ML20062G256

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Monthly Operating Rept for June 1982
ML20062G256
Person / Time
Site: LaSalle Constellation icon.png
Issue date: 07/07/1982
From: Manning P
COMMONWEALTH EDISON CO.
To:
Shared Package
ML20062G243 List:
References
NUDOCS 8208120294
Download: ML20062G256 (13)
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Text

LASALLE NUCLEAR POWER STATION UNIT I MONTHLY PERFORMANCE REPORT JUNE, 1982 C0 tim 0f1 WEALTH EDlSON COMPANY NRC DOCi'.ET N0. 050-373 LICErlSE NO. tJPF-II 8208120294 820708 PDR ADOCK 05000373 PDR R

TABLE OF CONTENTS

1. INTRODUCTION ll.

SUMMARY

OF OPERATING EXPERIENCE FOR UNIT ONE 111. PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMLNTS, AND SAFETY RELATED MAINTENANCE A. Amendments to Facility License or Technical Specifications B. Facility or Procedure Changes Requiring NRC Approval C. Tests and Experiments Requiring NRC Approval D. Corrective Maintenance of Safety Related Equipment IV. LICENSEE EVENT REPORTS V. DATA TABULATIONS A. Operating Data Report B. Average Daily Uni t Power Level C. Unit Shutdowns and Power Reductions VI. UNIQUE REPORTING REQUIREMENTS A. Main Steam Relief Valve Operations B. Control Rod Drive Scram Timing Data C. ECCS System Outages D. Off-Site Dose Calculation danual Changes E. Major Changes to Radioactive \laste Treatment System F. Changes to the Process Control Program 5

l. !NTRODUCTION The LaSalle Nuclear Power Station Unit One is a Boiling Water Reactor wi th a designed electrical output of 1078 MWe net, located in fiarsei l les, Illinois. The Station is owned by Commonwealth Edison Company. The Architect / Engineer was Sargent & Lundy, and the primary constructor was Commonwealth Edison Company.

The condenser cooling method is a closed cycle cooling pond. The plant is subject to License Number NPF-11, issued on April 17, 1982. The date of ini tial cri ticali ty was June 21. 1982. The uni t has not commenced commercial generation of power.

This report was compiled by P. F. Manning, telephone number l'15)357-6761, extension 244.

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SUMMARY

OF OPERATING EXPERIENCE FOR UNIT ONE June 21 - 3_0 Unit achieved initial criticality at 0537 hours0.00622 days <br />0.149 hours <br />8.878968e-4 weeks <br />2.043285e-4 months <br />, on June 21, 1982. This initial criticality was terminated af ter 108 minutes, with an initial period of 400 seconds. Criticality was achieved four more times during the period June 21 - 22. The reactor was shutdown on June 22 at 0115 hours0.00133 days <br />0.0319 hours <br />1.901455e-4 weeks <br />4.37575e-5 months <br /> due to NPF-11 License Condition 2.C.(4). Startup testing and maintenance on the uni t continuted through the end of the month.

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lli. PLANT OR PROCEDURE CHANGE, TESTS, EXPERIMENTS AND SAFETY RELATED MAINTENANCE A. Amendments to Facility License or Technical Specifications There were no amendnents to facility license or technical specifications during the reporting period.

B. Facility or Procedure Changes Requiring NRC Approval There were no facility or procedure changes requiring NRC approval during the reporting period.

C. Tests and Experiments Requiring NRC Approval There were no tests or experiments requiring NRC approval during the raporting period.

D. Corrective Maintenance of Safety Related Equipment The following table presents a summary of safety-related maintenance completed on Unit One during the reported period.

The headings indicated in this summary include: Work Request Numbers, LER Numbers, Component Name, Cause of Malfunctions, Results and Effects on Safe Operation, and Corrective Action.

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WORK REQUEST LER COMPONENT CAUSE OF MALFUNCTION RESULTS AND EFFECTS CORRECTIVE ACTION ON SAFE OPERATION L16218 'I B" RHR Hea t iotor burned up. Valve in required open iotor operator replaced Exchanger position. and adjusted.

L16325 82-038/01T-0 Vessel Level Scram Worn meter movement low level switch oper- Instrument replaced Gauge precluded cal ibra- able on "B" channel, and calibrated.

tion. "A" channeI fully ope ra t i ona l .

L16260 RHR Suction Valves High differential Valves could be operated Motor operators A & B. pressure across manually. replaced.

valves.

IV. LICENSEE EVENT REPORTS The following is a tabular summary of all licensee event reports for LaSalle Nuclear Power Station, Unit One, occurring d ring the reporting period, June 21 to June 30, 1982. This information is provided persuant to the reportable occurrence reporting require-ments as set forth in section 6.6.B.1 and 6.6.B.2 of the Technical Specifications.

