ML20126H372

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Monthly Operating Repts for May 1985
ML20126H372
Person / Time
Site: LaSalle  Constellation icon.png
Issue date: 05/31/1985
From: Diederich G, Rohrer R
COMMONWEALTH EDISON CO.
To:
NRC OFFICE OF ADMINISTRATION (ADM), NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
NUDOCS 8506180325
Download: ML20126H372 (33)
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LASALLE NUCLEAR POWER STATION i UNIT 1 ,,

MONTHLY PERFORMANCE REPORT l MAY 1985 f f

C00000NWEALTH EDISON COMPANY [

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MRC DOCKET NO. 050-373 f LICENSE NO. WPF-11 i

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I 8506180325 850531 r\,.{ Q. L PDR ADOCK 05000373 R PDR  ;

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s t l TABLE OF CONTENTS l 1

I. INTRODUCTION II. MONTHLY REPORT POR UNIT ONE A. Susunary of Operating Experience i B. PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS, AND ;

SAFETY RELATED MAINTENANCE

1. Amendments to Facility License or Technical i 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 l E. UNIQUE REPORTING REQUINXMENTS $

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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 t

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i I. INTRODUCTION The LaSalle County Nuclear Power Station is a two-unit facility owned by Commonwealth Edison Comepny and located near Marseilles, Illinois. Each unit is a Boiling Water Reactor with a designed net electrical output of 1078 Megawatts. Waste heat is rejected to an artificial 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 April 17, 1982. Initial criticality was achieved on June 21, 1982, and commercial power operation was commenced on January 1, 1984.

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

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. a ll. MONTHLY REPORT FOR UNIT ONE A.

SUMMARY

OF OPERATING EXPERIENCE FOR UNIT ONE May le31 May 1, 0000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />. Reactor critical at 98% power, generator on-line.

May 1, 0700 hours0.0081 days <br />0.194 hours <br />0.00116 weeks <br />2.6635e-4 months <br />. Reactor power reduced to 78% for LTS-1100-4. Scram Timing for CRD 22-59.

May 2, 0700 hours0.0081 days <br />0.194 hours <br />0.00116 weeks <br />2.6635e-4 months <br />. Reactor power restored to 96%.

May 6,1645 hours0.019 days <br />0.457 hours <br />0.00272 weeks <br />6.259225e-4 months <br />. Reactor power reduced to 84%, to manipulate control rods.

May 7, 0700 hours0.0081 days <br />0.194 hours <br />0.00116 weeks <br />2.6635e-4 months <br />. Reactor power restored to 96%,

May 10, 2300 hours0.0266 days <br />0.639 hours <br />0.0038 weeks <br />8.7515e-4 months <br />. Reactor power at 95%.

May 11, 0200 hours0.00231 days <br />0.0556 hours <br />3.306878e-4 weeks <br />7.61e-5 months <br />. Reactor power reduced to 76% to manipulate control rods.

May 11, 2300 hours0.0266 days <br />0.639 hours <br />0.0038 weeks <br />8.7515e-4 months <br />. Reactor power restored to 94%.

May 19, 0200 hours0.00231 days <br />0.0556 hours <br />3.306878e-4 weeks <br />7.61e-5 months <br />. Reactor power reduced to 58% to allow maintenance on heater drains.

May 20, 1500 hours0.0174 days <br />0.417 hours <br />0.00248 weeks <br />5.7075e-4 months <br />. Reactor power restored to 89%.

May 20, 1942 hours0.0225 days <br />0.539 hours <br />0.00321 weeks <br />7.38931e-4 months <br />. Reactor power reduced to 86% due to humber 3 Control Valve oscillations.

May 24, 0700 hours0.0081 days <br />0.194 hours <br />0.00116 weeks <br />2.6635e-4 months <br />. Reactor power at 84%.

May 24, 0855 hours0.0099 days <br />0.238 hours <br />0.00141 weeks <br />3.253275e-4 months <br />. Reactor power reduced to 74% due to trip of *B" circulating i

Water Pump.

