ML20132G841

Monthly Operating Repts for Jul 1985

ML20132G841
Person / Time
Site:	LaSalle
Issue date:	07/31/1985
From:	Diederich G, Rohrer R COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
NUDOCS 8510010638
Download: ML20132G841 (35)

Text

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e' s-t LASALLE NUCLEAR POWER STATION UNIT 1 i

1 MONTHLY PERFORMANCE REPORT JULY 1985

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COPMONWEALTH EDISON COMPANY 4

NRC DOCKET NO. 050-373 LICENSE NO. NPF-ll I

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ADOCK 05000373 1C/l Document 0043r/0005r f

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INTRODUCTION The LaSalle County Nuclear Power Station is a two-unit facility owned by Commonwealth Edison Comapny 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 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 April 17, 1982. Initial criticality was achieved on June 21, 1982, and commercial power operation was commenced on January 1, 1.984.

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

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g.P TABLE OF CONTENTS I.

INTRODUCTION II.

MONTHLY REPORT FOR UNIT ONE 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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MONTHLY REPORT FOR UNIT ONE A.

SUMMARY

OF OPERATING EXPERIENCE FOR UNIT ONE July ~1-26 July 1, 0001 Hours Reactor power at 6.3%.

July 1, 0230 Hours Generator Synchronized to Grid July 1, 0700 Hours Reactor Power at 34%.

July 2, 1500 Hours Reactor Power at 66%.

July 3, 2300 Hours Reactor Power at 86%.

July 6, 0830. Hours Suppression pool spray inoperable, commence 7 day timeclock.

July 11, 2300 Hours Reactor Power at 47%.

July 12, 0615 Hours Reactor manually scrammed. The reactor was critical for 270 hours0.00313 days <br />0.075 hours <br />4.464286e-4 weeks <br />1.02735e-4 months <br /> and 15 minutes.

JULY 27-31 July 27, 1930 Hours Reactor Critical July 28, 1215 Hours Generator Synchronized to Grid.

July 28, 2300 Hours Reactor Power at 45%.

July 29, 0700 Hours-Reactor Power at 72%.

July 31, 2300 Hours Reactor Power at 96%. The reactor was critical for 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> and 30 minutes. Totaling 370 hours0.00428 days <br />0.103 hours <br />6.117725e-4 weeks <br />1.40785e-4 months <br /> and 45 minutes for the i

month of July.

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

1.

Amendments to facility license or Technical Specification.

There were no amendments to the facility license or Technical Specifications during this reporting period.

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, Results and Effects on Safe Operation, and Corrective Action.

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TABLE 1 CORRECTIVE MAINTENANCE OF SAFETY RELATED EQUIPMENT WORK REQUEST COMPONENT CAUSE OF MALFUNCTION RESULTS AND EFFECTS CORRECTIVE ACTION ON SAFE PLANT OPERATION L33149 RHR Shutdown Cooling Eroded seat and disc.

Vave leaked in excess of allow-Lapped seat and ground Discharge Valve, able limits, disc.

IE12-F053A.

L49899 Hathaway Sequence-of-Faulty series switch MSIV 1/2 Isolation on Jumpered switch out.

Events recorder.

IE21-N008A.

erroneous signal.

L49994 Outboard MSIV "A".

Limit switch in improper Dropped out RPS K3B relay and Corrected Limit Switch

position, would not reset.

Position.

L50046 1A RHR Heat Exchanget. Fouled tubes.

Could not obtain desired service Cleaned tubes.

water flow.

L50066 Accident Monitoring Recorder Out-of-Calibration Incorrect indication.

Recalibrated.

Wide Range Level Recorder.

L50100 RHR Suppression Pool Faulty torque switch.

Tripped Thermal Overloads while Cleaned and adjusted' Spray Valve,-

closing.

torque switch.

IE12-F0278.

L50121 IA Drywell Pneumatic Bent tubing allowed control Compressor would not. load.

Installed new tubing.

Compressor.

air to leak.

L50122 Division I Post-LOCA Faulty reagent flow Indicated low.

