ML20128K627

Monthly Operating Rept for June 1985

ML20128K627
Person / Time
Site:	LaSalle
Issue date:	06/30/1985
From:	Diederich G, Rohrer R COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF ADMINISTRATION (ADM), NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
NUDOCS 8507240183
Download: ML20128K627 (16)

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LASALLE NUCLEAR POWER STATION UNIT 1 MONTHLY PERFORMANCE REPORT f

JUNE 1985 COMONWEALTH EDISON COMPANY s

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NRC DOCKET NO. 050-373 LICENSE NO. NPF-11 I'

I DR f 850630 R

5000373 h

POR 6y 4

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TABLE OF CONTENTS I.

INTRODUCTION.

II.

MONTHLY REPORT POR UNIT ONE A.

Summary of Cperating Experience i

B.

PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS, AND SAFETY RELATED MAINTENANCE 1.

Amendments to Facility License or Technical Specifications 2.

Facility or Procedure Changes Requiring NRC Approval 3.

Tests and Experiments Requiring NRC Approval 4.

Corrective Maintenance of Safety Related Equipment C.

LICENSEE EVENT REPORTS D.

DATA TABULATIONS 1.

Operating Data-Report 2.

Average Daily Unit Power Level 3.

Unit Shutdowns and Power Reductions.

E.

UNIQUE REPORTING REQUIREMENTS 1.

Main Steam Relief Valve Operations 2.

ECCS System Outages 3.

Off-Site Dose Calculation Manual Changes 4.

Major Changes to Radioactive Waste Treatment System i

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INTRODUCTION The LaSalle County Nuclear Power Station is a two-unit facility owned by Commonwealth Edison Comapny and located near Marseilles, Illinois. Each unit is a Boiling Water Reactor with a designed net electrical output of 1078 Megawatts. Vaste heat is rejected to a man-made cooling pond using the Illinois River for make-up and blowdown. The architect-engineer was Sargent and Lundy, and the primary construction contractor was Commonwealth Edision Company.

Unit one was issued operating license number NPP-ll on April 17, 1982. Initial criticality was achieved on June 21, 1982, and commercial power operation was commenced on January 1, 1984.

This report was compiled by Richard J. Rohrer, telephone number (815)357-6761 extension 575.

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II.

MONTHLY REPORT POR UNIT ONE A.

SUfflARY OF OPERATING EXPERIENCE FOR UNIT ONE June 10-29 June 10, 1235 hours0.0143 days <br />0.343 hours <br />0.00204 weeks <br />4.699175e-4 months <br />.

Reactor Critical.

June 11, 0100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br />.

Generator on-line.

June 11, 0700 hours0.0081 days <br />0.194 hours <br />0.00116 weeks <br />2.6635e-4 months <br />.

Reactor power at 26.5%.

June 11, 2300 hours0.0266 days <br />0.639 hours <br />0.0038 weeks <br />8.7515e-4 months <br />.

Reactor power at 70.9%.

June 13, 0100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br />.

Reactor power decreased to 58%

in order to manipulate control rods.

June 13, 0700 hours0.0081 days <br />0.194 hours <br />0.00116 weeks <br />2.6635e-4 months <br />.

Reactor power restored to 74.6%.

June 15, 0700 hours0.0081 days <br />0.194 hours <br />0.00116 weeks <br />2.6635e-4 months <br />.

Reactor power at 84.7%.

June 17, 1915 hours0.0222 days <br />0.532 hours <br />0.00317 weeks <br />7.286575e-4 months <br />.

Commenced normal Unit shutdown to repair Electro-Hydraulic control system.

June 18, 0500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br />.

Generator off-line.

June 18, 2300 hours0.0266 days <br />0.639 hours <br />0.0038 weeks <br />8.7515e-4 months <br />.

Reactor power at 18.0%,.

Generator off-line.

June 19, 0605 hours0.007 days <br />0.168 hours <br />0.001 weeks <br />2.302025e-4 months <br />.

Generator on-line.

June 19, 0807 hours0.00934 days <br />0.224 hours <br />0.00133 weeks <br />3.070635e-4 months <br />.

Pcwer reduction commenced due to loss of cooling to transformer 1E.

June 19,.0900 hours0.0104 days <br />0.25 hours <br />0.00149 weeks <br />3.4245e-4 months <br />.

Power increased after cooling was restored to transformer lE.

June 19, 1050 hours0.0122 days <br />0.292 hours <br />0.00174 weeks <br />3.99525e-4 months <br />.

Turbine trip due to error in troubleshooting.

i June 19, 1135 hours0.0131 days <br />0.315 hours <br />0.00188 weeks <br />4.318675e-4 months <br />.

