ML20212C630

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Monthly Operating Repts for Aug 1986
ML20212C630
Person / Time
Site: LaSalle  Constellation icon.png
Issue date: 08/31/1986
From: Diederich G, Peters J
COMMONWEALTH EDISON CO.
To:
NRC OFFICE OF ADMINISTRATION (ADM), NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
NUDOCS 8612310125
Download: ML20212C630 (32)
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LASALLE NUCLEAR POWSR STATION UNIT 1 MONTHLY PERFORMANCE REPORT AUGUST, 1986 COfMONWEALTH EDISON COMPANY NRC DOCKET NO. 050-3'73 LICENSE NO. NPF-ll i

l 8612310125 860831 PDR ADOCK 05000373 R PDR l

Document 0043r/0005r

a TABLE OF CONTENTS I. INTRODUCTION II. MONTHLY REPORT POR UNIT ONE A. Susunary 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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. 1 I. INTRODUCTION The 1.aSalle County Nuclear Power Station is (1 two-unit facility owned by Cosumonwealth Edison Compan/ 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 Edison Company.

Unit one was issued operating license number NPP-ll on April 17, 1982. Initial criticality was achieved on i June 21, 1982 and commercial power operation was commenced on January 1, 1984.

This report was compiled by James P. Peters, telephone number (815)357-6761 extension 325.

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o II. MONTHLY REPORT FOR UNIT ONE A. SUfflARY OF OPERATING EXPERIENCE FOR UNIT ONE August 1-31 -

August 1, 0001 Hours. The unit entered August with the Reactor subcritical and off-line in Cold Shutdown for First Refueling Outage.

August 31, 2400 Hours. Reactor in Cold Shutdown for First Refueling Outage.

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. D. . PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS AND SAFETY RELATED

. MAINTENANCE.

1. Amendments to facility license or Technical Specification.

Amendment 45 - Revised Rod Block Monitor Setpoint.

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 i

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 L15913 Redundant Pault Pro- M-1-1-82-290 Back-up Circuitry Required per Completed per tection for Elect- License Cond. - 23 License Condition. Modification Package.

rical Penetrations.

L33013 IB Fuel Oil Transfer Bad Valve Internals. Leaking Valve. Rebuilt Valve.

Valve ID6014.

L39598 Differential M-1-1-84-091 Does not meet EQ Completed per Pressure Switches. Requirements. Modification Package.

L53811 Div-II - MCC 136X-1 M-1-1-85-048 To eliminate overloading on Completed per LAP 788 30 Amp Breaker. Modification Package.

L54016 Inboard MSIV Accumula- Bad Disc. O-Ring Does not hold pressure. Replace Disc, Disc O-Ring tor Check Valve and Bonnet. and Bonnet.

1B21-F024A 4 L56902 "C" RHR Test Return M-1-1-84-090 Not Reset as Required by Reset Thermal O/L and Valve IE12-F021 M-1-1-84-090. Magnetic Settings per ECW-ED-167-3.

L57139 CRD Header Pressure Bad Internals. Leakage Past Seats. Vented Cleaned and Scram Transmitter Replaced.

L57271 Mechartical Snubber Damaged Snubber. Failure of LTS-500-14. Replaced Snubber.

IRH04-1022S L57477 "A" RHR Testable Packing Leak then Leading Failed LLRT Rebuilt Valve.

check Valve into Valve Internal LTS-900-6.

IE12-F050A. Failure.

L.58845 RCIC Barometric Bad Control Switch. Pump would not autostart when Replaced Control Swtich.

Condensor Vacuum ,

RCIC initiates.

l Pump.

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TT.8LE 1 CORRECTIVE MAINTENANCE OF SAFETY RELATED EQUIPMENT WORK REQUEST COMPONENT CAUSE OF MALFUNCTION RESULTS AND EFFECTS CORRECTIVE ACTION ON SAFE PLANT OPERATION L59380 RR Process Sample Improper Adjustment per Adjustment to Allow for Proper Adjusted Pressure INBD/OUTBD Pressure M-1-1-84-140. Valve Regulation. Regulators.

Regulator IB33-F019/20 L59618 LPCS Pump lE21-C002. Small Oil Ledk. No Potential Effect. Rebuilt Pump.

L59885 "B" VC Supply Fan Loop Out of Calibration. Switch Trips too soon. Recalibrated Loop.