Replaced reagent flow Oxygen Monitor.

regulator.

regulator.

L50130 RHR Suppression Pool Worn seat and disc.

Excessive leakage through valve Lapped Valve seat and Spray Valve, B RHR could not be maintained disc.

IE12-F0278.

full in standby.

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l CORRECTIVE MAINTENANCE OF SAFETY RELATED EQUIPMENT WORK REQUEST COMPONENT CAUSE OF MALFUNCTION RESULTS AND EFFECTS CORRECTIVE ACTION ON SAFE PLANT OPERATION L50134 HCU Accumulator for Stem bent on instrument Leaked nitrogen; potential to Replaced Valve.

CRD 02-31.

block stop valve.

cause failure to scram this rod if combined with other events.

L50196 Ammonia Detector.

Optics wire broken Inoperable detector.

Repaired wire.

during surveillance.

L50251 Control Room Venti-Blown Oil seal 9egraded ventilation from "B" Replaced seal.

Iation Air Condition-Control Room HVAC.

Compressor "B".

L50416 IB Diesel Generator Loose bolts on turbocharger Potential to cause degraded Torqued bolts.

Diesel performance L50460 IB Diesel Generator Bent Plunger Striker on Prevented proper over-current Installed new plunger K9 Relay.

Switchgear 143 cubicle 001. trip function of ACB 1432.

striker.

L50481 Standby Liquid Control Would not open at desired Potential to cause failure Changed relief of Standby Liquid Control Piping. setting.

Pump 1A Discharge pressure.

Relief Valve.

L50525 HCU Accumulator for III Valve leaked Nitrogen. Potential to cause failure to Replaced valve.

CRD 34-51.

scram this rod if combined with other events.

L50643 HCU for CRD 30-35, Instrument Block Valves Potential to cause failure to Replaced valves.

and HCU for CRD 46-07. leaked nitrogen to scram these rods if combined atmosphere.

with other events.

L40644 HCU for CRD 54-39.

Instrument block valve Potential to cause failure Replaced valve.

leaked nitrogen to to scram this rod if combined atmosphere.

with other events.

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TABLE 1 CORRECTIVE MAINTENANCE OP SAFETY RELATED EQUIPMENT WORK REQUEST COMPONENT CAUSE OF MALIMINCTION RESULTS AND EFFECTS CORRECTIVE ACTION ON SAFE PLANT OPERATION L41909 Reactor Recirculation Degraded packing Packing leak.

Repacked Valve.

Discharge Valve, 2B33-FO67A.

L50069 1A RHR Service Assembled incorrectly Strainer leaked considerably; Reassembled strainer.

Water Strainer.

following maintenance.

potentially degraded RHR "A" performance.

L50513 1A RHR Heat Exchanger Tubes fouled.

Could not obtain required Service Cleaned tubes.

Water flow.

L50336 Safety Relief Valve Broken set screw on nozzle No significant effect.

Replaced with improved C.

ring.

set screw.

LS0337 Safety Relief Valve Broken set screw on nozzle No significant effect.

Replaced with improved D.

ring, set screw.

L50338 Safety Relief Valve Broken set screw on nozzle No significant effect.

Replaced with imrpoved E.

ring.

set screw.

L50339 Safety Relief Valve Broken set screw on nozzle No significant effect.

Replaced with. improved F.

ring.

set screw.

L50342 Safety Relief Valve Broken set screw on nozzle No significant effect.

Replaced with imrpoved J.

ring.

set screw.

L50344 Safety Relief Valve Broken set screw on nozzle No significant effect.

Replaced with improved L.

ring.

set screw.

L50345 Safety Relief Valve Broken set screw on nozzle No significant effect.

Replaced with improved M.

ring.

set screw.

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TABLE 1 CORRECTIVE MAINTENANCE OF SAFETY RELATED EQUIPMENT WORK REQUEST COMPONENT CAUSE OF MALFUNCTION RESULTS AND EFFECTS CORRECTIVE ACTION ON SAFE PLANT OPERATION L50347 Safety Relief Valve _

Broken set screw on nozzle No significant effect.

