ML20113F555

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Monthly Operating Repts for Nov 1984
ML20113F555
Person / Time
Site: LaSalle  Constellation icon.png
Issue date: 11/30/1984
From: Diederich G, Dus R
COMMONWEALTH EDISON CO.
To:
NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
NUDOCS 8501240056
Download: ML20113F555 (29)
v • d • e


Text

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l LASALLE NUCLEAR PONER STATION UNIT 1 i

MONTHLY PERFORMANCE REPORT NOVEMBER 1984 COlWONWEALTH EDISON COMPANY NRC DOCKET NO. 050-373 LICENSE NO. NPF-ll .

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.4 8501240056 841130 PDR ADOCK 05000373 R PDR Document 0043r/0005r 1

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~' I. 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 c w alth Edison Company. The Architect / Engineer was Sargent & Lundy, and the primary construction contractor was r e alth 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 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 compiled by Randy S. Dus telephone number (815)357-6761, extension 324.

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TABLE OF CONTENTS I. INTRODUCTION ,

II. MONTHLY REPORT FOR UNIT ONE A. Staunary 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. Main Steam Relief Valve Operations
2. ECCS System Outages
3. Off-Site Dose Calculation Manual Changes
4. Major Changes to Radioactive Waste Treatment System r

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II. MONTHLY REPORT POR UNIT ONE A. SUIMARY OF OPERATING EXPERIENCE FOR UNIT ONE NOVEMBER 1-23 The Unit started the reporting period in cold shutdown.

The outage commenced September 29, 1984.

NOVEMBER 24-30 On November 24 at 0915 hours0.0106 days <br />0.254 hours <br />0.00151 weeks <br />3.481575e-4 months <br />, the reactor went critical. At 0240 hcurs on November 26, the generator was synchronized to the grid. At 1000 hours0.0116 days <br />0.278 hours <br />0.00165 weeks <br />3.805e-4 months <br /> on November 26, reactor power was raised to 24%. On November 27, at 0000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> reactor power was raised to 43%. At 2300 hours0.0266 days <br />0.639 hours <br />0.0038 weeks <br />8.7515e-4 months <br /> on November 27, reactor power was raised to 64%.

The reactor was critical for 158 hours0.00183 days <br />0.0439 hours <br />2.612434e-4 weeks <br />6.0119e-5 months <br /> and 45 minutes.

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B. PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS AND SAFETY RELATED l i

MAINTENANCE. I i

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1. Amendments to facility license or Technical Specification.

During the reporting period, Amendment 19 was approved to appendix A of license NPF-11 (Unit 1 Technical Specification).

This Amendment changed the limiting condition for operation of the Accident Monitoring Instrumentation. The LCO's in specific that here changed were those of the containment high-range radiation monitors and containment hydrogen monitor.

2. Facility or procedure changes requiring NRC approval.

i There were no facility or procedure changes requiring NRC approval.

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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 safety-related maintenance completed on Unit one during the reporting 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.

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TABLE 1 <

CORRECTIVE MAINTENANCE OF '

SAFETY RELATED EQUIPMENT WORK R9 QUEST 00ff0NENT CAUSE OF MALFUNCTION RESULTS AND EFFRCTS 00RRECTIVE ACTION ON SAFE OPERATION-blH979, RK Vessel Pressure Wire the spare switch Provides Redundancy Modification Installed.

Switch -contacts to provide a "RX press HI" alarm.

.L27584 .Instrinnent Air Line several Air Connections Excessive loss of air to Replaced flex hoses Leakage were leaking. drywell equipment. and verified no leakage..

L29714. Leak detection The main steam tunnel May cause false "High AT" Element relocated temperature element AT element needs to be isolations. per modification relocated. package.

'h33999 "B" RHR testable Valve failed local leak Potential loss of containment Performed maintenance Check ~ rate test. Due to over- integrity. on valve and per-tightened packino which formed local leak rate Prevented valve from test.

