ML20132H218

Monthly Operating Rept for Jul 1985

ML20132H218
Person / Time
Site:	La Crosse File:Dairyland Power Cooperative icon.png
Issue date:	07/31/1985
From:	Goodman L, Malin L, Taylor J DAIRYLAND POWER COOPERATIVE
To:	NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
LAC-11062, NUDOCS 8510020094
Download: ML20132H218 (6)

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NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE JULY 1985 At the onset of the July reporting period, power generation continued at 98%

Reactor Rated Thermal Power (47 MWe-net). At 0850 on July 10, the 1A Forced Circulation Pump Discharge Valve closed reducing power from 97% to 65%. Power was then manually reduced below 50% per Technical Specification. The valve  !

also closed twice on July 11, each time reducing power from approximately 45-50% l to 25-30%. Valve closure was postulated to be due to spiking on the loop differential temperature unit output and " sluggish" operation of the automatic valve control system.

On July 14 a reactor shutdown was commenced from approximately 96% power due to a small steam leak at No. 3 Feedwater Heater. The leak was temporarily patched on July 15. Power was reduced to approximately 40% prior to re-escalation.

Operating power was reached on July 17. Power generation ranged from 95-98%

f rom July 17-25. At 1115 on July 25, the reactor automatically shutdown due to a ground in the-low gas pressure scram circuit on Control Rod Drive Mechanism No. 8. While shutdown, Fuse 55/2, which is in the rod control circuit, blew. The

' fuse was replaced. The grounded wire was located and repaired. The reactor was returned to critical at 0538 on July 26. During the startup, at approximately 0.06% power, a high flux. spike occurred at 1051 on Nuclear Instrumentation Channel 5 when its range switch was upscaled. The spike could not be duplicated.

The range switch was cleaned. During the shutdown the power range Nuclear Instrumentation recorder was replaced.

The reactor was taken critical at 1655 on July 26. The turbine-generator was connected to the DPC grid at 0426 on July 27. On July 30, 97% power was achieved. Power-generation continued at 96-97% for the remainder ~of the reporting period.

During the month of July troubleshooting was conducted following failure of the 1A High Pressure Service Water / Alternate Core Spray Diesel. Refer to LER 85-13 for details.

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8510020094 e50 9 PDR ADOCK O PDR R

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OPERATING DATA REPORT DOCKET NO. 50-409 DATE 08/06/85 COMPLETED BY Loree Malin TELEPHONE 608-689-2331 OPERATING STATUS NOTES:

1. Unit Name: La Crosse Boiling Water Reactor

2. Reporting Period: 0000, 07/01/85 to 2400, 07/31/85

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 MWe ):

10. Reasons for Restrictions, If Any:

This Month Yr.-to-Date Cumulative

11. Hours in Reporting Period 744 5,087 138,050

12. Number Of Hours. Reactor Was Critical 719.6 4,154.3 92,478.0

13. Reactor Reserve Shutdown Hours 0 0 478

14. Hours Generator On-Line 702.8 4,038.7 85,942.0

15. Unit Reserve Shutdown Hours 0 0 79

16. Gross Thermal Energy Generated (MWH) 100,732.3 566,252.2 11,913,654.0

17. Gross Electrical Energy Generated (MWH) 30,299 174,213 3,569,824

-18. Net Electrical Energy Generated (MWH) 28,386 163,089 3,308,925

19. Unit Service Factor 94.5 79.4 62.3

20. Unit Availability Factor 94.5 79.4 62.3

21. Unit Capacity Factor (Using MDC Net) '/ 9. 5 66.8 49.9

22. Unit Capacity Factor (Using DER Net) 76.3 64.1 47.9

23. Unit Forced Outage Rate 5.5 3.1 9.9

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

None j i

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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 WP-6.8 k-

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-409 UNIT LACBWR DATE 08/06/85 COMPLETED BY L.S. Goodman TELEPHONE 608-689-2331 MONTH July 1985 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 47 17 44 2 47 18 46 3 47 19 46 4 47 20 46 5 47 21 46 6 47 22 46 7 47 23 46 8 47 24 46 9 46 25 21 10 28 26 0 11 18 27 12 12 28. 28 27 13 35 29 38 l

14 41 30 45 15 22 31 46 16 34 _

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.

WP-6.8 L _ _ __

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UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-409 -

UNIT NAME LACBWR +

DATE 08/06/85 REPORT M0!ffH July 1985 COMPLETED BY L.S. Goodman TELEPHONE 608-689-2331 Method of Licensee Cause & Corrective Duration Shutting Down Event System Component Action to '

No. Date Type l

-(Hours) Reason2 Reactor 3 Report # Code 4 . Code 5 Prevent Recurrence 85-05 07/10/85 F 0 A' 4 NA CB INSTRU Power decreased from 97% to 65% when the 1A Forced Circulation Pump Discharge Valve closed when a spurious high differential loop temperature signal occurred.

Power was manually reduced below 50%.

85-06 07/14/85 F 0 A 4 NA HH PIPEXX Manual shutdown was commenced due to a small steam leak at No. 3 Feedwater Heater. The leak was temporarily patched and power was re-escalated.

l 85-07 07/25/85 F 41.2 A 3 85-14 RB ELECON Reactor shutdown automatically l due to a. ground in the gas l pressure scram circuit on j Control Rod Drive Mechanism No. 8. Troublshooting was conducted which determined 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 (Explain) Exhibit 1 - Same Source H-Other (Explain)

J~ I UNIT SHUTDOWNS AND POWER REDUCTIONS I

I DOCKET NO. 50-409 ,

UNIT NAME LACBWR DATE 08/06/85 REPORT MONTH July 1985 COMPLETED BY L.S. Goodman TELEPHONE 608-689-2331 I

l Method of Licensee Cause & Corrective l Duration Shutting Down Event System Componen t Action to No. Date Type l (Hours) Reason 2 Reactor 3 Report # Code 4 Code 5 Prevent Recurrence 85-06 07/25/85 F 41.2 A 3 85-14 RB ELECCh location of the ground. Wire (CONTINUED) was repaired. The range switch for Nuclear Instru-mentation Channel.5 was cleaned following a scram during startup which occurred when the switch was upscaled.

The recorder for the power range Nuclear Instrumentation channels was replaced during the shutdown.

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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 l D-Regulatory Restriction 4-Other (Explain) (NbREG-0161) l E-Operator Training & License Examination F-Administrative 5 G-Operational Error (Explain) Exhibit 1 - Same Source H-Other (Explain) i

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D DA/RYLAND h [k COOPERAT/VE

• PO BOX 817 261'S EAST AV SOUTH August 6, 1985 LA CROSSE WISCONSIN S4601 (608) 788eo In reply, please refer to LAC-11062 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 JULY 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. July 1985.

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

Very truly yours, DAIRYLAND POWER COOPERATIVE y Af$Y h James W. Taylor, General Manager JWT:LSG:sks cc: J. G. Keppler, Regional Administrator, NRC-DRO III Walter Paulson, LACBWR Project Manager NRC Resident Inspector '

D. Sherman (ANI Library)

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