Differential Pressure Switch OPDS-VC051.

L60016 Mechanical Snubber Failed Snubber. Failed LTS-500-14. Replaced Snubber.

IRI24-1069S.

L60143 IRM "C" IC51-K601C Inoperable Inhibit Switch. Inhibit Switch causes spurious Replaced Inhibit Switch.

1/2 Scrams during LIS-NR-302.

L60527 "lB" Diesel Generator Inoperable K39 Relay HPCS Diesel Failed to start. Replaced K39 Relay.

IE22-S001 Changing states instantly.

L60658 121Y, Cubicle 4B Inoperable Thermal O/L Thermal O/L does not reset. Replaced Thermal O/L lE51-F045 Reldy. Relay.

L60783 125 VDC, DIV. I, Illy Grounded Pressure Switch 130 VDC Positive Ground. Cleared Ground.

BRK-1, IDCllE 1812-N413A through improper termination.

L60812 "A" RHR Hx Outlet Temporary System Change. Rewired Valve so Valve Closes Completed Temporary Valve IE12-F003A 1-1482-86 on Limits. System Change 1-1482-86.

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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, August 1 through August 31, 1986. This information is provided pursuant to the reportable occurrence reporting requirements as set forth in 10CFR 50.~13.

Licensee Event Report Number Date Title of Occurrence 86-031-00 07/15/86 Spurious trip of VC Radiation Monitor due to bad HI Voltage Board in indicator relay.

86-032-00 07/22/86 Reactor Level 3 Scram, Static O-Ring Switch out of tolerance due to drift.

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

1. Operating Data Report
2. Average Daily Unit Power Level
3. Unit Shutdowns and Power Reductions Document 0043r/0005r

1, . OPERATING DATA REPORT

, DOCKET NO. 050-373 UNIT LaSalle One DATE 9/10/86 COMPLETED BY James P. Peters TELEPHONE (815)357-6761  ;

OPERATING STATUS

1. REPORTING PERIOD: August, 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 (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) -12655 -82638 9921819
12. REACTOR SERVICE FACTOR 0.0% 0.0% 51.5%
13. REACTOR AVAILABILITY FACTOR 0.0% 0.0% 58.5%
14. UNIT SERVICE FACTOR 0.0% 0.0% 49.8%
15. UNIT AVAILABILITY FACTOR 0.0% 0.0% 49.8%
16. UNIT CAPACITY FACTOR (USING MDC) -1.6% -1.4% 40.9%
17. UNIT CAPACITY FACTOR (USING DESIGN MWe) -1.6% -1.3% 39.3%
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 Began October 18, 1985 and will last till September 14, 1986.

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

September 14, 1986.

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2. AVERAGE DAILY UNIT POWER LEVEL DOCKET NO: 050-373 UNIT: LASALLE ONE DATE: 9/10/86 COMPLETED BY: James P. Peters TELEPHONE: (815) 357-6761 MONTH: AUGUST 1986 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net)
1. -17 17. -16
2. -16 18. -17 3 -16 19. -18
4. -16 20. -18
5. -17 21. -18
6. -17 22. -16
7. -17 23. -16
8. -17 24. -16
9. -20 25. -16
10. -18 26. -16
11. -18 27. -16
12. -18 28. -16
13. -21 29. -17
14. -18 30. -17
15. -16 31. -16
16. -17 l

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ATTACHMENT E .

3. UNIT SHUTDOWNS AND POWER REDUCTIONS .

DOCKET NO. 050-373 UNIT NAME LaSalle On_e_

DATE 9/10/86 REPORT MONTH AUGUST, 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 /COfMENTS -

There were no Unit shutdowns and power reductions during this reporting period.

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E. UNIQUE REPORTING REQUIREMENTS

1. Safety / Relief valve operations for Unit One.

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

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. 2. ECCS Syatens OuttgI3

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

1 OUTAGE NO. SOUIPMENT PURPOSE OF OUTAGE 0-158-86 ODG08CA Remove Motor for Repair.

0-162-86 0" DG Air Compressor Prevent from Tripping.

0-1221-86 LPCS Pp Disch. Flow Raychem Transmitter 1-1222-86 LPCS Pp Disch. Press. Raychem Transmitter 1-1226-86 RCIC Flow Instr. Raychem 1-1235-86 Misc. RCIC Valves Raychem 1-1237-66 RHR Hx Stm. Cond. Viv. Repair Terminations and controller on Solenoids.

