power Station Unit'l'

>  ; Enclosed >are tenLeoples of'the Monthly Operating Report _for, Davis-Besse -

Nuclear Power Station Unit No. 1 for the month of December-1989.  ;

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

>Very truly.y'ours, 1 i

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i . 'O - i Y m Louis F.-'Stor:  !

Plant' Manager p  ; Davis'-Besse' Nuclear ~ Power Station BMS/$ij b.

', . Enclosures 1

!cc: l'Mr.-A. Bert Davis

. Regional Administrator, Region III  ;

Mr. Paul; Byron.

.NRC Resident Inspector 1; . . .

Mr. T.-V. Vambach NRC Senior . Project Manager y;

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, AVERAGE DAILY UNIT POWER LEVEL' y . ,.

'kk DOCKET NO . 50-346 -

UNIT Davis-Besse il

-t DATE January: 10,:1990  ;

COMPLETED BY Bilal Sarsour

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December'1989

MONTN .; a DAY $ AVER AGE DAILY POWER LEVEL DAY. . AVER AGE DAILY POWER LEVEL

, (MWe Net)3 (MWe Net)

L ', , li 883 37 867 c, 4 g 2

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ig 883 .

3- 883- 39 886 4'- , 885 20 886 5; 884 883 21 6: 883 883 22 M'

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9- 883 25 882-

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12: 883 884 28 l'3 882 881 29 N 884

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• INSTRUCTIONS

- On this format list the average daily unit power lesel in MWe Net for each day in the reporting month. Compute to o -the nearest whole megawatt, (4/771  :

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OPERATING DATA REPORT. ,

4 DOCKET No.' 50-346 DATE January -10,1990 COMPLETED BY Eilal Sarsour TELEPHONE (419) 321-7384

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OPERATING STATUS Davis-Besse Unit- #1 Notes

1[ Unit Na'me: l l 2; Reporting Period: Deceinber 1989 .i 2772

, 3. Licensed Thermal Power (MWt)i

, , 4. Nameplate Rating (Gross MWe): 925

" 5 Design Electrical Rating (Net MWe): 906 918 8

6. Maximum Dependable Capacity (Gross MWe)s

7. Maximum Dependable Capacity (Net MWe):' 874-1 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 Which Restricthd,if Any(Net $1We):

~10i Reasons For Restrictions,if Any:

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1 This Month Yr..to Date Cumulative

11. Hours in Reporting Period . 744.0 8,760.0 -100,129.0

12. Number Of Hours Reactor Was Critical 744.0 8,547.1 54,154.6

13. ' Reactor Reserve Shutdown Hours 0.0 89.0 5.393.7 -

e 14. Hours Generator on Line 744.0 8,506.6 52,200.4

.15J Unit Reserve Shutdown Hours 0.0 0.0 1.732.5 16; Gross Thermal Energy Generated (MWH) 2,055.715 23.094.531 124.963.920 :I

17. Gross Electrical Energy Generated (MWH) 690,101

-7,709,117 41,350,301  !

18 Net Electrical Energy Generated (MWH) 656,780 7.322.106 38.787.158

.19.' Unit Service Factor 100.0 97.1 52.1

20. Unit Availability Factor.

100.0 97.1 53.9 g 21. Unit Capacity Factor (Using MDC Net) 101.0 95.6 44.3 22; Unit Capacity Factor (Using DER Net) 97.4 92.3 42.8

23. Unit Forced Outage Rate 0.0 1.8 28.7

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

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

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

26. Units in Test Status (Prior to Commercial Operation): Forecast Achiesed INil'lA L CRITICALITY INITIAL ELECTRICITY i COMMERCIAL OPERATION (9/77 )

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• REPORT sormt December -1989 "u. "

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NO SIONIFICANT UNIT SHU1 DOWNS _

OU POWER REDUCTIONS I Plethods Exhibit C - Instructions for Properation'of Data r: rorced Reason:

S: Sche <1uled A-Erpsi pment failure (Explain)- 1-Manual Entry Sheets for. Licensee Event Report ( M )

s-Maintenance or Test 2-etanual scram File (IEUREG-0161)

,C-Refueling 3-Automatic Scram D-Regulatory Restriction 4-Continuation from E-operator Training & License Examination Previous Month 'Enhibit 2 - Some source F-Administrative 5-load Reduction -* Report challenges to Power operated Relief valves.

W rational Error (Explain) 9-Other'{ Explain) (ports) and Pressuriser Code Safety valves (PC5V5)

H-other (Explain)

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SUMMARY

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[f December 1989 h ,

b sLReactor power vas maintained'at approximately 100% full power until 0100 h hours on December 17, 1989,'.when a manual power reduction _to approximately-4:

. -85% was initiated'to perform turbine control valve testing and control rod L " drive exercise testing.

w lAfter'th'e completion of turbine control valve testing, reactor _ power was slowly increased to approximately 100% full power at 0654 hours0.00757 days <br />0.182 hours <br />0.00108 weeks <br />2.48847e-4 months <br /> on

[  ; December.17, 1989, and maintained'at this power level for the rest of the

-month.

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y. M~ --REFUELING INFORMATION Date: December 1989 9

. l 1.1 'Name'of facility:: Davis-Besse Unit 1 4

y ' 2. : Scheduled date for next refueling outage? February 1990 3.1 Scheduled date for restart lfrom current refueling: N/A 4 .' Vill refueling or resumption of operation thereafter require a technical specification change or,other license amendment? If answer is yes, what in general.will-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 vith the core reload (Ref. 10 CFR'Section

.o 50.59)?-

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• Anst' A license amendment request to remove cycle-specific values from Section 3 of the Technical Specifications was subm3".ted to ti.: NRC on June 16, 1989, based on Generic Letter 88-16. Assuming approval of this submittal in January 1990, no Cycle 7 Technical Specification changes are expected for the Technical Specifications though Bases changes vill likely result.

5'. Scheduled date(s) for submitting proposed licensing action and supporting informations_ For Bases, January, 1990.

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

Lnew 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, Nev fuel-design Mark B8A (Reconstitutable, removable upper end

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b.

, ' 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 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

.