ML20094N255

Monthly Operating Repts for Jul 1984

ML20094N255
Person / Time
Site:	LaSalle
Issue date:	07/31/1984
From:	Diederich G, Dus R COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
NUDOCS 8408160140
Download: ML20094N255 (27)

Text

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I LASALLE NUCLEAR POWER STATION UNIT 1 l

NONTHLY PERFORMANCE REPORT JULY 1984 C00st00MCALTH EDISON COMPANY NRC DOCKET NO. 050-373 LICENSE NO. NPF-11 0

8408160140 840731 PDR ADOCK 05000373 l

N PDR l

Document 0043r/0005r r

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TABLE OF CONTENTS I.

INTRODUCTION II.

MONTMLY REPORT FOR l' NIT ONE A.

Susenary of Operating Esperience E.

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

Amendments to Facility License or Techalcal speelfications 2.

Facility or Procedure Changes Requiring NRC Approval 3.

Tests and Esperiments Requiring NRC Approval 4.

Corrective Malatenance of Safety Related Equlpment C.

LICENSEE EVENT REPORTE D.

DATA TARULATIONS 1.

Operating Data Report 2.

Average Daily Unit Power Level 3.

Unit shutdowns and Power Reductions E.

UNIQUE REPORTING REQUIRENENTS 1.

Mala Steam Rollef Valve Operations 2.

ECCS System Outages 3.

Off-site Dose Calculation Manuel Changes 4.

Major Changes to Radioactive Weste Treatment System L

r Document 0043r/0005r I-

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INTRODUCTION The LaSalle Nuclear Power Station is a Two Unit Facility Located in Marsellies, 1111 acts. Each Unit is a Bol11ag Water Reactor with a designed electrical output of 1078 IRfe net. The Station is owned by Coasmonwealth Edison Company. The Architect / Engineer was Sargent & Lundy, and the primary construction contractor was Coasmonwealth Edison Company.

The condenser cooling method is a closed cycle coollas pond. Unit One la subject to License Number NPF-11, issued on Apell 17, 1982. The date of initial criticality was June 21, 1982. 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 complied by Randy S. Dus telephone number (815)357-6761, entension 324.

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Document 0043r/000Sr

II.

MONTMLY REPORT FOR UNIT ONE A.

SUIglARY OF OPERATING EXPERIENCE FOR UNIT ONE JULY 1-31 The Unit started the reporting period at 94% power. At 0900 hours0.0104 days <br />0.25 hours <br />0.00149 weeks <br />3.4245e-4 months <br /> on July 17. Reactor power was reduced to 76%

due to a single rod scram. At 2200 hours0.0255 days <br />0.611 hours <br />0.00364 weeks <br />8.371e-4 months <br /> on July it, reactor power was raised to 92% power. At 2030 hours0.0235 days <br />0.564 hours <br />0.00336 weeks <br />7.72415e-4 months <br /> on July 20, reactor power was raised to 100E. At 2200 hours0.0255 days <br />0.611 hours <br />0.00364 weeks <br />8.371e-4 months <br /> on July 21, reactor power was reduced to 92% due to high condensate temperature and high condenser back pressure. The reactor was critical for the entire month of July totaling 744 hours0.00861 days <br />0.207 hours <br />0.00123 weeks <br />2.83092e-4 months <br />.

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B.

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

I 1.

Amendments to facility license or Technical Specification.

~

Amendment No. 17. - This amendment revised the main steam tunnel differential temperature setpoint as.specified in Technical Specification Table 3.3.2-2.

The change was necessitated to reflect actual plant as built conditions rather than original design criteria.

2.

Facility or procedure changes requiring NRC approval.

l 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 appraval.

4.

Corrective maintenance of safety related equipment.

The following table (Table 1) presents a su.Tracy of i

safety-related malr.tenance completed on Unit One during the l

{

reporting period. The headings indicated in this summary l

include: Work Request numbers, LER numbers, Component Name, cause of Malfunction, Results and Effects on Safe Operation, and

~ Corrective Action.