1-1253-86 HPCS DG Replace Fuel Priming Pp.

1-1257-86 LPCS Pp Lubrication.

1-1258-86 A RER Pp Lubrication.

1-1261-86 lE51-F045 Change Brkr. Settings.

1-1300-86 lE12-F047A Repair Pinion Gear.

1-1306-86 lE12-F051A Repair Actuator.

1-1312-86 LPCS Valves / Motor Electrical Inspection.

1-1313-86 A LPCI Valves Electrical Inspection.

1-1325-86 Mcc 135Y-2, Compt. D3 Replace Contactor.

1-1335-86 1812-F003A Limit Switch Wiring Change.

1-1344-86 RCIC Valve Electrical Inspection.

1-1345-86 HPCS Electrical Inspection.

1-1346-86 lE12-F047A/48A Retape Terminals.

1-1349-86 HPCS Pp Sample 011.

1-1352-86 lE22-F004 Test Brkr.

1-1355-86 B RHR Valves Inspect Terminations.

i 1-1360-86 B RHR Pp Lubrication.

1-1361-86 C RHR Pp Lubrication.

1-1362-86 B/C RHR Water Leg Pp Repair Terminations.

1-1368-86 IE12-F027B Inspection.

1-1383-86 lE51-F069 Inspection.

1-1385-86 IE12-F047A/lE22-F012 Inspection.

1-1387-86 IE12-K99 (Relay) Replace Relay.

1-1390-86 IE12-F099B Repair Torque Switch.

! l-1395-86 B DG Replace 1886-T142X3 Relay.

l 1-1397-86 lE31-N012BB Replace Switch.

t 1-1398-86 lE31-N007AA Replace Switch.

l l-1399-86 lE31-N013BB Replace Switch.

1-1400-86 lE12-F099A Determination. '

I l-1404-86 1B21-N503A/B M-1-1-82-266 Test.

1-1405-86 RCIC VDC Power Panel Investigation.

I l-1406-86 lE51-F045 Overload Testing.

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- 3. Off-Sit @' Dose C01culction Manual I There were no changes to the ODCM during this reporting period.

4. Radioactive Waste Treatment Systems. l There were no 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 AUGUST, 1986 COfMONWEALTH EDISON COMPANY NRC DOCKET NO. 350-314 .

LICENSE NO. NPP-18 ij i

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DOCUMENT ID 0036r/0005r

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TABLE OF CONTENTS l i

l I. INTRODUCTION I II. MONTHLY REPORT FOR UNIT TWO I l

A. Summary of Operating Experience l

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

1. Amendments to Facility License or Technical Specifications
2. Facility or Procedure Changes Requiring NRC Approval
3. Tests and Experiments Requiring NRC Approval l
4. Corrective Maintenance of Safety Related Equipment l l

C. LICENSEE EVENT REPORTS I 1

D. DATA TABULATIONS l

1. Operating Data Report i
2. Average Daily Unit Power Level
3. Unit Shutdowns and Power Reductions E. UNIQUE REPORTING REQUIREMENTS
1. Safety / Relief Valve Operations
2. ECCS System Outages
3. Off-Site Dose Calculation Manual Changes
4. Major Changes to Radioactive Waste Treatment System I

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I. INTRODUCTION The LaSalle County Nuclear Power Station is a two-unit facility owned by Commonwealth Edison company and located near Marseilles, Illinois. Each unit is a 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 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 FOR UNIT TWO

. A. SUf91ARY OF OPERATING EXPERIENCE FOR UNIT WO Auoust 1-31 August 1, 0001 Hours. The Unit entered July with the Reactor suberitical and off-line due to investigation and corrective actions in progress to resolve Static O-Ring Drift Problem.

August 9, 0600 Hours. Scheduled Reactor Scram due to 950/500 lb.

Level Drop Test, LST-86-183.

August 11, 0820 Hours. Reactor went critical.

August 12, 0210 Hours. Main Turbine Roll.

August 12, 0240 Hours. Main Generator Synchronized to Grid.

August 12, 2000 Hours. Reactor Power Increased to 23% Power (260 Me).

August 13, 0445 Hours. Reactor Power Increased to 50% Power (534 me).

