ML20212F561

Monthly Operating Repts for Jul 1986

ML20212F561
Person / Time
Site:	LaSalle
Issue date:	07/31/1986
From:	Diederich G, Peters J COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF ADMINISTRATION (ADM), NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
0043R-0005R, 43R-5R, NUDOCS 8608130344
Download: ML20212F561 (34)

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{ LASALLE NUCLEAR POWER STATION UNIT 1 MONTHLY PERFORMANCE REPORT i '

j JULY, 1986 1

i COMMONWEALTH EDISON COMPANY j

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' NRC DOCKET NO. 050-373 LICENSE NO. NPF-ll i

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o e TABLE OF CONTENTS s,

I. INTRODUCTION II. MONTriLY REPORT FOR UNIT OWs 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 '

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, 1 I. INTRODUCTION The LaSalle County Nuclear Power Station is a two-unit l facility owned by commonwealth Edison company and I located near Marseilles, Illinois. Each unit is a l Boiling Water Reactor with a designed net electrical  !

output of 1078 Megawatts. Waste heat is rejected to a i man-made cooling pond using the Illinois River for I make-up and blowdown. The architect-engineer was Sargent and Lundy and the primary construction contractor was Commonwealth Edison Company.

Unit one was issued operating license number NPF-11 on l April 17, 1982. Initial criticality was achieved on l June 21, 1982 and commercial power operation was i commenced on January 1, 1984. l This report was compiled by James P. Peters, telephone number (815)357-6761 extension 325.

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i II. MONTHLY REPORT FOR UNIT ONE A.

SUMMARY

OF OPERATING EXPERIENCE FOR UNIT ONE July 1-31 July 1, 0001 Hours. The unit entered July with the reactor subcritical and off-line in cold shutdown for first refueling outage.

July 31, 2400 Hours. Reactor in Cold Shutdown for First Rafueling Outage.

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

[ MAINTENANCE.

1. Amendmanta to facility license or Technical Specification.

There were no amendments to facility license or Technical Specifiction Changes 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 N e

CORRECTIVE MAINTENANCE OF SAFETY RELATED EQUIPMENT WORK REQUEST COMPONENT CAUSE OF MALFUNCTION RESULTS AND EFFECTS CORRECT 3NE ACTION ON SAFE PLANT OPERATION L26062 PRM Sample Skid Uncontrolled Rad Area. Move PRM Skid into the Turbine Keeping Radiation Area in OD18-J007. M-1-0-83-022. Building 663 Level. Plant and Not Outside.

L30323 MSIV-LCS Blower Environmental Qualification. Replaced Plastic Fan Blade Replaced Fan Blade.

Fan Blade 1832-c001. M-1-1-84-012. with Aluminum.

L30324 MSIV-LCS Blow for Fan Environmental Qualification Replaced Plastic Fan Blade Replace Fan Blade.

Blade 1832-C002. M-1-1-84-012. with Aluminium.

L30325 MSIV-LCS Blower Environmental Qualification Replaced Plastic Fan Blade Replaced Fan Blade.

Fan Blade 1832 M-1-1-84-012, with Aluminium.

L35016 Suppression Pool Level Common Circuitry Loop to Control Room and Remote Completed per Loop IC61-P001. M-1-1-84-047. Shutdown are isolated. Modification.

L44130 North D/W Pneumatic Sporadic Operation. Excessive Loss of Bottle Rebuilt Regulator Bottle Bank Regulator Pressure. Valve.

LINO 38.

L54572 Reactor Water Level Bad Transmitter. Needed to complete LIS-NB-107. Replaced Transmitter.

Active Fuel Zone IB21-F044.

L55001 1A Reactor Recirc. Packing Leak. Contamination Control. Repack Valve.

Disch. Valve IB33-F067A.

L56414 RBCCW Isolation No Limiter Plate on Torque No Potential effect. Installed Limiter Valve IWRI?9. Switch. Plate.

L56427 Mechanical Snubber Failed Snubber. Failed LTS-500-14. Replaced Snubber.

IMSc6-1005S.

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TABLE 1 CORRECTIVE MAINTENANCE OF SAFETY RELATED EQUIPMENT WORK REQUEST COMPONENT CAUSE OF MALFUNCTION RESULTS AND EFFECTS CORRECTIVE ACTION ON SAFB PLANT OPERATION L56995 RCIC Vacuum Bkr. Current in excess of 130%. Valve Bound up but operable. Replaced and repacked IE51-F086. the valve.

