Text

Monthly Operating Repts for Aug 1985
	ML20135F928
Person / Time
Site:	LaSalle
Issue date:	08/31/1985
From:	Diederich G, Rohrer R; COMMONWEALTH EDISON CO.
To:	; NRC OFFICE OF ADMINISTRATION (ADM)
References
	NUDOCS 8509180021
	Download: ML20135F928 (33)
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LASALLE NUCLEAR POWER STATION I UNIT 1 MONTHLY PERPORMANCE REPORT AUGUST, 1985 COMMONWEALTH EDISON COMPANY NRC DOCKET NO. 050-373 LICENSE NO. NPF-ll y..

8509180021 BW ADOCK O5000373 PDR pg ,

R i M Doctanent 0043r/0005r d\

e I. INTRODUCTION The LaSalle County Nuclear Power Station is a two-unit facility owned by Commonwealth Edison Comapny and located near Marsellies, Illinois. Each unit is a Boiling Water Reactor with a designed net electrical output of 1078 Megawatts. Waste 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 NPF-11 on i April 17, 1982. Initial criticality was achieved on June 21, 1982, and comunercial power operation was comumenced on January 1,1984.

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

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TABLE OF CONTENTS I. INTRODUCTION L

II. MONTHLY REPORT FOR UNIT CNE 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. Main Steam Relief Valve Operations

2. ECCS System Outages

3. Off-Site Dose Calculation Manual Changes

4. Major Changes to Radioactive Waste Treatment System Document 0043r/0005r

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II. - MONTHLY REPORT POR UNIT ONE A. SUffUutY OF OPERATING EXPERIENCE FOR UNIT ONE August 1-17.

Aug. 1, 0001 hours1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months . The unit entered August with the reactor critical at 96% power i

and the generator on-line at 1043 MWe-net.

Aug. 2, 0305 hours0.00353 days 0.0847 hours 5.042989e-4 weeks 1.160525e-4 months . Reactor power reduced to to 94%

to manipulate control rods.

'Aug. 6, 2300 hours0.0266 days 0.639 hours 0.0038 weeks 8.7515e-4 months . Reactor power at 92%.

Aug. 7, 0415 hours0.0048 days 0.115 hours 6.861772e-4 weeks 1.579075e-4 months . Reactor power reduced to 88% per load dispatcher (L.D.)

Aug. 7, 1500 hours0.0174 days 0.417 hours 0.00248 weeks 5.7075e-4 months . Reactor power restored to 91%.

Aug. 9. 0000 hours0 days 0 hours 0 weeks 0 months . Reactor power reduced to 86% to manipulate control rods. Left ,

at this level per L.D.

Aug. 9, 0700 hours0.0081 days 0.194 hours 0.00116 weeks 2.6635e-4 months . Reactor power restored to 91%.

Aug. 11, 0445 hours0.00515 days 0.124 hours 7.357804e-4 weeks 1.693225e-4 months . Reactor power reduced to 56% to manipulate control rods.

Aug. 13, 0700 hours0.0081 days 0.194 hours 0.00116 weeks 2.6635e-4 months . Reactor power restored to 97%.

Aug. 15, 0200 hours0.00231 days 0.0556 hours 3.306878e-4 weeks 7.61e-5 months . Reactor power reduced to 75% per L.D.

Aug. 15, 0420 hours0.00486 days 0.117 hours 6.944444e-4 weeks 1.5981e-4 months . Reactor power further reduced to 60% to withdraw control rods.

Aug. 16, 0700 hours0.0081 days 0.194 hours 0.00116 weeks 2.6635e-4 months . Reactor power restored to 97%.

All control rods fully withdrawn.

Aug. 16, 1525 hours0.0177 days 0.424 hours 0.00252 weeks 5.802625e-4 months . Reactor Recirculation Pumps spuriously downshifted. Reactor ,

power fell to 50%. l Aug. 16, 1650 hours0.0191 days 0.458 hours 0.00273 weeks 6.27825e-4 months . Reactor power recovered to 83%. ,

Aug. 17, 1500 hours0.0174 days 0.417 hours 0.00248 weeks 5.7075e-4 months . Reactor pcwer at 93%.