May 24, 1500 hours0.0174 days <br />0.417 hours <br />0.00248 weeks <br />5.7075e-4 months <br />. Reactor power at 84t.

May 30, 2352 hours0.0272 days <br />0.653 hours <br />0.00389 weeks <br />8.94936e-4 months <br />. Reactor power reduced to 78% for surveillance LOS-AA-W1.

May 31, 0700 hours0.0081 days <br />0.194 hours <br />0.00116 weeks <br />2.6635e-4 months <br />. Reactor power at 84%.

May 31, 1945 hours0.0225 days <br />0.54 hours <br />0.00322 weeks <br />7.400725e-4 months <br />. Reactor manually scrammed following flooding of Lake Screen House when "B" Circulating Water Pump Olscharge Line leaked.

The reactor was critical for 739.8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> during May.

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i B. PLANT OR PROCEDURE CllANGES, TESTS, EXPERIMENTS RND SAFETY RRLATED i e MAINTENANCE.

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1. Amendments to facility license or Technical Specification.

I Three ammendments were made to the Unit one operating license and Technical Speciafications during May.

Ammedment 21 modifies the calculational technique used in determining duct heater performance for the standby Gas Treatment System. Ammendment 22 changes the channel check requirements to accommodate new instruments installed by Environmental Qualification modifications. Ammendment 23 incorporates the requirements of 10 CFR 50.73.

2. Facility or procedure changes requiring NRC approval.

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

3. Tests and Experiments requiring NRC approval.

There were no tests or experiments requiring NRC approval during this 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 number, Component Name, Cause of Malfunction, Hesults and Effects on Safe Operation, and corrective Action, i

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TABLE I N DSCTIVE MRINTENANCE OF SAFETY RELATED SQUIPfE!NT WORK REQUEST C0ff0NENT CAUSE OF MALFL2fCTION RESULTS AND EFFECTS CORRECTIVE ACTION ON SAFE OPERATION L41793 Division I Switch- Faulty Actuator Damper would not stroke Sent actuator to vendor gear Heat Removal for repair. Reinstalled Outside Air Damper. and verified operability.

L45261 control Room zone Actuator Shaft is not Damper would not operate. Connected shaft to Mixing Damper "A". coupled to damper. damper.

L48324 Ammonia detector "B" Out-of-calibration. Detector alarmed and actuated Recalibrated detector.

for "B" Control Room ESF's.

Ventilation.

L48347 Sequence of Events Swapped Alarm messages for Wrong Alarm messages printed. Corrected Alarm Recorder. Chlorine and Asumonia Alarms messages.

L48478 Unit One Stand-by Flow Recorder out-of- Wrong flow indication. Recalibrated Recorder Gas Treatment System calibration. and adjusted recorder Recorder, scale.

L48535 Scram pilot valve for valve hung up in an inter- Inadvertantly Scrammed this Replaced scram pilot CRD 22-59. mediate position. rod during half-scram testing. valves.

L48580 1A R W Service Faulty Motor. Pump would not work as designed. Replaced motor with Water Pump. motor from 2B RM service water pump.

ta48651 Ammonia detector "B" Detector out-of-calibration Detector alarmed and actuated Recalibrated detector.

for "A" Control Room ESF's.

Ventilation.

L48846 "A" Rod Block Monitor Blown fuse. Generated Spurious Rod Blocks. Replaced fuse.

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TABLE I CORRECTIVE PRINTEMMICE OF SAFETY RELATED EQUIFANT WORK REQUEST COWOBENT CAUSE OF PRLF120CTION RESULTS ABS EFFECTS CORRECTIVE ACTIOtt ON SAFE OPERATIOtt L48918 "A" Standby Liquid Valve Leaked through port Injection of Liquid Control Cleaned and adjusted control Relief Valve. hole, solution would have been valve. Installed new slightly slower

  • m otherwise, bellows and lapped the if required. seat.