Turbine on-line.

June 21, 1500 hours0.0174 days <br />0.417 hours <br />0.00248 weeks <br />5.7075e-4 months <br />.

Reactor power at 72%.

June 22, 0445 hours0.00515 days <br />0.124 hours <br />7.357804e-4 weeks <br />1.693225e-4 months <br />.

Reactor pcwer decreased to 58.3%

in order to manipulate control rods.

June 24, 0700 hours0.0081 days <br />0.194 hours <br />0.00116 weeks <br />2.6635e-4 months <br />.

Reactor power restored to 86%.

June 24, 0745 hours0.00862 days <br />0.207 hours <br />0.00123 weeks <br />2.834725e-4 months <br />.

Slight power reduction commenced due to oscillations in the number 3 Turbine Control Valve.

June 29, 0700 hours0.0081 days <br />0.194 hours <br />0.00116 weeks <br />2.6635e-4 months <br />.

Reactor power at 91.5%.

June 29, 0815 hours0.00943 days <br />0.226 hours <br />0.00135 weeks <br />3.101075e-4 months <br />.

Reactor scram on loss of CRD flow. The reactor had been critical for 451 hours0.00522 days <br />0.125 hours <br />7.457011e-4 weeks <br />1.716055e-4 months <br /> and 40 minutes in June so far.

June 30 June 30, 0900 hours0.0104 days <br />0.25 hours <br />0.00149 weeks <br />3.4245e-4 months <br />.

Reactor critical.

June 30, 2300 hours0.0266 days <br />0.639 hours <br />0.0038 weeks <br />8.7515e-4 months <br />.

Reactor power at 6.3%; Generator off-line.

The reactor was critical for 466 hours0.00539 days <br />0.129 hours <br />7.705026e-4 weeks <br />1.77313e-4 months <br /> and 40 minutes in June.

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Be PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS AND SAFETY RELATED MAINTENANCE.

1.

Amendments to facility license or Technical Specification.

There were no amendments to the facility license or Technical Specifications during this reporting period.

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Facility or procedure changes requiring NRC approval.

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There were no facility or procedure changes requiring NRC approval during this reporting period.

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3.

Tests and Experiments requiring NRC approval.

There were no tests or experiments requiring NRC approval during i

this reporting period.-

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Corrective maintenance of safety related equipment.

1 The following table (Table 1) presents a summary of safety-related maintenance completed on' Unit One during the reporting period. The headings indicated in this stannary include: Nork Request number, Component Name, Cause of j

Malfunction, Results and Effects on Safe Operation, and Corrective Action.

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m TABLE 1 COICECTIVE MAINTENANCE OF -

SAFETY RELATED BQUIPMEMT WORK REQUEST CONONENT CAUSE OF MALFUNCTION RESULTS AND EFFECTS..

-CORRECTIVE ACTION

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ON SAFE PLANT OPERATION L36208 Division III 125 Volt Faulty cell.

Potential for degraded voltage Replaced faulty cell.

Batteries cell number of Division III DC bus.

28.

L42234 Auxiliary Electrical Jammed damper at. inlet Charcoal filter in continuous Sent damper to vendor.

Room.HVAC Filter Train to charcoal filter, use.

for repairs. Installed "A".

upon return.

L45143 Reactor Low Pressure Leaky instrument stop

'No Significant Effects.

Replace Valve.

RCIC Isolation-valve.

Switches.

L46678 Auxiliary Electrical Damper at inlet to Could not fully close damper.

Repaired Linkage.

Bquipment RooG INAC charcoal filter had a Filter train "A".

broken linkage.

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L48201, Valve IE12-F053A.

Failed Motor-in operator.

Could not remotely operate Replaced Motor.

valve; breaker kept tripping.

L48319 Reactor Vessel Low-Five-Valve Manifold No Significant effects.

Replaced five-valve Low-Low Level LPCS/

Leaked.

manifold.

l RHR Initiation, ADS Permissive..

L49353 Diesel Generator B Would not trip.

Diesel lost.some protection Replaced switch.

-High Water Temperature from overheating.

Switch.

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L49358 Division II Battery Charge Current Limiter out-Potential to overcharge Replaced printed

Charger, of-tolerance.

Batteries, circuit boards.

L49432 HCU Accumulator for Leaky Valve.

Potential to cause failure to Replaced valve.

CRD 02-27.

scram this rod if combined with other events.

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TABLE 1 CORRECTIVE MAINTENANCE OF SAFETY RELATED EQUIPMENT 9

WORK REQUEST COMPONENT CAUSE OF MALFUNCTION RESULTS AND EFFECTS CORRECTIVE ACTION ON SAFE PLANT OPERATION L49440 "B" Narrow Range Reference line partially Incorrect reading.