~ fully closing.

L36'112 RR pump seal Pump seal failed. RX water. leakage which could Replaced seal, result in more pump damage. ,

LS8175 RR sample'line . Valve. failed local leak Potential loss of containmant Replaced diaphra p.

isolation valve. rate test due to a leaking Integrity.

diaphrap.

'L40454- Service Air to Install spool piece to' Unit-shutdown for maintenance. Spool piece removed Drywell. ~

Provide service air to prior to unit startup.

.drywell for outage work.

L41166 . Main steen. Isolation- Found valve to be leaking . Potential loss of Primary Repaired valve

. valve. in excess of Tech Spec containment Integrity. & performed leak rate limits. test.

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TABLE 1 j CORRBCTIVE MAINTENANCE OF  :

SAFETY RELATED EQUIPMENT t

WORK REQUEST CONOMENT CAUSE OF MALFUNCTION RESULTS AND EFFECTS CORRECTIVE ACTION ON SAFE OPERATION, L42048 shutdown cooling Valve was unable to be Alternate shutdown cooling Strain. gage instru-suction valve. -opened.following a unit methods had to be employed. mentation installed on-  ;

shutdown, valve to monitor effects of temperature on valve.

L42099 HPCS Discharge Valve has ruptured bellows. Potential loss of containment Replaced bellows and pressure relief Integrity. verified leak tight. ,

4 valve. ,

, L42215 RCIC Steam Gupply Valve found to have a high Potential loss of containment Repaired valve seat [

& reassembled.

Isolation valve. leakage rate. Integrity.

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, ,L42727 RR pump suction Replace the existing Continuous leakage and heat Replaced with new line. drain valves. double block valve inputs to drywell sump. double block valve dffdH96BGil6 with two arrangement.

valves in series.  ;

L43082

! DIV I Post LOCA Monitor indicating 12% Redundant channel still Reca11brated monitor.

02 monitor, oxygen while it should operable.

be reading 20%. l L43087 Peedwater .

Valve exhibits excessive Potential loss of primary Repaired valve and  !

testable check -leakage during local leak containment Integrity. and ratested.

valve. rate test..

L43561 RX Low Level <

Micro switch in level could cause spurious scram Replaced micro switch

-scram switch, transmitter is very when unit is running, and recalibrated.  !

sensitive & very erratic, i

'L43720 DIV 2 125V . Modify battery rack to Not seismically mounted. Shimmed. gaps with batteries.- meet manufacturer's plywood and readjusted-  !

recommendations. brackets on unistrut.

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TABLE 1 s

O CORRECTIVE MAINTENANCE OF SAFETY RELATED SQUIPMENT  :

IdORK REQUEST COMPONENT CAUSE OF MALFUNCTION RESULTS AND EFFECTS CORRECTIVE ACTION ON SAFE OPERATION L43755 Personnel access Inner door seal damaged. Access hatch required to be Replaced gasket.

hatch. leak tight.

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  • .t C. LICENSEE EVENT REPORTS The following is a tabular sumusary of all licensee event reports for LaSalle Nuclear Power Station, Unit One, occurring during the reporting period, November 1 through November 30, 1984. This information is provided pursuant to the reportable occurrence reporting requirements as l

set forth in 10CFR 50.73. ]

Licensee Event Report Number Date Title of Occurrence 1 84-063-00 11/8/84 Mechanical Snubber Found Locked During Visual Inspection.

84-064-00 11/2/84 Excessive Leak Rate (Loss of P/C integrity) 84-065-00 11/9/84 LPCI Testable Check Valve LLRT Failure.

84-066-00 11/13/84 Amunonia, Chlorine ESF Actuation.

84-067-00 11/19/84 Mechanical Fire Penetrations Degraded.

84-068-00 11/29/84 Spurious Trip of B VC C12 Detector.

84-069-00 11/21/84 Loss of Variable Leg to lH22-P027 Instrument Rack.

