ML20212L929

Monthly Operating Rept for Oct 1986

ML20212L929
Person / Time
Site:	La Crosse File:Dairyland Power Cooperative icon.png
Issue date:	10/31/1986
From:	Goodman L, Malin L, Taylor J DAIRYLAND POWER COOPERATIVE
To:	NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
LAC-11949, NUDOCS 8701290439
Download: ML20212L929 (7)

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NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE OCTOBER 1986 -

During the October 1986 reporting period, the plant remained in the shut down condition. The outage had commenced September 24, 1986.

Major maintenance activities performed during October including work on Upper Control Rod Drive Mechanisms (CRDM) 2, 5 and 18, lower CRDHs, Nuclear Instrumentation, the Main Generator, and the 1A High Pressure Service Water Diesel. The 1A Shutdown Condenser Steam Inlet Valve Operator was reworked and work was also performed on the IB Static Inverter and the Containment Building Monitor.

A Type B leakage test was performed on the emergency airlock. An acceptable leakage rate of 0.13 SCFH was measured.

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I 8701290439 861031 PDR ADOCK 05000409 R PDR i

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OPERATING DATA REPORT DOCKET NO. 50-409 DATE 11/07/86 COMPLETED BY Loree Malin TELEPHONE 608-689-2331 i

~ 0PERATING STATUS NOTES:

1. Unit Name: La Crosse Boiling Water Reactor

2. Reporting Period: 0000, 10/01/86 to 2400, 10/31/86

3. Licensed Thermal Power (MWt ): 165 4, Nameplate Rating (Gross NW ): 65.3

5. Design Electrical Rating (Net MW,): 50

' 6. Maximum Dependable Capacity (Gross MW,): 50

7. Maximum Dependable Capacity (Net MW,)

48

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

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! 9. Power Level To Which Restricted, If Any (Net MW,):

j 10. Reasons for Restrictions, If Any:

This Month Yr.-to-Date Cumulative e

11. Hours In Reporting Period 745 7,296 149,019 4

12. Number Of Hours Reactor Was Critical 0 3,110.9 99,191.8

13. Reactor Reserve Shutdown Hours 0 ~~

39.2 517.2

14. Hours Generator On-Line 0 2,773.8 92,274.7

15. Unit Reserve Shutdown Hours 0 41.5 120.5

16. Cross Thermal Energy Generated (MWH) 0 377.460.2 12,836,422.8

17. Gross Electrical Energy Generated (MWH) 0 115,110 3,854,319

18. Net Electrf :al Energy Generated (MWH) - 515 104,275 ,

3,573,020

, 19. Unit Service Factor 0 38.0 61.9

20. Unit Availability Factor 0 38.6 62.0

21. Unit Capacity Factor (Using MDC Net) 0 29.8 50.0 4 22. Unit Capacity Factor (Using DER Net) 0 28.6 48.0

23. Unit Forced Outage Rate 100.0 50.4 11.9

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

Refueling Outage, March 15, 1987, 6 weeks 1

25. If Shut Down At End Of Report Period, Estimated Date of Startup: November 4,1986

26. Units In Test Status (Prior to Commercial Operation): Forecast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION 1

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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-409 UNIT LACBWR DATE 11/07/86 COMPLETED BY L.S. Goodman TELEPHONE 608-689-2331 MONTH October 1986 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 0 17 0 2 0 18 0 3 0 19 0 4 0 20 0 5 0 21 0 6 0 22 0 7 0 23 0 8 0 24 0 ,

9 0 25 0 10 0 26 0 11 0 27 0 12 0 28 0 13 0 29 0 14 0 30 0 15 0 31 0 16 0 INSTRUCTIONS 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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UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-409

• UNIT NAME 1ACBWR DATE 11/07/86-REPORT MONIH OCTOBER 1986 COMPLETED BY L. S. Goodman

'fELEPHONE 608-639-2331

.v Method of Licensee "

Cause & Corrective Duration Shutting Down Event System Component Action to No. Date Type l (Hours) Reason 2' Reactor 3 Report # Code 4 Code 5 Prevent Recurrence 86-23 09/24/86 S/F 745.0 F/B 1 NA RB CRDRVE Shutdown which commenced September 24, 1986 continued.

Major maintenance items included work on Control Rod Drive Mechanisms, Nuclear Instrumentation, the Main Generarqr and the 1A High Press 6re SES:vice Water Diesel.

O 1 2 3 4 Reason: Method: Exhibit C-Instructionse F: Forced A-Equipment Failure (Explain) 1-Manual for Praparation of Data S: Scheduled B-Maintenance or Test 2-Manual Scram Ent .- Sheets for Licensee C-Refueling 3-Automatic Scram Event Report (LER) File D-Regulatory Restriction 4-Other (Explain) (NUREG-0161)

E-Operator Training & License Examination F-Administrative 5 G-Operational Error (Explain) Exhibit 1 - Same Source H-Other (Explain)

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' REFUELING INFORMATION REOUEST c

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1. Name of Facility ,

La Crosse Boiling Water Reactor (LACBWR) x

2. Scheduled Date for Next Refueling Shutdown The tentative date for the next refueling shutdoun (EOC-X) is March 15, 1987.

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3. Scheduled Date for Restart Following Refueling The tentatively scheduled date for subsequent reactor startup is approximately April 28,'1987

4. Will Refueling or Resumption of Operation Thereaf ter 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 unreviewed safety questions are ascociated 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 relaod plan vill be reviewed by the safety Revleu Connittee 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 WP-6.8 r-

. e e-REFUELING INFORMATION REQUEST - (Continued)

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

(b) in the Spent Fuel Pool.

Core Loading: 72 Fuel Assemblies 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 i

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D DA/RYLAND hhh[ COOPERA7/VE

• P O BOX 817

• 2615 EAST AVC.(608) SO LA CR 788-4000 JAMES W. TAYLOR November 7, 1986 General Manager In reply, please refer to LAC 11949 DOCKET NO. 50-409 Office of Management Information and Program Control ,

U. S. Nuclear Regulatory Commission Washington, D. C. 20555

Subject:

DAIRYLAND POWER COOPERATIVE LA CROSSE BOILING WATER REACTOR (LACBWR)

PROVISIONAL OPERATING LICENSE NO. DPR-45 MONTHLY OPERATING DATA REPORT FOR OCTOBER 1986

Reference:

(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 Specification Amendments contained in Reference (2), we are submitting information concerning operability and availability of the La Crosse Boiling Water Reactor (LACBWR) for the Month of October 1986.

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

Sincerely, JWT:LSG:sks cc: J. G. Keppler, Regional Administrator, NRC-DRO III Roby Bevan, LACBWR Project Manager NRC Resident Inspector D. Sherman (ANI Library)

INPO 9* >-

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