ML20154J357

Monthly Operating Rept for Apr 1988

ML20154J357
Person / Time
Site:	Davis Besse
Issue date:	04/30/1988
From:	Cipriani J, Storz L TOLEDO EDISON CO.
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
KB88-00209, KB88-209, NUDOCS 8805260312
Download: ML20154J357 (6)

Text

_4.

s OPERATIONAL

SUMMARY

April 1988 The milestone of 1,000,000 manhours worked without a lost time accident was reached on April 6, 1988. April 30, 1988 was the 52nd day of the 187 day outage.

A major milestone was reached when the Decay Heat Removal Loop No. 1 and its associated support systems was placed into operation on April 17, 1988. The Reactor Vessel head lift and removal occurred on April 25, 1988.

A newly designed head-lifting device was used for the first time and performed well. The Decay Heat Loop No. 2 maintenance is projected to start on May 3, 1988, immediately following a complete core offload.

Work is expected to progress smoothly by incorporating Decay Heat Loop No. 1 maintenance experience. The outage is tracking on schedule with identified emergent work items being incorporated into the original scope without affecting the overall outage duration.

l 8805260312 880430

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PDR ADOCK 05000346

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DCD fj(

AVER AGE DAILY UNIT POWER LEVEL

.e DOCKET NO, 50-346 DB-1 WIT DATE May 13, 1958 COMPLETED BY J. Cipriani 249-5000, ext. 4460 TELEPHONE.

MONTH April 1988 DAY AVER AGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe Neil 0

0 17 0

2 0

gg 19 0

0 d

20 0

0 5

33 0

0 6

0 23 0

U 24 0

9 25 0

0 to 26 0

0 11 27 0

0 12 73 0

13 29 0

0 14 30 0

15 31 l

16 l

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INSTRUCTIONS I

l On this forrnat.! st the aserage daily unit power lesel in MWe. Net for each da in the reponing inonth. Compute to the nearest whde rnegawatt, i

p1/77 )

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s OPERATLNG DATA REPORT DOCKET NO.

50- % 6 DATE _May 13, 1988 COMPLETED BY J.

G1priani TELEPHONE 249-5000 ex t '. 4460 OPERATING STATUS

1. Unit Name:

Davis-Besse, Unit No. 1 Notes April, 1988

2. Reporting Period:

2772

3. Licensed Thermal Power (MWt):

925

4. Nameplate Rating (Gross MWe):

5. Design Electrical Rating (Net MWe):

6. Maximum Dependable Capacity (Gross MWe):

904

7. Maximum Dependable Capacity (Net MWe):

f60

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 i1. Hours in Reporting Period 719 2,903 85,559

12. Ncmber Of Hours Reactor Was Critical 0.0 1,661.3 45,142.1

13. Reactor Reserve Shutdown Hours 0.0 0

5,050.1 0.0 1,580 43,381

14. Hours Generator On.Line o

1,732.5 u.u

15. Unit Reserve Shutdown Hours

16. Gross Thermal Energy Generated (MWH) 0.0 3,306,442 7 01,268,641

17. Gross Electrical Energy Generated (MWH) 0.0 1,072,485 33,448,288

18. Net Electrical Energy Generated (MWH) 0.0 998,787 31,299 T3T

19. Unit Service Factor 0.0 54.4 50.7 0.0 54.4 52.7

20. Unit Availability Factor

21. Unit Capacity Factor (Using MDC Net) nn 40.0 42.5

22. Unit Capacity Factor (Using DER Net) 0.0 38.0 40.4

23. Unit Forced Outage Rate 0.0 0

32.5

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

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

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

• Forecast Achiesed

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INITIAL CRITICA LITY j

INITIAL ELECTRICITY COMMERCIAL OPER ATION l

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e UNIT SHUTDOWNS AND POWER REDUCTIONS INTttET NO.

50-146

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UNIT NAME Davie-Seese I a

DATE Mnv l 'l _ 19R8 mens av J. uprnat REPORT HONTH April 1988 TELEFHONE (419) 249-5 2 ext. 7365 "w

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Cause & Corrective Licensee g7 g

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Event gu Date I5f er...nt R.curr.nc.

Report 8 A~

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88-3-10 S

719 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 April, 1988.

See Operational Summary for further details.

L 3

F: Forced Reason:

Method:

'Enhibit C - Instructione for Freparation of Data 5: Scheduled A-Equipment Failure (Emplain) 1-Manual Entry Sheets for Licensee Event Report (LER) 3-Maintenance or Test 2-Manual Scram File (NUREC-0161)

C-Refueling 3-Automatic Scram D-Regulatory Restriction 4-Continuation free E-Operater Training & License Emme1 nation Previous Month Enhtbit I - Same Source F-Admintetrative 5-Lead Reduction eReport challenges to Fouer Operated Relief Yelves C-operational Error (Emplain) 94ther (Emplain)

(FORVe) and Fressuriser Code Saferv Valves (FCSVe)

N-Other (Explain)

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Le REFUELING INFORMATION Dates April 1988 1.

Name of facility:

Davis-Besse Unit 1 2:.

Scheduled date for next refueling outage? Tentative Outage Windov October 1989 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 Committee to determine whether any unreviewed safety questions are associated vith 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 vith 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.

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

b.

The discrete neutron sources will 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) 268 - Spent Fuel Assemblies (c) 0 - 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 requented 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

e TOLEDO

%mm EDISON-EDISON PLAZA 300 MADISON AVENUE TOLEDO. OHIO 43652-0001 Hay 16, 1988 KB88-00209 Docket No. 50-346 License No. NPF-3 Document Control Desk U. S. Nuclear Regulatory Commission Vashington, D. C.

20555 Gentlemen:

Monthly Operating Report, April 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 April 1988.

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

Very truly yours, J

W pu Louis F. Storz Plant Manager Davis-Besse Nuclear Power Station LFS GAG:ECC:BMS plg Enclosures cc:

Mr. A. Bert Davis, v/1 Regional Administrator, Region III Hr. Paul Byron, v/1 NRC Resident Inspector Mr. A. V. DeAgazio NRC Project Manager i