Replacedwithimrhved P.

ring, set screw.

L50348 Safety Relief Valve' Broken set screw on nozzle No significant effect.

Replaced with improved R.

ring.

set screw.

L50350 Safety Relief Valve Broken set screw on nozzle No significant effect.

, Replaced with improved

.U.

. ring, set screw.

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LICENSEE EVENT REPORTS The following is a tabular. summary of all licensee event reports for LaSalle Nuclear Power Station, Unit One, logged during the reporting period, July 1 through July 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 85-048-00 6-14-85 "A" RHR WS PRM INOP 85-049-00 6-25-85 Chlorine Detector Trip 85-050-00 6-26-85 "A" VC/VE Ammonia / Chlorine Detector Alarms 85-051-00 6-27-85 Spurious Chlorine Detector Trip.

85-052-00 6-29-85 Manual Reactor Scram 85-053-00 7-17-85 RHR Shutdown Cooling Suction

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High Flow Isolation Switches Installed Backwards.

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

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Operating Data Report i

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Average Daily Unit Power Level 3.

Unit Shutdowns and Power Reductions 4

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

REPORTING PERIOD: JULY, 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):

N/A 4.

REASONS FOR RESTRICTION (IF ANY):N/A THIS MONTH YR TO DATE CUMULATIVE 5

NUMBER OF HOURS REACTOR WAS CRITICAL 370.8 3879.5 10161 6.

REACTOR RESERVE SHUTDOWN HOURS 373.3 476.2 1642 7.

HOURS GENERATOR.ON LINE 351.5 3726.0 9783 8.

UNIT RESERVE SHUTDOWN HOURS 0.0' O.0 0.0 9.

GROSS THERMAL ENERGY GENERATED (MWH) 847778 10290841 27114130 10.

GROSS ELEC. ENERGY GENERATED (MWH) 266164 3375933 8846576 11.

NET ELEC. ENERGY GENERATED (MWH) 249325 3244270 8439332 12.

REACTOR SERVICE FACTOR 49.8%

75.9%

73.1%

13.

REACTOR AVAILABILITY FACTOR 100%

85.2%

84.9%

14.

UNIT SERVICE FACTOR 47.2V 72.9%

70.4%

15.

UNIT AVAILABILITY FACTOR 47.2%

72.9%

70.4%

16.

UNIT CAPACITY FACTOR (USING MDC) 32.3%

61.3%

58.6%

17.

UNIT CAPACITY FACTOR (USING DESIGN MWe)

_31.1%

58.9%

56.3%

18.

UNIT FORCED OUTAGE RATE 52.6 23.6%-

19.9%

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 REPORT PERIOD, ESTIMATED DATE OF STARTUP: NA i

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

(MWe-Net) 1.

170 17.

-18 2.

439 18.

-17 3

814 19.

-17 4.

749 20.

-18 4

5.

884 21.

-18 6.

871 22.

-21 7.

785 23.

-17 i

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878-24.

-15 9.

877 25.

-16 10.

879 26.

-16 11.

821 27.

-16 12.

51 28.

90 13.

-18 29.

695 14.

-17 30.

724 15.

-17 31.

923 16.

-19 3

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ATTACHMENT E 3.

UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 050-373 UNIT NAME LaSalle One

.i DATE JULY 10, 1985 REPONT MONTH JULY 1985 COMPLETED BY Richard J. Rohrer TELEPHON3 (815)357-6761 METHOD OF TYPE SHUTTING DOWN F: FORCED DURATION THE REACTOR OR CORRECTIVE NO.

DATE S: SCHEDULED (HOURS)

REASON REDUCING POWER ACTIONS /COPMENTS

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l 14 850629 F

2.5 A

4 Continuation of outage I

from previous month, 15 850712 F

390.0 A

2 Unit shutdown due to inoperable suppression pool spray valve IE12-F0278.

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UNIQUE REPORTING REQUIREMENTS t

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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ECCS Systems Outtg:s s.

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

OUTAGE NO.