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TABLF,1 CORRECTIVE MAINTENANCE OF-SAFETY RELATED EQUIPMENT 1

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WORK REQUEST LER COMPONENT CAUSE OF MALFUNCTION RESULTS AND EFFECTS CORRECTIVE ACTION, ON SAFE OPERATION l'

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L31475 Cable Tray Hanger support missing None. Other supporti still Added hanger to provide; functional.

additional support.

L31700 Post LOCA _

Recorder Pen ramps upscale None. Redundant channel still Installed new output' Monitor after warm up.

operable.

transistor and regulator chip.

L35485 Computer Room Damper sticks closed.

Inadequate ventilation in Freed up binding l

Supply Damper computer room.

linkage ~and lub-ricated.

L36772

' Suppression Trips on Thermals after Valve still functional-Replaced defective Pool Spray valve closes after reset.

torque switch.

Valve L38158 RHR Service Lube oil leak from pump Potential loss of pump Repaired oil leak.

Water Pump bearing lubrication.

L38249 LPRM Reads downscale at 75%

None.

Redundant channel Cleaned connectors.

power operable.

L38327 LPCS water Pump coupling damaged.

'Could cause pump failure Repaired coupling Leg pump Cover 0-rings out of leaving LPCS system unfilled cover 0-rings.

position.

L38481 HPCS Water-Valve. leaks through Allows backflow through pump Repaired check leg discharge from HPCS system.

valve seat.

check valve.

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L38989 Suppression Recorder stops driving None.

Redundant channel Replaced low speed pool temper-while points still still' operable.

servo motor for ature re-printing.

chart drive.

I corder DOCUMENT 0044r/0005r

C.

LICENSEE EVENT REPORTS The following is a tabular summary of all licensee event reports for LaSalle Nuclear Power Station, Unit One, occurring during the reporting Period, July 1 through July 31, 1984. 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 84-031-00 6/15/84 Reactor Water Cleanup Isolation on Pump Mode Differential Temperature.

84-032-00 6/12/84 Reactor Water Cleanup High Differential Flow Isolation.

84-033-00 6/24/84 Reactor Water Cleanup Differential Flow.

84-034-00 6/17/84 Unsecured High Radiation Area Door.

84-035-00 6/19/84 B Diesel Fire Pump Flywheel.

84-036-00 6/14/84 Unsecured High Radiation Area Door.

84-037-00 6/21/84 OA Dierel Fire Pump Flywheel.

84-038-00 6/22/84 Unsealed Fire Fenetration/ Sleeve.

84-039-00 6/24/84 Scram on Low Reactor Water Level.

84-040-00 6/25/84 Reactor Water Cleanup Differential Flow Isolation.

84-041-00 6/28/84 Mechanical Fire Penetrations.

84-042-00 7/3/84 High Radiation Area Unsecured and Unposted.

l 84-043-00 6/27/84 Reactor Water Cleanup Differential Flow Isolation.

84-044-00 7/2/84 Failure of High Pressure Core l

Spray Water Les Pump Check l

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D.

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

i 1.

Operating Data Report 2.

Average Daily Unit Power Level

3.

Unit Shutdowns and Power Reductions f

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Document 0043r/0005r

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OPERATING DATA REPORT DOCKET NO. 050-373 UNIT LaSalle One DATE August 6. 1984 COMPLETED BY Randy S.

Dus TELEPHONE (815)357-6761 OPERATING STATUS j

1.

REPORTING PERIOD: JULY 1984 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 744.0 4001.8 4001.8 6.

REACTOR RESERVE SHUTDOWN HOURS 0.0 1076.3 1076.3 7.

HOURS GENERATOR ON LINE 744.0 3841.7 3841.7 8.

UNIT RESERVE SHUTDOWN HOURS 0.0 1.0 1.0 9.