August 14, 1330 Hours. Ramp at 4 Ne/Hr. due to Xenon burnout.

August 15, 0437 Hours. Reactor Power Increased to 52% Power (550 We).

August 16, 1415 Hours. Reactor Power Decreased to 40% Power (447 Ne) due to "A" TDRFP Trip.

August 16, 1830 Hours. Reactor Power Increased to 54% (51~1 W e) after "A" TDRFP Reset.

August 20, 1445 Hours. Reactor Power Increased to 85% (900 me).

August 28, 2130 Hours. Reactor Power Decreased to 46% (516 w e) due to control Rod Manipulation.

August- 30, 2220 Hours. Reactor Power at 859,(913 Ne).

August 31, 2400 Hours. Reactor Power at 85% (914 We).

DOCUMENT ID 0036r/0005r

, :B. ' PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS AND SAF@rY RELATED MAINTENANCE.

1. . Amendments to facility license or Technical Specification.

There were no acendments to Facility License or Technical Specification changer during this reporting period.

2. Facility or procedure changes requiring NRC approval.

There were no facility or procedure change requiring NRC approval ,

during the reporting period.

3. Tests and experiments requiring NRC approval.

There were rio 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 sumunary 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 1

L54501 H2 Recombiner Thermocouple was in With controller _ set at 1200*F, Move Thermocouple to 2HG01A Contact with Heater. It Operated between 1140* '

Appropriate Location.

Il50*F.

L59734 250 VDC Battery Battery Cell #33 and.#34 No Potential Effect. Replaced Battery.

2DC01E has Hairline-Cracks in Plexiglass Case.

L59081 "A" RHR Hx Outlet Temporary System Change Rewired Valve so Valve Closes Complete Temporary i Valve 2E12-F003A 2-756-86 on Limits. System Change 2-756-86 L59831 "B" VC Radiation Bad HI Voltage Power Radiation Monitor is Replaced Hi Voltage Monitor 2D18-K751B. Supply. De-energized. Power Supply.

L60080 MSIV Not Full Open Broken Actuating Arm K3B Relay did not Energize. Repaired Actuating Arm i 2B21-F028A/K3B on Valve, on Valve.

4 L60081 MSIV Not Full Open Inoperable Limit Switch. K3F Relay did not Energize. Repaired Unit Switch.

2B21-F028C/K3F i

L60126 RHR/RCIC HI Stm Flow To Accommodate Observed New Setpoint is 111.4" WC, Changed Setpoint.

Isol. Switch Characteristics of SOR 2E31-N007AA Differential Pressure Switch.

L60127 RHR/RCIC HI Stm To accommodate observed New Setpoint is 111.4" WC. Changed Setpoint.

Flow Isolation Switch charateristics of SOR 2E31-N007AB Differential Pressure Switch.

l L60128 RHR HI Suction Flow To accommodate observed New Setpoint is 168.4" WC. Changed Setpoint.

j Isolation Switch Characteristics of SOR  ;

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2E31-N012AA Differential Pressure Switch.

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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 L60129 RHR HI Suction Flow To acommodate. observed New Setpoint is 168.4" WC. Changed Setpoint.

Isolation Switch Characteristics.of SOR 2E31-N012AB Differential Pressure Switch.

L60130 RHR HI Suction Flow To accommodate observed New Setpoint.is 168.4" WC. Changed Setpoint.

Isolation Switch Characteristics of SOR 2831-N012BA Differential Pressure Switch.

I L60131 RHR HI Suction Flow To accommodate observed New Setpoint is 168.4" WC. Changed Setpoint.

Isolation Switch Charteristics of SOR 2831-N012BB. Differential Pressure Switch.

L60132 RCIC HI Stm Flow To accommodate observed New Setpoint is 168.4" WC. Changed Setpoint.

. Isolation Switch Characteristics of SOR 2E31-N013AA. Differential Pressure Switch.

t L60133 RCIC HI Stm Flow To accommodate observed New Setpoint is 166.4" WC. Changed Setpoint.

1 Isolation Switch Characteristics of SOR 2E31-N013AB. Differential Pressure Switch.

L60134 RCIC HI Stm Flow To accommodate observed New Setpoint is 166.4" WC. Changed Setpoint.