L49054 HCU Accumulator for Leaky fill valve. Potential to cause failure to Replaced valve.

CRD 22-23. scram this rod if combined with other events.

L49059 "A" Rod Block Plonitor. Faulty power supply. Failed downscale. Replaced power supply and fuses, tested.

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, e 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, .May 1 through . May 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 85-037-00 4-l~i-85 Division II ADS Inop.

85-038-00 4-12-85 Ammonia Detector Actuation.

85-039-00 4-19-85 Ammonia Detector Actuation.

85-040-00 4-23-85 Ammonia Detector Failure.

85-041-00 5-5-85 Spurious Auto-start of Emergency Make-up Fan.

85-042-00 5-5-85 Arunonia/ Chlorine Detector Actuations.

85-043-00 5-8 85 Chlorine Detector Actuation.

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

1. Operating Data Report
2. Average Daily Unit Power Level l
3. Unit Shutdowns and Power Reductions '

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

1. REPORTING PERIOD: MAY, 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 l THIS MONTH YR TO DATE CUMULATIVE 5 NUMBER OF HOURS REACTOR WAS CRITICAL 739.8 ,G042.0 9323
6. REACTOR RESERVE SHUTDOWN HOURS 4. L 102.9 1269
7. HOURS GENERATOR ON LINE 739.8 _2969.2 9025
8. UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 0.0
9. GROSS THERMAL ENERGY GENERATED (MWH) 2184310 8433887 25257176
10. GROSS ELEC. ENERGY GENERATED (MWH) 724455 27887650 8259408
11. NET ELEC. ENERGY GENERATED (MWH) 703230 2687914 7882976
12. REACTOR SERVICE FACTOR 99.4% 83.4% 75.0%
13. REACTOR AVKILABILITY FACTOR 100% 86.2% 85.2%
14. UNIT SERVICE FACTOR 99.4% 81.4% 72.6%
15. UNIT AVAILABILITY FACTOR 99.4% _81.4% 72.6%
16. UNIT CAPACITY FACTOR (USING MDC) 91.2% 71.1% 61.2%
17. UNIT CAPACITY FACTOR (USING DESIGN MWe) _87.*M _68.4% 58.8%
18. UNIT FORCED OUTAGE RATE 0.6% 12.2% 13.9%
19. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH)

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

20. IF SHUT DOWN AT END OF REPCRT PERIOD, ESTIMATED DATE OF STARTUP: June 9,

, 1985

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

1. 924 17. 1043
2. 1040 18, 1032 3 1042 19. 766
4. 975 20. 915
5. 875 21. 879
6. 943 22. 905
7. 1032 23. 904
8. 1034 24. 878
9. 1036 25. 877
10. 1030 26. 876
11. 926 27. 873
12. 1030 28. 874
13. 1035 29. 876
14. 1025 30. 883
15. 1020 31. 725
16. 1029 Document 0043r/0005r

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E. UNIQUE REPORTING REQUIREMENTS

1. Safety / Relief valve operations for Unit One.

VALVES NO & TYPE PLANT DESCRIPTION E ACTUATED ACTUATION CONDITION OF EVENT RA_T_E 5-31-85 1821-F013A 1 Manual 620 psig Manu.sily opened 1821-F013B 1 Manual 545 psig succ(ssively to provide 1B21-F013C 1 Manual 530 psig controlled cool-down of IB21-F013D 1 Manual 595 psig the reactor following 1821-F013E 1 Manual 510 Psig Main Steam Line Isolation.

IB21-F013F 1 Manual 460 psig 1B21-F0130 1 Manual 435 psig 1B21-F013H 1 Manual 435 psig IB21-F013K 1 Manual 560 psig 1821-F013L 1 Manual 275 psig valve 1B21-F013L opened at 2330 on May 31, 1985 and closed at 0030 on June 1, 1985. Other valves (1821-F013 M,N,P,Q,R,S) were opened and will be reported in the Monthly Report for June.