GROSS THERMAL ENERGY GENERATED (MWH) 2328797 10902922 10902922" 10.

GROSS ELEC. ENERGY GENERATED (MWH) 756661 3569784 3569784 11.

NET ELEC. ENERGY GENERATED (MWH) 725819 3402863 3402863 12.

REACTOR SERVICE FACTOR 100%

78.3%

78.3%

13.

REACTOR AVAILABILITY FACTOR 100%

99.3%

99.3%

14.

UNIT SERVICE FACTOR 100%

75.2%

75.2%

15.

UNIT AVAILABILITY FACTOR 100%

75.7%

75.2%

16.

UNIT CAPACITY FACTOR (USING MDC) 94.7%

64.3%

64.3%

17.

UNIT CAPACITY FACTOR (USING DESIGN

,s

MWe) 90.5%

61.8%

61.8%

18.

UNIT FORCED OUTAGE RATE 0.0%

20.7%

20.7%

19.

SHJTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, AND DURATICN OF EACH)

On October 1, 1984 there will be a four week outaEe to inspect the drywell and perform acheduled surveillances.

20.

IF SHUT DOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP:N/A 21.

UNITS IN TEST STATUS (PRIOR TO CONNERCIAL OPERATION):

FORECAST ACHIEVED INITIAL CRITICALITY 6/21/82 INITIAL ELECTRICITY 9/04/82 COMMERCIAL OPERATION 1/1/84 i

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2. AVERACE DAILY UNIT POWER LEVEL DOCKET NO: 050-373 UNIT: LASALLE ONE DATE: AUGUST 6. 1984 COMPLETED BY: Randy S. Dus TELEPHONE: (815) 357-6761 MONTH: July 1984 DAY AVERAGE DAILY POWER LEVEL DAY AVERACE DAILY POWER LEVEL (NWe-Net)

(NWe-Net) 1.

995 17.

831 2.

1014 18.

912 3

954 19.

962 4.

995 20.

995 5.

1010 21.

1019 6.

971 22.

927 7.

920 23.

933 8.

967 24.

988 9.

1051 25.

972 10.

1037 26.

997 11.

1055 27.

1008

' * ~

12.

1058 28.

990 13.

1052 29.

950 14.

888 30.

1028 15.

893 31.

937 16.

933 INSTRUCTIONS On this form list the average daily unit power level in NWe-Net for each day in the reporting month. Compute to the nearest whole megawatt.

Thase figures will be used to plot a graph for each reporting month. Note

)

that wher maximum dependable capacity is used for the net electrical rating of j

the unit there may be occasions when the daily average power level exceeds the 100% line (or the restricted power level line.)

In such cases the average daily unit power output sheet should be footnoted to explain the apparent anomaly.

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ATTACHMENT E 3.

UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 050-374 UNIT NAME LaSalle One DATE August 6. 1984 REPORT MONTH JULY 1984 COMPLETED BY Randr S. Dus TELEPHONE (815)357-6761 NETHOD OF TYPE SHUTTING DOWN F: FORCED DURATION THE REACTOR OR CORRECTIVE NO.

DATE S: SCHEDULED (HOURS)

REASON (1)

REDUCING POWER ACTIONS /CONNENTS 1

- NONE.

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UNIQUE REPORTING REQUIREMENTS 1.

Safety / Relief valve operations for Unit One.

There were no relief valve operations for Unit One for this reporting period.

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2.

ECCS System 3 Outtgon 1

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

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OUTAGE NO.

ROUIPNENT PURPOSE OF OUTAGE f

(

l-560-84 Suppression Pool Replace Torque Switch

[

Spray Isolation L

Valve.

• l-562-84

'HPCS Diesel / Gen.

Replace air starter motor.

1-563-84 HPCS Water Leg Pump Repair discharge check valve.

1-564-84 HPCS Water Les Pump Repair discharge check valve.

discharge check valve.