84-070-00 11/21/84 Uncontrolled High Radiation Area.

84-071-00 11/21/84 Inadvertent closure of 1G33-F004 84-072-00 11/28/84 SBOT Train Low Flow.

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D. 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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l. OPERATING DATA REPORT DOCKET NO. 050-373 UNIT LaSalle One DATE December 10, 1984 COMPLETED BY Randy S. Dus TELEPHONE (815)357-6761 OPERATING STATUS
1. REPORTING PERIOD: November 1984 GROSS HOURS IN REPORTING PERIOD: 720
2. CURRENTLY AUTHORIZED POWER LEVEL (MWt):3323 MAX DEPEND CAPACITY l

(ftde-Met): 1036 DESIGN ELECTRICAL RATING (MWe-Net):1078

3. POWER LEVEL TO WHICH RESTRICTED (IF ANY) (MWe-Net): N/A i
4. REASONS FOR RESTRICTION (IF ANY):

THIS MONTH YR TO DATE CUMULATIVE I

5 NUMBER OF HOURS REACTOR WAS CRITICAL 158.8 5536 5536

6. REACTOR RESERVE SHUTDOWN HOURS 0.0 1165 1165 1 7. HOURS GENERATOR OW LINE 117.3 5311 5311
8. UNIT RESERVE SHUTDOWN HOURS 0.0 1.0 1.0
9. GROSS THERMAL ENERGY GENERATED (MWH) 224474 14806183 14806183
10. GROSS ELEC. ENERGY GENERATED (MWH) 66600 4806389 4806389
11. NET ELEC. ENERGY GENERATED (MWH) 54438 4556099 4556099
12. REACTOR SERVICE FACTOR 22.1% 68.9% 68.9%
13. REACTOR AVAILABILITY FACTOR 22.1% 83.3% 83.3%
14. UNIT SERVICE FACTOR 16.3% 66.1% 66.1%
15. UNIT AVAILABILITY FACTOR 16.3% 66.1% 66.1%
16. UNIT CAPACITY FACTOR (USING MDC) 7.3% 54.7% 54.M
17. UNIT CAPACITY FACTOR (USING DESIGN MWe) 7.0% 52.6% 52.6%
18. UNIT FORCED OUTAGE RATE 0.0 16.8% 16.8%
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:

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,, 2. AVERAGE DAILY UNIT POWER LEVEL DOCKET NO: 050-373 UNIT: LASALLE ONE DATE: DECEMBER 11, 1984 COMPLETED BY: Randy S. Dus TELEPHONE: (815) 357-6761 MONTH: NOVEMBER, 1984 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net)

1. 0 17. 0
2. 0 18. 0 3 0 19. 0
4. 0 20. 0
5. 0 21. 0
6. 0 22. 0
7. 0 23. 0
8. 0 24. 0
9. 0 25. 0
10. 0 26, 147
11. 0 27. 525
12. 0 28. 657
13. 0 29. 656
14. 0 30. 645
15. 0 31.
16. 0 1

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ATTACHMENT E ,

3. UNIT SHUTDOWNS AND POWER CEDUCTIONS .

DOCKET NO. 050-374 '

UNIT NAME LaSalle One' DATE December 1984 REPORT MONTH NOVEMBER 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) REASON REDUCING POWER ACTIONS /COftlENTS 20 84/12/01 A 602.7 H 4 Continuation of outage tehich started on September 29.

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I E. UNIQUE REPORTING REQUIREMENTS l

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1. Safety / Relief valve operations for Unit One.

VALVES NO & TYPE PLANT DESCRIPTION j DATE ACTUATED ACTUATION CONDITION OF EVENT Rach SRV was cycled once when RX pressure was @ 150 psig, per modification #1-1-84-075. ,

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  1. 2.

ECCS Sy2tems OutCge3 l

The following outages were taken on ECCS Systems during '

the reporting period.