L57701 A VC Air Conditioning Excessive Loading / Unloading Excessive Compressor operation. Drained oil and replaced compressor OvC05CA. oil filter and repaired freon leak.

L58057 "A" RHR Outlet Valve Packing Leak. Contamination Control. Replaced Valve.

IE12-F068A.

LS8137 Mechanical Snubber Failed Snubber. Failed LTS-500-14. Replaced Snubber.

ILC01-1059S.

LS8532 Ian G IC51-K60lG Bad Switching Relays. Improper Instrument Operation. Installed New switches and cleaned connectors.

L58819 SRV Relief Valve Bad Control Fuse. Solenoid would not energize. Replaced control fuse.

1B21-F013E.

LS8851 Mechanical Snubber Failed Snubber. Failed LTS-500-14. Replaced Snubber.

INB13-1002S L58998 0 DG "A" Air Compressor Pressure switch out of Does not cycle at desired Recalibrated Switch.

I calibration, pressures.

! L59020 "A" VC Cooler Switch out of Calibration. Sticking switch inter locks "A" 'Recalibrated switch.

Condensing Fan VC Compressor From Starting.

Differential Pressure Interlock OPDS-VCO95A L59023 Div-II Post LOCA. System Backpressure too With Drywell Purged, indicated Readjusted Back Pressure Monitor System. High. Air O2 concentration at to 1/2 inch vacuum.

13%.

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o TABLE 1 CORRECTIVE MAINTENANCE OF l SAFETY RELATED EQUIPMENT I

WORK REQUEST COMPONENT CAUSE OF MALFUNCTION RESULTS AND EFFECTS CORRECT 2VE ACTION ON SAFE PLANT OPERATION L590% 1B RR Flow Control Blown Control Power Fuse. Valve would not move when Replaced Fune.

Valve 1B33-F0608. given a signal.

L59099 South Bank D/W Bad Check Valve O-Rings. Failed LTS-600-15, would not Replaced 0-rings.

Pneumatic Check Hold Pressure.

Valve IIN044.

4 L59207 MSL Drain Valve Bad Transformer and Breaker would not stay closed. Replaced Transformer and IB21-F068. Grounded Wiring. Repaired Bad Wires.

! L59349 "lA" VC Compressor Bad Compressor Intervals. Compressor Tripped on High Oil Replaced Compressor.

OVC05CA. Temperature.

L59419 1B RHR Loop B Monitor Bad Transistor (Q14). High Alarm will not work when Replaced Trainsistor (Q14).

ID18-K605. given a trip signal during LIS-RH-105.

, L59456 IB VC Ammonia Bad Capstan Pulley. Cassette Drive Appears to be Replaced Capstan Pulley.

Detector OXY-VC165A. dragging causing periodic trips of Detector.

L5951*l IB VC Ammonia Broken Head on Fuse Holder Ammonia Detector Tripped and Repaired Broken Head Detector OXY-VC165A. and Would Not Reset. on Fuse Holder.

L59548 1AP83E MCC-136Y, Compt Cracked and Defective OL OL Relay would not reset. Replaced OL Relay.

B4 for IC41-C001B. Relay.

L59563 SBGT WRGM. Failed Preamp Connector. Control Room Keeps Getting Inst. Rebuilt Preamp connector.

Failure Indication.

L59753 IB VC Ammonia Detector Alarm Relay Contacts Have System Would Not Trip Resoldered Alarm

- OXY-VC165A. Cold Solder Joints. During LIS-VC-053. Relay Contacts.

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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 One, logged during the reporting period, July 1 through July 31, 1986. 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 86-021-00 06/08/86 Spurious trip of VC Radiation Monitor due to possible electronics problem.

86-022-00 06/12/86 SDC Isolation due to inadvertant movement of wrong keylock switch.

86-023-00 06/13/86 VR Damper Isolatio.1 during Surveillance due to improperly installed jumpers.

86-024-00 06/17/86 Small Bore piping design error due to not being within limits.

86-025-00 06/25/86 Spurious ESF Actuation on "B" VC/VE not being completely stabilized following source calibration due to possible procedure problem.

86-026-00 06/23/86 Exceeded allowable frequency of airlock testing due to improper computer entry.

86-027-00 06/28/86 Spurious "B" VC/VE Ammonia Detector Trip due to broken chemcassette tape.