1-565-84 HPCS Pump Troubleshoot CY losses through HPCS suction.

1-571-84 LPCS Water Leg Repair Water Leg Pump.

Pump.

1-573-84 HPCS Suction from Reduce CY Utilization CY.

1-574-84 1A Diesel / Gen.

Lubrication.

1-575-84 IB Diesel / Gen.

Lubrication, 1-585-84 1RER Pump 011 Samplez.

1-615-84 RHR Heat Exchange Repair valve motor.

Outlet Stop Valve.

3.

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

4.

Radioactive Waste Treatment Systems.

There were no changes to the Radioactivo Waste Treatment System during this reporting period.

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LASALLE NUCLEAR POWER STATION UNIT 2 l

MONTHLY PERFORMANCE REPORT' JULY 1984 COMMONWEALTH EDISON COMPANY NRC DOCKET NO. 050-374 LICENSE NO. NPF-18 i

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DOCUMENT ID 0036r l

TABLE OF CONTENTS I.

INTRODUCTION j

II.

MONTHLY REPORT FOR UNIT TWO l

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.

Safoty/ Relief Valve Operations 2.

ECCS "ystem Outages 3.

Off-site Dose calculation Manual Changes 4.

Major Changes to Radioactive Waste Treatment System 4

DOCUMENT ID 0036r-

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INTRODUCTION The LaSalle Nuclear Power Station is a Two Unit Facility Located in Marsellies, Illinois. Each Unit is a Boiling Water Reactor with a designed electrical output of 1078 MWe net. The Station is owned by Commonwealth 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-11, issued on April 17, 1982. The unit. commenced commercial generation of power on January 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 complied by Randy S. Dus, telephone number (815)357-6761, extension 324.

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II.

,NONTHLY REPORT FOR UNIT TWO A.

-SUletARY OF @PERATING EXPERIENCE FOR UNIT TWO JULY 1-7 The unit started the reporting period at 64% power. At 2100 hours0.0243 days <br />0.583 hours <br />0.00347 weeks <br />7.9905e-4 months <br /> on July 5,'the turbine generator was manually tripped.as part of the startup test program. At 0040 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> on July 6, the mode swi&.ch was placed in

" Shutdown". The reactor was critical for 120 hours0.00139 days <br />0.0333 hours <br />1.984127e-4 weeks <br />4.566e-5 months <br /> and 40 minutes.

JULY 8-9 At 0617 hours0.00714 days <br />0.171 hours <br />0.00102 weeks <br />2.347685e-4 months <br /> on July 8, the reactor was critical. At 1750 hours0.0203 days <br />0.486 hours <br />0.00289 weeks <br />6.65875e-4 months <br /> on July 8, the generator was synchronized to the grid. At 2330 hours0.027 days <br />0.647 hours <br />0.00385 weeks <br />8.86565e-4 months <br /> on July 8, reactor power was raised to 19%. At 1906 hours0.0221 days <br />0.529 hours <br />0.00315 weeks <br />7.25233e-4 months <br /> on July.9, an intercept valve fast closure ocurred. At 2250 hours0.026 days <br />0.625 hours <br />0.00372 weeks <br />8.56125e-4 months <br /> on July 9, the reactor mode switch was placed in " Shutdown". The reactor was critical for 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> and 33 minutes.

]

' JULY 10-31 At 0646 hours0.00748 days <br />0.179 hours <br />0.00107 weeks <br />2.45803e-4 months <br /> on July 10, the reactor was critical..At 0500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br /> on July 11, the generator was synchronized to the grid. At 0630 hours0.00729 days <br />0.175 hours <br />0.00104 weeks <br />2.39715e-4 months <br /> on July 11, reactor power was raised to 26%. At 1500 hours0.0174 days <br />0.417 hours <br />0.00248 weeks <br />5.7075e-4 months <br /> on July 11, reactor power was raised to 52%. At 1500 hours0.0174 days <br />0.417 hours <br />0.00248 weeks <br />5.7075e-4 months <br /> on July 13, reactor pcwer was raised to 70%. At 0700 hours0.0081 days <br />0.194 hours <br />0.00116 weeks <br />2.6635e-4 months <br /> on July 20, reactor power was raised to 85%. At 0700 hours0.0081 days <br />0.194 hours <br />0.00116 weeks <br />2.6635e-4 months <br /> on July 21, resetor power was reduced to 63% for flux shaping.