Aug. 17, 1614 hours0.0187 days 0.448 hours 0.00267 weeks 6.14127e-4 months . Reactor SCRAM due.to error during surveillanc;e.. The reactor had been critical for 400 hours0.00463 days 0.111 hours 6.613757e-4 weeks 1.522e-4 months . and 14 minutes so far ,

in August.

August 18-31 Aug. 18, 0215 hours0.00249 days 0.0597 hours 3.554894e-4 weeks 8.18075e-5 months . Reactor critical.

Aug. 18, 1630 hours0.0189 days 0.453 hours 0.0027 weeks 6.20215e-4 months . Generator synchronized to the grid _. 1 Aug. 19, 2300 hours0.0266 days 0.639 hours 0.0038 weeks 8.7515e-4 months . Reactor power at 84%.

-Aug. 20, 0425 hours0.00492 days 0.118 hours 7.027116e-4 weeks 1.617125e-4 months . Reactor power reduced to 60% in order to withdraw control rods.

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Aug. 20, 2300 hours0.0266 days 0.639 hours 0.0038 weeks 8.7515e-4 months . RIcctor power at 91%. All control rods fully withdrawn.

Aug. 28, 2300 hours0.0266 days 0.639 hours 0.0038 weeks 8.7515e-4 months . RWctcr power &t 88%.

-Aug. 29, 2300 hours0.0266 days 0.639 hours 0.0038 weeks 8.7515e-4 months . Reactor power at 91%. Coasting down.

Aug. 31, 2400 hours0.0278 days 0.667 hours 0.00397 weeks 9.132e-4 months . Unit one left August on-line at ,

89% power (908 MWe-net). .

Coasting down. !

The reactor was critical for a total of '733 hours0.00848 days 0.204 hours 0.00121 weeks 2.789065e-4 months and 59 minutes for the month of August.

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

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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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2. Facility or procedure changes requiring NRC approval.

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 j

this reporting period.

4. Corrective maintenance of safety related equipment.

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

safety-related maintenance completed on Unit one during the i reporting period. The headings indicated in this summary e

include: Work Request number, Component Name, Cause of Malfunction, Results and Effects on Safe Operation, and Corrective Action.

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TABLE I CORRECTIVE MAINTENANCE OF -

SAFETY RELATED EQUIPMENT WORK REQUEST COMPONENT. CAUSE OF MALFUNCTION. RESULTS AND EFFECTS- CORRECTIVE ACTION ON SAFE PLANT OPERATION L48832 Standby Gas Treatment Dirty. Power supply Indication spiked high cleaned connector.

System Wide-Range. connector, occassionally,

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Gas Monitor.

L49378 "A" Reactor Protection Faulty circuit breaker. Breaker failed to trip- Replaced breaker.

' System Power Supply electrically during testing.

Monitoring Assembly.

L50455 Auxiliary Electrical Actuator needed lubrication. Damper stuck open when it cleaned and lubricated Equipment Room HVAC should have been closed, actuator.

"A" return air damper Possibly degraded ventilation.

OVE06YA.

L50476 ' Division I 12G Low specific. gravity in Potentially degraded bus Replaced cell.

VDC Batteries, cell No. 8. voltage.

L50789 Unit One Leak Broken leads on Point #11 trended upscale. Relanded leads.

Detection Temperature Thermocouple.

Recorder.

-L50895 1A Residual Heat Worn Packing on Valve. Valve leaked at stem when off Repacked valve.

Removal. Service Water its seat.

Strainer Back-Wash

. Valve, 1E12-F336A.

L50943 Reactor Core Isolation Worn valve disc. Valve leaked excessively. Replaced Valve disc.

Cooling System Water Potential to drain Reactor Core Leg Pump Discharge Isolation Cooling Injection Line Check Valve, 1851-F061. if Water Leg Pump stopped running.

'L51284 "B" Rod Block Monitor Faulty Second Level Failed Surveillance. Replaced card.

Multiplexer Card.

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j C. LICENSEE EVENT REPORTS i

- The following is a tabular summary of all licensee event reports for LaSalle Nuclear Power Station, Unit One, logged during the reporting period. August I through August 31, 1985. This information is provided pursuant to the reportable occurrence reporting requirements as set forth I

in 10CFR 50.73.

Licensee Event Report Number Date Title of Occurrence 85-054-00 7-18-85 Auto start of emergency makeup train.

85-055-00 7-22-85 Reactor Scram from false low level signal.

