ML20052G174

Monthly Operating Rept for Mar 1982

ML20052G174
Person / Time
Site:	La Crosse File:Dairyland Power Cooperative icon.png
Issue date:	04/02/1982
From:	Gadow G DAIRYLAND POWER COOPERATIVE
To:
Shared Package
ML20052G170	List: ML20052G169 ML20052G174
References
NUDOCS 8205140374
Download: ML20052G174 (9)

Text

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t OPERATING DATA REPORT 50-409 DOCKET NO.

DATE 04-02-82 COMPLETED BY G.R.GADOW TELEPHONE AnA-6RQ-2331 OPERATlhG STATUS LA CROSSE B0ILING WATER REACTOR Notes

l. Unit Name:

0001, 03-01-82 TO 2400, 03-31-82

2. Reporting Period:

3. Licensed Thermal Power (MWt):

165 65.3

4. Nameplate Rating (Gross MWe):

5. Design Electrical Rating (Net MWe):

50 50

6. Masimum Dependable Capacity (Gross MWe):

48

7. Maximum Dependable Capacity (Net MWe):

8. If Changes Occur in Capacity Ratings (items Number 3 Through 7) Since Last Report, Gise Reasons:

9. Power Lesel To which Restricted,1f Any (Net MWe):

10. Reasons For Restrictions.If Any:

This Month Yr.-to-Date Cumulatise 744 2160 108,819 I1. Hours in Reporting Period

12. Number Of Hours Reactor Was Critical 728.18 1598.68 72872.3

13. Reactor Reserse Shutdown Hours 0

0 478

14. Hours Generator On-Line 715.78 1508.35 67.200.56

15. Unit Rewrve Shutdown Hours 0

0 79 16' Gross Thermal Energy Generated (MWH) 92,536.8 189,052.6

._9,184,841.4

17. Grow Electrical Energy Generated (MWH) 26.210_ _ _.

52.542 2.742.400

18. Net Electrical Energy Generated (MWH) 24.516 48.601

_2 536_593

19. Unit Service Factor 96.2 69.8 61.7 20 Unit Availability Factor 96.2 69.8 61.8-

21. _ Unit Capacity Factor IUsing MDC Net)

'68.6 46.9 48.6 i

22. Unit Capacity Factor (Using DER Net) 65.9 45.0 46.6

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23. Unit Forced Outage Rate 3.8 30.2 8.1

24. Shutdowns Scheduled Oser Next 6 MonthsIType.Date.and Duration of Eacht:

REFUELING OUTAGE APRIL 9, 1982, 7 WEEKS NA t

25. If Shut Down At Fnd Of Report Period. Estimated Date of Startup:

26. Units in Test Status IPrior to Commercial Operatiem):

Forecast Achiesed INITIA L CRITICA LITY INITIAL ELECTRICITY CO%I\\lERCI \\L OPE R ATION 4

i-1 8205140374 820407 m

PDR ADOCK 05000409 R

PDR

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-409 LACBWR UNIT DATE 04-07-R2 COMPLETED BY G.R.GADOW 608-689-2331 TELEPHONE MONT11 MARCH, 1982 DAY AVER AGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL IMhe-Net)

(MWe-Net) i 32 17 32 35 14 2

ig 3

37 19 15 4

37 27 20 5

33 2:

31 33 36 6

22 7

33 37 23 32 3

24 27 32 25 30 10 26 37 3 "'

il 27 38 32 8

12 3

38 32 33 13 2,

32 26 14 3o 15 32 0

3 16 32 INSTRUC110NS I

i On this format, list the average dady umt power level in MWe Net for each day in the reportmg m. nth. Compute to the nearest whole rnegawitt.

l (9/77)

I

UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.

50-409 UNIT NAME LACBWR DATE 04-07-82 REPORT MONTH MARCH 1982 COMPLETED BY G.R.GADOW TELEPHONE 608-689-2331 n.