At 1700 hours0.0197 days <br />0.472 hours <br />0.00281 weeks <br />6.4685e-4 months <br /> on July 23, reactor power was raised to 86%. At 0000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> on July 27, reactor power was raised to 96%. At 2025 hours0.0234 days <br />0.563 hours <br />0.00335 weeks <br />7.705125e-4 months <br /> on July 27, a power reduction was i

commenced for TDRFP testing. At 0700 hours0.0081 days <br />0.194 hours <br />0.00116 weeks <br />2.6635e-4 months <br /> on July 28, reactor power was reduced to 47%. At 1400 hours0.0162 days <br />0.389 hours <br />0.00231 weeks <br />5.327e-4 months <br /> on July 28, reactor power was reduced to 1A% for investigation of steam leaks on the Moisture Separator Reheater. At i

2115 hours0.0245 days <br />0.588 hours <br />0.0035 weeks <br />8.047575e-4 months <br /> on July 28, the main turbine was tripped. At 2130 hours0.0247 days <br />0.592 hours <br />0.00352 weeks <br />8.10465e-4 months <br /> on July 28, the reactor was manually scrammed 4

so that repairs could be made to the Moisture Seperator Reheater. The reactor was critical for 446 hours0.00516 days <br />0.124 hours <br />7.374339e-4 weeks <br />1.69703e-4 months <br /> and 44 minutes.

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DOCUMENT ID 0036r

B.

PLANT OR PROCEDURE CHANCES, TESTS, EXPERIMENTS AND SAFETY RELATED MAINTENANCE.

1.

Amendments to f acility license or Technical Specifications.

Amendment No. 2 - This amendment revised the main steam tunnel i

differential temperature setpoint as specified in Technical Specification Table 3.3.2-2.

The change was necessitated to reflect. actual plant as built conditions rather than original

~

design criteria.

4 Amendment No. 3-This amendment added a reator scram on low control rod drive pump discharge pressure as required by license condition 2. c(7).

2.

Facility or procedure changes requiring NRC approval.

There were no faellity or procedure changes requiring NRC

' approval daring the reporting period.

3.

Tests and experiments requiring NRC approval.

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

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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 l

reporting period. The headings indicated in this summary l

include: Work Request numbers, LER Numbers, Component Name, l

cause of malfunction, results and effects on safe operation, and corrective action.

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TABLE 1 COERECTIVE MAINTENANCE OF SAFETY SELATED EQUIPMENT I

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WORK REQUEST LER COMPONENT CAUSE OF MALFUNCTION RESULTS AND EFFECTS CORRECTIVE ACTION ON SAFE OPERATION I

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L33233 Control Room Rad Monitor would not None.

Redundant channels Replaced defective Rad Monitor operate due to faulty still operable, detector and detector detector.

connectors.

L37122 "O" Diesel /

Small Fuel oil leak into Could cause a breakdown of Stopped leak.

Generator the lube oil system.

Lubricating oil causing bearing damage.

L38262 RHR Service Suction pressure reading None. Redundant pressure Repaired defective Water Pump.

Incorrectly.

indication available.

suction pressure gauge.

L38030 Rod Block Defective power supply Reads 50% when APRM read Replaced power Monitor causing falso reading 65%.

supply.

L38452 LPRM Occassionally bouncing Causes downscale alarm.

Replaced defective causinr. false indication.

cards.

j L38597 Main Steam Solenoid valve leaking Potential loss of air to Replaced solenoid Isolation air.

main steam isolation valve.

valve.

