ML20214M508

Monthly Operating Rept for June 1986

ML20214M508
Person / Time
Site:	La Crosse File:Dairyland Power Cooperative icon.png
Issue date:	06/30/1986
From:	Malin L, Taylor J DAIRYLAND POWER COOPERATIVE
To:	NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
LAC-11706, NUDOCS 8609110145
Download: ML20214M508 (6)

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t oI NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE JUNE 1986 At the onset of the June 1986 reporting period, the reactor was operating at approximately 83% Rated Thermal Power (39 MWe-net) during a power escalation.

The reactor reached 99% power (48 MWe-net) on June 13 and was held between 99 and 100% power.

At 1010 on June 22, the reactor automatically shutdown when an erroneous " Main Steam Isolation Valve Not Full Open" signal was generated by a relay failure.

Following the scram, a tubing connection on a reactor water level transmitter reference leg separated. The leak was manually isolated. All the reactor water level transmitters used for reactor operation were recalibrated.

The reactor was taken critical at 1916 on June 23. Maintenance was performed on the Main Steam bypass valve control system, since the control system was not functioning properly. At 1522 on June 25, the turbine-generator was connected to the DPC grid.

At 1538 on June 27, the reactor automatically shutdown from 81% power (38 MWe-net) due to a high power / recirculation flow signal when excess feedwater was injected into the reactor, causing a power spike. The operating (18) reactor feed pump had malfunctioned, decreasing feedwater flow. The other pump was started. It was brought up to speed so quickly, to prevent a low water level scram, that it overshot and excessive feedwater was injected into the reactor. Maintenance was performed on the IB reactor feed pump controller.

The reactor was taken critical at 0312 on June 28 and at 1630, the plant was synchronized to the DPC grid. At the end of the reporting period, reactor power was approximately 75% (34 MWe-net).  ;

A Type B leakage test was performed on the emergency airlock during June. No leakage was measured.

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3h 1 0609110140 060630 PDR

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R ADOCK 0*J000409 YDR

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.O OPERATING DATA REPORT DOCKET NO. 50-409 DATE 07/08/86 COMPLETED BY Loree Malin TELEPHONE 608-689-2331 OPERATING STATUS NOTES:

1. Unit Names La Crosse Boiling Water Reactor

2. Reporting Period: 0000, 06/01/86 to 2400, 06/30/86

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 MW e ): 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 .-t o-Da t e Cumulative

11. Ilours In Reporting Period 730 4.343 146,066

12. Number Of Ilours Reactor Was Critical 675.3 2,507.4 98,588.2

13. Reactor Reserve Shutdown llours 0 0 418

14. Ilours Generator On-Line 617.9 _2.242.9 91,T43.8

15. Unit Reserve Shutdown llours 0 0 79

16. Cross Thermal Energy Generated (MWil) 93,641.3 307,457.5 12,766,420.1

17. Cruss Electrical Energy Generated (MWil) 28,224 94,245 3,833,454

18. Not Electrical Energy Generated (MWil) 26,408 86,660 3,555,405____

19. Unit Service Factor 85.8 51.6 62.8

20. Unit Availability Factor 85.8 51.6 62.9

21. Unit Capacity Factor (Using MDC Net) 16.4 41.6 50.7

22. Unit Capacity Factor (Using DER Net) 73.4 39.9 48.7

23. Unit Forced Outage Rate 14.2 16.3 9.9

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 Startups . _ , ,

26. Units In Test Status (Prior to Commercial Operation): Forecast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION WP-6.8

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-409 UNIT LACBWR DATE 07/08/86 COMPLETED BY L.S. Goodman TELEP110NE 608-689-2331 MONTil June 1986 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (HWe-Net) 1 43 17 48 2 42 18 47 3 43 19 47 4 45 20 47 5 47 21 47 6 48 ,

22 20 7 48 23 0 8 48 24 0 9 48 25 3 10 48 26 22 11 48 27 21 12 48 28 2 13 48 29 23 __

14 48 ,,

30 30 15 49 31 NA 16 48 1

INSTRUCTIONS l

l Un this format, list the average daily unit power level in HWe-Net for each day in the repirting month. Compute to the nearest whole megawatt.

l WP-6.8

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

UNIT NAME 1ACBER DATE 07/08/86 REPORT M0hIH JUNE 1986 COMPLETED BY L.S. Goodman TELEPHONE 608-689-2331 l

Method of Licensee Cause & Corrective Duration Shatting Down Event System Component Action to No. Date Type l (Hours) Reason2 Reactor 3 Report i Code' Code 5 Prevent Recurrence 86-18 06-22-86 F 77.2 A 3 86-18 CD REIAYX Reactor automatically shut-down when a relay failed, generating an erroneous Main Steam Isolation Valve not i

full open signal. During the shutdown, reactor water level transmitters were recalibrated and the main steam bypass valve control system were worked on.

86-19 06/27/86 F 24.9 A 3 86-19 CH PLMPXX Reactor automatically shutdown due to a high power /recircul-l lation flow signal when excess feedwater was injected iato the reactor, causing a power spike. The operating reactor feed pump had malfunctioned.

The other pump was started.

It was brought up to speed so quickly that it overshot and excessive feedwater was 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-Redulatory Restriction 4-Other (Explain) (NUREG-0161)

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

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LYIT SHUTDOWNS AK3 P0EsER REDUCTIONS I

• DOCKET No. 50-409 .

UNIT MAN IX:3WE DATE 07/08/86 RIPORT MONTH JUNE 1986 COMPLETED BY L.S. Goodasa TELEPHONE 608-689-2331 Method of Licensee Cause & Corrective Duration . Shutting Down Event System Component Action to No. Date Typel (Hours) Reason 2 3eactor3 Report i Code 4 Code 5 Prevent Recurrence i

l 86-19 06/27/85 F 24.9 A 3 86-19 CH PIMPXX injected into the reactor.

j (continued) Maintenance was performed on

! the reactor feed peep l controller.

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1 2 3 4 Reason: Hethod: 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-Ol61)

Z-Operator Training & License Eummination

! F-Administrative 5 l G-Operational Error (Explain) Exhibit 1 - Same Source

! H-Other (Explaia) *

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• D COOPERAT/VE

• PO BOX 817

• 2615 EAST AV SOUTH

• LA CROSSE. WISCONSIN S4601 July 8, 1986 In reply, please refer to LAC-Il706 1

DOCKET No. 50-409 Office of Management Information and Program Control U. S. Nuclear Regulatory Commission Washington, D. C. 20555 i

SUBJECT:

DAIRYLAND POWER COOPERATIVE

.I LA CROSSE BOILING WATER REACTOR (LACBWR) i PROVISIONAL OPERATING LICENSE NO. DPR-45 MONTHLY OPERATING DATA REPORT FOR JUNE 1986 References (1) NRC lettter, Reid to Madgett, dated September 19, 1977.

(2) NRC latter, Reid to Madgett, dated December 29, 1977 i

4 Centlement i

in accordance with instructions contained in Reference (1) and Technical Specification Amendmenta contained in Reference (2), we are submitting information concerning operability and availability of the La Crosse Boiling Water Reactor (LACBWR) for the

, Honth of June 1986.

Plense contact us if there are any questinna concerning thin report.

j Very truly yours,

! DAIRYLAND POWER COOPERATIVE i James W. Taylor, General Manager JWTILSG sks cc J. C. Reppler, Regional Administrator, NRC-DRO 111

, John Stang, LACBWR Project Manager NRC Resident inspector D. Sherman ( ANI Library)

INPO l

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