85-056-00 8-3-85 Spurious trip of "B" VC radiation monitor for "A" train.

85-057-00 8-2-85 Contamination found outside controlled area.

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i 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 1

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, 1. dPERATING DATA

REPORT i

DOCKET No. 050-373 i

UNIT LaSalle One DATE September 10, 1985 COMPLETED BY Richard J. Rohrer TELEPHONE (815)357-6761 j OPERATING STATUS i

1. REPORTING PERIOD: August, 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 (IP ANY) (MWe-Net): 970

4. REASONS FOR RESTRICTION (IF ANY): Fuel Consumption.

THIS MONTH YR TO DATE CUMULATIVE 5 NUMBER OF HOURS REACTOR WAS CRITICAL. 734.0 4613.5 10895 1

6. REACTOR RESERVE SHUTDOWN HOURS 0.0 476.2' 1642

7. HOURS GENERATOR ON LINE 719.7 4445.7 10503 4

8. UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 0.0

9. GROSS THERMAL ENERGY GENERATED (MWH) 2139456 12430297 29253586

10. GROSS ELEC. ENERGY GENERATED (MWH) 695946 4071879 9542522 ;

11. NET ELEC. ENERGY GENERATED (MWH) 669517 3913787 9108849

12. REACTOR SERVICE FACTOR 98.7% 79.1% 74.4%

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13. REACTOR AVAILABILITY FACTOR 98.% 87.3% 85.6% ,

14. UNIT SERVICE FACTOR 96.% 76.2% 71.7%

i 15. UNIT AVAILABILITY FACTOR 96.% 76.2% 71.7%

I 16. UNIT CAPACITY FACTOR (USING MDC) 86.9% 64.8% 60.1%

17. UNIT CAPACITY FACTOR (USING DESIGN MWe) 83.5% 62.% 57.%

18. UNIT FORCED OUTAGE RATE 3.3% 20.2% 16.8%

l 19. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH)

An outage for refueling maintenance, surveillance, and modifications is scheduled to begin September 22, 1985 and will last 26 weeks.

20. IF SHUT DOWN AT END OF REPORT PERIOD,' ESTIMATED DATE OF STARTUP: NA s

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

1. 1021 17, 637

2. 1008 18 . __- 77 3 998 19. 697

4. 988 20. 826

5. 981 21, 988

6. 972 22. 975

7. 954 23. 974

8. 954 -24, 966

9. 939 25. 959 10, 948 26. 955

11. 743 27, 944

12. 924 28. 918

13. 1011 29. 937

14. 978 30. 931

15. 843 31. 923

16. 929 l

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ATTACHMENT E

3. UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 050-373 UNIT NAME LaSalle One DATE SEPTEMBER 10, 1985 REPORT MONTH AUGUST 1985 COMPLETED BY Richard J. Rohrer TELEPHONE (815)357-6761

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METh0D OF-TYPE SHUTTING DOWN F: FORCED DURATION THE REACTOR OR CORRECTIVE NO. DATE S: SCHEDULED (HOURS) REASON REDUCING POWER ACTIONS /COPMENTS 16 850817 F 24.3 0 3 Scrammed due to error during surveillance.

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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 There were no Safety Relief Valves Operated for Unit One during this reporting period.

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. 2. ECCS.Sy2 tees Outtg;2 The following outages were taken on ECCS Systems during the reporting period.

OUTAGE NO. EOUIPMENT PURPOSE OF OUTAGE 1-701-85 IE12-F336A 1A-RHR WS Strainer Repack valves.

1-767-85 lE12-C300D Replace Inboard Seal.

1-722-85 1A D/G Replace Air Starts.

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3. Off-Site Dos 3 CalculEtion Manual There were no changes to the off-site dose calculation Manual during this reporting period.

4. Radioactive Waste Treatment Systems.

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

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d LASALLE NUCLEAR POWER STATION UNIT 2 MONTHLY PERFORMANCE REPORT AUGUST 1985 COfMONWEALTH EDISON COMPANY NRC DOCKET NO. 050-374 i

, LICENSE NO. NPF-18 l

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TABLE OF CONTENTS i

I. INTRODUCTION II. MONTHLY REPORT FOR UNIT TWO A. Sunuaary 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

1. Safety / Relief Valve Operations

2. ECCS System Outages

3. Off-Site Dose Calculation Manual Changes

4. Major Changes to Radioactive Waste Treatment System 1

4 DOCUMENT ID 0036r/0005r

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I. INTRODUCTION The LaSalle County Nuclear Power Station is a two-unit facility owned by commonwealth Edison Company and ,

located near Marseilles, Illinois. Each unit is a l Boiling Water Reactor with a designed net electrical j output of 1078 Megawatts. Waste heat is rejected to a i man-made cooling pond using the Illinois River for make-up and blowdown. The architecht-engineer was l Sargent and Lundy, and the primary construction l contractor was Commonwealth Edison Company.