EOUIPMENT PURPOSE OF OUTAGE l-552-85 1C RHR Pump Lubrication 1-554-85 1A RHR Heat Clean Tubes Exchanger 1-556-85 IE12-F027B Repair Valve 1-557-85 lE12-F027B Repair Valve 1-558-85 IE12-F027B Adjust Limit Switches 1-565-85 lE12-F063A Keep RRR pressurized 1-568-85

~1B RHR Service Repair Pump Water Pump 1-572-85 IB D/G Lubrication 1-573-85 Shutdown Cooling PreventInitiation Suction Header with vents open.

1-574-85 lE12-F027B Maintain Primary containment.

1-576-85 1B D/G Calibration l-577-85 lE12-F027B Maintain Primary containment 1-578-85 lE12-F027B Remove Actuator:

1-579-85 IE12-F027B Remove Actuator 1-585-85 IE12-F053A Repair Valve 1-586-85 1E12-F053A Repair Actuator 1-587-85 1E12-F004A Prevent Operation 1-588-85 lE12-F027B Repair Valve.

I-1-594-85 IB RHR Pump Oil Sample 1-609-85 lE12-F004A Repair Torque Switch l

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OUTAGE MO.

BOUIPMENT PURPOSE OF OUTAGE I

1-611-85 1E12-F023 Prevent-operation 1

'l-626-85 1812-N012AA Repipe Instrument 1-630-85 1E12-F004A Repair Limitorque 1-636-85 1A RHR Heat Clean Tubes' Exchanger 1-638-85 1812-D300A Inspect and Clean 1-642-85 1812-F023 verify wiring on valve 1-652-85 1E12-F008 Perform LIS-NB-311 1-653-85 1E12-D300A Repair Leaks 1-655-85 RHR Shutdown Vent path for LST-85-45 Cooling Valves 1-658-85

,1E12-F336A Replace Retainer Ring J

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3.

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

4.

Radioactive Waste Treatment Systems, i

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

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1 LASALLE NUCLEAR POWER STATION UNIT 2 MONTHLY PERFORMANCE REPORT J

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COfMONWEALTH EDISON COMPANY i

4 NRC DOCKET NO. 050-374 LICENSE NO. NPF-18 f

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TABLE OF CONTENTS 1.

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 Le'iel 3.

Unit Shutdowns and Power Reductions E.

UNIQUE REPORTING REQUIREMENTS l

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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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 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 architecht-engineer was Sergent 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 number (815)357-6761 extension 575.

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MONTHLY REPORT FOR UNIT TWO A.

SUfftARY OF OPERATING EXPERIENCE FOR UNIT TWO JULY 1 July 1, 0001 Hours Reactor subcritical. Unit two still in scheduled outage.

JULY 20-31 July 20, 2125 Hours Reactor Critical July 22, 0530 Hours Generator Synchronized to Grid July 22, 0630 Hours Main Turbine Trip Due to High Level in MSR Drain Tank.

July 22, 0800 Hours Generator Synchronized to grid.

July 23, 0300 Hours Removed Main Turbine From Grid for RCIC Surveillance i

July 23, 0420 Hours Generator Synchronized to Grid July 24, 0700 Hours Reactor Power at 34%

July 25, 1500 Hours Reactor Power at 64%

July 26, 1500 Hours Reactor Power at 82%.

July 27, 0700 Hours Reactor Power reduced to 67% for Rod Shuffle July 27, 1500 Hours Reactor Power at 86%.

July 31, 0700 Hours Reactor Power at 96%.

July 31, 1500 Hours Reactor Power at 78%.

July 31, 2300 Hours Reactor Power Reduced to 23%.

Bringing Unit Down to Investigate High Drywell Temperatures. The Reactor was Critical for 266 Hours and 35 Minutes During.the Month of July.

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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.

2.

Facility or procedure changes requiring NRC approval.

There werue n 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 t

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.

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1 TABLE ~1 CORRECTIVE-MAINTENANCE OF SAFETY.RELATED EQUIPMENT WORK REQUEST COMPONENT CAUSE OF MALFUNCTION PESULTS AND EFFECTS CORRECTIVE ACTION-ON SAFE PLANT OPERATION L43822 HCU for CRD 02-39 Scram pilot valve had an Potential to cause half-scram Replaced 0-ring seals in air leak.

for this rod.

valve.