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3

.Y Licensee

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Cause & Corrective L.

Date g

3=

4

,g g 5 Event

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El Action to j'

$E jig Report :

mU Prevent Recurrence c5 82-06 03-30-82 F'

28.2 H

3 NA EB TRANSF PARTIAL SCRAM OCCURRED AS A RESULT OF ACTUATION OF DEVICE 86G1, GENER-ATOR TRIPPING RELAY. THIS RELAY WAS ENERGIZED BY RELAY 151 GMT1 C0-6, MAIN POWER TRANSFORMER NEUTRAL GROUND.

THE MOST PROBABLE CAUSE OF RELAY 151 ACTION WAS HIGH SURFACE WINDS IN THE DAIRYLAND SYSTEM WHICH CAUSED NUMER-OUS 69KV TRANSMISSION LINE BREAKER OPERATIONS.

RELAYS AND TRANSFORMER WERE CHECKED.

EQUIPMENT OPERATED AS DESIGNED. NO MALFUNCTIONS NOTED.

I 2

3 4

F: Forced Reason:

Method:

Exhibit G-Instructions S: Scheduled A Equipment Failure (Explain) 1-Manual for Preparation of Data B-Maintenance of Test 2 Manual Scram.

Entry Sheets for Licensee C Refueling 3 Automatic Scram.

Event Report (LER) File INUREG-D Regulator) Restriction 4-Other (Explain) 0161)

E Operator Training & License fixamination F-Administ rative 5

G-Operational En or (Explain)

Exhibit 1 - Same Source 19/77)

Il Other (Explain) i

MARCH 1982 1 of 1-MECIIANICAL MAINTENANCE LER OR NATURE OF OUTAGE MALFUNCTION EQUIPMENT MAINTENANCE NUMBER CAUSE RESULT CORRECTIVE ACTION CONTAINMENT BUILDING PREVENTIVE NA NA NA INSPECTION PER PREVENTIVE CRANE MAINTENANCE-MAINTENANCE (PM) PROGRAM CONTROL AIR FILTER CORRECTIVE NA SATURATED WITH HIGH D/P CHANGED FILTER MR-0181 0IL REACTOR COOLANT POST-NEW INSTALLATION NA NRC REQUIREMENT NEW SYSTEM FABRICATING NEW SYSTEM ACCIDENT SAMPLING SYSTEM FACILITY CHANGE N0. 70-80-1 SEISMIC RESTRAINTS NEW INSTALLATION.

NA NA NA FABRICATING RESTRAINTS FACILITY CHANGE NOS. 78-84-4, 78-84-5 &

74-82-12 i

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MARCH 1982 1 of 2 INSTRUMENT AND ELECTRICAL MAINTENANCE

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LER OR NATURE OF OUTAGE MALFUNCTION EQUIPMENT MAINTENANCE NUMBER CAUSE RESULT CORRECTIVE A,CTION SECURITY CAMERA 5 CORRECTIVE NA INCORRECT FOCUS P00R PICTURE ADJUSTED FOCUS MR-0166 SECURITY CAMER 10 CORRECTIVE NA VIDICON WORN OUT DARK PICTURE REPLACED VIDICON MR-0174 SECURITY DIST. AMP CORRECTIVE NA DEFECTIVE DIODE NO PICTURE REPLACED AMPLIFIER, CHANNEL 10 MR-0105 REPAIRED SECURITY CAMERA 4 CORRECTIVE NA INTERNAL ADJUST-P00R PICTURE ADJUSTED INTERNALLY MR-0201 MENTS SECURITY CAMERA 5 CORRECTIVE NA VIDICON WORN OUT P00R PICTURE REPLACED VIDICON MR-0205 SECURITY BATTERY BANK PREVENTIVE NA UNKNOWN POOR BATTERY CELL REPLACED WARRANTEED MR-0211 BATTERY SECURITY RADIO CHARGER CORRECTIVE NA UNKNOWN NO CHARGE ON CELL CLEANED CONTACTS AND MR-0215 REPLACED LAMP REACTOR FEED PUMP IB CORRECTIVE NA DEFECTIVE TRAN-P00R CONTROL REPLACED AMP AND DRIVE CONTROL AMP AND MOTOR MR-0169 SIST0RS MOTOR TELEPHONE PAGE SYSTEM CORRECTIVE NA DEFECTIVE RELAYS P00R TRANSMISSION REPLACED RELAYS BY MR-0125 PHONE COMPANY REACTOR FEED PUMP 1A CORRECTIVE NA DEFECTIVE SCR P00R CONTROL REPLACED AMP SCR UNITS CONTROL AMP MR-0188 CONTROL FREIGHT D0OR FLOOD CORRECTIVE NA CONTAMINATED FALSE ALARM CLEANED DETECTOR AND CONTROL DETECTOR MR-0219 DETECTOR TESTED NUCLEAR CHANNELS N-5 PREVENTIVE NA TEST DUE COMPLETED TESTS COMPLETED TESTS N-5 THROUGH N-9 THROUGH N-9 SAFETY SYSTEM CH 1, 2 &