Unit two was issued operating license number NPF-18 on December 16, 1983. Initial criticality was achieved on March 10, 1984, and commercial power operation was commenced on June 19, 1984.

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

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DOCUMENT ID 0036r/0005r

II . , MONTHLY REPORT 70R UNIT TWO A. SUfGEARY OF OPERATING EXPERIENCE FOR UNIT TWO August 1 Aug. 1, 0001 hours1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months . Unit Two entered August on-line at 17% power (150 MWe-net). A normal unit shutdown was in progress.

Aug. 1, 0040 hours4.62963e-4 days 0.0111 hours 6.613757e-5 weeks 1.522e-5 months . Generator taken off-line.

Aug. 1, 0600 hours0.00694 days 0.167 hours 9.920635e-4 weeks 2.283e-4 months . Mode Switch moved to " Shutdown".

The Unit had been shutdown to investigate high drywell temperatures. The reactor had been critical for six hours and zero minutes so far in August.

August 3-31 Aug. 3, 2205 hours0.0255 days 0.613 hours 0.00365 weeks 8.390025e-4 months . Reactor critical.

Aug. 4, 0625 hours0.00723 days 0.174 hours 0.00103 weeks 2.378125e-4 months . Generator synchronized to the grid.

Aug. 5, 0700 hours0.0081 days 0.194 hours 0.00116 weeks 2.6635e-4 months . Reactor power at 70%.

Aug. 5, 1150 hours0.0133 days 0.319 hours 0.0019 weeks 4.37575e-4 months . "A" Turbine-Driven Reactor Feed Pump tripped. Power fell to 60%.

Aug. 5, 1500 hours0.0174 days 0.417 hours 0.00248 weeks 5.7075e-4 months . Reactor power restored to 76%.

Aug. 6, 0230 hours0.00266 days 0.0639 hours 3.80291e-4 weeks 8.7515e-5 months . Reactor power reduced to 55% per Load Dispatcher (L.D.)

Aug. 6, 1500 hours0.0174 days 0.417 hours 0.00248 weeks 5.7075e-4 months . Reactor power restored to 76%.

Aug. 8. 0700 hours0.0081 days 0.194 hours 0.00116 weeks 2.6635e-4 months . Reactor power at 96%.

Aug. 9, 0310 hours0.00359 days 0.0861 hours 5.125661e-4 weeks 1.17955e-4 months . Reactor power reduced to 62% per L.D.

Aug. 9, 1500 hours0.0174 days 0.417 hours 0.00248 weeks 5.7075e-4 months . Reactor power restored to 90%.

Aug. 11, 0000 hours0 days 0 hours 0 weeks 0 months . Reactor power reduced to 56% per L.D.

Aug. 11, 1030 hours0.0119 days 0.286 hours 0.0017 weeks 3.91915e-4 months . Reactor power raised to 70% per L.

D.

Aug. 12, 0700 hours0.0081 days 0.194 hours 0.00116 weeks 2.6635e-4 months . Reactor power restored to 83%.

Aug. 14, 1500 hours0.0174 days 0.417 hours 0.00248 weeks 5.7075e-4 months . Reactor power at 96%.

Aug. 14, 2000 hours0.0231 days 0.556 hours 0.00331 weeks 7.61e-4 months . Economic Generation Control test comumenced. Reactor power reduced to 93%. -

Aug. 15, 1345 hours0.0156 days 0.374 hours 0.00222 weeks 5.117725e-4 months . Moisture separator spill valve i failed. Power dropped 10 MWe-net.

Aug. 15, 2000 hours0.0231 days 0.556 hours 0.00331 weeks 7.61e-4 months . Reactor power further reduced to j 83% per Economic Generation Control test.