L42825-HCU for CRD 02-39 Scram pilot valve had an Potential,to cause half-scram Replaced 0-ring seals 1

air leak.

for this rod.

in vlave.

l L46594 HCU for CRD 10-31.

Scram pilot valve had Potential to cause half-scram Rebuilt valve.

an air leak.

for this rod.

t.

L46655 RCIC Outboard Steam Degraded valve packing.

Significant steam leak through Repacked valve.

_ Isolation valve.

packing.

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L47320 Outboard Feedwater Actuating Cylinder leaked Degraded Valve Operation.

Rebuilt actuating d

~ Check valve "B".

air.

cylinder.

L47356 Outboard Feedwater Both actuating cylinders Degraded Valve Operation.

Rebuilt Actuating check Valve'"A"._

leaked air, cylinders L47518 Drywell Pneumatic Worn Valve seat.-

Leakage in excess of desired Lapped seat.

j Dryer Purge Valve.

amount.

L47529 Floor. Drain Inboard Crud obstructing valve Valve leaked in excess of Cleaned valve.

Isolation valve,

motion, allowable amount.

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L47591 Safety Relief Valve Damaged Valve Seat and Valve leaked steam by.

Replaced valve, i

"E".'

disc.

. L47592 SaCaty Relief Valve Damaged Valve seat and Valve leaked-steam by.

Replaced valve.

"R".

disc.

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L47631 RCIC Turbine Exhaust Limit Switches out of Valve would not fully close Repositioned limit Isolation valve.

Adjustment.

exept manually, switches.

2E51-F068.

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TABLE 1 CORRECTIVE MAINTENANCE OF SAFETY RELATED EQUIPMENT WORK REQUEST COMPONENT CAUSE OF MALFUNCTION RESULTS AND EFFECTS CORRECTIVE ACTION ON SAFE PLANT OPERATION L47692 HCU for CRD 18-07.

Scram, pilot valve had Potential to cause a half-scram Rebuilt valve.

a severe air leak.

of this control rod.

L47763 HCU for CRD.06-27.

Scram pilot valve leaked Potential to cause a half-scram Rebuilt valve.

air.

of this control rod.

-4 L48300 Hydrogen Recombiner Worn valve disc.

Failed local leak rate test.

Replaced Valve disc.

exhaust upstream isolation valve, 2HG006A.

j L48693 Reactor Pressure No instrument rack stop.

Could not isolate instrument.

Installed new stop 1-interlock switch, valve.

valve.

2B21-N039L.

L49227 Hydrogen Recombiner Worn Valve disc. and seat. Valve failed local leak rate Replaced disc and exhaust downstream test.

lapped seat.

isolation valve, i

2HG005A.

i L49768 RHR Shutdown Cooling Switches were piped back-Switches were inoperable.

Piping corrected.

High Flow isolation

wards, switches, 2812-N012AA and AB.

L49788 HCU for CRD 06-35.

Leaking drain valve on Potential to cause failure Rebuilt Valve.

accumulator.

to scram this rod if combined with other events.

L49843 Feedwater Check Valve Incorrect solenoids Air leaked on actuator; Possibly Installed correct 4

2B21-F032A.

installed.

possibly degraded valve solenoids.

operation.

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E TABLE 1 CORRECTIVE MAINTENANCE OF.

SAFETY RELATED EQUIPMENT l

WORK REQUEST COMPONENT CAUSE OF MALFUNCTION RESULTS AND EFFECTS CORRECTIVE ACTION-l CN SAFE PLANT OPERATION

?

L49856 Scram Reset Switch.

Switch stuck in reset Groups 1 and 4 would automaticaly Installed new switch position.

reset if scram signal cleared.

operator.

L49858 Safety Relief Valve Broken set screw in nozzle No significant effect.

Replaced with improved 3

A.

ring.

set screw.

j. L49860 Safety Relief Valve Broken Set Screw in nozzle No significant effect.

