ML20054A064

Monthly Operating Rept for Feb 1982

ML20054A064
Person / Time
Site:	La Crosse File:Dairyland Power Cooperative icon.png
Issue date:	03/05/1982
From:	Goodman L DAIRYLAND POWER COOPERATIVE
To:
Shared Package
ML20054A055	List: ML20054A054 ML20054A064
References
NUDOCS 8204150256
Download: ML20054A064 (10)

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1 OPERATING DATA REPORT DOCKET NO. 50-409 DATE 03-05-82 COMPLETED BY I S_ GOODMAN TELEPilONE 60R-6R9-2331 OPERATING STATUS N"

1. Unit Name: LA CROSSE BOILING WATER REACTOR

2. Reporting Period: 0001, 02-01-82 TO 2400, 02-28-82 165

3. Licensed Thermal Power (MWt):

65.3 4 Nameplate Rating (Gross MWe):

50

5. Design Electrical Rating (Net MWe):

j

6. Maximum Dependable Capacity (Gross MWe):

60

7. Masimum Dependable Capacity (Net MWe):

48 i

S. If Changes Occur in Capacity Ratings (Items Number 3 Through 7)Since Last Report.Gise Reasons:

j

9. Power Lesel To Which Restricted.lf Any (Net MWe):

10. Resums For Restrictions,if Any:

This Month Yr..to.Dat e Cumulatise i1. Hours in Reporting Period 672 1416 108.075

12. Number Of Hours Reactor Was Critical 663.2 870.5 72,001.8

13. Reactor Resene Shutdownllours 0

0 478

14. Ilours Generator On.Line 653.6 792.6 66,484.8

15. Unit Reserve Shutdown Hours 0

0 79

16. Gross Thermal Energy Generated (MWil; 82,536.5 96,515.8 9,092,304.6

17. Gross Electrical Energy Generated (MWHI 22,857 26,332 2,716,190

18. Net Electrical Energy Generated (MWH) 21,371 24,085 2,516,682

19. Unit Senice Factor 97.3 56.0 61.5

20. Unit Asailability Factor 97.3 56.0 61.6

21. Unit Capacity Factor (Using MDC Net) 66.2 35.4 48.4

22. Unit Capacity Factor (Using DER Net) 63.6 34.0 46.5

23. Unit Forced Outage Rate 2.7 44.0 8.2

24. Shutdowns Scheduled Oser Nest 6 Months (Type.Date.and Duration of Eacht:

REFtJELING OUTAGE. APRIL _9_,

1982. 6 WEEKS NA j

25. If Shut Down At End OiReport Period. Estimated Date of Startup:

26. Units in Test Status (Prior to Commercial Operationi:

Forecast A chiesed j

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50-409 UNir siivil> owns AND powl R RI DUCTioss IXX'KET NO.

UNIT N AME LALBWR DATE 05-82 RI PORI MONTil FEBRUARY 1982 COMPLETED SY I 1 G00DMAN TELEPHONE 608-609-2431

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CAUSED SCRAM.

FLOW TRANSMITTER AND CONVERTER WERE CHECKED.

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4 NA CB PUMPXX REACTOR POWER WAS REDUCED FROM l

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83% TO 48% DUE TO THE 18 FORCED i

CIRCULATION PUMP TRIPPING WHEN SEAL INJECTION PUMPS WERE BEING TRANSFERRED. MAINTENANCE WILL BE PERFORMED ON SEAL INJECTION SYSTEM DURING UPCOMING REFUELING OUTAGE.

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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-409 LACBWR UNIT 03-05-82 DATE L.S. GOODMAN COMPLETED BY 608-689-2331 TELEPilONE

MONT1, FEBRUARY, 1982 DAY AVERAGE DAILY POWER LEVEL DAY AVER AGE DAILY POhER LEVEL (MWe-Neo q y we.Neg) i 32 17 32 2

35 14 i3 3

37 i9 15 4

37 20 27 5

33 31 21 6

33 36 22 7

33 23 37 32 8

24 27 9

32 25 30 10 32 37 26 32 27 38 12 32 38 28 13 32 29 14 17 30 is 32 33 16 32 INSTRUCTIONS On this format,hst the aserage daily unit power level in Mwe. Net f or each day in the reporting in.. nth. Compute to the nearest whole megawatt.

