ML20112A552

Monthly Operating Repts for Jan 1985

ML20112A552
Person / Time
Site:	LaSalle
Issue date:	01/31/1985
From:	Diederich G, Dus R COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF ADMINISTRATION (ADM), NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
NUDOCS 8503180357
Download: ML20112A552 (29)

Text

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4 LASALLE NUCLEAR POWER STATION UNIT 1 MONTHLY PERPORMANCE REPORT JANUARY 1985 4

C00m0NWEALTH EDISON COMPANY NRC DOCKET NO. 050-373 t

LICENSE NO. NPF-11 i

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Doctament 0043r/0005r

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INTRC9UCTION The LaSalle Nuclear Power Station is a Two Unit Facility Located in Marseilles, Illinois. Each Unit is a Boiling Nater Reactor with a designed electrical output of 1078 j

MWe net. The Station is owned by Cosmoonwealth Edison Company. The Architect / Engineer was Sargent & Lundy, I

and the primary construction contractor was Cosanonwealth j

Edison company.

The condenser cooling method is a closed cycle cooling l

pond. Unit one is subject to License Number NPF-11, issued on April 17, 1982. The date of initial criticality was June 21, 1982. Unit Tteo is subject to license number NPF-18, issued on December 16, 1983. The date of initial criticality was March 10, 1984.

This report was compiled by Randy S. Dus telephone i

number (815)357-6761, extension 324.

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TAOLE OF CONTENTS 1.

INTRODUCTION II.

MONTHLY REPORT FOR UNIT ONE A.

Susumary of Operating Experience B.

PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS, AND SAFETY RELATED MAINTENANCE i

1.

Amendments to Facility License or Technical Specifications 2.

Facility or Proct. dure 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

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MONTHLY REPORT POR UNIT ONE A.

SUIGERY OF OPERATING EXPERIENCE FOR UNIT ONE i

f JANUARY 1-5 Jan. 1, 0001 hours1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> - Reactor power at 90%.

Jan. 5, 1310 hours0.0152 days <br />0.364 hours <br />0.00217 weeks <br />4.98455e-4 months <br /> - Reactor manually scrammed due to a generator field ground. The reactor was critical for 109 hours0.00126 days <br />0.0303 hours <br />1.802249e-4 weeks <br />4.14745e-5 months <br /> and 10 minutes.

1 JANUARY 6-31 Jan. 6, 1840 hours0.0213 days <br />0.511 hours <br />0.00304 weeks <br />7.0012e-4 months <br /> - Reactor critical.

i Jan. 7, 0615 hours0.00712 days <br />0.171 hours <br />0.00102 weeks <br />2.340075e-4 months <br /> - Generator synchronized to grid.

.i Jan. 7, 0700 hours0.0081 days <br />0.194 hours <br />0.00116 weeks <br />2.6635e-4 months <br /> Reactor power at 36%.

Jan. 8, 0700 hours0.0081 days <br />0.194 hours <br />0.00116 weeks <br />2.6635e-4 months <br /> - Reactor power at 71%.

Jan. 11, 1500 hours0.0174 days <br />0.417 hours <br />0.00248 weeks <br />5.7075e-4 months <br /> - Reactor power at 94%.

Jan. 13, 0145 hours0.00168 days <br />0.0403 hours <br />2.397487e-4 weeks <br />5.51725e-5 months <br /> - Reactor power at 85%.

j Jan. 26, 0700 hours0.0081 days <br />0.194 hours <br />0.00116 weeks <br />2.6635e-4 months <br /> - Reactor power was reduced to 34%

i for a rod sequence change.

Jan. 26, 1035 hours0.012 days <br />0.288 hours <br />0.00171 weeks <br />3.938175e-4 months <br /> - The main turbine was manually tripped for maintenance work on the 83 turbine control valve.

Jan. 26, 1803 hours0.0209 days <br />0.501 hours <br />0.00298 weeks <br />6.860415e-4 months <br /> - Generator synchronized to grid.

Jan. 27, 0820 hours0.00949 days <br />0.228 hours <br />0.00136 weeks <br />3.1201e-4 months <br /> - Reactor power raised to 58%.

