ML20148B296

Monthly Operating Rept for Feb 1988

ML20148B296
Person / Time
Site:	Davis Besse
Issue date:	02/29/1988
From:	Cipriani J, Storz L TOLEDO EDISON CO.
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
KB88-00159, KB88-159, NUDOCS 8803210429
Download: ML20148B296 (6)

Text

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I OPERATING DATA REPORT 50-346 DOCKET NO.

DATE J/14/85 COMPLETED BY J. Cipriaui TELEPHONE X7365 OPERATING STATUS Notes

1. Unit Name:

nw4 -nn.. nn4e i

2. Reporting Period:

February 1988

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):

904

7. Maximum Dependable Capacity (Net MWe):

860

8. If Changes Occur in Capacity Ratings (Items Number 3 Throu.h 7) Since last Report, Give Reasons:

(Net MWe :

Centinued at approximately 81% (s2e Opgagggi

9. Power Level To Which Restricted,If AIue to th)e removal of two and the gagging of a third

10. Reasons For Restrictions,1f A mainsteamsafetyvabe: on October 10, 1987.

This Month Yr.-to Date Cumulative

11. Hours la Reporting Period 696 1440 84,096

12. Number Of Hours Reactor Was Critical 696 1440

,44,920.8 5,050.I

13. Reactor Reserve Shutdown Hours 14, Hours Generator On-Line 696 1,359.5 43,160.5

15. Unit Reserve Shutdown Hours 1,732.5

16. Gross Thermal Energy Generated (MWH) 1,458,959 2,924,571 100,886,770

17. Gross Electrical Energy Generated (MWH) 476,145 949,145 33,324,948 446,078 886,963 31,187.610

18. Net Electrical Energy Generated (MWH)

19. Unit Service Factor 100 94.4 31.3 100 94.4 53.4

20. Unit Availability Factor

21. Unit Capacity Factor (Using MDC Net) 74.5 71.6 43.1

22. Unit Capacity Factor (Using DER Net) 70.7 68.0 40.9

23. Unit Forced Outage Rate 32.6 l

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

Refueling - Start on March 10, 1988 - 26 wegs-EndsSeptember8,1988

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

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

Forecast Achiesed INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPER ATION M

(9/77) 8803210429 880229 t/

PDR ADOCK 05000346

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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-346 UNIT - Davis-Besse Unit 1 3/14/88 DATE COMPLETED BY J. Cipriani TELEPHONE X 7365 February 1988 MONTH DAY AVER AGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL (MWe Net)

(MWe Neti I

685 645 17 2

687 is 624 3

686 19 623 686 623 4

20 686 5

2 597 6

6R1 22 595 685 594 7

23 595 8

AR6 24 9

683 23 575 684 564 10 26 563 ll 682 27 12 683 564 3g 683 546 13

,9 14 A74 30 15 653 3;

654 16 INSTRUCTIONS On this format, hst the average daily unit power lesel in MWe Net for each day in the reporting anonth. Compute to the nearest whole megawatt.

14I77)

4 UNIT SHUTDOWNS AND POWE3 E. EDUCTIONS is0CKET NO.

50-14%

UNIT NAME Devia-Sesse 1 DATE 3/14/88 I

C M t.ETED BY

.I. Ciprians REPORT MONTH February 1988 TEt.EPHONE (419) 249-5000 a

eat. 7365

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$3 753

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Event pu Action to u;

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e No sign [ficant unit sht tdown or powei reduct ions l

l 3

' Exhibit C - Instructions for Preparation of Data F: FIrced Resoon:

Method S: Scheduled A-Equipment Failure (Emplain) 1-Manual Entry Sheets for Licensee Event Report (LER) 3-Maintenance or Test 2-Manuel Scram File (NUREC-Ol61)

C-Refueling 3-Automatic Scree D-Regulatory Restriction 4-Continuation from E4perator Training & License Emme1 nation Freviove Month Enhibit I - Same Source F-Administrative 5-14e4 Reduction

• Report challenges to Power Operated Relief Valves C-Operational Error (Emplain) 9-Other (Emplain)

(FORys) and Pressuriser Code Safety Valves (FCSve)

M-Other (Emplain)

r OPERATIONAL

SUMMARY

February 1988 Reactor power was maintained at approximately 81% power (Reactor power was limited at this power level as a result of removal of two main steam safety valves and gagging of a third main steam safety valve) until 0130 hours0.0015 days <br />0.0361 hours <br />2.149471e-4 weeks <br />4.9465e-5 months <br /> on February 15, 1988 when reactor power was manually reduced in steps to approximately 65% vhich was achieved on February 29, 1988. This power reduction was due to a plant coastdovn to insure the maximum efficiency and fuel depletion before shutdown to perform scheduled maintenance and refueling.

v.

REFUELING INFORMATION Date:

February 1988 1.

Name of facility: Davis-Besse Unit 1 2.

Scheduled date for next refueling outage? Harch 1988 3.

Scheduled date for restart following refueling:

September 1988 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 answer is no, has the reload fuel design and core configuration been reviewed by your Plant Safety Review Conmittee to determine whether any unreviewed safety questions are associated with the core reload (Ref. 10 CFR Section 50.59)?

Ans Expect the Reload Report to require standard reload fuel design Technical Specifications changes (2. Safety Limits and Limiting Safety System Settings, 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: May 1988 6.

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

new or different feel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures.

1.

The highly absorbing silver-indium-cadmium axial power shaping rods vill be replaced with reduced absorbing inconel rods.

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, and (c) the new fuel storage areas.

(a) 177 (b) 204 - Spent Fuel Assemblies (c) 64 - New Fuel Assemblies 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: 0 (zero) 9.

The projected 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

5, e s

VMEDO EDISON EDISON PLAZA 300 MADISON AVENUE TOLEDO. OHIO 436520001 March 15, 1988 KB88-00159 Docket No. 50-346 License No. NPF Document Control Desk U. S. Nuclear Regulatory Commission 7920 Norfolk Avenue

Bethesda, MD 20555 Gentlemen:

Monthly Operating Report, February 1988 Davis-Besse Nuclear Power Station Unit 1 Enclosed are ten copies of the Monthly Operating Report for Davis-Besse Nuclear Power Station Unit 1 for the month of February 1988.

If you have any questions, please contact Bilal Sarsour at (419) 249-5000, extension 7384.

Very truly yours, py p'l -

/-

Louis F. Storz Plant Manager Davis-Besse Nuclear Power Station LFStGAG:ECC BMS:jah Enclosures l

cc:

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

Mr. Paul Byron, v/1 NRC Resident Inspector Mr. A. V. DeAgazio NRC Project Manager 4

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