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FEBRUARY 1982 1 of 3 INSTRUMENT AND ELECTRICAL MAINTENANCE LER OR NATURE OF OUTAGE MALFUNCTION EQUIPMENT MAINTENANCE NUMBER CAUSE RESULT CORRECTIVE ACTION WATER LEVEL RECORDER CORRECTIVE NA GEAR WORN OUT CHART DRIVE REPLACED MOTOR MR-0094 INOPERATIVE HPSW DIESEL AMMETER CORRECTIVE NA UNKNOWN AMMETER IN0PER-REPLACED AMMETER MR-1042 ATIVE MACHINE SHOP VENT FAN CORRECTIVE NA DEFECTIVE BEARING MOTOR TRIP REPLACED MOTOR BEARING MOTOR MR-0101 TURBINE VIBRATION MG SET CORRECTIVE NA WORN MOTOR END DEFECTIVE BEARING REPAIRED END BELL AND MR-0114 BELL BEARING NUCLEAR CHANNEL N-3 CORRECTI'!E NA NORMAL USAGE RECORDER LOW REPLACED AMPLIFIER RECORDER MR-0119 SENSITIVITY CONDENSER VACUUM INDICATOR CORRECTIVE OUTAGE NORMAL USAGE MERCURY CONTAMIN-CLEANED VACUUM TUBE MR-0135 82-04 ATION FCP 1A FLOW INSTRUMENTS CORRECTIVE OUTAGE UNKNOWN SPIKES CHECKED TRANSMITTER, MR-0136 82-04 SQ. RT., RECORDER CRD CHARGING RELIEF CORRECTIVE OUTAGE UNKNOWN LEAKING ADJUSTED PRESSURE VALVES MR-0137 82-04 SETTING 25NB1 AIR SYSTEM CORRECTIVE NA BROKEN PULLY AIR COMPRESSOR REPLACED PULLEY AND MR-0153 INOPERATIVE BELT TURBINE LAMP BALLAST CORRECTIVE NA NORMAL USAGE LAMP IN0 PERATIVE REPLACED LAMP BALLAST MR-0154 AWNUNCIATOR CARD CORRECTIVE NA LOOSE SCREW FALSE ALARM REPLACED ALARM CARD MR-0160 ANNUNCIATOR CLEAR RING-CORRECTIVE NA WRONG CARD IN-NO RING-BACK REPLACED WITH CORRECT BACK MR-0162 STALLED CARD NUCLEAR CHANNELS N-5 PREVENTIVE NA TEST C!!E COMPLETED TESTS COMPLETED TESTS N-5 THROUGH N-9 THROUGH N-9

FEBRUARY 1982 INSTRUMENT AND ELECTRICAL MAINTENANCE 1

LER OR NATURE OF OUTAGE MALFUNCTION EQUIPMENT MAINTENANCE NUMBER CAUSE RESULT CORRECTIVE ACTION i'

SAFETY SYSTEM CHANNELS PREVENTIVE NA TEST DUE COMPLETED TESTS COMPLETED SAFETY SYSTEM 1 2&HO 3 TESTS 2

0 NUCLEAR CHANNELS N-3 & N-4 PREVENTIVE NA TEST REQUESTED COMPLETED TESTS COMPLETED CHANNELS N-3, N-4 TESTS NUCLEAR CHANNEL N-5 CORRECTIVE OUTAGE BALANCE INCORRECT LOW END DRIFT ADJUSTED BALANCE AMD RANGE SWITCH MR-0105 82-04 REPLACED SWITCH MULTICHANNEL ANALYZER CORRECTIVE NA UNKNOWN ANALYZER IN0PER-REPLACED I.C.

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MR-0102 ATIVE AIR EJECTOR MONITOR CORRECTIVE NA INCORRECT POWER FUSE BLOWN INSTALLED TO CORRECT MR-0116 SOURCE POWER PLUG RADVATION MONITORS CORRECTIVE NA DIRTY CONTACTS ALARMS INOPERATIVE CLEANED STACK, LIQUID MR-0122 WASTE AND VAULT MONITOR MR-0129 CONTACTS MR-0130 STACK AND MOBILE MONITOR CORRECTIVE NA CLUTCH SLIPPING FILTER FEED SLOW ADJUSTED CLUTCHES MR-0144 MR-0145 CONTAINMENT AIR MONITOR CORRECTIVE NA DIRTY CONTACTS FILTER ALARM CLEANED CONTACTS MR-0146 INOPERATIVE SECURITY ZONE 25-6 CORRECTIVE NA UNKNOWN FALSE ALARMS ADJUSTED BALANCE P0T MR-0084 SECURITY CAMERA FRONT CORRECTIVE NA VIDICON DEFECTIVE N0 PICTURE REPLACED CAMERA DOOR MR-0082 SECURITY ALARM CARD 25-6 CORRECTIVE NA UNKNOWN FALSE ALARMS REPLACED ALARM CARD MR-0138 SECURITY ZONE 19-2 CORRECTIVE NA UMKNOWN FALSE ALARMS ADJUSTED BALANCE POT MR-0148