Aug. 16, 2325 hours0.0269 days 0.646 hours 0.00384 weeks 8.846625e-4 months . Reactor power recovered to 93%.

Aug. 19, 0400 hours0.00463 days 0.111 hours 6.613757e-4 weeks 1.522e-4 months . Reactor power reduced to 81% per L. D.

i Aug. 19,.0700 hours0.0081 days 0.194 hours 0.00116 weeks 2.6635e-4 months . Reactor power testored to 94%.

Aug. 20, 0355 hours0.00411 days 0.0986 hours 5.869709e-4 weeks 1.350775e-4 months . Reactor power reduced to 52% to repair moisture separator spill valve.

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Aug. 20, 1500 hours0.0174 days 0.417 hours 0.00248 weeks 5.7075e-4 months . Rsictor power at 88%.'

Aug. 21, 0030 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months . Ratctor power rsduc::d to 76% par L.D.

Aug. 21, 1500 hours0.0174 days 0.417 hours 0.00248 weeks 5.7075e-4 months . Reactor power restored to 92%.

Aug. 22, 0600 hours0.00694 days 0.167 hours 9.920635e-4 weeks 2.283e-4 months . . Reactor power reduced to 56% per L.D. l

, Aug. 22, 2300 hours0.0266 days 0.639 hours 0.0038 weeks 8.7515e-4 months . Reactor power at 8M. Ramping. j

.down in compliance with unusual ,

event declared for standby control problems.

l Aug. 23, 0300 hours0.00347 days 0.0833 hours 4.960317e-4 weeks 1.1415e-4 months . Descension in power terminated at

', 72%.

Aug. 23, 1500 hours0.0174 days 0.417 hours 0.00248 weeks 5.7075e-4 months . Reactor power restored to 91%.

Aug. 24, 0430 hours0.00498 days 0.119 hours 7.109788e-4 weeks 1.63615e-4 months . Reactor power reduced to 56% per

! L. D.

Aug. 24, 0730 hours0.00845 days 0.203 hours 0.00121 weeks 2.77765e-4 months . Reactor power raised to 74% per L.D.

Aug. 26, 2300 hours0.0266 days 0.639 hours 0.0038 weeks 8.7515e-4 months . Reactor power restored to 99%.

Aug. 30, 0245 hours0.00284 days 0.0681 hours 4.050926e-4 weeks 9.32225e-5 months . Reactor power briefly dropped during control rod manipulation.

Aug. 31, 2400 hours0.0278 days 0.667 hours 0.00397 weeks 9.132e-4 months . Unit two left August on-line at 99% reactor power (1055 MWe-net).

The reactor was critical for a total of 679 hours0.00786 days 0.189 hours 0.00112 weeks 2.583595e-4 months and 55

. minutes in August, i

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

1. Amendments to facility license or Technical Specifications.

Ther were no Amendments to the facility License or Technical Specifications for this reporting Month.

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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.

3. Tests and experiments requiring NRC approval.

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

I j 4. Corrective Maintenance of Safety Related Equipment, f ~

! The following table (Table 1) presents a susumary of '

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safety- ? lated maintenance completed on Unit Two during the .

1 reporting period. The headings indicated in this summary 1

I include: Work Request number, Component Name, cause of malfunction, results and effects on safe operation, and J

corrective action.

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r TABLE 1 CORRECTIVE MAINTENANCE OF SAFETY RELATED BQUIPMENT

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WORK REQUEST COMPONENT CAUSE OF MALFUNCTION 'RESULTS AND EFFECTS CORRECTIVE ACTION ON SAFB PLANT OPERATION

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L47228 Automatic Depressur- Brittle O-Rings.in conn-- Potential to cause fialure to Replaced 0-Rings.

ization System ection to actuator for open Automatic Depressurization Accumulator "C". Valve 2B21-F013C. Allowing Valve 2B21-F013C.

accumulator pressure to bleed off.

L47544 Division I 250 VDC Battery cell No. 3 had low Potentially degraded bus Charged cell until Batteries. specific gravity. . Voltage.. specific gravity was within specifications.

L47876 Reactor Water Clean Worn Valve Seat. Valve leaked excessively; Built up valve seat Up Inboard Isolation failed Local Leak Rate Test. and machined smooth..

Valve, 2G33-F001.

L49389 Suppression Pool Valve did not torque Excessive leakage; failed Local Adjusted torque Vent and Purge Valve, tightly on motor operator. Leak Rate Test. switch.

