ML20237K921

Monthly Operating Rept for Mar 1987

ML20237K921
Person / Time
Site:	La Crosse File:Dairyland Power Cooperative icon.png
Issue date:	03/31/1987
From:	Malin L DAIRYLAND POWER COOPERATIVE
To:
Shared Package
ML20237K340	List: ML20237K337 ML20237K921
References
NUDOCS 8708190452
Download: ML20237K921 (6)

Text

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SUMMARY

OF OPERATING EXPERIENCE The plant operated.at 98-99% Rated Thermal Power (48-50 MWe-net) during the-March 1987 reporting period. No major safety-related maintenance was conducted.

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'PDR ADOCK 05000409

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~ h OPERATING DATA REPORT DOCKET NO. 50-409 DATE 04-06-87 COMPLETED BY L. Malin TELEPHONE 608-689-2331 OPERATING STATUS

1. - Unit Name: La Crosse Boiling Water Reactor

2. Report Period: 0000, 03/01/87 to 2400, 03/31/87

3. Licensed Thermal Power (MWt): 165

4. Nameplate rating (Gross MWe): 65.3

5. Design Electrical Rating (Net MWe): 50

6. Maximum Dependable Capacity (Gross MWe): 50

7. Maximum Dependable Capacity (Net MWe): 48

8. If Changes Occur in Capacity Ratings (Items 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 Year-to-Date Cumulative Hours In Reporting Period 744 2.160 152,643 11.

744 2,101.2 102,583.3

12. Number of Hours Reactor Was Critical

13. Reactor Reserve Shutdown Hours 0 0 517.2 744 2,071.5 95,570.5

14. Hours Generator On-Line

15. Unit Reserve Shutdown Hours 0 0 120.5 Gross Thermal Energy Generated (MWH) 120,926.6 327,628.3 13,344,849.4 16.

17. Gross Electrical Energy Generated (MWH) 38,557 103,013 4,013,504 Net Electrical Energy Generated (MWH) 36,512 97,526 3,723,450 18.

19. Unit Service Factor 100.0 95.9 62.6

20. Unit Availability Factor 100.0 95.9 62.7

21. Unit Capacity Factor (Using MDC Net) 102.2 94.1 50.8

22. Unit Capacity Factor (Using DER Net) 98.2 90.3 48.8

23. Unit Forced Outage Rate 0 4.1 11.8

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

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Refueling, September 1, 1987, approximate 1v 6 weeks

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

26. Units In Test Status (Prior to Commercial Operation): Forecast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY

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I AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-409 UNIT LACBWR DATE 04/06/87 COMPLETED BY L. S. Goodman TE!2 PHONE 608-689-2331 MONTH March 1987 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 48 17 49 l

2 48 18 49 l 3 48 19 50 4 48 20 50 -

5 48 21 49 6 48 22 49 7 49 23 50 8 49 24 49 9 49 25 49 10 49 26 46-11 49 27 49 12 49 28 49 13 49 ')

- 49 14 49 30 49 15 49 31 49 16 49 Instruction On this format, list the average daily unit power level in MWe-Net for each day in the reporting month. Compute to the nearest whole megawatt.

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REFUELING INFORMATION SHEET _

1. Name of Fa-ility La Crosse Boiling Water Reactor (LACBWR)

2. Scheduled Date for Next Refueling Shutdown The tentative date for the next refueling shutdown (EOC-X) is September 1, 1987.

3. Scheduled Date_2*2r Restart Following Refueling The tentativc scheduled date for subsequent reactor startup is approximately October 13, 1987.

4. Will Refueling or Resumption of Operation Thereafter Require a Technical Specification Change or other License Amendment?

If answer is yeas, what, in general, will 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 Reference 18 CFR Section 50.597 If no such review has taken place, when is it scheduled?

No license amendment will be needed for refueling.

The reloed plan will be reviewed by the Safety Review committee prior to refueling.

5. Scheduled Date(s) for Submitting Proposed Licensing Action and Supporting Information.

NA s

6. Important Licensing Considerations Associated with Refueling, e.g., New or Different Fuel Design or Supplies, Unreviewed Design or Performance Analysis Methods, Significant Chariges in Fuel Design, New Operating Procedure.

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REFUELING INFORMATION REQUEST - (Continued)

7. The Number of Fuel Assemblies  ;

l (a) in the Core and  ;

1 (b) in the Spent Fuel Pool.

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Core Loading: 72 Fuel Assemblies Spent Fuel Storage Pool Loading 261 Irradiated Fuel Assemblies The Present Licensed Spent Fuel Pool Storage Capacity and the Size of any 8.

Increase in Licensed Storage Capacity that has been Requested or is Planned, in Number of Fuel Assemblies, f 440 Fuel Assemblies

9. The Proiected Date of the Last Refueling that can be Discharged to the Spent Fuel Pool Assuming the Present Licensed Capacity 1993 l

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