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FEBRUARY 1982 1 of 1 MECHANICAL MAINTENANCE LER OR

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NATURE OF OUTAGE MALFUNCTION EQUIPMENT MAINTENANCE NUMBER CAUSE RESULT CORRECTIVE ACTION EMERGENCY SERVICE WATER FABRICATE NEW "Y" NA NA NA LIGHTER WEIGHT CONNECTOR SAFETY SYSTEM (ESWSS)

STACK GAS SAMPLE SYSTEM FACILITY CHANGE NA NA NA NEW SYSTEM FC-45-81-4 j

IB FORCED CIRCULATION CORRECTIVE NA INSPECTION OIL LEAK REMOVED BOLT, USED RTV, PUMP MR-0132 C0VER LEAK AND PUT BOLT BACK SOURCE RANGE DETECTOR CORRECTIVE NA BROKEN WOULD NOT LATCH WELDED CLIP N-1 EXTENSION R00 MR-0139 1A REACTOR FEED PUMP CORRECTIVE NA TRU ARC CLIP PIN COULD BACK REPLACED WITH NEW CLIPS i

SC0OP TUBE MR-0147 MISSING OUT IB REACTOR FEED PUMP PREVENTIVE NA NA NA REPLACED TRU ARC CLIPS' SC0OP TUBE MR-0156 1

IB SEAL INJECTION PUMPS CORRECTIVE NA WORN PACKING LEAKAGE REPLACED PACKING ON ALL MR-0149 3 PLUNGERS (ESUSS)

PREVENTIVE NA NA NA 6-MONTH TEST i

MR-0164 s

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NARRATIV.E

SUMMARY

OF OPERATING EXPERIENCE FEBRUARY 1982 At the onset of the February 1982 reporting period, power escalation continued following the January outages.

The reactor achieved 85% Rated Thermal Power (37 MWe-Net) on February 3, 1982.

This power level was scheduled to extend the time period between refueling outages.

On March 5, 1982, power was decreased to 77%

Rated Thermal Power (33 MWe-Net) to further extend core life.

At 1042 on February 18, the reactor automatically shut down when a spurious upward and downward spike was indicated for 1A Forced Circulation Pump flow.

This spurious signal was also transmitted to Power-Flow Safety Channel No.

1, generating a scram signal on hi@l Power-to-Flow ratio. The reactor was returned to critical at 1932.

The generator was synchronized to the DPC grid at 0508 on February 19, 1982.

Power escalation continued until February 22, when 83% Reactor Rated Thermal Power (36 MWe-Net) was achieved.

At 0902 on February 24, the IB Forced Circulation Pump (FCP) tripped due to oscillations in seal injection flow while the Seal Injection Pumps were being transferred.

Reactor power decreased to a minimum of 48% Rated Thermal Power.

The IB FCP was restarted at 0934.

Escalation continued until February 27, when 85% Rated Thermal Power ( 38 MWe-Net ) was achieved.

Power generation continued at this level for the remainder of the February reporting period.

Significant maintenance items performed during the reporting period are indicated on the attached Mechanical Maintenance and Instrument i

1 and Electrical Maintenance listings.

REFUELING INFORMATION REQUEST 1.

Name of Facility La Crosse Boiling Water Reactor (LACBWR) 2.

Scheduled Date for Next Refueling Shutdown The tentatively scheduled date for the next refueling shutdown (EOC-VII) is April 9, 1982.

3.

Scheduled Date for Restart Following Refueling The tentatively scheduled date for subsequent reactor startup is May 21, 1982.

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 conficura-tion been reviewed by your Plant Safety Review Committee to determine whether any unreviewed safety questions are associated with the core reload (Ref. 10 CFR Section 50.59)?

,If no such review has taken place, when is it scheduled?

No Technical Specification Change or license. amendment will be needed for refueling or subsequent resumption of operation.

The Safety Review Committee's 50.59 review of the reload fuel design and core configuration was conducted on February 9, 1982.

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 Supolies, Unreviewed Design or Performance Analysis Methods, Significant Changes in Fuel Design, New Operating Procedure.

None 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:

165 Irradiated Fuel Assemblies

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j REFUELING INFORMATION REQUEST - (Cont'd) j 8.

The Present Licensed Spent Fuel Pool Storage Capacity and the Size of any Increase in Licensed Storage Capacity that has been j

, Requested or is Planned, in Number of Fuel Assemblies.

440 Fuel Assemblies 9.

The Projected Date of the Last Refueling that can be Discharged j

to the Spent Fuel Pool Assuming the Present Licensed Capacity.

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