ML20215D688

Monthly Operating Rept for Jul 1986

ML20215D688
Person / Time
Site:	La Crosse File:Dairyland Power Cooperative icon.png
Issue date:	07/31/1986
From:	Goodman L, Malin L, Taylor J DAIRYLAND POWER COOPERATIVE
To:	NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
LAC-11754, NUDOCS 8610140246
Download: ML20215D688 (6)

Text

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OPERATING DATA REPORT DOCKET NO. 50-409 DATE 08/05/86 COMPLETED BY Loree Malin TELEPHONE 608-689-2331 OPERATING STATUS NOTES:

1. Unit Name: La Crosse Boiling Water Reactor

2. Reporting Period: 0000, 07/01/86 to 2400, 07/31/86

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:

l This Month Yr.-to-Date Cumulative

11. Hours In Reporting Period 744 5,087 146,810

12. Number Of Hours Reactor Wss Critical 358 8 2,866.1 98,947 0

13. Reactor Reserve Shutdown Hours 0 0 478

14. Hours Generator On-Line 348.3 2,591.2 92,092.1

15. Unit Reserve Shutdown Hours 0 0 79

16. Gross Thermal Energy Generated (MWR) 51,138.2 358,595.8 12,817,558.3 t 17. Gross Electrical Energy Generated (MWH) 15,543 109,788 3,848,997 l 18. Net Electrical Energy Generated (MWH) 14,266 100,926 3,569,671

19. Unit Service Factor 46.8 50.9 62.7

20. Unit Availability Factor 46.8 50.9 62 8

21. Unit Capacity Factor (Using MDC Net) 40.0 41 3 50 7

22. Unit Capacity Factor (Using DER Net) 38.4 39.7 48.6

23. Unit Forced Outage Rate 53.2 24.3 10.2

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

None

25. If Shut Down At End Of Report Period, Estimated Date of Startup: September 1, 1986

26. Units In Test Status (Prior to Commercial Operation): Forecast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION 8610140246 860731 9" WP-6 8 DR ADOCK 0500 t,

r-NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE JULY 1986 At the onset of the July 1986 reporting period, reactor power was at 74 percent rated Thermal Power (36 MWe-net). Plant power was escalated until approximately 98 percent power (47 MWe-net) was reached on July 3.

At 1920 on July 8, the reactor automatically shutdown when a solenoid on Control Rod Drive Mechanism (CRDM) No. 12 failed. Opening of the solenoid resulted in low gas pressure for that CRDM, which is a scram signal. It could not be determined whether the failure was random in nature or due to water intrusion. Reactor water . level instrumentation was recalibrated during the shutdown. The reactor was taken critical at 2003 on July 9 and the turbine generator was connected to the DPC grid at 0633 on July 10.

On July 16, at 2328, the reactor automatically shutdown from 97.5 percent power (46 MWe-net) when the 1A. Static Inverter transferred to its alternate source, momentarily de-energizing one of the scram trains. Extensive troubleshooting was conducted on the cause of the inverter transfer. The inverter was replaced. During the shutdown, two small cracks were observed on the decay. heat line. It was decided to replace the section of pipe containing

'the cracks. Preparations are underway. Major maintenance performed also included work on the 1A Forced Circulation Pump seal,-CRDM No. 12, the reactor sight glass, and 1B Shutdown Condenser Steam Inlet Valve.

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'.T AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-409 UNIT LACBWR DATE 08/05/86 COMPLETED BY L.S. Goodman TELEPHONE 608-689-2331 4

MONTH July 1986 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 35 17 0 2 40 18 0 3 47 19 0 4 47 20 0 5 47 21 0 6 47 22 0 7' 47 23 0 8 38 24 0 9 0 25- 0 10 10 26 0 11 28 27 0 12 38 28 0 13 46 29 0 14 46 30 0 15 46 31 0 16 46 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 P0k'ER REDUCTIONS ,

DOCKET NO. 50-409

• UNIT NAME LACBWR DATE 08/05/86 REPORT MONTH JULY 1986 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) Reason 2 Reactor 3 Report # Code' Code 5 . Prevent Recurrence 86-20 07/08/86 F 35.2 A 3 86-20 RB CRDRVE Reactor automatically shut down when a solenoid on Control Rod Drive Mechanism (CRDM) No. 12 failed. Opening of the solenoid resulted in low gas pressure for that CRDM,which is a scram signal.

The lower CRDM was replaced.

It could not be determined whether the solenoid failure was random or due to water intrusion.

86-21 07/16/86 F 360.5 A 3 86-21 ED GENERA Reactor automatically shut down when the 1A Static Inverter transferred to its alternate source, momentarily de-energizing a scram train.

Extensive troubleshooting has been conducted on the cause of the inverter transfer. The inverter has been replaced.

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)

UNIT SHUTDOWNS AND POWER REDUCTIONS -

DOCKET No. 50-409 ',

UNIT NAME LACBiAt

• DATE 08/05/86 REPORT MONTH JULY 1986 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) . Reason 2 Reactor 3 Report i Code 4 Code 5 Prevent Recurrence 4

86-21 07/16/86 During shutdown, two small (continued) cracks were observed in the decay heat line. Preparations j are under way for replacement i of the pipe. Major i maintenance performed also included work on the 1A Forced Circulation Pump sight glass and 1B shutdown

. condenser steam inlet valve.

J l

I 4

i i

, 1 2 3 4 3

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)

0 D DA/RYLAND hhh[ COOPERATNE . P O. BOX 817 2615 EAST AVE. 30. . LA CRO (608) 788-4000 JAMES W. TAYLOR August 5, 1986 General Manager In reply, please refer to LAC 11754 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 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 July 1986.

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

Sincerely, dWfWh/f' JWI:LSG: lam cc: J. G. Keppler, Regional Administrator, NRC-DRO III John Stang, LACBWR Project Manager NRC Resident Inspector D. Sherman (ANI Library)

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