Isolation Switch characteristics of SOR i 2E31-N013BA. Differentidl Pressure Switch.

L60135 RCIC HI Stm Flow To accommodate observed New Setpoint is 166.4" WC. Changed Setpoint.

-j Isolation Switch Characteristics of SOR 2831-N013BB. Differential Pressure j Switch.

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TABLE 1-CORRECTIVE MAINTENANCE OF -

i SAFETY RELATED EQUIPMENT ..

WORK REQUEST COMPONENT CAUSE OF MALFUNCTION RESULTS AND EFFECTS CORRECTIVE ACTION ON SAFE PLANT OPERATION L60169 Level 2 Groups To accommodate observed New Setpoints are 134" WC. Changed Setpoint..

1-5 Isolation Characteristics of'SOR Switches Differential Pressure 2821-N026AB-DB. Switch.

- L60197 "B" SBLC Pp Disch. Rupture Bellows. Initiated 7 Day Time Clock Repaired Bellows.

Relief Valve till completed.

2C41-F029B.

L60218 MSL HI Stm Flow To accommodate observed New Setpoint is 85 psid. Changed Setpoint.

Isolation Switches Characteristics of SOR

, 2E31-N008A-D Differential Pressure i

2E31-N009A-D Switch.

2E31-N010A-D ,

2831-N0ilA-D L60219 Level 8 RCIC Shutoff To accommodate observed New Setpoint is 38.7 WC Changed Setpoint.

Isolation Switch Characteristics of SOR (48 RWL)

2B21-N0101B. Differential Pressure Switch.

l L60268 RHR/NCIC Steam Line To accommodate observed New Setpoint is 75.4" WC. Changed Setpoint.

i HI Flow Isolation Characteristics of SOR Switch 2E31-N007BA/BB Differential Pressure Switch.

L60403 LPCS Int. Valve Pressure Switch could not The Setpoint was above the LCO, Change Pressure Switch.

1 Permissive 2821-N413 be adjusted to High Side No Potential Effect.

Tolerance.

i L60428 Rx HI Level Rack Inoperable Switch. Switch will not hold Setpoint. Replaced Switch.

Turbine Trip 2B21-N101A. ,

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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, August 1 through August 31, 1986. This information is provided pursuant to the reportable occurrence reporting requirements as set forth in 10CFR 50.73.

Licensee Event Report Number D!Ltg Title of Occurrence 86-011-00 07/01/86 Failur.e of 12.5 inches Differential Pressure Static O-Ring Level Switch to respond to low level due to drift.

86-012-00 07/19/86 Improper Terminations of Environmental Qualification Equipment due to Improper Construction Installation-Procedures.

86-013-00 07/31/86 Improper Terminations of Environmental Qualification Solenoids due to Improper construction Installation Procedures.

86-014-00 07/31/86 Terminations at Environmental Qualifications Equipment lacks Compatibility / Documents.

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t D. DATA TABULATIOC 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 DOCUMENT ID 0036r/0005r 4

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. 1. OPERATING DATA REPORT DOCKET NO. 050-374 UNIT LaSalle Two DATE 9/10/86 COMPLETED BY James P. Peters TELEPHONE (815)357-6761 l OPERATING STATUS l l

1. REPORTING PERIOD: August. 1986 GROSS HOURS IN REPORTING PERIOD: 744
2. CURRENTLY AUTHORIZED POWER LEVEL (MWt):3323 MAX DEPEND CAPACITY l (MWe-Net): 1036 DESIGN ELECTRICAL RATING (MWe-Net): 1078
3. POWER LEVEL TO WHICH RESTRICTED (IP ANY) (MWe-Net): 880

.4. REASONS FOR RESTRICTION (IP ANY): New MSL SOR Switch Setpoints.

