ML20043G121

Monthly Operating Rept for May 1990 for Davis-Besse Nuclear Power Station Unit 1.W/900613 Ltr

ML20043G121
Person / Time
Site:	Davis Besse
Issue date:	05/31/1990
From:	Sarsour B, Storz L TOLEDO EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
KB90-0328, KB90-328, NUDOCS 9006190088
Download: ML20043G121 (6)

Text

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4 TOLEDO EDISON-EDISON PLAZA .

300 MADISON AVENUE l TOLEDO, OHIO 43652-0001 l

June 13, 1990 KB90-0328 j Docket No. 50-346 License No. NPF-3 Document Control Desk ,

U. S. Nuclear Regulatory Commission i' 7920 Norfolk Avenue

-Bethesda, MD 20555 1

Gentlemen:  !

-l Monthly Operating Report, May 1990 .

Davis-Besse Nuclear Power Station Unit 1 Enclosed are ten copies of the Monthly Operating Report for Davis-Besse Nuclear Power Station' Unit No. 1 for the month of May 1990. .!

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

Very truly yours, )

1

$N Louis F. Storz j Plant Manager Davis-Besse Nuclear Power Station 3 i

BHS/tld j Enclosures 1'

cc Mr. A. Bert Davis Regional Administrttor, Region III Hr. Paul Byron-NRC Resident Inspector i Hr..T. V. Vambach NRC Senior Project Manager <

l 9006190088 900531 PDR ADOCK 05000346 / J R PDC i( i(

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l .

AVER AGE D AILY UNIT POWER trYEL DOCKET NO. 50-346 L pggy Davis-besse Unit #1 DATE _ June 13,1990

)MPLETED BY Bilal Sarsour TELEPHONE (419) 321-7384 MONTH _Mny- 1990 DAY AVER AGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL c IMhe NetI g gw,.N,g ,

I I o

,, o

[ 2 0 th 0 3 0 in o 4 0 0 20 __

0 O 6 0 0 22 7 0 0 23 I 8 0 0 24

' O 0 25 10 -

0 0

- 26 5 11 0 o 77 12 0 0 2h r 0 g 13 - o 29 14 0 0. ,

43 15 0 o 16 0 a

k

c. INSTRUCTIONS 2

a On this format lu. :he aserage daih unit powet lesel in MWe Nei for each day in the reporting nunth. Compute to the nearest wisu nrjawati, (0177i I

d

OPERATING DATA REPORT DOCKET NO. _50-346 DATE June 13 1990 COMPLETED BY Eiln1 SgIsour

.T ELEPHONE / L 101 1'1-7384 OPER ATING ST ATUS Notes

1. Unit Name: .Dnvis-Besse #1

2. Reporting Period: N- 1000

3. Licenwd Thermal Power (MW:): 2772

4. Nameplate Rating (Gross MWe): 925

$. Design Electrical Rating (Net MWe): 906

6. Maximtim Dependable Capacity (Gross MWe): 918

7. Maximum Dependable Capacity (Net MWe): 874

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

9. Power LeselTo Which Restricted.lf Any(Net MWe):

10. Resums For Restrictions.lf Any:

This Month Yr. to Date Cumulatise

11. Hours in Reporting Period 7'A n 3.623.0 103.752

12. Number OI Hours Resetor has Critical 0.0 60R.R 54.761.4  ;

13. Reactor Reierte Shutdown Hours 0.0 0.0 g _no,_y  !

14. Hours Generator On Line 0.0 608.8 sg.gog,7 l

15. Unit Rewne Shutdown Hours 0.0 0.0 1.732.5

16. Gross Thermal Energy Generated (MWH) 0.0 1.601.1?; 126.567.245

17. Gross Electrical Energy Generated (MWH) 0 .S. ,,. . . . 536.477 41.886.778

18. Net Electrical Energy Generated (MWH) 0.0 508.740 lo.90s gog

19. Unit Senice Factor 0.0 16.8 so,9

20. Unit Assilability Factor 0.0 16.8 52.6

21. Unit Capacity factor (Using MDC Net y 0.0 16.1 43.3

22. Unit Capacity factor (Using DER Net) 0.0 15.5 41.8 l

23. Unit Forced Outage Rate 0.0 18.2 28.6 l

24. Shutdowns Scheduled Oser Ne At 6 MonthdType. Date,and Duration of Eacht: 3 i

25. If Shut Down At End Of Report Period,Istimated Date of Startup: Jwie 2?. 1490

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

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Forecast Achiesed INill A L CRITICALITY INill AL ELECT RICITY CO\l%1ERCI AL OPER ATION _

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• DOCFET 180. 50-346 arIT met Davis-a sse et .

tare June 13- 1990 -

<xertrrEn er sital Serseer mEraser narrn May, 1990 TErzynanE (*19 321-73e4 T c,"'.

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o rre.ent m o r.nce a 8 3 90-02-01 S 744 C 4 NA NA NA The unit outag which began on January 2f, 19c.; was still in progress through the end of May, 1990.

See Operational Sumary for further details.

I I Method: Exhitrit G - Instructions for Properation of Data F: Forced Beeson:

A-ETsipment Failure (Empt. tin) 1-4tanuel Entry Sheets for Licensee Event Papert (12R)

S: Schedsled S-Maintenance or Test 2-Manual Scree File (NUREG-0161)

C-Refueling 3-Aartourtic Scram D-Itegulatory Pestriction 442mtinuatice fcese E-operator Training a License Ermehmetion Previous Month Exhibit I - Same Source T h aistrative 5-toed Reduction

• Report challenges to Power operated pelief valves r @ retional Error (Explain) 9-other (EmplainD (PostTs) and Pressuriser Code Sefety valves (PCSVs)

N-other (EmpiainI

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,, 4- i

. . I OPERATIONAL

SUMMARY

I

! May, 1990 The unit outage which began on January 26, 1990, was still in progress through j the end of May, 1990. '

-The following are the more significant outage activities performed during the  ;

month of May, 1990.

1. Completed the refurbishment of the #1 turbine control valve.

2. Completed maintenance and repairs to the Air Ejector System j Components.  ;

I

3. All reactor incore detectors were installed except for Incore 31 which could not be inserted. +

4. All control rod drive mechanisms were coupled and the power cables were installed. ,

5. Completed the re-installation of the #3 condensate pump.

f

6. Cooling tower repair was completed. l

,' 7. The main condenser steam side work was completed, and a condenser dye I test for leakage was performed. A crack in the condenser foot has ,

been identified and repaired. ,

t

8. The Auxiliary Boiler repair was completed.  ;

4

9. The overspeed trip testing of both main feed pump turbines and the auxiliary feedvater pump turbines was successfully completed.

10. The installation of all missile shields was completed.  !

11. Completed the steam generator hydrostatic test.  ;

12. The coupling and alignment of the main feed pump and booster feed -l pump was completed. }

+

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1

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'[ ' REFUELING INFORMATION Date: May 1990

)

l L 1. Name of facilityt Davis-Besso Unit 1 l

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 L 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 J questions are associated with the core reload (Ref. 10 CFR Section  :

50.59)? l, 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, and was approved in January 1990. No Cycle 7 Technical Specification changes to the Technical Specification, except for Bases changes.

5. Scheduled date(s) for submitting proposed licensing action and '

supporting information: Changes to the bases were submitted on .

February 2, 1990 and issued by the NRC on June 4, 1990.

i

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

new or different fuel design or supplier, unrevieved design or performance analysis methods, significant changes in fuel design, nev i 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.

f a) 177 (b) 328 (c) 0 r

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