Licensee Event Report Number Date Title of Occurrence 82-050/03L-0 6/21/82 Failure of VC "B" Tornado Damper 82-051/01T-0 6/23/82 Failure of Diesel Fire Pump "0B"

V. DATA TABULATIONS The following data tabulations are presented in this report:

A. Operating Data Report B. Average Daily Unit Power Level C. Uni t Shutdowns and Power Reductions i

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' OPERATING DATA REPORT 373 COCKET NO.

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DATE 7-7-82 P. F. Hanning COMPl.ETED BY

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Gross. HOURS IN REPORTissG PERICO:

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2. CURRENTLY AUTHORIZED POWER LEVEL (WWti:107d DESICN ELECTRICAL R ATING (MWMet):
3. POWER LEVELTO WHICH RESTRICTED (IF ANY) (MWo. Net):
4. REAs0Ns FOR RESTRICTION UF ANY1: NRC Hold at Mode 2 per Facility Operating License NPF-11 Twis mouv7N vnTo cATE CuuutATivE 5.1 5.1 5.I
5. NUM8ER OF HOURS REACTOR WAS CRITICAL ...............

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a. R EACTOR R ESERV E SHUTCCWN HOUR $ . . . . . . . . . . . . . . . . . .
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7. HOURS

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0 0 n L UdT RE5ERVE SHUTDOWN HOURS ......................

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9. GROSS THERMAL ENERGY GENERATED (MWH1 . .............

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10. GROSS ELECTRICAL ENERGY GENER ATED (MWHi . . . . . . . . . . . . .

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' 11. NET ELECTRICAL ENERGY GENER ATED (MWM) .............. .

NA NA NA
12. R EA CTO R S E RvlCE F ACTOR . . . . . . . . . . . . . . . . . . . . . . . . . .

j NA NA NA f 13. REACTOR AVAILA'elLITY F ACTOR . . . . . . . . . . . . . . . . . . . . . . .

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14. UNIT SERVICE FACTOR . . ............................

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15. UNIT AVAILABILITY F ACTOR . . . . . . . . . . . . . . . . .

NA un m l to. UNIT CAPACITY F ACTCR [Useng MDC3 . . . . . . . . . . . . . . . . . . . . . t NA NA NA

17. UNIT CAPACITY F ACTOR (Usang Dougn MWel . . . . . . . . . . . . . . . . . l NA NA NA
18. UNIT FORCED OUTAGE RATE .........................

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19. 5HUTDOWNS SCHEDULED OVER NEXT 6 MONTHS ITYPE OATE. AND QuRATION OF EACHl:

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20. IF SHUT DOWN AT END OF REPORT PERIOD. ESTIMATED CATE OF STARTuP. Uoon FORECAST ACHIEVED
21. UNITS IN TEST STATUS (PRICR TO COMMERCIAL CPERAT10N):

6-21-82 f INITI AL CRITICALITY i

- 8/1/82 INITIAL ELECTRICtTY COMMERCI AL OPERATION .

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ATTACH. MENT A AV' RAGE DAILY UNIT POWER LEVEL DOCKET NO. 050-373 tiNIT 1 DATE 7-7-82 COMPLETED BY P. F. Manning TELEPHONE- 815-357-6761 X-244 MONTH June 1982 DAY AVERAGE DAILY POWER LEVEL . DAY AVERAGE DAILY POWER LEVEL (MWe-Ne t) (MWe-Ne t) 1.

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NOT E: LaSalle is not yet licensed to produce power.

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l VI. UNIQUE REPORTING REQUIREMENTS 1

The following items are included in this report based on prior commitments to the Commission.

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I l A. Main Steam Relief Valve Operations At 1340 on June 26, the "C" safety relief valve (1821F013C) opened for no apparent reason. At the time of the incident, the "A" RHR pump was shutting down and instrument surveillance was in progress; however, an investigation revealed that the

two were unrelated to the inadvertent opening. The valve i

remained open for 40 minutes, at which time the "C" SRV control I switch on the Division 2 ADS relay board was being cycled to l

"open" then to "off". This action closed the valve. No other 1 I SRV's were involved in this incident.

l B. Control Rod Drive Scram Timing Data There was no control rod drive scram timing data for the report-Ing period, a

? C. ECCS Systems Outages There were no ECCS outages reported in LER's during this report-ing period.

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VI. Unique REPORTING REQUIREMENTS (CONTINUED)

D. Of f-Si te Dose Calculation Manual There were no changes to the Of f-Si te Dose Calculations Manual during this reporting period.

E. Radioactive Waste treatment System There were no changes to the radioactive waste treatment system during this reporting period.

F. Process Control Program There were no changes to the Process Control Program during this reporting period.

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