Jan. 27, 2800 hours0.0324 days <br />0.778 hours <br />0.00463 weeks <br />0.00107 months <br /> - Reactor power at 72%..

jl Jan. 30, 1600 hours0.0185 days <br />0.444 hours <br />0.00265 weeks <br />6.088e-4 months <br /> - Reactor power at 90%. The reactor was critical for 714 hours0.00826 days <br />0.198 hours <br />0.00118 weeks <br />2.71677e-4 months <br /> and 30 minutes.

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PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS AND SAFETY RRLATED MAINTENANCE.

1.

Amendments to facility license or Technical Specificatica.

Amendment No. 20-This amendment eliminates the Reactor Water Cleanup pump room ambient and differential temperature monitoring requirments.

2.

Facility or procedure changes requiring NRC approval.

There were no facility or procedure changes requiring NRC approval.

3.

Tests and Experiments requiring NRC approval.

There were no tests or experiments requiring NRC approval.

4.

Corrective maintenance of safety related equipment.

The following table (Table 1) presents a summary of se!.ety-related maintenance completed on Unit One during the rmvirting period. The headings indicated in this summary include: Work Request numbers, LER numbers, Component Name, cause of Malfunction, Results and Effects on Safe Operation, and Corrective Action, i

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TABLE 1 CORRECTIVE MAINTENANCE OF SAFETY RELATED EQUIPMENT WORK REQUEST COMPG'.iENT CAUSE OF MALFUNCTION RESULTS AND EFFECTS CORRECTIVE ACTION ON SAFE OPERATION L35771 Drywell penetration Penetration leaks excess Penetrations required to be Recharged penetration No. E-32.

ively.

fully charged.

L39371 RHR heat exchanger Recalibrate associated Instruments required to be Calibrated instru-recalibrations.

instrumentation.

calibrated periodically.

mentation.

L43602 IE12-F009 Shutdown Overload reset pushbutton Not able to reset thermal Remounted reset push-Cooling suction is-does not contact OL reset overloads button.

olation valve due to misalingnment.

L44022 VC/VE ammonia de Chescassette tape Preventative maintenance Replaced mechanism tector transport carriage mechanism beginning to corrode.

L44787 VE return fan Damper would not open, Inadequate Aux. Elec. Equip.

Exercised sticking isolation damper preventing the return room ventilation.

limit switch and fan from running.

cycled damper.

L44892 Div I Post LOCA 02 Recorder failed down-Div. II still operable.

Recalibrated per monitor scale.

LIS-PC-07.

L44982 "B" APRM 5 volt power Power supply failed No APRM indication from channel Replaced power supply supply.

"B".

L45019 A Train "B" ammonia Ammonia detector failed Required to be operable.

Replaced master fault detector.

to trip during LIS-VC-053.

lamp and flow lamp &

cleaned optics.

L45062 "F" APRM 5' volt power Power supply failed No APRM indication from channel Replaced power supply, supply.

"F".

L45107 PCIS Level switch

. Switch out of calibration Actuates earlier than Performed applicable calibration sheets dictate portioe of LIS-NB-102 DOCUMENT 0044r/0005r

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TABLE 1 CORRECTIVE MAINTENANCE OF SAFETY RELATED EQUIPMENT WORK REQUEST COMPONENT CAUSE OF MALFUNCTION RESULTS AND EFFECTS CORRECTIVE ACTION ON SAFE OPERATION L45112

1. 2 control Valve Limit Switch actuating could not get half-scram when Replaced missing limit

-ARM missing.

CV#2 closed during LOS-RP-M4.

switch actuating ape.

L45363 Suppression Pool Control Room pool level Inaccurate suppression pool Recalibrated Loop Level recorder indicating lower than level indication.

Per LIS-CM-01, local sight glass.

'L45603

.SBGT WRGM SBGT WRGM Inoperable.

Hi range Of SBGT WRGM has Cleaned power supply erratic signal.

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LICENSEE EVENT REPORTS The following is a tabular suunnary of all licensee event reports for LaSalle Nuclear Power Station, Unit One, occurring during the reporting period, January 1 through January 31, 1985. This information is provided pursuant to the reportable occurrence reporting requirements as set forth in 10CFR 50.73.

Licensee Event Report Number Date Title of Occurrence 84-086-00 9/27/84 Radweste Discharge With Incorrect Monitor Setpoint.

84-087-00 12/26/84 Suppression Pool High Level.

84-088-00 12/2/84 Potential Failure of Containment Penetration.

84-089-00 01/09/85 Actuation of VC Amusonia Detector.