OUTAGE NO. BOUIPMIDrf PURPOSE OF OUTAGE 1-1204-84 1E12-C002B Remove and inspect coupling.

1-1205-84 1E12-F068B Repair cable splice.

1-1206-84 1812-D300B Replace valve 1812-F410A.

1-1208-84 1812-F048B Repair Cable Splice.

1-1209-84 lE12-F009 Check Overloads 1-1222-84 1812-C300B Bad Bearing noise 1-1223-84 HPCS CY Spool Remove CY Spool Piece 1-1228-84 1812-F053A Butt Splice 1-1229-84 1E12-F074A Butt Splice 1-1230-84 1812-F048A Butt Splice 1-1231-84 1812-F064A Butt Splice f

1-1232-84 1812-C002A Inspect coupling 1-1246-84 lE12-C002A Inspect Coupling 1-1264-84 Ul SDC LST 84-212 1-1278-84 SDC Vents LST 84-212

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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LASALLE NUCLEAR POWER STATION UNIT 2 MONTHLY PERFORMANCE REPORT NOVEMBER 1984 COIMONWEALTH EDISON COMPANY NRC DOCKET NO. 050-3~14 l

LICENSE NO. NPF-18 l

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DLBLE OF CONTENTS 4

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 / 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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. l I. INTRODUCTION I

The LaSalle Nuclear Power Station is a Two Unit Facility

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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 comunonwealth Edison Company.

The condenser cooling method is a closed cycle coatirg pond. Unit one is subject to License Number NPP-I?..

issued on April 17, 1982. The unit commenced cot 'T 11 generation of power on January 1, 1984. Unit Twc

  • subject to license number NPF-18, issued on Decemi.g ,,.

1983. The date of initial criticality was March 1.,

1984.

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

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II. M0trfHLY REPORT POR UNIT TWO A. SupMARY OF OPERATING EXPERIENCE FOR UNIT TWO l

November 1-30 4 1 The unit started the reporting period at 84% power. At  !

1530 hours0.0177 days <br />0.425 hours <br />0.00253 weeks <br />5.82165e-4 months <br /> on November 1, Reactor power was %%. At 1700 hours0.0197 days <br />0.472 hours <br />0.00281 weeks <br />6.4685e-4 months <br /> on November 4, reactor power was reduced for stop valve limit switch work. On November 4 at 2200 i hours, reactor power was 26%. At 0035 on November 5, the main turbine was tripped. At 2137 on November 5, the main generator was synchronized to the grid. At 1500 hours0.0174 days <br />0.417 hours <br />0.00248 weeks <br />5.7075e-4 months <br /> on November 6, reactor power was increased to 70%. At 1500 hours0.0174 days <br />0.417 hours <br />0.00248 weeks <br />5.7075e-4 months <br /> on November 8, reactor power was increased to 90%. On November 11 at 0200, a power reduction was started for a rod sequence change. At 0700 hours0.0081 days <br />0.194 hours <br />0.00116 weeks <br />2.6635e-4 months <br /> on November 11, reactor power was 27%. On November 11 at 2300 hours0.0266 days <br />0.639 hours <br />0.0038 weeks <br />8.7515e-4 months <br />, reactor power was 65%. At 4 0000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> on November 14, reactor power was 83%. On November 15 at 1500, reactor power was %%. On November l