86-028-00 07/02/86 Spurious "B" VC/VE Ammonia Detector Trip due to loss of control power.

86-029-00 07/03/86 possible IRM Design problem due to failue of 24 VDC fuses.

86-030-00 07/04/86 Auto Start of "B" VC Emergency Make-up Train on HI Radiation due to Bad sensor.

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l D. DATA TABULATIONS

The following data tabulations are presented in this repcrt:

1 l 1. Operating Data Report

2. Average Daily Unit Power Level

3. Unit Shutdowns and Power Reductions l

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1. OPERATING DATA REPORT DOCKET NO. 050-373 UNIT LaSalle One DATE 8/10/66 COMPLETED BY James P. Peters

. TELEPHONE (815)357-6761 OPERATING STATUS

1. REPORTING PERIOD: July 1986 GROSS HOURS IN REPORTING PERIOD: 744

2. CURRENTLY AUTHORIZED POWER LEVEL (MWt):3323 MAX DEPEND CAPACITY (MWe-Net): 1036 DESIGN ELECTRICAL RATING (MVe-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 0.0 0.0 12039.00

6. REACTOR RESERVE SHUTDOWN HOURS 0.0 0.0 1642.00

7. HOURS GENERATOR ON LINE 0.0 0.0 11642.00

8. UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 0.0

9. GROSS THERMAL ENERGY GENERATED (MWH) 0.0 0.0 32213650

10. GROSS ELEC. ENERGY GENERATED (MWH) 0.0 0.0 10499394

11. NET ELEC. ENERGY GENERATED (MWH) -11191 -69983 9934474

12. REACTOR SERVICE FACTOR 0.0% 0.0% 53.1%

13. REACTOR AVAILABILITY FACTOR 0.0% 0.0% 60.4%

14. UNIT SERVICE FACTOR 0.0% 0.0% 51.4%

15. UNIT AVAILABILITY FACTOR 0.0% 0.0% 51.4%

16. UNIT CAPACITY FACTOR (USING MDC) -1.5% -1.3% 42.3%

17. UNIT CAPACITY FACTOR (USING DESIGN MWe) -1.4% -1. 31, 40.7%

18. UNIT FORCED OUTAGE RATE 0.0% 0.0% 17.4%

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

The First Refueling Maintenance, Surveillance and Modification Outage l Began October 18, 1985 and will last till September, 1986.

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

Start-up in September, 1986 is determined by administrative postulation upon completion of static O-ring problem pending NRC approval and Unit #2 Start-Up Date.

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2. AvuaAGE DAILY UNIT POWER LEVEL '

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- DOCKET NO: 050-373 UNIT: LASALLE ONE DATE: 8/10/86 COMPLETED BY: Jasses P. Peters TELEPHONE: (815) 357-6761, MONTH: JULY 1986 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY'M 4ER LEVEL (MWe-Net) (MWe9f at) s i-

1. -13 17. -14

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2. -14 18. -14

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4. -16 20.,  !

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6. -16 22. -15

7. -16 ~ 23. -15

8. 116 24. -14 __

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9. -15 25. -15

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10. -16 26.

11.  :' -16 27. -14

12. -15 2?. -13

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13. -16 29. -14 i.

14. -16 30. -17 l

15. -15 31. -16 16 _ -14 '

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3. UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 050-373 UNIT NAME MSalle One DATE 8/10/86 REPORT MONTH JULY 1986 COMPLETED PY James P. Peters TELEPHONE (815)357-6761 METHOD OF TYPE SHUTTING DOWN F: PORCED DURATION THE REACTOR OR CORRECTIVE NO. DATE S: SCHEDULED (HOURS) REASON REDUCING POWER ACTIONS /COfMENTS Th re were no Unit shutdowns or power reductions during this reporting period due to the first refueling outage.

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E. UNIQUE REPORTING REQUIREMENTS

1. Safety / Relief valve operations for Unit One.

VALVES NO & TYPE PLANT DESCRIPTION DATE ACTUATED ACTUATION CCNDITION OF EVENT There were no Safety Relief Valves Operated for Unit One during this reporting period.

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. 2. ECCS Systems Outtgas

,' JThe following outages were taken on ECCS Systeus during the reporting period.

OUTAGE NO. EOUIPMENT PURPOSE OF OUTAGE 0-145-86 "O" DG Repair Indication and i Switches.

