ML20237K357

Monthly Operating Rept for Feb 1987

ML20237K357
Person / Time
Site:	La Crosse File:Dairyland Power Cooperative icon.png
Issue date:	02/28/1987
From:	Goodman L, Malin L, Taylor J DAIRYLAND POWER COOPERATIVE
To:	NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
LAC-12140, NUDOCS 8708190218
Download: ML20237K357 (7)

Text

l a g .

i NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE 1

February 1987 At the onset of the February 1987 reporting period, the reactor was operating at approximately 97% Rated Thermal Power (48 MWe-net). l i

At 1702 on February 16, the reactor was manually scrammed from 98% power, l following receipt of a first out alarm on the annunciator scram panel, which was I not followed by an automatic scram. The alarm was " Turbine Building Motor l Control Center lA Voltage Low." The voltage was normal and no other actions occurred which would be expected if low voltage existed. However, a commitment had been made to the NRC and a directive issued following a September 1986 event j (LER 86-30), which required the reactor to be manually scrammed if a scram alarm l occurred without a scram. j The alarm card was replaced. The card's input capacitor was determined to be shorted.

Following discussion with an NRC representative, the directive was changed to allow required action to be dependent on whether the alarm is the result of a valid scram signal, except in the case of specified Nuclear Instrumentation channels.

The reactor was taken critical at 1400 on February 17 and at 2306 the turbine generator was synchronized to the DPC grid. Power escalation continued until February 21, when 97% power (48 MWe-net) was achieved. Power generation l continued at approximately this level for the remainder of the reporting-period.

A Type B test was performed on the emergency airlock on February 16 with acceptable results. The leakage rate measured was 0.0259 SCFH.  ;

On February 3, the chain broke on the main airlock exterior door. The link was replaced and the door interlocks tested with satisfactory results.

PCI-21 8708190218 870228 f PDR ADOCK 05000409 (

R PDR [

OPERATING DATA REPORT DOCKET NO. 50-409 DATE 03/06/87

! H0 608 6 2331 OPERATING STATUS

1. IJnit Nmnes _ La Crosse Boiling Water Reactor

2. Report Period: 0000, 02/01/87 to 2400, 02/28/87 )

l 3. Licensed Thermal Power (MWt): _

165 j i 4. Nameplate rating (Gross MWe): 65.3 4

5. Design Electrical Rating (Not MWe): 50 l 6. Maximum Dependable Capacity (Gross MWe): -50 Maximum Dependable Capacity (Net MWe): 48

7. .l

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:

1 This Month Year-to-Date Cumulative

11. Hours In Reporting Period 672 1,146 151,899 f

12. Number of Hours Reactor Was Critical 651.0 1,357.2 101,839.3 1

13. Reactor Reserve Shutdown Hours 0 0 517.2 i

14. Hours Generator On-Line 641.9 1,327 T 94,826.5 .l

15. Unit Reserve Shutdown Hours 0 0 120.5

16. Gross Thermal Energy Generated (MWH) 100,146 206,701.7 13,223,922.7

17. Gross Electrical Energy Generated (MWH) 31,258 64,456 3,974,947

18. Net Electrical Energy Generated (MWH) 29,618 61,014 3,686,938

19. Unit Service Factor 95.5 93.8 62.4

20. Unit Availability Factor 95.5 93.8 62.5

21. Unit Capacity Factor (Using MDC Net) 91.8 89.8 50.6

22. Unit Capacity Factor (Using DER Net) 88.2 86.2 48.5

23. Unit Forced Outage Rate 4.5 6.3 11.9

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

l Refueling, September 1, 1987, approximately 6 weeks.

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

26. Units In Test Status (Prior to Commercial Operation): Forecast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY 1 COMMERCIAL OPERATION PCI-21 i _ _ _ . Y

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-409 UNIT _ _

LACBWR l DATE 03/06/87 l COMPLETED BY L. S. Goodman l- TELEPHONE 608-689-2331 l

l MONTH February 1987 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL l (MWe-Net) (MWe-Net) 1 48 17 0 4 1

2 48 18 20 3' 48 19 34 1

4 48 20 45 j 1

5 48 21 48 j i

6 48 22 48 I 7 48 23 48 8 47 24 48 9 47 25 49 10 48 26 49 11 48 27 49 i l

12 48 28 48 13 48 29 NA 14 48 30 NA 15 48 31 NA 16 34 l

Instruction  !

l 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 Facility

? La Crosse Boiling Water Reactor (LACBWR) 1 l I 1

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

September 1, 1987.

l l 3. Scheduled Date for Restart Following Refueling The tentative scheduled date for subsequent reactor startup is l approximately October 13, 1987.

l

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

If answer is yes, 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 l unreviewed safety questions are associated with the core reload Reference 10 CFR Section 50.597 If no such review has taken place, when is it scheduled?

No license amendment will be needed for refueling.

The zeload 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

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

None l

l l

REFUELING INFORMATION REQUEST - (Continued) l l

7. The Number of Fuel Assemblies (a) in the Core and i

I (b) in the Spent Fuel Pool.

l Core Loadings 72 Fuel Assemblies l Spent Fuel Storage Pool Loading 261 Irradiated 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.

440 Fuel Assemblies

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

)

_ _ - - _ - - - - - - - - - - -- -. . - - - - -. - - 1

L()CS i'

l D DA/RYLAND hh[M[ COOPERAT/VE . P O box 817 2615 EAST AVE 50 . LA CROSS iG08) 788 4000 JAMES W. TAYLOR k

t General Manager March 6, 1987 l l

In reply, please refer to LAC-12140 l DOCKET NO. 50-409 l I

Office of Management Information and Program Control l U. S. Nuclear Regulatory Commission Washington, DC 20555

SUBJECT:

DAIRYLAND POWER COOPERATIVE LA CROSSE BOILING WATER REACTOR (LACBWR)

PROVISIONAL OPERATING LICENSE NO. DPR-45 i MONTHLY OPERATING DATA FOR FEBRUARY

REFERENCES:

1) NRC Letter, Reid to Madgett, dated September 19, 1977.

2) NRC Letter, Reid to Madgett, dated December 29, 1977.

Gentlemen:

In accordance with instructions contained in Reference (1) and Technical i Specification Amendments contained in Reference (2), we are submitting l information concerning operability and availability of the La Crosse Boiling Water Reactor (LACBWR) for the Month of February 1987.

Please contact us if there are any questions concerning this report.

Sincerely, JWT:LSG:sks cc: A. Bert Davis, Regional Administrator, NRC-DRO-iII Roby Bevan, LACBWR Project Manager NRC Resident Inspector D. Sherman (ANI Library)

INPO I

PCI-21 E

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