Back filled reference Level Indication, empty.

line.

L49472 HCU Accumulator for Leaky Valve.

Potential to cause failure Replaced Valve.

- CRD 10-31.

to scram this rod if combined-with other. events.

L49523 "A" Rod-Block Monitor. Blown fuses.

Rod Block Monitor "A" did not Replaced fuses, read any local power range monitors.

L49705

- RCIC High vessel Out-of-Tolerance.

Signal to stop RCIC steam Recalibrated switch.

Level Switch, supply not generated when it should have been.

L49855-B RHR Water leg pump Worn Spring.

Would not fully close.

Replaced spring and discharge control gaskets.

valve.

L49905 "D" Inboard MSIV Plow indicator was dirty.

Incorrect. Reading.

Cleaned indicatior.

Leakage Control Flow Indication.

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LICENSEE EVENT REPORTS The following is a tabular sununary of all licensee event reports for LaSalle Nuclear Power Station, Unit One, logged during the reporting period, June 1 through June 30, 1985. This information is provided pursuant to the reportable occurrence reporting requirements as set forth

i in 10CFR 50.~13.

Licensee Event Report Nusaber Date Title of Occurrence 85-044-00 5-9-85 Chlorine Detector Actuation.

85-045-00 5-31-85 Manual Scram Due to Loss of Circulating Water.

85-046-00 6-17-85 Loss of both Diesel Fire Pumps.

85-047-00 6-10-85 Missed off-gas Hydrogen Sample, Document 0043r/0005r

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

1.

Operating Data Report l

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Average Daily Unit Power Level

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Unit Shutdowns and Power Reductions i

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OPERATING DATA REPORT DOCKET NO. 050-373 UNIT LaSalle One DATE July 10, 1985 COMPLETED BY Richard J. Rohrer TELEPHONE (815)357-6761 1

OPERATING STATUS 1.

REPORTING PERIOD: JUNE, 1985 GROSS HOURS IN REPORTING PERIOD: 720 2.

CURRENTLY AUTHORIZED POWER LEVEL (MWt):3323 MAX DEPEND CAPACITY (MWe-Net): 1036 DESIGN ELECTRICAL RATING (MWe-Net):1078 3.

POWER LEVEL TO WHICH RESTRICTED (IF ANY) (MWe-Net):

N/A 4.

-REASONS FOR RESTRICTION (IP ANY):N/?.

THIS MONTH YR TO DATE CUMULATIVE 5

NUMBER OF HOURS REACTOR WAS CRITICAL 466.7 3508.7 9790 6.

REACTOR RESERVE SHUTDOWN HOURS 0.0 102.9__

1269 ____

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HOURS GENERATOR ON LINE 405.3 3374.5 9431 8.

UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 0.0 9.

GROSS THERMAL ENERGY GENERATED (ItfH) 1009176 9443063 26266352 10.

GROSS ELEC. ENERGY GENERATED (MWH) 321004 3109769_

8580412 11.

NET ELEC. ENERGY GENERATED (MWH) 307031 2994945 8190007 12.

REACTOR SERVICE FACTOR 64.8%

- 80.3%

74.4%

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REACTOR AVAILABILITY FACTOR 64.8%

82.7%

84.1%

14.

UNIT SERVICE FACTOR

'56.3%

77.3%

71.7%

15.

UNIT AVAILABILITY FACTOR

, 56.3%

77.3%

71.7%

16.

UNIT CAPACITY FACTOR (USING MDC) 41.2%

66.'%

60.1%

17.

UNIT CAPACITY FACTOR (USING DESIGN MWe) 39.6%

63.6%

57.8%

18.

UNIT FORCED OUTAGE RATE 43.7%

17.4%

15.5%

19.

SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH)

Unit one is scheduled for a refueling, maintenance, modification, and surveillance outage beginning September 3, 1985 and lasting 26 weeks.

20.

IF SHUT IJOWN AT END OF REPORT PERIOD, BSTIMATED DATE OF STARTUP: July 1, 1985 l

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2. AVERAGE DAILY UNIT POWER LEVEL DOCKET NO: 050-373 UWIT: LASALLE ONE DATE: July 10, 1985 COMPLETED BY: Richard J. Rohrer TELEPHONE: (815) 357-6761 MONTH: JUNE, 1985 DAY AVERAGE DAILY POWEk LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) j 1.

-6 17.

855 2.

-7 18.

27 3

-5 19.

96 4.

-6 20.

238 5.

-8 21.

738 6.

-9 22.

739 7.

-7 23.