0-155-86 "O" DG Fuel Oil Repair Pp.

Transfer Pp.

0-156-86 "O" DG Repair Air Valves 1-1086-86 "lB" DG Change Filters.

1-1094-E6 lE51-F063 LES-AP-101 1-1100-86 lE12-F047B Inspect Heat Shrink.

1-1101-86 1E12-F040A Inspect Heat Shrink.

1-1102-86 IE12-F040B Inspect Heat Shrink.

1-1103-86 IWR179 Inspect Heat Shrink.

1-1110-86 HPCS DG Motor Air Repair Compressor Compressor 1-1116-86 "B" RHR SDC lE12-F050B Set Limits.

1-1117-86 HPCS Pp Inspect Motor Terminations 1-1118-86 HPCS Water Leg Pp Inspect Motor Terminations 1-1120-86 RCIC Water Leg Pp Inspect Terminals 1-1126-86 IN62-F326- Repair 1-1128-86 "B/C" RHR SDC/LPCI LES-RH-101/104 1-1133-86 lE12-C002 Inspect Motor Terminations 1-1134-86 lE12-C001 Inspect Motor Terminations 1-1135-86 IE12-C002A Inspect Motor Terminations 1-1150-86 lE12-N010CB Repair Valve Manifold 1-1162-86 "lA" DG "B" Air Repair Inst. Stop Compressor on Reciever.

1-1163-86 "lA" DG Repair Oil Leaks 1-1186-86 Div. III UV Relays Calibrations 1-1196-86 RCIC Bkr. Replace Brkr. O/L l-1197-86 lE12-F047A Inspect Gear Box 1-1198-86 1E12-F050B Splice Cable 1-1204-86 "lB" DG Air Compressor Repair Air Compressor 1-1207-86 lE12-F063B Fill Suppression Pool.

1-1211-86 lE12-F063B Fill RHR System.

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3. Off-Site Dose Calculation Manual-There were no changes to the OCDM 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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i LASALLE NUCLEAR POWER STATION

' UNIT 2 MONTHLY PERFORMANCE REPORT JULY 1986 COMMONWEALTH EDISON COMPANY

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

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< TABLE OF CONTENTS I. INTRODUCTION 1

II. MONTHLY REPORT FOR UNIT TWO l l

A. Summary of Operating Experience B. PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS, AND SAFETY RELATED MAINTENANCE

1. Amendments to Facility License or Technical Specifications

2. Facility or Procedure Changes Requiring NRC Approval

3. Tests and Experiments Requiring NRC Approval

4. Corrective Maintenance of Safety Related Equipment C. LICENSEE EVENT REPORTS D. DATA TABULATIONS

1. Operating Data Report

2. Average Daily Unit Power Level

3. Unit Shutdowns and Power Reductions E. UNIQUE REPORTING REQUIREMENTS

1. Safety / Relief Valve Operations

2. ECCS System Outages

3. Off-Site Dose Calculation Manual Changes

4. Major Changes to Radioactive Waste Treatment System DOCUMENT ID 0036r/0005r

I. INTRODUCTION The LaSalle County Nuclear Power Station is a two-unit I

facility owned by Commonwealth Edison Company and located near Marseilles, Illinois. Each unit is a Boiling Water Reactor with a designed net electrical l 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 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 James P. Peters, telephone number (815)357-6761 extension 325.

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II. MONTHLY REPORT POR UNIT TWO l

SUlttARY OF OPERATING EXPERIENCE FOR UNIT TWO

< A.

e Ju1Y 1-31 July 1, 0001 Hours. The Unit entered July with the reactor subcritical and off-line due to investigation in progress to resolve the static O-ring drift problems.

July 31, 2400 Hours. The Reactor is in Cold Shutdown, While investigation of Static o-ring drift problems are being closed out and are nearing completion.

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

MF.INTENANCE.

1. Amendments to facility license or Technical Specification.

There were no aumendments to Facility License or Technical Specification changes during this reporting period.

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2. Facility or procedure changes requiring NRC approval.

There were no facility or procedure change requiring NRC approval i

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.

i 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 I

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

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TA*LE 1

• CORRECTIVE MAINTENANCE OF SAFETY RELATED EQUIPMENT WORK REQUEST COMPONENT CAUSE OF MALFUNCTION RESULTS AND BFFECTS CORRECTIVE ACTION ON SAFE PLANT OPERATION L58934 "F" IRM 2C51-N002F Dirty Connectors. F IRM Spiking Causing 1/2 Scrams cleaned Connectors.