84-090-00 01/09/85 HPCS Transfer to Suppression Pool on HI Suppression Pool Level.

84-091-00 1/11/85 Actuation of B VC Alumonia Detector.

i 84-092-00 12/30/84 Unsecured Hi-Rad Door.

84-093-00 12/19/84 Unsecured Hi-Rad Area.

I 85-001-00 1/2/85 Reactor Vessel Hi-Level HPCS Injection Valve Closure Switch Out of Cal.

85-002-00 1/5/85 Reactor Scram on Low Level.

85-003-00 1/6/85 Reactor Water Cleanup Isolation.

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

1.

Operating Data Report 2.

Average Daily Unit Power Level 3.

Unit shutdowns and Power Reductions i

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OPERATING DATA REPORT DOCKET NO. 050-373 UNIT LaSalle One DATE February 10, 1985 COMPLETED BY Randy S. Dus TELEPHONE (815)357-6761 OPERATING STATUS 1.

REPORTING PERIOD: January 1985 GROSS HOURS IN REPORTING PERIOD: 744 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 (IF ANY):

THIS MONTH YR TO DATE CUMULATIVE 5

NUMBER OF HOURS REACTOR WAS CRITICAL 714.5 714.5 6995 6.

REACTOR RESERVE SHUTDOWN HOURS 29.5 29.5 1195 7.

HOURS GENERATOR ON LINE 695.5 695.5 6751 8.

UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 0.0 9.

GROSS THERMAL ENERGY GENERATED (MWH) 1884113 1884113 18707402 10.

GROSC ELEC. ENERGY GENERATED (MWH) 618288 618288 6088931 11.

NET ELEC. ENERGY GENERATED (MWH) 594395 594395 5789457 12.

REACTOR SERVICE FACTOR 96.0%

96.0%

73.4%

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REACTOR AVAILABILITY FACTOR 100%

100%

86.0%

14.

UNIT SERVICE FACTOR 93.5%

93.5%

70.9%

15.

UNIT AVAILABILITY FACTOR 93.5t 93.5%

70.9%

16.

UNIT CAPACITY FACTOR (USING MDC) 77.1%

77.1%

58.7%

17.

UNIT CAPACITY FACTOR (USING DESIGN MWe) 74.1%

74.1%

56.4%

18.

UNIT FORCED OUTAGE RATE

_6.5%

6.5%

14.3%

19.

SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH) 20.

IF SHUT DOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP: N/A Document 0043r/0005r

4 20 AVERAGE DAILY UNIT POWER LEVEL DOCKET NO: 050-373 1

UNIT: LASALLE ONE DATE: FEBRUARY 10, 1985 COMPLETED BY: Randy S. Dus TELEPHONE: (815) 357-6761 MONTH: JANUARY, 1985 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1.

1030 17, 920 2.

1030 18.

912 3

972 19.

916 4.

1026 20.

918 5.

588 21.

915 6.

0 22.

915 7.

182 23.

917 8.

709 24, 916 9.

641 25.

870 10.

788 26.

233 11.

979 27.

621 12.

940 28.

611 13.

914 29.

779 14.

849 30.

944 15.

895 31.

944 16.

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UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 050-374 UNIT NAME LaSalle One DATE February 10, 1985 REPORT MONTH JANUARY 1985 COMPLETED BY Randy S. Dus 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 1

85/01/5 F

41.1 A

2 While the unit was at approximately 99%

power, a generator field ground occurred due to high stator cooling water conductivity.

2 85/01/26 F

7.5 A

1 The main turbine was tripped so that maintenance could be performed on the #3 control valve.

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ECCS Systems Outtg:s The following outtgas were t& kin on ECCS Systems during

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the reporting period.

OUTAGE NO.

BOUIPMENT PURPOSE OF OUTAGE 1-3-85 1E12-C300D Megger Motor i

1-4-85 1E12-C300A Megger Motor l

1-6-85 lE12-F068A Repair Valve l-15-85 1E22-C302B Overhaul Diesel 1-16-85 1E22-C302B Overhaul Diesel 1-15-85 IE12-C300A Megger Motor 1-41-85 1A D/G Lubrication 1-42-85 1A D/G Lubrication 1-44-85 1E12-F009 Repair Breaker 1-48-85 RHR Water Leg Pump Lubrication 1-49-85 "B" RHR Service LEP-GM-120 Water Pump 1-52-85 "A" RHR Pump Lubrication i

3.

