ML20237C024

Monthly Operating Rept for Nov 1987

ML20237C024
Person / Time
Site:	Davis Besse
Issue date:	11/30/1987
From:	Cipriani J, Storz L TOLEDO EDISON CO.
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
KB87-01001, KB87-1001, NUDOCS 8712180051
Download: ML20237C024 (6)

Text

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AVERAGE DAILY UNIT POWER LEVEL l

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DOCKET NO.

50-346 l

1 UNIT Davis-Besse 1 DATE December 14. 1987 7

COMPLETED BY J. Ciorfani TELEPHONE-7365 i

MONTH, November 1987 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL l

t (MWe Net)

(MWe-Net) j i

694 37 690 2

647 18 693 3

685 693-i 19 j

684 693 4

20 695 693 5

21 j

698 l

6 22 693 697 7

23 692 8

697 693 24 9

697 697 25 694 10 26 698 Il 696 27 696 j

12 695 704 i

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l 13 696 685

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9 696 14 30 697 697 15 l

38 16 693 INSTRI>CDONS On this format, hst the average daily unit power leselin MWe-Net for each day in the reporting :nonth. Compute to the nearest whole rnegawatt.

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1 OPERATING DATA REPORT 1

50-346 DOCKET NO.

i DATE December 14, 1987 1

COMPLETED BY J. Cipriani I

TELEPHONE N j

OPERATING STATUS

1. Unit Name:

Davis-Besse. Unit No. 1 Notes

2. Reporting Peiod:. November 1987 j

2772

3. Licensed ThermalPower(MWt):

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4. Nameplate Rating (Gross MWe):

925

5. Design Electrical Rating (Net MWe): 3.0fl.. - -

904

6. h8aximum Dependable Capacity (Grors MWe):

7. Maximum DepeMable Capacity (Net isWe):

860

8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Siete Last Report.Give Reasons:

i

9. Power Level To Which Restricted,if Any (Net MWe):

c ntinued at 81 percent

10. Reasons For Resnictbus.lf Any:

Due to the removal of two and the gagging ot a

third main steam safety valve on October 10, 1987.

This Month Yr.-to-Date Cumulative

11. Hours In Reporting Period 720 8,016 81,912

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12. Number Of Hours Reactor Was Critical 720 6,714.6 42,769.7

13. Reackor Reserve Shutdown Hours 0

392.4 5,017.2

14. Hours Generator On-Line 720 6,610.9 41.099.5

15. Unit Reserve Shutdown Hours 0

0 1,732.5

16. Gross Thermal Energy Generated (.MWH) 1,603,990 14,992,750 96,419,415 1*. Gross Electrical Energy Generated (MWH)

V30,992 4.902,533 31,864,920

18. Net Electrical Energy Generated (MWH) 499,846 4,585,428 29,822,091

19. Unit Service Factor 100 82.5 50.2

20. Unit Availability Factor 100 82.5 52,3

21. Unit Capscity Factor (Using MDC Net)

M.5 42.3

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22. Unit Capacity Factor (Using DER Net) 76.6 63.1 40.2

23. Unit Forced Outage Rate 0

6.9 33.6

24. Shutdowns Scheduled Over Next 6 Months (Type.Date.and Duration of Each t Refueling - Start on February 15, 1988 - 26 weeks

• End en August 15, 1988

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

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

Forecast Achined INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION W/77) u___________________________________________

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OPERATIONAL

SUMMARY

November 1987 Reactor power was limited at approximately 81 percent for the entire month. This power level was as a result of the removal of two and the gagging of a third main steam safety valve.

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'TDLEDO

%sm EDISON EDISON PLAZA 300 MADISON AVENUE TOLEDO OHIO 43652-0001 December 14, 1987 KB87-01001 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 1987 Davis-Besse Nuclear Power Station Unit 1 Enclosed are ten copies of the Monthly Operating Report for Davis-Besse Nuclear l

Power Station Unit 1 for the month of November 1987.

1 If you have any questions, please feel free to contact Bilal Sarsour at (419) 249-5000, Extension 7384.

1 Very truly yours, l

J',

/

&hitc+v

~

l ev.4 Louis F. Storz Plant Manager l

Davis-Besse Nuclear Power Station LFS GAG:ECC:BMS:plg Enclosures 1

cc:

Mr. A. Bert Davis, v/1 Regional Administrator, Region III l

Mr. Paul Byron, v/1 NRC Resident Inspector i

Nuclear Records Management, Stop 3220 1

5EP'I

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REFUELING INFORMATION Date: November 1987 1.

Name of facility: Davis-Besse Unit 1 2.

Scheduled date for next refueling shutdown: February 1988 3.

Scheduled date for restart following refueling: August 1988 4.

Vill refueling or resumption of operation thereafter require a I

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 Safety Review Committee to determine whether any unreviewed safety questions are associated with the core reload (Ref. 10 CFR Section-50.59)?

1 Ans: Expect the Reload Report to require standard reload fuel design Technical Specifications changes (2. Safety Limits and Limiting Safety i

System Settinds, 3/4.1 Reactivity Control Systems, 3/4.2 Power Distribution Limits and 3/4.4 Reactor Coolant System.)

5.

Scheduled date(s) for submitting proposed licensing action and supporting information: February 1988 6.

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

l new or different fuel design or supplier, unreviewed design or i

performance analysis methods, significant changes in fuel design, new operating procedures.

l 1.

The highly absorbing silver-indium-cadmium axial power shaping i

rods vill be replaced with reduced absorbing inconel, rods.

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1 2.

The discrete neutron sources vill be removed from the core and not replaced.

7.

The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pool.

i (a) 177 (b) 204 - Spent Fuel Assemblies 8.

The present licensed spent fuel pool storage capacity and the size of any increased in licensed storage capacity that has been requested i

or is planned, in number of fuel assemblies.

Present:

735 Increased size by:

0 (zero) 9.

The.prajected 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 l

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