L59032 Control Room Intake Bad ARM Detector Spurious Trips on Hi-Rad. Replaced ARM Detector.

HVAC ARM 2D18-K~151D.

L59063 LPCS Waterleg Pp Worn and Dirty Internal Valve Sticks Open. Dissassembled Cleaned, Discharge Check Valve Components. Lapped and Reassembled 2821-F033. Valve.

L59102 2B RR Flow Indication Components out of Both indications show flow Performed LIS-RR-201.

on M/A and Recorder. Calibration, with pump S/D and Out of Service l L59256 LPCS Pump Cooler Limits were extremely Cycled Valve and would not Cleaned and Reset Open

. Upstream Stop 2DG035. Dirty. Reopen. Limits.

L59333 Reactor Vessel Lo H 2O Inoperable SOR Switch. To much Static Shift. Replaced SOR Switch.

LVL Confirmed ADS Permissive 2B21-NO38B L59345 Reactor Low LVL Scram Failed Micro-Switch. Erratic Operation of SOR Switch. Replaced SOR Switch.

I Switch 2B21-N0248.

L59444 HPCS Min. Flow To accommodate observed New Setpoint is 1540 GPM. Changed Setpoint.

Differential Pressure charateristics of SOR Switch 2E22-N006. Differential Pressure

Switches.

L59445 LPCS Min. Flow To accommodate observed New Setpoint is 1719 GPM. Changed Setpoint.

Differential Pressure Characteristics of SOR Switch 2E21-N004. Differential Pressure Switches.

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TABLE 1 o CORRECTIVE MAINTENANCE OF SAFETY RELATED EQUIPMENT WORK REQUEST COMPONENT CAUSE OF MALFUNCTION RESULTS AND EFFECTS CORRECTIVE ACTION ON SAFE PLANT OPERATION L59446 RHR LPCI "A" Flow To acomunodate observed New Setpoints is 1977 GPM. Changed Setpoint.

Differential Pressure Characteristics of SOR Switch 2812-N010AA. Differential Pressure Switches.

L59847 RHR LPCI "A" Plow To accomunodate observed New Setpoint is 1977 GPM. Changed Setpoint.

Differential Pressure Charteristic of SOR Switch 2E12-N010AB. Differential Pressure i Switches.

1 L59448 RHR LPCI "B" Flow To accomunodate observed New Setpoints 1977 GPM. Changed Setpoint.

Differential Pressure Charteristics of SOR Switch 2E12-N010BA. Differential Pressure Switches.

s L59449 RHR LPCI "B" Plow To accomunodate observed New Setpoint is 1977 GPM. Changed Setpoint.

1 Differential Pressure Characteristics of SOR

, Switch 2E12-N010BB. Differential Pressure switches.

I L59450 RHR LPCI "C" Flow To accomunodate observed New Setpoints 1977 GPM. Changed Setpoint.

Differential Pressure Characteristics of SOR Switch 2E12-N010CA. Differential Pressure Switch.

L59451 RHR LPCI "C" Flow To accomunodate observed Dew Setpoint is 1977 GPM. Changed Setpoint.

Differential Pressure Characteristics of SOR Switch 2E12-N010CB. Differential Pressure Switch.

L59587 Level 3 Scram To accomunodate observed New Setpoint is 19.4 inches changed Setpoint.

Differential Pressure Characteristics of SOR Switch 2821-N024A. Differential Pressure Switch.

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TABLE 1

• CORRECTIVE MAINTENANCE OF SAFETY RELATED EQUIPMENT WORK REQUEST (X)MPONENT CAUSE OF MALFUNCTION RESULTS AND EFFECTS CORRECTIVE ACTION ON SAFE PLANT OPERATION L59588 Level 3 Scram To accommodate observed New Setpoint is 19.4 inches. Changed Setpoint.

Differential Pressure Characteristics of SOR Switch 2B21-N024B. Differential Pressure Switch.

L59589 Level 3 Scram To accommodate observed New Setpoint is 19.4 inches. Changed Setpoint.

Differential Pressure Characteristics of SOR Switch 2B21-N024C. Differential Pressure Switch.

L59590 Level 3 Scram To accommodate observed New Setpoint is 19.4 inches. Changed Setpoint.