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

4.

Radioactive Waste Treatment Systems.

There were no changes made to the radioactive waste treatment system during this reporting period.

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UNIQUE REPORTING REQUIREMENTS

1. Safety / Relief valve operations for Unit One.

VALVES NO & TYPE PLANT DESCRIPTION DATE ACTUATED ACTUATION CONDITION OF EVENT There were no safety relief valve actuations for this reporting period.

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o LASALLE NUCLEAR POWER STATION UNIT 2 i

MONTHLY PERFORMANCE REPORT JANUARY 1985 COletONWEALTH EDISON COMPANY NRC DOCKET NO. 050-374 LICENSE NO. NPF-18 I

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k TABLE OF CONTENTS I.

INTRODUCTION II.

MONTHLY REPORT FOR UNIT TWO A.

Summary of Operating Experience 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.

Safety /Rellef 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 Nuclear Power Station is a Two Unit Facility Located in Marseilles, Illinois. Each Unit is a Boiling Water Reactor with a designed electrical output of 1078 MWe net. The Station is owned by Comunonwealth Edison company. The Architect / Engineer was Sargent & Lundy, and the primary construction contractor was Commonwealth Edison Company.

The condenser cooling method is a closed cycle cooling pond. Unit One is subject to License Number NPF-ll, issued on April 17, 1982. The unit commenced commercial generation of power on,Tanuary 1, 1984. Unit Two is subject to license number NPF-18, issued on December 16, 1983. The date of initial criticality was March 10, 1984.

This report was compiled by Randy S. Dus, telephone number (815)357-6761, extension 324.

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MONTHLY REPORT FOR UNIT TWO A.

SUfMARY OF OPERATING EXPERIENCE FOR UNIT TWO s

JANUARY 1-31 Jan. 1, 0001 hours1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> - The unit started the reporting period at 90% power.

Jan. 4, 0700 hours0.0081 days <br />0.194 hours <br />0.00116 weeks <br />2.6635e-4 months <br /> - Reactor power at 99%.

Jan. 4, 2200 hours0.0255 days <br />0.611 hours <br />0.00364 weeks <br />8.371e-4 months <br /> - Reducing Reactor power for a Rod Sequence exchange.

Jan. 5, 0700 hours0.0081 days <br />0.194 hours <br />0.00116 weeks <br />2.6635e-4 months <br /> - Reactor power at 70%.

Jan. 6, 0700 hours0.0081 days <br />0.194 hours <br />0.00116 weeks <br />2.6635e-4 months <br /> - Reactor power at 82%.

Jpn. 9, 1400 hours0.0162 days <br />0.389 hours <br />0.00231 weeks <br />5.327e-4 months <br /> - Reactor power at 97%.

Jan. 21, 1920 hours0.0222 days <br />0.533 hours <br />0.00317 weeks <br />7.3056e-4 months <br /> - Reactor power reduced to 75% due to stuck RBCCW control valve.

Jan. 22, 2300 hours0.0266 days <br />0.639 hours <br />0.0038 weeks <br />8.7515e-4 months <br /> - Reactor power at 96%. The reactor was critical for 744 hours0.00861 days <br />0.207 hours <br />0.00123 weeks <br />2.83092e-4 months <br />.

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PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS AhD SAFETY RELATED MAINTENANCE.

1.

Amendments to facility license or Technical Specifications.

Amendment No. 7 - This amendment eliminates the Reactor Water Cleanup pump room ambient and differential temperature monitoring requirements.

2.

Facility or procedure changes requiring NRC approval.

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

j 3.

Tests and experiments requiring NRC approval.

There were no tests or experiments requiring NRC approval during the reporting period.

4.

Corrective Maintenance of Safety Related Equipment.

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 summary include: Work Request numbers, LER Numbers, Cor,x)nent Name, cause of malfunction, results and effects on safe operation, and corrective action.

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e-TABLE 1 CORRECTIVE MAINTENANCE OF SAFETY RELATED EQUIPMENT W RK REQUEST COMPONENT CAUSE OF MALFUNCTION RESULTS AND EFFECTS CORRECTIVE ACTION ON SAFE OPERATION L35213 RCIC pump suction Pressure gauge giving false Gauge is reading approximately Recalibratd Gage.

pressure gauge.

indication when pump is not 50 psig low.

running L36890 "2B" Diesel Generator Remove and renew the lube The lube oil has been diluted Changed oil filter oil & lube oil filter.

with fuel oil.

and oil.