Valve.

L39254 Div. III Corrosion on b.attety Potential loss of DC power Replaced connections Battery.

terminals.

supply to HPCS pump.

bolts & nuts and cleaned connector i

i DOCUMENT 0044r/0005r 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, July 1 through July 31, 1984.

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 84-026-00 6-9-84 RWCU Hi Differential Temperature Pump Room and Heat Exchanger Room Isolation, Div.

I.

84-027-00 6/4/84 Loss of Reactor Water Cleanup Isolation Leak Detection.

84-028-00 6/17/84 Reactor Water Cleanup High Ambient Temperature Isolation.

84-029-00 6/11/84 Reactor Water Cleanup High Differential Flow Isolations.

84-030-00 6/18/84 ~ HPCS Discharge Relief Valve

,i Failure.

84-031-00 6/22/34 Reactor Water Cleanup Differential Temperature Isolation.

84-032-00 6/26/84 Reactor Water Cleanup Isolation.

84-033-00 6/8/84 Failure of Isolation Valve to close.

84-034-00 7/3/84 High Radiation Area Unsecured and Unposted.

84-035-00 7/9/84 Scram On Reactor Vessel High Pressure.

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DOCUMENT ID 0036r

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DATA TABULATIONS t

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 a

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1. OPERATING DATA REPORT DOCKET NO. 050-374 UNIT LaSalle Two DATE August 6, 1984 COMPLETED BY Randy S. Dus TELEPHONE (815)357-6761 OPERATING STATUS i

1.

REPORTING PERIOD: July 1984 GROSS HOURS IN REPORTING PERIOD: 744 2.

CURRENTLY AUTHORIZED POWER LEVEL (ilWt):3323 MAX DEPEND CAPACITY l

(MWe-Net): 1036

-DESIGN ELECTRICAL RATING (MWe-Net):1078 J

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 608.0 2518.5 2518.5 l

6.

REACTOR RESERVE SHUTDOWN HOURS 136.1 928.4 928.4 7.

HOURS GENERATOR ON LINE 566.5 1704. 9 1704.9 8.

UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 0.0 9.

GROSS THERMAL ENERGY GENERATED (MWH) 1324810 2813768 2813768 10.

GROSS ELEC. ENERGY GENERATED (MWH) 400934 777450 777450 l

11.

NET ELEC. ENERGY GENERATED (MWH) 382416 730509 730509 12.

REACTOR SERVICE FACTOR N/A N/A N/A 13.

REACTOR AVAILABILITY FACTOR N/A N/A N/A 14.

UNIT SERVICE FACTOR N/A N/A N/A 15.

UNIT AVAILABILITY FACTOR N/A N/A N/A 16.

UNIT CAPACITY FACTOR (USING MDC)

N/A N/A N/A 17.

UNIT CAPACITY FACTOM(USING DESIGN MWe)

N/A___

N/A N/A 18.

UNIT FORCED OUTAGE RATE N/A h/A N/A 19.

SHUTDWN:, SCHEDULdD OVER NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACII) 20.

IF SliUT DOWN AT END OF REPORT PE2IOD, E3TIMATED DATE OF STARTUP: A_ugun 1.1984 21.

UNITS IN TEST ST%Td8 (FRIOR TO COMMERCIAL OPERATION):

FORSCAST ACHIEVED INITIAL CRITICALITY 3/10/84 INITIAL ELECTRICITY 4/20/C4_

COMMERCIAL OPERATION Aug. 84 DOCUMENT ID 0036r

2. AVERAGE DAILY UNIT POWER LEVEL DOCKET NO: 050-374 UNIT: LASALLE TWO DATE: August 6. 1984 COMPLETED BY: Randy S.

Dus TELEPHONE: (815) 357-6761 NONTH: July 1984 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (NWe-Net)

(NWe-Net) 1.

606 17.

650 2.

658 18.

469 3

680 19.