2VQO27.

L50064 Hydraulic. Control Unit Leaking instrument block Potential to cause failure to Replaced valve.

Accumulator for Control valve (111). scram this rod ~1f combined with Rod Drive 22-47. other events.

- L50502 . Residual Heat Removal' Loose packing. Valve leaked at stem. Adjusted-packing to System "A"-Full. Flow 'stop leak.

Test valve, 2E12-F024A.

L50800 Scram Pilot Valves Valves worn. Control Rod scrammed too slowly Rebuilt valves.

. for Control Rod Drive during test.

02-43.

L50801 Scram Pilot Valves'for Valves Worn, Control Rod Scrammed too slowly Rebuilt valves.

Control Rod Drive during test.

50-15.

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t TABLE 1 CORRECTIVE MAINTENANCE OF SAFETY RELATED EQUIPMENT WORK REQUEST COMPONENT CAUSE OF MALFUNCTION RESULTS AND EFFECTS CORRECTIVE ACTION ON SAFE PLANT OPERATION L50809 Residual Heat Removal Valve would not torque Allowed 2000 gpm of flow Temporarily changed logic System "B" Full Flow fully closed. through valve. to stop motor-operator Test Valve, 2E12-F0248 from closed limit switch, not torque switch.

L50886 Hydraulic Control Unit Instrument Block Valve Potential to cause failure Replaced Valve.

for Control Rod Drive (111) leaked by stem. to scram this rod if combined 26-07. with other events.

L50916 Reactor Core Isolation Open coil in relay. Could not isolate Reactor Core Replaced relay.

Cooling System Low Isolation Cooling System on pressure Isolation low pressure.

Relay, 2E51-K58.

L50935 Reactor Manual Faulty transponder cards Tripped on rods 26-39 and 14-35. Replaced cdrds.

Control System. at locations 14-35 and 18-35.

L50993 Hydraulic Control Unit Instrument Block Valve Potential to cause failure Rebuit Valve.

Accumulator for Control (Ill) . leaked by. to scram this rod if combined Rod Drive 34-23. with other events.

L51049 Reactor Core Isolation Out-of-calibration. I of 2 relays required to Recalibrated.

, Cooling System High isolate Reactor Core Isolation Level Switch, Cooling was energized.

2LIS-B21-N101B.

i L51,168 Main Steam Isolation Broke lug for "A" phase Heater output reduced to one- Replaced lug.

Valve Leakage Control during surveillance. -third of design.

Heater, 2E32-B001A.

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TABIE 1 CORRECTIVE MAINTENANCE OF SAFETY RELATSD EQUIPMENT WORK REQUEST COMPONENT CAUSE OF MALFUNCTION RESULTS AND EFFECTS CORRECTIVE ACTION ON SAFE PLANT OPERATION L51192 . Hydraulic Control Unit Worn fitting on instrument Potential to cause failure to Replaced fitting.

.. for control Rod Drive stop valve (111) causing scram this rod if combined 1

30-55. nitrogen leak. with other events.

'L51369 . Circuit Breaker for Breaker failed Cooling Water Pump was Replaced Breaker and' 2B Diesel Generator catastrophically. inoperable. cleaned and inspected Cooling Water Pump.' adjoining switchgear.

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< L51514 Reactor Water Clean Broken wire on resistor. Degraded system operation. Replaced resistor.

Up.High Differential

Temperature

Compensating Resistor.

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C. ' LICENSEE EVENT REPORTS The following is a tabular sununary of all licensee event reports for LaSalle Nuclear Power Station, Unit Two, logged during the reporting period, August 1 through August 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 85-035-00 7-23-85 Actuation of E and N SRV's.

85-036-00 7-30-85 RWC Isolation on High Flow 85-037-00 7-19-85 Missed Surveillance on RCIC.