L39972 VG Filter train High DP across demister Actual measured DP is sat-Installed new probes causing control room isfactory. Improper flow and recalibrated.

alarms.

elements installed.

L41953 C RHR pump Inspect pump / driver Preventive maintenance Removed coupling coupling to be sure that spacer and exposed set screws are in place.

nut & set screws.

Found to be tight.

L44543 B RHR service water Hi back ground in area Unable to get true service Added more lead PRM.

of PRM.

water indication.

blankets around PRM.

L44856 Div. II Post Loca Reading zero locally and Ox/ gen concentration required Replaced O2 analyzer Monitor 2% in control room.

to be known at all times.

amp card and recali-brated.

L44907 24 point cam /2PL15J Sample pump cycles on Continuous air monitor required Tightened vacuum leaks and off every 30 seconds to be sampling at all times.

at flow indicator pipe connections.

Recalibrated Hi-Lo trip switches.

L45024 LPRM 24-41 LPRM drifting low Showing downscale reading.

New current gain applied to detector channel.

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CORRECTIVE MAINTENANCE OF g

SAFETY RELATED EQUIPMENT WORK REQUEST COMPONENT CAUSE OF MALFUNCTION RESULTS AND EFFECTS CORRECTIVE ACTION ON SAFE OPERATICN L45185 Suppression Pool High indicated level Inaccurate pool level indication Backfilled reference Level recorder.

compared to local sight leg.

glass and other instruments.

L45235 HPCS D/G Will not start due to low Required to be operable.

Found oil filter oil pressure.

installed backwards.

L45314 IRM/APRM flux Pen is very slow to respond Untrue flux indications.

Tightened carriage recorder assembly, cleaned and lubricated gears.

L45383 Excess Flow Check Vlv Check valve is stuck Results in a incorrect Disassembled valve, suppression pool level, cleaned and re-assembled.

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4 C.

LICENSEE EVENT REPORTS The following is a tabular summary of all licensee event reports for LaSalle Nuclear Power Station, Unit Two, occurring during the reporting Period, January 1 through January 31, 1985.

This information is provided pursuant to the reportable occurrence reporting requirements as set forth in 10CFR 50.73.

Licensee Event Report Number Date Title of Occurrence 84-082-00 12/7/84 Uncontrolled Access to High Radiation Area.

84-083-00 12/8/84 Primary Containment Vacuum Breaker Cycled.

84-084-00 12/14/84 Failure of RCIC high Temperature Isolation Switch.

84-085-00 12/14/84 Scram from Hi Vibration Turbine Trip.

84-086-00 1/8/85 Strut #RH14-2820X Inoperable.

84-087-00 1/7/85 High Suppression Pool Level-HPCS Suction Swap.

84-088-00 1/9/85 Vacuum Breaker a Cycled.

84-089-00 12/15/84 Reactor Water Cleanup Hi Delta Flow Isolation.

84-090-00 12/16/84 Vacuum Breaker Cycling.

84-091-00 12/17/84 vacuum Breaker Actuation.

84-092-00 12/17/84 vacuum Breaker cycled.

84-093-00 12/20/84 Reactor Water Cleanup Hi Delta Flow Isolation.

85-001-00 1/7/85 HPCS Suction Valves Swapped.

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

1. Operating Data Report

2. Average Daily Unit Power Level

3. Unit Shutdowns and Power Reductions 4

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1. OPERATING DATA REPORT DOCKET NO. 050-374 UNIT LaSalle Two DATE February 10, 1985 COMPLETED BY Randy S. Dus TELEPHONE (815)357-6761 i

OPERATING STATUS 1.

REPORTING PERIOD: January 1985 GROSS HOURS IN REPORTING PERIOD: 744 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):

THIS MONTH YR TO DATE CUMULATIVE 5

NUMBER OF HOURS REACTOR WAS CRITICAL 744 744 2355.8 6.

REACTOR RESERVE SHUTDOWN HOURS 0.0 0.0 125.3 7.

HOURS GENERATOR ON LINE 744 744 2281.4 8.

UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 0.0 9.

GROSS THERMAL ENERGY GENERATED (MWH) 236220*/

2362207 6874799 10.

