ML20195C923

Monthly Operating Rept for May 1988 for Davis-Besse Nuclear Power Station Unit 1

ML20195C923
Person / Time
Site:	Davis Besse
Issue date:	05/31/1988
From:	Cipriani J, Storz L TOLEDO EDISON CO.
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
KB88-00231, KB88-231, NUDOCS 8806220327
Download: ML20195C923 (6)

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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 346 Davis-Besse Unit 1.

UNIT DATE.

June 14, 1988 COMPLETED BY J. Cinriani TELEPHONE x 4460 MONTH DAY AVERAGE DAlt.Y POWER LEVE..

DAY AVER AGE DAILY POWER LEVEL (MWe-Net)

1. MWe-Net )

1 0

17 0

0 0

2

g 0

0 3

,9 0

4 20 0

5 0

21 0

0 0

6 22 0

7 23 0

8 0

24 0

9 0

0 25 0

10 26 0

li 0

27 0

12 0

0 28 0

13 29 n

14 n

30 0

i 3

O 15 0

0 16 INSTRUCTIONS On this format. fist the average daily unit power leselin MWe Net for each day in the reporting month. Compute to the nearest whole megawatt.

4 (9/77 )

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.s OPERATING DATA REPORT DOCKET NO.

50-346 DATE June 14, 1988 COMPLETED BY J. Cipriani TELEPHONE x4460 OPERATING STATUS

1. Unit Name:

Davis-Besse. Unit No. I Notes

2. Reporting Period:

May 1988

3. Licensed Thermal Power (MWt):

2772 925

4. Nameplate Rating (Gross MWe):

5. Design Electrical Rating (Net MWe):

906

6. Maximum Dependable Capacity (Gross MWe):

904 860

7. Maximum Dependable Capacity (Net MWe):

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

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

10. Reasons For Restrictions,if Any:

This Month Yr. to.Date Cumulative

11. Hours in Reporting Period 744 3.647 86,303

12. Number Of Hours Reactor Was Critical 0.0 1,661.2 45,142.1

13. Reactor Reserve Shutdown Hours 0.0 0.0 5.050,1

14. Hours Generator On.Line 0.0 1,580 43,381

15. Unit Reserve Shutdown Hours 0.0 0.0 1,732.5

16. Gross Thermal Energy Generated (MWH) 0.0 3,306,442 101.268.641

17. Gross Electrica' Energy Generated (MWH) 0.0 1,072,485 33,448.288

18. Net Electrical Energy Generated (MWH) 0.0 998,787 31,299,434

19. Unit Service Factor 0.0 43.3 50.3

20. Unit Availability Factor 0.0 43.3 52.3

21. Unit Capacity Factor (Using MDC Net) 0.0 31,8 42.2 0.0 30.2 40.0

22. Unit Capacity Factor (Using DER Net)

23. Ur t Forced Outage Rate 0.0 0.0 32.5

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

Refueling - Started on March 10, 1988 - 26 weeks - Ends on September 12, 1988

25. If Shut Down At End Of Report Period. Estimated Date of Startup: sentember 12. 1988

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

Forecast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION i

(9/77)

_- ~,

UNIT SHUTDOLINS AND POblER REDUCTIONS g.KET NO.

50-346 UNIT NAME Davie-Basee !

DATE June 14_ l988 COMPI.ETED BY J. Cipriani REPORT MONTH May 198R TELEPHONE (419) 249-5000 ext. 4460 ooO cg 2*.

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3e Licensee "3

C

• Cause & Corrective 8

No.

Date N

• 2 f"

^U Action to Event c

3" j

2m Report f Prevent Recurrence i

i 2

88-3-10 S

744 C

1 N/A N/A N/A The unit outage which began on March 10, 1988 was still in progress through the end of May, 1988.

See Operational Summary for further details.

l 1

I 3

i F: Firced Reason:

Method:

' Exhibit C - Instructions for Preparation of Data 5: Scheduled A-Equipment Failure (Emplain) 1-Manual Entry Sheets for Licensee Event Report (LER) 8-Maintenance or Test 2-Manual Scree File (NUREC-0161)

C-Refueling 3-Automatic Scree D-Regulatory Resttiction 4-Continuation from E-Operator Training & License Eramination Frevious Month Exhibit I - Same S.rce F-Administrative 5-Load Reduction

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

(PORVs) and Pressurizer Code Safety Valves (PCSVs)

H-Other (Emplain) i

OPERATIONAL

SUMMARY

Hay 1988 The eleventh veek of the scheduled 26 week Refueling Outage has been completed and remains on schedule.

Ducing Hay, the following significant outage activities were completed:

Fuel Handling Bridge Modifications and Testing UT of Upper Core Barrel Bolts Reactor Core Offload Station Battery Replacement Pressurizer Heater Bundle Replacement Generator Field Installation Eddy Current Testing of No. 1 Steam Generator Control Room Center Console Installation A major ef fort is underway to release completed items to the test group ahead of schedule.

The test program is expected to be in full sving in early July with the completion of the majority of our extensive control Room Hodifications by July 1.

The Decay Heat Loop Train 2 Outage i

consisting mainly of extensive check valve modifications, continues on schedule and will be completed in early June.

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REFUELING INFORMATION Date:

May 1988 1.

Name of facility:

Davis-Besse Unit 1 2.

Scheduled date for next refueling outage? Tentative Outage Vindov October 1989 3.

Scheduled date for restart from current 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 gene al 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)?

Ans: The Reload Report requires standard reload fuel design Technical Specifications changes (2. Safety Limits and Limiting Safety System Cettings, 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:

Submitted May 18, 1988 6.

Important licensing 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.

The highly absorbing silver-indium-cadmium axial power shaping a.

rods vill be replaced with reduced absorbing inconel rods.

b.

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

The physics testing has been reduced in scope.

c.

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) 0 (b) 445 (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:

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

'/

R)LEDO EDISON EDISON PLAZA 300 MADISON AVENUE TOLEDO. OHIO 43652-0001 June 14, 1988 KB88-00231 Docket No. 50-346 License No. NPF-3 Document Control Desk U. S. Nuclear Regulatory Commission Washington, D. C.

20555 Gentlemen:

Monthly Operating Report, May 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 May 1988.

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

Very truly yours, d

f&,,

69 Louis F. Storz Plant Manager Davis-Besse Nuclear Power Station BMS/JEC/plg Enclosures cc:

Mr. A. Bert Davis Regional Administrator, Region III Mr. Paul Byron NRC Resident Inspector Mr. A. V. DeAgazio NRC Project Manager

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