20 at 1400 hours0.0162 days <br />0.389 hours <br />0.00231 weeks <br />5.327e-4 months <br />, a reactor shutdown was started because l of an inoperable bypass valve. At 1906 hours0.0221 days <br />0.529 hours <br />0.00315 weeks <br />7.25233e-4 months <br /> on November 20, the generator was taken off the grid. At 2300 hours0.0266 days <br />0.639 hours <br />0.0038 weeks <br />8.7515e-4 months <br /> on November 21, reactor power was 9%. At 0530 hours0.00613 days <br />0.147 hours <br />8.763227e-4 weeks <br />2.01665e-4 months <br /> on November 22, the generator was synchronized to the grid. At 0700 hours0.0081 days <br />0.194 hours <br />0.00116 weeks <br />2.6635e-4 months <br /> on November 22, reactor power was increased to 42%. On November 23 at 2200 hours0.0255 days <br />0.611 hours <br />0.00364 weeks <br />8.371e-4 months <br />, reactor power was 65%. At 0100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> on 1 November 26, Reactor power was 84%. On November 26 at 1900 hours0.022 days <br />0.528 hours <br />0.00314 weeks <br />7.2295e-4 months <br />, reactor power was 96%. The reactor was critical for 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> and 0 minutes.

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

i j 1. Amendments to facility license or Technical Specifications.

1 During the reporting period, Amendment 5 was approved to j

Appendix A of License NFP-18 (Unit 2 Technical Specification).

This Amendment changed the limiting cond? tion for operation of the Accident Monitoring Instrumentation. The Lco's in specific that were changed were those of the conta16 veer t High-Range Radiation Monitors and Containment Hydrogen 19;nitor.

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2. Facility or procedure changes requiring NRC approval.

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

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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 1

1 safety-related maintenance completed on Unit One during the reporting 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.

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TABLE 1

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CORRECTIVE MAINTENANCE OF .

SAFETY RELATED BQUIPMENT ,

WORK R8 QUEST COFFONENT CAUSE OF 7".ALFUNCTION R;TSULTS AND EFFECTS CORRECTIVE ACTION ON SAFE OPERATION L39566 RCIC Steam supply to Repair packing leak and Steam leakage causing Tighened packing and RHR. check motor for proper radiological concern, verified motor amps current. acceptable.

L42516 Ion Chamber power Power supply in APRM "C" APRM reading offscale. Replaced defective supply. power supply.

L43721 250 V Battery Rack Modify battery rack to Batteries not seismically Adjusted brackets meet manufacturer supported. and installed plywood recommendations. in gaps around batteries.

L310% HPCS to suppression Stake the setscrew in the Could potentially lose control Staked setscrew to pool test valve. Anti-Rotation stem clamp of valve. . prevent slippage.

to prevent loosening from vibration.

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C. LICENSEE EVENT REPORTS The following is a tabular sumanary of all licensee event reports for LaSalle Nuclear Power Station, Unit Two, occurring during the reporting period, November 1 through November 30, 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 84-070-00 11/07/84 Unsecured High Radiation Area.

84-071-00 11/26/84 APRM Hi-Hi Scram 84-072-00 11/26/84 Reactor Building Vent System Fan Trip.

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I D. DATA TABULATIOblS 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 DOCUMElfT ID 0036r/0005r

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1. OPERATING DATA REPORT DOCKET NO. 050-374

. UNIT LaSalle Two DATE December 10, 1984 COfrLETED BY Randy S. Dus TELEPHONE (815)357-6761 OPERATING STATUS

1. REPORTING PERIOD: November 1984 GROSS HOURS IN REPORTING PERIOD: 720
2. CURRENTLY AUTHORIZED PONER LEVEL (MWt):3323 MAX DEPEND CAPACITY (Infe-Met): 1036 DESION ELECTRICAL RATING (MWe-Met):1078
3. PONER LEVEL TO WICH 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 720 993 993