PREVENTIVE NA TEST DUE COMPLETED TESTS COMPLETED SAFETY SYSTEM H O #3 TESTS 2

=

MARCH 1982 INSTRUMENT AND ELECTRICAL MAINTENANCE 2 of 2 LER OR NATURE OF OUTAGE MALFUNCTION EQUIPMENT MAINTENANCE NUMBER CAUSE RESULT CORRECTIVE ACTION MPT MEGGER AND TRT TESTS PREVENTIVE OUTAGE DUE TO STORM, PLANT TRIP COMPLETED MPT TESTING (MAIN POWER TRANSFORMER)

MR-0223 82-06 CAUSED GROUND RELAY TRIP NUCLEAR CHANNEL N-5 CORRECTIVE OUTAGE INTERNAL INSTRU-RANGE SWITCH BALANCED SIGNAL INPUT MR-0224 82-06 MENTATION DRIFT READING 0FF TO CHASSIS OFF-GAS FLOW METER CORRECTIVE NA CONTAMINATION HIGH READ 0UT CLEANED ORIFICE ORIFICE MR-0173 WATER ACTIVITIES MONITOR CORRECTIVE NA CONTAMINATION READING DRIFTING CLEANED SWITCH AND SLIDE RECORDER MR-0196 WIRE ON RECORDER STACK MONITOR FILTER CORRECTIVE NA MISUSE BY HEALTH CAPSTAIN DRIVE REPAIRED DRIVE PINS CAPSTAIN MR-189 PHYSICS DEPT.

PINS BROKEN

NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE MARCH 1982 At the onset of the March 1982 reporting period, the reactor was at 80% Rated Thermal Power'(37 MWe-Net).

A gradual de-escalation was in progress due to the extent of core life.

On March 30, 1982 at 1847, the reactor automatically shut down from 76% Rated Thermal Power (33 MWe-Net).

The probably cause of the trip was due to a line fault in the DPC 69 KV grid, tripping _a Main Power-Transformer relay.

The reactor was taken critical at 0427 on March 31, 1982 and at 0502, automatically shut down due to Nuclear Instrument _ Channel 5 pico-ammeter being out of balance.

After corrective actions were completed, the reactor was taken critical at 1036 and the turbine was synchron-ized to the DPC grid at 2300 and escalation commenced.

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

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er 7

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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 refue.'".ng shutdown (EOC-VII) is April 9, 1982.

3.

Scheduled Date for Restart Following Refueling The tentatively scheduled date for subsequent reactor startup is May 24,1982.

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 configura-tion been reviewed by your Plant Safety Review Committee to determine whether any unreviewed safety questions are associated with the core reload (Ref. 10 CPR 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 Licensino 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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REFUELING INFORMATION REQUEST - (Cont'd) 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.

1990