ML20011D688

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Monthly Operating Rept for Nov 1989 for Davis-Besse Nuclear Power Station Unit 1.W/891211 Ltr
ML20011D688
Person / Time
Site: Davis Besse Cleveland Electric icon.png
Issue date: 11/30/1989
From: Sarsour B, Storz L
TOLEDO EDISON CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
KB89-00589, KB89-589, NUDOCS 8912280260
Download: ML20011D688 (6)
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EbISON EDISON PLAZA 300 MADtSON AVENUE TOLEDO, OHIO 43652-0001 December 11, 1989 KB89-00589 Docket No. 50-346 License No. NPF-3 Document Control Desk U. S. Nuclear Regulatory Commission 7920 Norfolk Avenue Bethesda, MD 20555 Gentlemen:

Monthly Operating Report, November 1989 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 November 1989.

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

Very truly yours, r '

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Louis F. Storz Plant Manager  ;

Davis-Besse Nuclear Power Station ,

BMS/mjb Enclosures

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cc Mr. A. Bert Davis Regional Administrator, Region III Mr. Paul Byron '

NRC Resident Inspector "

Mr. T. V. Vambach NRC Senior Project Manager

.i 8912280260 891130 PDR ADOCK 05000346 '\\ '

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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-346 UNIT Davis-Besse #1 DATE December 11, 1989 >

COMPLETED BY Bilal Sarsour TELEPHONE -(419) 321-7384 MONTH November 1989 DAY AVERAGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL (MWe NetI (MWe Net) 882 886 37-2 884 Ig 885 '

3 885 39 864 4 885 20 884  ;

5 878 21 885 6 878 886 22 7 876 885

  • 23 8 877 886-24 9 877 883 25 10 882 882 26 11 882 881 27 12 882 881 28 13 878 884' 29 14 879 884 30 l$ 877 31 16 884 INSTRUCTIONS On this format,lis the average daily unit power lesel in MWe Net for each day in the reporting month. Compute to the nearest whole megawatt.

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L OPERATING DATA REPORT l DOCKET NO. 50-346 DATE December 11, 1989 COMPLETED BY Bilal Sarsour TELEPHONE (419) 321-7384 OPERATING STATl'S Davis-Besse Unit #1 Notes -

1. Unit Name:
2. Reporting Period: November 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 ,

l S. If Changes Occur in Capacity Ratings (items Number 3 Through 7) Since Last Report. Give Reasons:

9. Power Level To Which Restricted.lf Any (Net MWe):
10. Reasons For Restrictions,If Any:
  • This Month Yr. to Date Cumulative l
11. Hours in Reporting Period 720.0 8,016.0 99,385.0
12. Number Of Hours Reactor Was Critical 720.0 7,803.1 53,410.6
13. Reactor Reserve Shutdown Hours 0.0 89.0 5,393.7
14. Hours Generator On Line 720.0 7,762.6 51,456.4
15. Unit Reserve Shutdown Hours 0.0 0.0 1,732.5
16. Gross Thermal Energy Generated (MWH) 1,990,518 21,038,816 122,908,205
17. Gross Electrical EnerFy Generated (MWH) 666,574 7.019.016 40.660.200'
18. Net Electrical Energy Generated (MWH) 634,586 6,665,326 38,130,378
19. Unit Service Factor 100.0 96.8 51.8
20. Unit Availability Factor 100.0 -96.8 53.5
21. Unit Capacity Factor IUsing MDC Net) 100.8 95.1 43.9-
22. Unit Capacity Factor iUsing DER Net) 97.3 91.8 42.3
23. Unit Forced Outage Rate 0.0 2.0 29.0
24. Shutdowns Scheduled Oser Next 6 Months (Type. Date,and Duration of Each):

Refueling - Start February l', 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 IPrior to Commercial Operation): Forecast Achiesed  ;

. INITIAL CRITICALITY INITIAL ELECTRICITY C0%IMERCIAL OPERATION '

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OPERATIONAL

SUMMARY

November 1989 Reactor power was maintained at approximately 100% full power until 2358 hours0.0273 days <br />0.655 hours <br />0.0039 weeks <br />8.97219e-4 months <br /> on November 18, 1989, when a manual power reduction to approximately 85% vas:

initiated to perform turbine control valve testing.

After the completion of turbine control valve testing, reactor power was slowly increased to approximately 100% full power at 0757 hours0.00876 days <br />0.21 hours <br />0.00125 weeks <br />2.880385e-4 months <br /> on. November 19, 1989, and maintained at this power level for the r.est of the month.

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A TRIT Snt7fDONRS AND POWER REDUCT10rts +.

200G"* No. 50-346 -

tarIT Ige: Davis-Besse 91 * "[

oRrE Deco =her 11, 1989 .

CO W12TED SY Bilal Sarseur

  • REPORT mfar November 1989 TErzmPvE (41n 321-use ygo
    • un c a es o Licensee **

Cause & Corrective

. Date ) i iE  !

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=~t Report 9 (40 fa

~ti= t-Prevent Recurrence NO S IGNIFICANT UNIT SHJTDOWNS OR POWER REDUCTI )NS

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F: Forced Reason: M*+ hod: Exhibit G - Instructions for Preparation of Data S: Scheduled A-Equi'fwnt Failure (Explain) 1-Panual Entry Sheets for Licensee Event Report (IER)

B-M,iintenance or Test 2-ftenual Scram File (NUREG-0161)

,C-Refueling 3-Automatic Scram D-Regulatory Restriction 4-Continuation from E-operator Training & License Examination Previous Mmth 'Eshibit I - Same Source q F-Astatnistrativa S-toed Reduction

  • Report challenges to Power operated Relief Valves I cr-operational Error (Explaint 9-other (Explain) (PORVs) and Pressurizer Code Safety valves (PCSVs)

H-other (Explain)

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e Date November 1989 REFUELING INFORMATION

1. Name of facility: Davis-Besse Unit 1 1 2.- Scheduled date for next refueling outage? February 1990 Scheduled date for restart from current refueling: N/A 3.
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 i l

Safety Review Committee to determine whether any unreviewed safety 1 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 in December 1989, no Cycle 7 Technical Specification changes are expected for the Technical Specifications though Bases .

changes will likely result.

5. Scheduled date(s) for submitting proposed licensing action and supporting information: For Bases, January, 1990.
6. Important licansing 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 lower end cap, lover prepressurization, and annealed guide tubes.

l 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

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.

l Present: 735 Increased size by: approximately 900 by 1994 is '

planned i

f 9. The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity.

l l Date: 1996 - assuming ability to unload the entire core into the spent l fuel pool is maintained l

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