Replaced with improved C.

ring, set screw.

L49861 Safety Relief Valve Broken set screw in nozzle No significant effect.

Replaced with improved l

D.

ring.

set screw.

I L49863 Safety Relief Valve Broken set screw in nozzle No significant effect.

Replaced with improved l

F.

ring.

~

set screw.

j L49864 Safety Relief Valve Broken set screw in nozzle No significant effect.

Replaced with improved j

G.

ring.

set screw.

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j L49865 Safety Relief Valve Broken set screw in nozzle.No significant effect.

Replaced with improved H.

ring.

set screw.

4 L49868 Safety Relief Valve Broken set screw in nozzle No significant effect.

Replaced with improved j

.L.

ring.

set screw.

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L49869 Safety Relief Valve Broken set screw in nozzle No significant effect.

Replaced with inproved M.

ring.

set screw.

' L49871 Safety Relief Valve

. Broken set screw in nozzle No significant effect.

Replaced with improved j

P.

ring.

set screw.

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L49875 Safety Relief Valve Broken set screw in nozzle iJo significant effect.

Replaced with inproved

]

V.

ring.

set screw.

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TABLE 1 CORRECTTVE MAINTENANCE OF SAFETY RELATED BQUIPMENT WONK REQUEST COMPONENT CAUSE OF MALFUNCTION RESULTS AND EFFECTS CORRECTIVE ACTION ON SAFE PLANT OPERATION j

L49900 Diesel Generator Bent Actuating Arm on Cooling Water Pump did not start Adjusted Actuating arm.

Cooling Water Pump B.

_ auxiliary contacts, when HPCS Pump started.

L49983 Various HCU's for Instrument block stop Potential to cause failure to Replaced leaking valves.

Control Rod Drives.

valves leaked at steam.

scram the affected rods if combined with other events.

L49988 HCU for CRD 26-03.

Instrument block stop Potential to cause failure to Replace Valve.

valve leaked by stem.

scram this rod if combined i

with other events.

i LS0366 Division III Battery High Voltage shutdown Charger output would not reach Reset'high voltage

}

Charger.

board set incorrectly.

desired value.

shutdown board.

i L50421 2A Diesel Generator.

Loose bolts on turbocharger. Potential for degraded diesel Torqued bolts.

j operation.

' L50479 HCU for CRD 18-39.

Instrument block stop valve Potential to cause failure to Replaced valve.

had a severe stem leak, scram this rod if combined with other events.

L50514 HCU for CRD 50-31.

Instrument block stop valve Potential to cause failure to Replaced valve.

i had a stem leak.

scram this rod if combined with other events.

L50602 RCIC Turbine.

Governor out of adjustment. Could not control turbine speed Adjusted governor, or pump output.

L50636 HCU for CRD 58-31.

Instrument Block stop valve Potential to cuase failure to Replaced valve.

leaked at packing.

scram this rod if combined with other events.

e T

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DOCUMENT 0044r/0005r

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C.

LICENSEE EVENT REPORTS The following is a tabular summary of all licensee event reports for LaSalle Nuclear Power Station, Unit Two, logged during the reporting period, July 1 through July 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 85-029-00 6-10-85 Pressure Switch 2B21-NO37AA and 2B21-NO37AB piped Backwards.

85-030-00 6-26-85 Group II Isoltion 85-031-00 6-22-85 RHR Shutdown Cooling High Suction Flow Isolation 85-032-00 7-1-85 Leak Detection Div. I & II RHR AT 85-033-00 7-1-85 RHR Shutdown Cooling Isolation.

85-034-00.

6-25-85 Temporary Voltage Degradation During 237 Transformer Failure.

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s DOCUMENT ID 0036r/0005r

s.

1

)

D.

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

4 i

1. Operating Data Report

2. Average Daily Unit Power Level

3. Unit Shutdowns and Power Reductions e

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l DOCUMENT ID 0036r/0005r-l

1. OPERATING DATA REPORT DOCKET NO. 050-374 UNIT LaSalle Two l

DATE August 10, 1985 l

COMPLETED'BY Richard J. Rohrer I

TELEPHONE (815)357-6761 l

OPERATING STATUS 1.