THIS MONTH YR TO DATE CUMULATIVE 5 NUMBER OF HOURS REACTOR WAS CRITICAL 471.66 3685.05 9074.45

6. REACTOR RESERVE SHUTDOWN HOURS 0.0 29.83 29.83
7. HOURS GENERATOR ON LINE 453.33 3605.62 8841.92
8. UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 0.0
9. GROSS THERMAL ENERGY GENERATED (MWH) 1112304 10261176 25769728
10. GROSS ELEC. ENERGY GENERATED (MWH) 349861 3400420 8510489
11. NET ELEC. ENERGY GENERATED (MWH) 331371 3263745 8086 % 0
12. REACTOR SERVICE FACTOR 63.4% 63.2% 55.4%
13. REACTOR AVAILABILITY FACTOR 63.4% 63.7% 55.5%
14. UNIT SERVICE FACTOR 60.9% 61.8% 53.9%
15. UNIT AVAILABILITY FACTOR 60.9% 61.8% 53.9%
16. UNIT CAPACITY FACTOR (USING MDC) 42.9% 21 0% 47.6%
17. UNIT CAPACITY FACTOR (USING DESIGN MWe) 41.3% 51.9% 45.7%
18. UNIT FORCED OUTAGE RATE 39.2% 38.2% 32.3%
19. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH):

The first Refueling, Maintenance, Surveillance and Modification Outage is scheduled to begin January 3, 1987.

20. IF SHUT DOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP NA DOCUMENT ID 0036r/0005r j
2. AVERAGE DAILY UNIT POWER LEVEL
  1. DOCKET NO: 050-374 UNIT: LASALLE TWO DATE: 9/10/86 COMPLETED BY: James P. Peters TELEPHONE: (815) 357-6761 MONTH: August. 1986 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net)
1. -16 17. 506
2. -16 18. 586 3 -16 19. 604
4. -16 20. 827
5. -16 21. 862
6. -16 22. 860
7. -17 23. 873
8. -17 24. 870
9. -20 25. 873
10. -18 26. 872
11. -18 27. 845
12. 156 28. 716
13. 455 29, 839
14. 488 30. 863
15. 510 31. 883
16. 503 DOCUMENT ID 0036r/0005r

ATTACHMENT E

3. UNIT SHUTDOWNS AND POWER REDUCTIONS .

' DOCKET NO. 050-373 .,

UNIT NAME LaSalle Two *

-DATE 9/10/86 REPORT MONTH AUGUST, 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 /COfflENTS 24 08/09/86 S 44:40 B 3 LST-86-183: This is a 950/500 lbs. Level Drop Test Directly Resulting in a Reactor Scram.

This tests all new Static O-Ring Level i Switches.

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DOCUMENT ID 0036r/0005r

E. UNIQUE REPORTING REQUIREMENTS

1. Safety / Relief Valve Operations for Unit Two.

DATE VALVES NO & TYPE PLANT DESCRIPTION i 8QTUATED ACTUATIONS CONDITION OF EVENT l All Unit #2 SRV's/ ADS were opened and reclosed on 8/9/86 as part of Operating Surveillance LOS-MS-RI. In accordance with this procedure, Relief Valves: {

2B21-F013C/D/E/K/R/S/U/V were opened twice while the remaining SRV's were I opened only once. Tailpipe temperatures as well as the number #1 Bypass Valve j Operation confirms that all SRV/ ADS successfully reclosed.

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l DOCUMENT ID 0036r/0005r

i

, 2. .ECCS Systems Outrge2 The following outages were taken on ECCS Systems during j the reporting period. 1 l

OUTAGE NO. EQUIPMENT PURPOSE OF OUTAGE 2-489-86 2E12-F065B Repair Terminations.

2-492-86 Div. II RHR SDC Calibration.

I 2-493-86 Div. I RHR SDC Calibration.

2-506-86 C RHR WS Disch Valve Running one WS Pump. i 2-513-86 2851-D003 Repair Leak.

2-516-86 RCIC Vacuum Pp Repair Motor.

2-535-86 HPCS DG Cooling Water Pp Diver Inspection.

2-540-86 2812-F048A Repack Valve.

2-547-86 B HPCS DG 2822-S001 Repair Access Cover.

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4 DOCUMENT ID 0036r/0005r

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3. Off-Site Dose calculation Manual There were no changes to the ODCM during this Reporting Period.
4. Radioactive Weste Treatment Systems.

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

Document 0043r/0005r

e SI f'N cCommonwealth Edison

', [ ) LaSall2 County Nuclear Stition

- f Ruc.l Route #1, Box 220

/ Telephone 815/357-6761 s  !

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l September'9, 1986 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 Powe,r Station for the period August 1, 1986 through August 31, 1986. .

Very truly yours, G. .D derich

' a' ation Manager LaSalle County Station GJD/JPP/jdp l 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 i

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

't b.l Y l (

Document 0043r/0005r

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