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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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1. OPERATING DATA REPORT DOCKET NO. 050-374 UNIT LaSalle Two DATE September 10, 1985 COMPLETED BY Richard J. Rohrer TELEPHONE (815)357-6761 OPERATING STATUS

1. REPORTING PERIOD: August, 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): N/A THIS MONTH YR TO DATE CUMULATIVE 5 NUMBER OF HOURS REACTOR WAS CRITICAL 679.9 2346.3 3958.1

6. REACTOR RESERVE SHUTDOWN HOURS 64.1 64.1 189.4

7. HOURS GENERATOR ON LINE 666.3 2295.3 3832.7

8. UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 0.0

9. GROSS THERMAL ENERGY GENERATED (MdH) 1914077 6794830 11302422

10. GROSS ELEC. ENERGY GENERATED (MWH) 619812 2236547 3721533

11. NET ELEC. ENERGY GENERATED (MWH) 594680 2109900 3502217

12. REACTOR SERVICE FACTOR 91.4% 40.2% 51.9%

13. REACTOR AVAILABILITY FACTOR 100.0% 41.3% 54.4%

14. UNIT SERVICE FACTOR 89.6% 39.4% 50.2%

15. UNIT AVAILABILITY FACTOR 89.6% 39.4% 50.2%

16. UNIT CAPACITY FACTOR (USING MDC) 72.2% 34.9% 44.3%

17. UNIT CAPACITY FACTOR (USING DESIGN 74.1% 33.6% 42.6%

MWe)

18. UNIT FORCED OUTAGE RATE 10.5% 1.3% 4.2%

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

N/A

20. IF SHUT DOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP N/A DOCUMENT ID 0036r/0005r

2. AyERAGE DAILY UNIT POWER LEVEL DOCKET NO: 050-374 UNIT: LASALLE TWO DATE: September 10, 1985 COMPLETED BY: Richard J. Rohrer TELEPHONE: (815) 357-6761 MONTH: August 1985 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL

, (MWe-Net) (MWe-Net)

1. -14 17. 967

2. -17 18. 963 3 -19 19. 943

4. 203 20. 805

5. 732 21. 894

6. 722 22. 768 930 23. 913 7.

8. 974 24. 730

9. 862 25. 829

10. 1030 26. 1011

11. 674 27. 1037

~

12. 844 28. 1040

13. _

1017 29. 1046

14. 994 30. 1046

15. 941 31. 1048

16. 866 e

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3. UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 050-374 UNIT NAME LaSalle Two DATE September 10, 1985 l REPORT MONTH AUGUST 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 /COfftENTS l

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6 850801 F 77.8 H 1 Shutdown to investigate High Drywell Temperatures.

7 850811 S 0.0 F 1 Power reduction ordered by Load Dispatcher.

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E. 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 Valves operated during this reporting period.

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. 2. ECCS -Systeds Outtg29 The following outages were taken cn ECCS Systems during l the reporting period.

PURPOSE OF OUTAGE !

OUTAGE NO. EOUIPMENT 2-1086-85 2E22-D310 Repair Flapper.

2-1089-85 RCIC RCIC Inboard Isolation Inoperable.

2-1094-85 2B D/G Replace Bendix.

2-1096-85 2B RHR SW PRM Equipment Protection.

2-1098-85 2B RHR WS PRM Repair Seal.

2-1106-85 HPCS Injection high point Repair vent sightglass.

2-1120-85 2E12-F0llA Change Motor.

2-1121-85 2E12-F026A Change Motor.

2-1125-85 2E12-F093 Change Motor.

2-1126-85 2E12-F094 Change Motor. ,

2-1128-85 2A D/G Replace air start motors &

repair oil union.

J 2-1137-85 2E22-C002 Repair breaker.

2-1138-85 Suppression Pool Maintain P.C. Integrity.

2-1140-85 2E12-F047A Replace Motor. -

2-1144-85 2E12-F003A Replace Motor.

2-1159-85 2E12-F068B EQ Motor Change.

2-1162-85 2E12-F049A EQ Mod.

2-1164-85 2E12-F026B EQ Mod. ,

2-1169-85 2E12-F011B EQ Mod.

2-1171-85 2E12-F003B EQ. Mod.

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. 3. Off-Site Dos 2 Calculction Manual There were no changes to the off-site dose calculation manual during this reporting period.

4. Radioactive Waste Treatment Systems.

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

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. , Conwnonw=lth Edison LaSal!e County Nuclear Station g gy 3 Rural Route #1, Box 220 Marseilles, Illinois 61341 ?j/M Telephone 815/357-6761 September 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 August 1 through August 31, 1985.

Very truly yours,

/ /Ad G J. Diederich Station Manager LaSalle County Station GJD/RJR/crh 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 e

l Document 0043r/000Sr

ML20135F928

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