670 4.

610 20.

811 5.

571 21.

613 6.

0 22.

699 7.

0 23.

839 8.,_

29 24.

946 9,

284 25.

983 10.

0 26.

990 11.

321 27.

908 12.

626 28.

764 13.

687 29.

0 14.

733 30.

0 15.

660 31.

0 16.

628 INSTRUCTIONS On this form list the average daily unit power level in NWe-Net for each day in the reporting month. Compute to the nearest whole megawatt.

These figures will be used to plot a graph for each reporting month. Note that when maximum dependable capacity is used for the net electrical rating of the unit there may be occasions when the daily average power level exceeds the 100% line (or the restricted power level line.)

In such cases the average daily unit power output sheet should be footnoted to explain the apparent anomaly.

DOCUMENT ID 0036r

ATT 3.

UMIT SHUTDOWNb AND POWER REDUCTIONS DOCKET NO. 050-374 UNIT NAME LaSalle Two DATE August 6. 1984 REPORT MONTE JULY 1984 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)

REASOh (1)

REDUCING POWER ACTIONS / COMMENTS 4

21 840706 S

68.8 B

2 Turbine / Generator manually tripped and reactor shutdown per STP-27-2.

22 840709 S

33.9 B

2 Unit shutdown to troubleshoot problem with turbine / Generator intercept valve.

23 840721 S

0.0 H

5 Power reduction for flux shaping.

24 840728 S

74.8 B

2 Unit shutdown to repair steam leaks on the moisture seperator-reheater.

/

I DOCUMENT 0044r/0005r 4

E.

~ UNIQUE REPORTING REQUIREMENTS 1.

Safety / Relief Valve Operations for Unit Two.

DATE VALVES' NO & TYPE PLANT DESCRIPTION ACTUATED ACTUATIONS CONDITION OF EVENT 6/9/84 2B21-F013D 1 AUTO 981 psig Rx Scram 6/9/84 2B21-F013S 1 AUTO 981 psig Rx Scram 6/9/84 2B21-F013U 1 AUTO 981 psig Rx Scram I

DOCUMENT ID 0036r

l 2.

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

OUTAGE NO.

EQUIPMENT PURPOSE OF OUTAGE 2-847-84 2A RHR Pump Oil Samples 2-867-84 2A Diesel / Generator Lubrication 2-870-84 HPCS Diesel / Generator Repair air compressor motor driven air start compressor.

2-871-84 HPCS Diesel / Generator Repair air compressor motor driven air start compressor.

2-900-84 2B Diesol/ Generator Repair air compressor, motor driven air start compressor.

2-912-84 MSR 1st stage reheat Repair valve.

scavenging steen stop valve.

2-928-84 2B Diesel Cecerator Repair mir compressor.

motor driven air start compressor.

2-929-84 2B Diesel Generatcr Repair air compressor motor driven air start compressor.

2-932-84 RilR heat exchanger Adjust limitorque shell side vent upstrecm stop valve.

3.

Off-Site Dose Calculation Manual There were no changes to the off-site dose calculations manual i

during this reporting period, i

4.

Radioactive Waste Treatment Systems.

l There were no changes'to the Radioactive Waste Treatment System l'

during this reporting period.

I l-l DOCUMENT ID 0036r

7 Commonwealth Edison LaSIlla County Nucl: r Station Rural Route #1, Box 220 Marseilles,ll!inois 61341 Telephone 815/357 6761 August 6, 1984 Director, Office of Management Information and Program Control United States Nuclear Regulatory Commission Washington, D.C.

20555 ATTN: Document Control Desk Centlemen:

Enclosed for your information is the monthly performance report covering LaSalle County Nuclear Power Station for the period covering July 1 through July 31, 1984.

Very truly yours,

/

Y G

J. Diaderich Superintendent LaSalle County Station GJD/RSD/ceh 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 W. R. Jackson, GE Resident Document 0043r/0005r I)f:

.