832 8.

-6 24.

891 9.

-7 25.

889 10.

-14 26.

885 s

11.

357 27.

883 12.

775 28.

875 13.

797 29.

313 14. __ _ _

902 30.

-16 15.

897 16.

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ATTACHMENT E j

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UNIT SHUTDOWNS AND POWER REDUCTIONS

'I DOCKET NO. 050-373 UNIT NAME LaSalle One DATE JULY 10. 1985' REPORT MONTH JULY 1985 COMPLETED BY Richard J. Rohrer-TELEPHONE (815)357-6761

. METHOD OF TYPE SHUTTING DOWN F: FORCED DURATION THE REACTOR OR CORRECTIVE NO.

, DATE S: SCHEDULED (HOURS)

REASON REDUCING POWER ACTIONS /COf9 TENTS 10 -

-850531 P

241.00 A

2 Manually scrammed reactor following flooding of Lake Screen House.

11 850618 F-25.08 8

1 Took generator off-line to troubleshoot oscillations in Number 3 Turbine control Valve.

12 850619 F

0.75 G

4 Turbine trip on.high

. level signal during troubleshooting of "B" Level Switch.

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850620 F-8.08 B

1 Took generator off-line to replace oil trip solenoid on turbine.

14 850629 F

39.75 A

3 Automatic scram caused by loss of CRD header flow when one CRD pump failed to remain "ON" after starting.

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E.

UNIQUE REPORTING REQUIREMENTS

1. Safety / Relief valve operations for Unit One.

VALVES NO & TYPE PLANT DESCRIPTION DATE ACTUATED ACTUATION CONDITION OF EVENT 6-1-85 IB21-F013M 1 Manual 170 psig Manually opened IB21-F013N 1 Manual 110 psig successively to provide IB21-F013F 1 Manual 85 psig controlled cool-down of 1821-F013R 1 Manual 115 psig the reactor following IB21-F013S 1 Manual 115 psig Main Steam Line Isolation.

Valves IB21-F013 A,B,C,D,E,F,G,H, and L were also actuated as part of this event..These actuations occurred on the evening of 5-31-85 and are reported in the Monthly Report for May, 1985.

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BCCS Syztems.Outagea The-following outages were taken on ECCS Systems during the-reporting period.

OUTAGE NO.

EQUIPMENT PURPOSE OF OUTAGE 1-472-85 IB Diesel Generator Surveillance.

1-479-85 IB Diesel Generator Testing.

i Cooling Water System.

1-480-85 HPCS Diesel Generator Testing.

Fuel Oil Transfer Pump.

1 1-483-85 lE12-F099 A & B Replace Handswitch.

l-489-85 "B" RHR Service Water Decontamination.

Process Radiation Monitor.

1-492-85' HPCS Suction Valve from Isolate Leak.

cycled condensate and full flow test valve.

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l-505-85 Shutdown Cooling suction Testing.

Header.

l-508-85 RHR Pump "A".

. Sample oil.

1-512-85 HPCS Pump.

Sample and change oil.

1-51'l-85 "B" RHR Service Water Decontamiantion.

Process Radiation Monitor.

1-523-85 1E12-F332A Throttle VaIve.

1-539-85 B/C RHR Water Leg Pump.

Repair check valve.

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1-571-85 "A" Diesel Generator and Change oil in pump.

cooling water pump.

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3.

Off-Site Dose Calculation Mar.ual There were no changes to the off-site dose calculation Manual during this reporting period.

4.

Radioactive Waste Treatiment Systems.

There were no significant changes to the radioactive waste treatineint system during this reporting period.

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v Commonwealth Edison L. Salla County Nuclear St; tion Rural Route #1. Box 220 Marseilles, Illinois 61341 Telephone 815/357-6761 July 10, 1985 Director, Office of Management Information and Program Control United States Nuclear Regulatory Commission Washington, D.C.

20555 ATTN: Document Control Desk Gentlemen:

Enclosed for your information is the monthly performance report covering LaSalle County Nuclear Power Station for the period June 1 through June 30, 1985.

Very truly yours,

'G J. Diederich Station Manager LaSalle County Station GJD/RJR/cth Enclosure xc:

J. G. Keppler, NRC, Region III NRC Resident Inspector LaSalle Gary Wright, Ill. Dept. of Nuclear Safety D. P. Galle, CECO D. L. Farrar, CECO INPO Records Center Ron A. Johnson, PIP Coordinator SNED J. E. Ellis, GE Resident J. M. Nowicki, Asst. Comptroller H. E. Bliss, Nuclear Fuel Services Manager C. F. Dillon, Senior Financial Coordinator, LaSalle QLc\\

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