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2. ECCS Systems Outtgr3 The following outages were taken on ECCS Systems during the reporting period.

OUTAGE NO. _ EQUIPMENT PURPOSE OF OUTAGE 0-323-85 0 Diesel Generator Relocate Cables Fuel Oil Transfer Pump.

1-399-85 1A RHR Service Water Repair.

Pump.

1-400-85 IB RHR Service Water Prevent Pump Discharge Valve. Runout.

1-425-85 IB Diesel Generator. Change Turbo filter.

1-447-85 1A RHR Service Water Repair Seal Leak.

Process Radiation Monitor.

1-448-85 High Pressure Core Repair Leak.

Spray Full-Flow Test Valve.

1-449-85 1A RHR Process Radiation Work on Pump Motor.

I Monitor.

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. . CUTA05 No. ROUIPMENT PURPOSE OF OUTAGE

3. Off-Site Dose Calculation Manual Revision 11 was made to the Off-site Dose Calculation Manual, incorporating changes requested by the Nuclear Regulatory Commission.
4. Radioactive Waste Treatment Systems.

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

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LASALLE NUCLEAR POWER STATION UNIT 2 MONTHLY PERFORMANCE REPORT MAY 1985 COfMONWEALTH EDISON COMPANY l

NRC DOCKET NO. 050-314 LICENSE NO. NPF-18 1

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TA!LE OF CONTENTS

1. INTRODUCTION II. MONTHLY REPORT FOR UNIT TWO A. Sunusary 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

.c DOCUMENT ID 0036r/0005r

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1. INTRODUCTION The LaSalle County Nuclear Power station is a two-unit facility owned by Comunonwealth Edison Company and i located near Marseilles, Illinois. Each unit is a Bolling Water Reactor with a designed net electrical output of 1078 Megawatts. Waste heat is rejected to an artificial cooling pond using the Illinois River for make-up and blowdown. The architecht-engineer was Sargent and Lundy, and the primary construction 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 nuinber (815)357-6761 extension 575.

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IL. MONTillJ REPORT FOR UNIT TWO l

A

SUMMARY

OF OPERATING EXPERIENCE FOR UNIT TWO MAY 1-31 f

The reactor was suberitical, and the generator was off-line for the entire month of MAY. Unit Two is in a schedied outage for maintenance, testing, and modifications.

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

1. Amendments to facility license or Technical Specifications.

Three ammendments were made to the Unit two operating license and Technical Specifications during May.

Ammendment 9 modifies the calculational technique used in determining duct heater performance for the standby Gas Treatment System. Ammendment 10 changes the channel check requirements to accommodate new instruments installed by Environmental Qualification modifications. Ammendment 11 incorporates the requirements of 10CFR50.73,

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 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 Two during the reporting period. The headings indicated in this summary include: Work Request number, Component Name, cause of malfunction, results and effects on safe operation, and corrective action.

DOCUMENT ID 0036r/0005r

TABLE I COFRECTIVE MAINTENANCE OF SAFE *Y RELATED EQUIPMENT CORRECTIVE ACTION RESULTS AND EFFECTS ON SAFE OPERATION CAUSE OF MALFUNCTION WORK REQUEST COMPONENT Changed "O-ring".

Leaking Scram Pilot valve Potential to cause failure to L60557 HCU Accumulator for scram this rod if combined with cap nut.

CRD 42-03. other events.

No indication of valve's position. Cleaned and adjusted Dirty Contacts on limit limit switch.

L41791 Main steam line out- switch.

board drain valve. Adjusted Torque and Valve tripped its thermals when limit switches.

L44542 "A" RHR Suction Valve. setting.

Torque switches at wrong cycled.

Replaced torque switch.

Faulty torque switch. Valve would not close from L44755 Steam line downstream remote handswitch.

drain, Corrected wiring and Wired incorrectly and blown Continuity Meter would not replaced fuse.