Differential Pressure Characteristics of SOR Switch 2B21-N024D. Differential Pressure Switch.

L59626 Level 3 ADS Permissive To accommodate observed New Setpoint is 19.4 inches. Changed Setpoints.

Differential Pressure Characteristics of SOR Switch 2B21-NO38A. Differential Pressure Switch.

L5%27 Level 3 ADS Permissive To accommodate observed New Setpoint is 19.4 Inches. Changed setpoint.

Differential Pressure Characteristics of SOR Switch 2B21-NO38B. Differential Pressure Switch.

L5%64 Level 3 Scram Failed Switch. During Testing Switch was Replaced Switch.

Differential Pressure Operating Erraticly.

Switch 2B21-N024A.

L59807 Level 3 Scram Failed Switch. During Testing Switch was Replaced Switch.

Differential Pressure Operating Erraticly.

Switch 2B21-N024C.

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TABLE 1

• CORRECTIVE MAINTENANCE OF SAFETY RELATED SQUIPMENT WORK REQUEST COMPONENT CAUSE OF MALFUNCTION RESULTS AND EFFECTS CORRECTIVE ACTION ON SAFE PLANT OPERATION L59808 Level 3 ADS Permissive Failed Switch. During Testing Switch was Replaced Switch.

Differential Pressure Operating Erraticly.

Switch 2B21-NO38A.

L59907 Level 2 HPCS To accomodate observed New Setpoint -33.8 inches. Changed Setpoint.

Initiation Characteristic of SOR Differential Pressure Differential Pressure Switch.

Switches 2B21-NO31A-D.

L59908 Level 2 RCIC Initiation To accomodate observed New setpoint is -33.8 inches. Changed Setpoint.

Differential Pressure Characteristic of SOR Switches 2B21-NO37AB-DB Differential Pressure Switch.

L59909 Level 1 BCCS Initiation To accomodate observed New Setpoint is -110.6 inches. Changed Setpoint.

Differential Pressure Characteristic of SOR Switches 2B21-NO37AA-DA Differential Pressure Switch.

L59923 RCIC Pp Suction Switch out of Tolerance Alarm is initiated without Recalibrated Switch.

Pressure Switch High Pressure.

2851-N021.

L60084 "A" RHR Pp Suction Bad Gage. Reads too high of Indication. Installed and Calibrated Pressure Switch New Gage.

2E12-R002A.

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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, 1986. 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 86-012-00 06/20/86 Improper Terminations at EQ Equipment due to improperly installed heat shrink.

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

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1. Operating Data Report i

2. Average Daily Unit Power Level

3. Unit Shutdowns and Power Reductions l l

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1. OPERATING DATA REPORT DOCKET NO. 050-374 UNIT LaSalle Two DATE 8/10/86 COMPLETED BY James P. Peters TELEPHONE (815)357-6761 OPERATING STATUS

1. REPORTING PERIOD: July, 1986 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 (IP ANY): N/A THIS MONTH YR TO DATE CUMULATIVE 5 NUMBER OF HOURS REACTOR WAS CRITICAL 0.0 _3213.39 8602.79

6. REACTOR RESERVE SHUTDOWN HOURS 0.0 29.83 29.83

7. HOURS GENERATOR ON LINE 0.0 3152.29 8388.59

8. UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 0.0

9. GROSS THERMAL ENERGY GENERATED (MWH) 0.0 9148872 24657424

10. GROSS ELEC. ENERGY GENERATED (MWH) 0.0 3050559 8160628

11. NET ELEC. ENERGY GENERATED (MWH) -10758 2932374 7755589

12. REACTOR SERVICE FACTOR 0.0% 63.2% 54.9%

13. REACTOR AVAILABTLITY FACTOR 0.0% 63.8% 55.2%

14. UNIT SERVICE FACTOR 0.0% 61.9% 53.6%

15. UNIT AVAILABILITY FACTOR 0.0% 61.9% 53.6%

16. UNIT CAPACITY FACTOR (USING MDC) -1.4% 55.6% 47.8%

17. UNIT CAPACITY FACTOR (USING DESIGN MWe) -1,3% 53.5% 45.9%

18. UNIT PORCED OUTAGE RATE 100% 38.0% 31.8%

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

None.