REPORTING PERIOb: July, 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 f

4.

REASONS FOR RESTRICTION (IP ANY): N/A

" EC OR RES $v"" " E ToOWN"'""^$US

'E*3

(

' " " ' ' ^ '

o 0

7.

HOURS GENERATOR ON LINE 231.7 1629.0 3166.4 8.

UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 0.0 9.

GROSS THERMAL ENERGY GENERATED (MWH) 493368 4880753 9388345 10.

GROSS ELEC. ENERGY GENERATED (MWH) 156348 1616735 3101721 11.

NET ELEC. ENERGY GENERATED (MWH) 141584 1515220 2907537 12.

REACTOR SERVICE FACTOR 35.8%

32.6%

47.6%

13.

REACTOR AVAILABILITY FACTOR 35.8%

32.6%

49.4%

14.

UNIT SERVICE FACTOR 31.3%

31.9%

46.0%

15.

UNIT AVAILABILITY FACTOR 31.1%

31.9%

46.0%

16.

UNIT CAPACITY FACTOR (USING MDC) 18.4%

_28.6%

40.8%

17.

UNIT CAPACITY FACTOR (USING DESIGN 17.7%

27.5%

39.2%

MWe) 18.

UNIT FORCED OUTAGE RATE 0.0%

0.0%

7.0%

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 I

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• '2. AVERAGE DAILY UNIT POWER LEVEL

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

(MWe-Net) 1.

-13 17.

-17 2.

-13 18.

-17 3

-15 19.

-16 4.

-18 20.

-17 5.

-14 21.

-18 6.

-15 22.

80 7.

-15 23.

165 8.

-15 24.

300 9.

-14 25.

563 10.

-15 26.

807

11. ~ 27.

668 12.

-16 28.

869 13.

-17 29.

1003 14.

-17 30.

1016 15.

-17 31.

765 16.

-18 i

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DOCUMENT ID.0036r/0005r

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ATTACHMENT E 3.

UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 050-374 UNIT NAME LaSalle Two DATE August 10,1985 REPORT MONTH JUNE 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 / COP 9fENTS 3'

850228 S

509.5 B

4 Maintenance and Surveillance outage l

continued from February.

4 850722-F 0.0 A

5 Turbine trip due to high le'/c1 in MSR Drain i

Tank.

5 850723 S

0.0 B

5 Took Turbine off for RCIC Surveillance.

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DOCUMENT 0044r/0005r r

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E.

. UNIQUE REPORTING REQUIREMENTS 1.

Safety / Relief Valve Operations for Unit Two.

DATE VALVES NO & TYPE PLANT DESCRIPTION ACTUATED ACTUATIONS' CONDITTON OF EVENT 7-23-85 2B21-F013E 2 Manual 960 PSIG Inadvertantly opened during Set Pressure verification Test.

7-23-85 2B21-F013N 1 Manual 960 PSIG Inadvertantly Opened during Set Pressure Verification Test.

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2.

ECCS Systems Outagrs L

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

OUTAGE NO.

EOUIPMENT PURPOSE OF OUTAGE 2-1013-85 LPCS Water Leg Pump Lubrication 2-1019-85 2E12-F024A Repair Limitorque 2-1023-85 2E12-F024A Disconect Motor 2-1030-85 2A D/G Lubrication 2-10'59-85 A/B RHR Service Polarization Test Water Pumps 2-1062-85 A/B RHR Shutdown LIS-NB-211 Cooling 2-1063-85 C/D RHR Service Surveillance Water Pump i

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DOCUMENT ID'0036r/0005r

. s 3.

Off-Site Dosa Calculation Manutl 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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C mm:nwIcith Edison a'..

LaSalle County Nuclear Station e

S

-i Rural Route #1, Box 220

'v' Marseilles, Illinois 61341

\\

Telephone 815/357-6761 August 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 July 1 through July 31, 1985.

Very truly yours, 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 f

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Document 0043r/0005r-

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