"4B" Standby Liquid function properly, L46397 fuse.

Control Explosive Valve Continuity Alarm. Recalibrated Monitor.

Incorrect reading.

Division I Post- Out-of-Calibration.

L47010 LOCA Oxygen Monitor. Recalibrated Monitor.

Incorrect Reading.

Division II Post- Out-of-calibration.

L470ll LOCA Oxygen Monitor. Replaced faulty cell.

Degraded battery performance.

L47273 Division III Batteries. Paulty cell. Increased spring tension.

Less-than-desirable spring Valve failed local leak rate Drywell Equipment test.

L47530 Drain Inboard tension.

Isolation Valve. Increased spring tension.

Less-than-desired spring Valve failed lxal leak rate L47578 Drywell Equipment test.

Drain Sump Valve. tension.

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TABLE 1 CORRECTIVE MINTaman OF SAFETY RELATED BQUIPfEINT 4

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WORK R9 QUEST COMPONENT CAUSE OF MRLFUNCTION RESULTS AND EFFECTS CORR 8CTIVE ACTION ON SAFE OPERATION L47708 "A" Standby Liquid Faulty Relay. Meter falsely indicated complete Replaced relay.

Control Explosive circuit.

Valve Continuity Meter.

L47773 RCIC Ambient Cables mislabeled and Instrument would not respond, Relabeled cables and Temperature Element. landed incorrectly. landed correctly.

L47839 "B" Primary Contain- Loose contacts on torque Valve would not open from remote Tightened torque switch ment Chill Water switch. handswitch, contacts.

Supply Inbcard Isolation valve.

L48149 125 Volt DC Battery Blown fuses. No Voltage indication in control Replaced fuses.

Charger. room.

L48329 Outboard Feed Water Actuating cylinder was Would not pull valve to closed Cleaned and lubricated Check Valve "A". binding. position. actuator cylinder.

L48375 Scram Discharge Air leak on supply to valve Possibility to increase the Cleaned coupling in volume vent valve. actuator. the length of time required to air line.

insert rods during a scram if combined with other events.

L48505 Average Power Range Blown fuse. Half of downscale lights were Replaced fuse.

Monitor "F*. out.

L48628 Reactor Water Clen-up Broken torque switch. Valve would not completely close Replaced torque switch.

Inboard Isolation with motor operator.

Valve.

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TAaLE i CORR 8CTIVE PRINTENANCE OF SAFETY REIATED EQUIPMNT COff0NENT CAUSE OF MRLFUNCTION RESULTS AND EFFECTS CORR 9CTIVE ACTION NORK REQUEST Off SAFE OPERATION L48654 Standby Gas Treatment Valves software degraded. Valves leaked by, causing char- Replaced softwaretin System Deluge Valves. coal filter to get wet, valves.

L48745 Reactor Building Stuck open contactor. Damper tripped thermals when Replaced motor, open ventilation Exhaust cycling open. Burned out the contactor, and mechanical Damper. the motor. relay.

L49053 Diesel Generator "2B" Faulty K33 relay. Diesel Generator tripped on low Replaced relay K33.

oil pressure shortly after starting.

L4!!!3 LPCS Minimum Flow Switch out-of-calibration. Minimum flow valve did not Recalibrated switch.

Switch. automatically open when required.

DOCUBEENT 0044r/0005r

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3 C. LICENSEE EVENT REPORTS ,

t The following is a tabular summary of all licensee event reports for 1

LaSalle Nuclear Power Station, Unit Two, occurring during the reporting j period, May 1 through May 31, 1985. This information is provided .

4 pursuant to the reportable occurrence reporting requirements as set forth in 10CFR 50.'73.

t

, bicensee Event Report Number pate Title of Occurrence i 85-019-00 4-12-85 Primary Containment Group I

Isolation Signal.

i j 85-020-00 4-24-85 Missed Service Water Sample, d

i 85-021-00 5-3-85 RCIC Temperature Leak Detection '

Miswired.

i 85-022-00 5-16-85 Reactor Scram.