GROSS ELEC. ENERGY GENERATED (MWH) 785448 785448 2270443 11.

NET ELEC. ENERGY GENERATED (MWH) 759220 759220 2151337 12.

REACTOR SERVICE FACTOR 100%

100%

93.5%

13.

REACTOR AVAILABILITY FACTOR 100%

100%

98.5%

14.

UNIT SERVICE FACTOR 100%

100%

90.5%

15.

UNIT AVAILABILITY FACTOR 100%

100%

90.5%

16.

UNIT CAPACITY FACTOR (USING MDC)_

98.5%

98.5%

82.4%

17.

UNIT CAPACITY FACTOR (USING DESIGN MWe) 94.7%

94.7%

79.2%

18.

UNIT FORCED OUTAGE RATE 0%

0%

9.5%

19.

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

There is an outage scheduled to begin on March 1, 1985 for maintenance and surveillances. This outage is expected to last approximately nine weeks.

20.

IF SHUT DOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP N/A i

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2. AVERAGE DAILY UNIT POWER LEVEL 0

DOCI:ET NO: 050-374 UNIT: 'aSALLE TWO DATE: February 10,1985 COMPLETED BY: Randy S. Dus TELEPHONE: (815) 357-6761 MONTH: January 1985 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1.

1032 17.

1066 -

2.

1038 18.

1054 3

1026 19.

1062 4.

1046 20.

1063 5.

702 21.

1015 6.

747 22.

971 7.

904 23.

1061 8.

1048 24.

1062 9.

1042 25.

1060 10.

1054 26.

1067 11.

1038 27.

1062 12.

1037 28.

1064 13.

1041 29.

1062 14.

1000 30.

1059 15.

1035 31.

1060 16.

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ATTACHMENT E A*

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UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 050-374 UNIT NAME LaSalle Two DATE FEBRUARY 10, 1985 REPORT MONTH JANUARY 1985 COMPLETED BY Randy S. Dus 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 /COPMENTS 1

85/01/05 S

0.0 H

5 Power reduction for rod sequence exchange.

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UNIQUE REPORTING REQUIREMENTS 1.

Safety / Relief Valve Operations for Unit Two.

DATE VALVES NO & TYPE PLANT DESCRIPTION ACTUATED ACTUATIONS CONDITION OF EVENT There were no safety relief valve actuators during this reporting period.

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4' 2.

ECCS Systems Outag:s a

The following outages were taken on ECCS Systems during the reporting period.

OUTAGE NO.

EQUIPMENT PURPOSE OF OUTAGE 2-1-85 LPCS pump Lubrication 2-6-85 B RHR pump Lubrication 2-13-85 2A D/G Air Replace blown Compressor Head Gasket 2-14-85 2A D/G Air Replace blown compressor Head Gasket 2-20-85 2B D/G LIP-DG-03 2-21-85 2B D/G Air Recalibrate compressors instruments 2-40-85 2B RHR pump Oil samples 2-51-85 A RHR pump Inspect coupling 2-57-85 B RHR pump Inspect coupling 2-61-85 2A RHR Service Lubrication Water pump 2-62-85 2A RHR service Megger motor Water pump 2-65-85 "C" RHR pump Coupling Check 2-75-85 "B" RHR Service Polarization check Water pump 2-77-85 "C" RHR pump Remove / Replace suction vent Sight Glass 3.

O!'f-Site Dose Calculatiori Manual Tt.ere were no changes to the off-site dose calculations manual during this reporting period.

4.

Radioactive Waste Treatment Systems.

1 There were no changes made to the radioactive waste treatment system during this reporting period.

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o Comm:nw cith Edison

& j. 4 LaSalle County Nuclear Station Rural Route #1, Box 220 Marseilles. Illinois 61341 Telephone 815/357-6761 February 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 covering January 1 through January 31, 1985.

Very truly yours, v'

G. J. Diederic Superintendent LaSalle County Station GJD/RSD/crh 3.,

Enclosure xc:

J. G. Keppler, NRC, Region III NRC Resident Inspector LaSalle Gary Wright, Ill. Dept. of Nuclear Safety l

D. P. Galle, CECO D. L. Farrar, CECO INPO Records Center Ron A. Johnson, PIP Coordinator SNED W. R. Jackson, GE Resident J. M. Nowicki, Asst. Comptroller t

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Document 0043r/0005r