6. REACTOR RESERVE SHUTDOWN HOURS 0.0 0.0 0.0
7. HOURS GENERATOR ON LINE 664.6 932.3 932.3
8. UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 0.0
9. OkO6S THERMAL ENERGY GENERATED (IRfH) 1913558 2730856 2730856
10. GROSS ELEC. ENERGY GENERATED (MWH) 628250 898623 898623
11. NET ELEC. ENERGY GEN 8tRATED (MWH) 607018 829715 829715 1
12. REACTOR SERVICE FAC'tw 100% 96.2% 96.2%
13. REACTOR AVAILABILITY FACTOR 100% 96.2% 96.2%

i 14. UNIT SERVICE FACTOR 92.3% 90.3% 90.3% ,

i 15. UNIT AVAILABILITY FACTOR 92.3% 90.3% 90.3%

i 16. UNIT CAPACITY FACTOR (USING MDC) 81.4% 77.6% 77.6%

I 17. UNIT CAPACITY FACTOR (USING DESIGN MWe) ~18.2% 74.6% 74.6%

18. UNIT FORCED OUTAGE RATE 7.7% 9.7% 9.7%
19. SHUTDONNS SCHEDULED GVER NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF BACH):

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

, 20. IF SHUT DOWN AT END CP NEPORT PERIOD, ESTIMATED DATE OF STARTUP N/A i,

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a J 2. AVERAGE DAILY UNIT POWER LEVEL DOCKET NO: 050-374 UNIT: LASALLE TWO DATE: December 10. 1984 COMPLETED BY: Randy S. Dus TELEPHONE: (815) 357-6761 MONTH: November 1984 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net)

1. 994 17. 1054
2. 1048 18. 1053 3 1048 19. 1048
4. 895 20. 744
5. 10 21. 0
6. 621 22. 374
7. 771 23. 754
8. 957 24. 837
9. 1002 25. 822
10. 1048 26. 1010
11. 603 27. 1027 12, 693 28. 1019 13, 805 29. 1013
14. _ . %5 30. 1022
15. 1028 31. -
16. 1045 l

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3. UNIT SHUTDOtAfS AND POhMER REDUCTIONS
  • DOCKET NO. 050-374 .

UNIT NAfE LaSalle Two DATE D8CEfBER 1984 REPORT MONTH MOVEpsER 1984 C0ffLETED BY Randy S. Dus TELEPHONE (815)357-6761 PutTHOD OF TYPE SMITTING DOWN F: PORCED DURATION THE REACTOR OR CORRECTIVE NO. DATE S: SCHEDULED (HOURS) REASON (1) REDUCING POWER ACTIONS /CONWENTS 2 841105 P 21.0 A 1 Turbine / Generator taken off line for stop valve maintenance work.

3 84/11/11 S .

0.0 H 5 Power reduction for a Rod sequence change.

4 84/11/20 F 34.4 A 1 Turbine / Generator taken off line for bypass valve maintenance work.

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r R. UNIQUE REPORTING RBQUIREMENTS

1. Safety / Relief Valve Operations for Unit Two.

P_AIE VALVES NO & TYPE PLANT DESCRIPTION ACTUATED ACTUATIONS CONDITION OF EVENT THERE WERE NO SAFETY RELIEF VALVE ACTIVATIONS DURING THE MONTH OF OCTOBER.

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

OUTAGE No. EQUIPMENT PURPOSE OF OUTAGE There were no outages taken on ECCS Systems during the reporting period.

3. Off-Site Dose calculation Manual

. There were no changes to the off-site dose calculations manual i

during this reporting period.

4. Radioactive Waste Treatment Systems.

See report for Unit one for changes to radioactive waste treatment system.

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Commonwealth Edison LaSalle County Nucl:Ir Station RuralRoute #1, Box 220 Marseilles, Illinois 61341 Tefephone 815/357-6761  !

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l December 11, 1984 '

Director, Office of Management Information and Program Control United States Nuclear Regulatory Commission Washington, D.C. 20555 ATTN: Document Control Desk

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Gentlemen:

Enclosed for your information is the monthly performance report covering LaSalle County Nuclear Power Station for the period covering November 1 through November 30, 1984.

Very truly yours,

/ 2. &

h G. J. Diederich Superintendent LaSalle County Station GJD/RSD/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 W. R. Jackson, GE Resident  !(f l J. M. Nowicki, Asst. Comptroller g ,

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.L-Document 0043r/0005r l

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