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o 8 s D. DATA TABULATIOtl8  ;

i 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 P

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DOCUNDfT ID 0036r/0005r

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1. OPERATING DATA REPORT DOCFET NO. 050-374 UNIT LaSalle Two DATE June 10, 1985 COMPLETED BY Richard J. Rohrer TELEPHONE (815)357-6761 OPERATING STATUS
1. REPORTING PERIOD: May, 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 WHICil RESTRICTED (IF ANY) (MWe-Net): N/A
4. REASONS FOR RESTRICTION (IF ANY):_N/A TilIS MONTil YR TO DATE CUMULATIVE 5 NUMBER OF HOURS REACTOR WAS CRITICAL 0.0 _1399.8 _3011.6
6. REACTOR RESERVE SliUTDOWN HOURS _ 0.0 _0.0 _125.3
7. HOURS GENERATOR ON LINE _ 0. 0 _1397.3 2934.7
8. UNIT RESERVE SitUTDOWN HOURS _ 0.0 _ 0.0 _ 0.0
9. GROSS THERMAL ENERGY GENERATED (MWH) 0.0 4387385 8894977
10. GROSS ELEC. ENERGY GENERATED (MWH) _ 0.0 _1460387 2945373
11. NET ELEC. ENERGY GENERATED (MWil) _-9397 1382193 2774510
12. HEACTOR SERVICE FACTOR __0.0% _38.4% _55.5%
13. HEACTOR AVAILABILITY FACTOR _ 0.0% _38.4% _57.8%
14. UNIT SERVICE FACTOR _ 0.0% _38.3% _.54.1%

lb. UNIT AVAILABILITY FACTOR _.0.0% _38.3% _54.1%

16. UNIT CAPACITY FACTOR (USING MDC)_ _-1.2% _36.6% _49.4%
17. UNIT CAPACITY FACTOR (USING DESIGN MWo) _-1.2% __3.5 . 2% _47.5%
18. UNIT FORCED OUTAGE NATE _ 0.0% _ 0.0% 4.4%
19. SHUTDOWNS SCliEDULED OVER NEXT 6 MONTitS (TYPE, DATE, AND DURATION OF EACH):

An outage for maintenance and surveillance was begun at 0520 on February 28, 1985.

20. IF SHUT DOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP June 14, 1985, DOCUMENT ID 0036r/0005r

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2. AVERAGE DAILY UNIT POWER LEVEL

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DCCKET NO: 050-374 UNIT: 1.A3At.t.E TWO DATE: June 10, 1985 COMPLETED BY: Richard J. Rohrer TELEPilONE: (815) 357-6761 MONTH: May 1985 DAY AVEHAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net)

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

DOCUMENT ID 0036r/0005r

ATTACMENT E

3. UNIT SHUTD0tAIS A M POWER REDUCTIONS DOCERT No. 050-374 UNIT NME LaSalle Ttso DATE JtalE 10, 1985 REPORT MONTH NY 1985 COWLETED BY Richard J. Rohrer TELEPHONE (815)357-6761 METHOD or TYPE SHUTTING DotM F: PORCED DURATION THE REACTOR OR CORRECTIVE NO. DATE S: SCHEDULED (HOURS) REASON REDUCING POWER ACTIONS /C0fGENTS 3 850228 S 744.00 B 2 Maintenance and Surveillance Outage begun 2-28-85 continues d

DOCUpstNT 0044r/0005r v_

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E. UNIQUE REPORTING REQUIREMENTS

1. safety / Relief valve operations for Unit Two.

VALVES NO & TYPE PLANT DESCRIPTION I PAIR ,

BCTUATED BCTUATIONS CONDITION OF EVENT i

5-23-85 2B21-F013D 1 Automatic Cold Shutdown Spurious Actuation, cause unknown.