20. IF SHUT DOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP Start-up is estimated to begin on August 7, 1986.

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, 2. AVERAGE DAILY UNIT POWER LEVEL DOCKET NO: 050-374 UNIT: LASALLE TWO DATE: 8/10/86 COMPLETED BY: James P. Peters TELEPHONE: (815) 357-6761 MONTH: July 1986 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net)

1. -13 17. -14

2. -13 18. -14 3 -15 19. -14

4. -15 20. -14 5._ -15 21. -14

6. -15 22. -14

7. -15 23. -14

8. -15 24. -14

9. -15 25. -14

10. -15 26. -14

11. -16 27. -13

12. -15 28. -12

13. -16 29. -14

14. -15 30. -16

15. -15 31. -16

16. -14 DOCUMENT ID 0036r/0005r

ATTACIDENT E *

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3. UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 050-373 UNIT NAME LaSa1le Two DATE 8/10/86 REPORT MONTH JULY 1986 COMPLETED BY James P. Peters 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 /COf9ENTS There were no Unit shutdowns or Power Reductions During this reporting Period Due to Static O-Ring problems, i

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DOCUMSNT ID 0036r/0005r

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E. UNIQUE REPORTING REQUIREMENTS l

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 for Unit #2 during this reporting period.

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DOCUMENT ID 0036r/0005r

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2. ECCS Syntens Outigea

• The following outages were taken on BCCS Systems during the reporting period. j OUTAGE WO. BOUIPMENT PURPOSE OF OUTAGE 2-373-86 2DG035 Inspect and/or Repair.

2-374-86 2E12-F063C Transfer Water From U2 Mot-Well to U2 Suppression Pool.

i 2-383-86 2E12-F003B Reconnect Wiring, i 2-384-86 2E12-F0998 Torque Switch Limit or Plate.

) 2-387-86 HPCS Water Leg Pp Cub. Fan Inspect Motor Terminations.

2-389-86 Div.11 BCCS "B/C" Inspect Motor Terminations.

RHR Water Leg Pp and Fan.

2-390-86 Div-I ECCS-A RHR Water Inspect Motor Terminations.

Leg Pp and Fan ,

2-394-86 2851-C003 Inspect Terminations.

2-396-86 2E12-C003 -Repair Terminations.

2-398-86 Protect SDC During LST-86-128 "2A" RHR

2-402-86 LPCS Water Leg Po Lubrication.

2-412-86 2N62-C001 Lubrication.

2-417-86 2851-N003 Repair Cable Terminations.

2-418-86 2821-N005 Repair Cable Terminations.

2-420-86 2E21-N003 Repair Cable Terminations.

7 2-444-86 2D RHR WS Pp Throttle Discharge.

l 2-447-86 2851-F051A Repair Terminations.

2-448-86 2851-F005 Repair Terminations.

l 2-449-86 2E51-F004 Repair Terminations.

2-450-86 2851-F026 Repair Terminations, i 2-451-86 2E51-F026 Repair Terminations.

! 2-456-86 2E12-F051B Repair Terminations.

2-471-86 Governor Control Fuses Investigate Terminations.

2-474-86 LPCS Water Leg Pp Inspect Motor Terminations.

}

2-475-86 "B/C" RHR Water Leg Pp Inspect Motor Terminations.

2-476-86 HPCS Water Leg Pp Inspect Motor Terminations.

2-447-86 RCIC Water Leg Pp Inspect Motor Terminations.

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3. Off-Cito Dosa Calculction Manual 8 There were no changes to the ODCM during this reporting period.

4. Radioactive Waste Treatsment Systeens.

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

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I Commonwerith Edison 4

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[=_ ..

's LaSalla County Nuclear Station Rural Route #1, Box 220 Marseilles, Illinois 61341 s Telephone 815/357-6761 August 9, 1986 Director, Office of Management Information and Program Control United States Nuclear Regulatory Commission Washington, D.C. 20555 ATTW: Document Control Desk Gentlemen:

4 Enclosed for your information is the monthly. performance report covering LaSalle County Nuclear Power Station for the period July 1, 1986 through July 31, 1986.

Very truly yours,

/

sg / 4tm "

G. J. Diederich Station Manager LaSalle County Station GJD/JPP/jdp 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 L. J. Anastasia, PIP Coordinator SNED J. E. Ellis, GE Resident H. E. Bliss, Nuclear Fuel Services Manager C. F. Dillon, Senior Financial Coordinator, LaSalle Document 0043r/0005r

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