ML20137U370

Monthly Operating Rept for Nov 1985

ML20137U370
Person / Time
Site:	La Crosse File:Dairyland Power Cooperative icon.png
Issue date:	11/30/1985
From:	Goodman L, Malin L, Taylor J DAIRYLAND POWER COOPERATIVE
To:	NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
LAC-11307, NUDOCS 8602190150
Download: ML20137U370 (7)

Text

e OPERATING DATA REPORT DOCKET NO. 50-409 DATE 12/06/85 COMPLETED BY Loree Malin TELEPHONE 608-689-2331 OPERATING STATUS NOTES:

l. Unit Name: La Crosse Boiling Water Reactor

2. Reporting Period: 0000, 11/01/85 to 2400, 11/30/85

3. Licensed Thermal Power (MWt ): 165

4. Nameplate Rating (Gross MWe ): 65.3

5. Design Electrical Rating (Net MW e): 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 MW e):

10. Reasons for Restrictions, If Any:

This Month Yr.-to-Date Cumulative

11. Hours In Reporting Period 720 8,016 140,979

! 12. Number Of Hours Reactor Was Critical 720 7,013.2 95,336.9

13. Reactor Reserve Shutdown Hours 0 0 478

14. Hours Generator On-Line 720 6,853.6 88,756.9

15. Unit Reserve Shutdown Hours 0 0 79

16. Gross Thermal Energy Generated (MWH) 110,529.1 996,039.1 12,343,441.0

17. Gross Electrical Energy Generated (MWH) 34,738 307,327 3,702,938

18. Net Electrical Energy Generated (MWH) 32,840 288,559 3,434,395

19. Unit Service Factor 100 85.5 63.0

20. Unit Availability Factor 100 85.5 63.0

21. Unit Capacity Factor (Using MDC Net) 95.0 75.0 50.8

22. Unit Capacity Factor (Using DER Net) 91.2 72.0 48.7

23. Unit Forced Outage Rate 0 3.4 9.8

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

Refueling, March 2, 1986, 5-6 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 COMMERCIAL OPERATION 1

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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-409 UNIT LACBWR DATE 12/06/85 COMPLETED BY L.S. Goodman TELEPHONE 608-689-2331 MONTH November 1985 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 48 17 36 2 48 18 25 3 48 19 35 4

4 48 20 45 5 48 21 48 6 49 22 48 7 49 23 49 8 49 24 49 9 49 25 49 10 48 26 49 11 48 27 48 12 49 28 49 13 49 29 48 14 48 30 48 15 39 31 NA 16 27 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 LACBWR DATE 12/06/85 REPORT MONTH November 1985 COMPLETED BY L.S. Goodman TELEPHONE 608-689-2331 Method of Licensee Cause & Corrective.

Euration Shutting Down Event System Component Action to No. Date Type l (Hours) Reason 2 Reactor 3 Report # Code 4 Code 5 Prevent Recurrence 85-13 11-15-85 F 0 A 4 NA CB INSTRU Power decreased when the 1A Forced Circulation Pump Dis-charge Valve closed.

85-14 11-18-85 F 0 A 4 NA CB INSTRU Power decreased when the lA Forced Circulation Pump Dis-charge Valve closed.

1 2 3 4 Reason: Method: Exhibit G-Instructionse F: Forced A-Equipment Failure (Explain) 1-Manual for. Preparation of Data S: Scheduled B-Maintenance or Test 2-Manual Scram Entry 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 (Explafn) Exhibit 1 - Same Source H-Other (Explain)

t REFUELING INFORMATION REQUEST

1. Name of Facility La Crosse Boiling Water Reactor (LACBWR)

2. Scheduled Date for Next Refueling Shutdown

'The tentative date for the next refueling shutdoun (EOC-IX) is March 2, 1986.

3. Scheduled Date for Restart Following Refueling The tentatively scheduled date for subsequent reactor startup is approximately' April 7, 1986

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 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?

.A license amendment vitt be needed for the new control roda which vitt be installed.

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

December 1985

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 some new control rode vill be utilized.

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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: 237 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 1992 l

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• P.O BOX 817 2615 EAST AV SOUTH =

LA CROSSE. W1SCONSIN 54601 (608) 788 4 000 December 6, 1985 In reply, please refer to LAC-11307 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 NOVEMBER 1985

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 November 1985.

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

Very truly yours, DAIRYLAND POWER COOPERATIVE WW James W. Taylor, General Manager JWT:LSG:sks cc: J. G. Keppler, Regional Administrator, NRC-DRO III John Stang, LACBWR Project Manager NRC Resident Inspector D. Sherman (ANI Library)

INPO I

NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE NOVEMBER 1985 At the onset of the November 1985 reporting period, power generation continued at approximately 98% Rated Thermal Power (48 MWe-net).

At 1603 on November 15, 1985, the 1A Forced Circulation Pump Discharge Valve closed. Reactor power was decreased to approximately 33% power and the valve was reopened at 1928. Power escalation then began and continued until November 18, reaching approximately 86% power. At 0156 on November 18, the 1A Forced

- Circulation Pump Discharge Valve closed. Reactor power was decreased to approximately 34%. At 0400, the valve was opened and power re-escalation commenced.

Reactor power reached 98% (48-49 MWe-net) on November 20. Power generation continued at this level through the remainder of the November reporting period.

During the month of November, maintenance was performed on the 1A Shutdown Condenser Steam Inlet Valve Positioner Cauge Manifold. The 1A Shutdown Condenser steam inlet manual valve was isolated while the manifold gasket-was replaced. A surveillance test was then performed on the 1A Shutdown Condenser Steam Inlet (Automatic) Valve. No other major safety-related maintenance was performed during the November reporting period.

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