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I DOCUMENT ID 0036r/0005r

~

  • *
  • 2. RCCS Sy;tems Outcge3 The following outages were taken on ECCS Systems during the reporting period.

QUTAGE NO. FOUIPMRNT EURPOSE OF OUTAGE 2-702-85 2H12-F004A Minor Maintenance.

2-706-85 2B Diesel Generator Assist Mechanical.

Fuel Oil Transfer Valve. Maintenance Department.

2-707-85 Low Pressure Core Spray. Check Coupling.

2-708-85 2A Diesel Generator "B" Repair A/C Poppet Air Compressor. relief.

2-710-85 2B RRR Service Water Pump Remove Motor.

2-714-85 Low Pressure Core Spray Water Clean and Lubricate Leg Pamp. Coupling.

2-740-85 High Pressure Core Spray Remove Spool piece.

Spool Piece.

2-747-85 20 Diesel Generator Fuel Oil Repair Leak.

Transfer Valve.

2-748-85 2812-C300C. Repair Motor.

2-755-85 2H12-F050A Assist Mechanical Maintenance Department.

2-756-85 2H12-F050A Reapair Binding.

2-760-85 2H12-F064A Repack Valve.

2-761-85 "A" RitR Pump Dreaker. Install Rubber Boots.

2-763-85 RCIC Pump. Repair Drain Line.

2-772-85 "B" RHR service Water Process Decontamination.

Radiation Monitor.

2-774-85 28 Diesel Generator. Maintenance and Surveillance.

2-785-85 RHR-Shutdown Cooling. Surveillance.

2-192-85 2A RHR Pump. Check Oil Level.

2-793-85 2A RilR Pump. Modification to Service Water Process Radiation Monitor.

DOCUMENT ID 0036r/0005r

o ,.

OUTAGE 40. EQUIPMENT PURPOSE OF OUTAGE 2-794-85 2A RHR. Surveillance.

2-799-85 200014 Troubleshooting.

2-801-85 2A RHR Service Water Process Decontamination.

Radiation Monitor.

2-802-85 2E22-F038. Testing.

2-803-85 "A" LPCI and LPCS Manual injection Valves. Surveillance.

2-805-85 High Pressure Core Spray. Isolate System.

2-806-85 28 Diesel Generator. Repair immersion Heater.

2-808-85 High Pressure Core Spray Determinate.

Full-Flow Line Heat Trace.

2-810-85 LPCS Water Leg Pump. Repai r Check Valve.

2-815-85 Division l Water Leg Pump. Repair Discharge Valve.

2-816-85 2A RHR Service Water Process Relocate.

Radiation Moni tor Skid.

2-822-85 High Pressure Core Spray Pump. Check Breaker.

  • **
  • 3. off-sito Dose C01culction Manual Revision 11 was made to the off-site Dose calcualtion Manual, incorporating changes requested by the Nuclear Regulatory comunission. l
4. Radioactive Waste Treatment Systems.

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

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t DOCUmtNT ID 0036r/0005r

Commonwealth Edison -

L S:llo County Nuclear Stahon RuralHouto #1, flox 220 Marsm!!as, llhnois 61341 Telephono 815/357 6761 June 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 May 1 through May 31, 1985.

Very truly yours, urkvS lG. J. Diederich S ation Manager LaSalle County Station GJD/RJR/cth Enclosure xc: J. G. Keppler, NRC, Region III NRC Resident Inspector LaSalle

  • Gary Wright, Ill. Dept. of Nuclear Safety D. P. Galle, Ceco D. L. Farrar, CECO INPO Records Center Ron A. Johnson, PIP Coordinator SNED J. B. Ellis, GE Resident J. M. Nowicki, Asst. Comptroller H. B. Bliss, Nuclear Fuel Services Manager C. F. Dillon, Senior Financial Coordinator ,J

((

y Document 0043r/0005r

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