ML20155C836

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Monthly Operating Repts for Mar 1986
ML20155C836
Person / Time
Site: LaSalle  Constellation icon.png
Issue date: 03/31/1986
From: Diederich G, Peters J
COMMONWEALTH EDISON CO.
To:
NRC OFFICE OF ADMINISTRATION (ADM)
References
NUDOCS 8604170128
Download: ML20155C836 (33)
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. 4-LASALLE NUCLEAR POWER STATION UNIT 1 MONTHLY PERFORMANCE REPORT MARCH, 1986 COff90NWEALTH EDISON COMPANY NRC DOCKET NO. 050-373 LICENSE NO. NPF-11

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8604170128 DR 860331 ADDCK 05000373 PDR Document 0043r/0005r h

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g; 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 l

Document 0043r/0005r ,

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. I. INTRODUCTION The LaSalle County Nuclear Power Station is a two-unit facility owned by Commonwealth Edison Company and located near Marseilles, Illinois. Each unit is a 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-Il 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 James P. Peters, telephone number (815)357-6761 extension 325.

Document 0043r/0005r

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. o II. MONTHLY REPORT FOft UNIT ONE A. SUfflARY OF OPERATING EXPERIENCE FOR UNIT ONE March 1 - 31 March 1, 0001 Hours. The Unit entered March with the reactor subcritical and unit off-line in cold shutdown for first refuel outage.

March 31, 2400 Hours. Reactor in cold shutdown for first refueling outage.

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

.4, MAINTENANCE.

1. Amendments to facility license or Technical Specification.

AMENDMENT 35 - This revised the Unit #1 specification for High Radiation Door Control.

AMENDMENT 36 - This revised the Unit #1 specification for Main Steam Line Low Pressure Response Time.

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 Experjments 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.

Document 0043r/0005r

TABLE 1 d

CTRECTI','E MAINTENANCE OF SAFETY RELATED EQUIPMENT

  • WORK REQUE,ST COMPONENT CAUSE OF MALFUNCTION RESULTS AND EFF8 CTS CORRECTIVE ACTION ON SAFE PLANT OPERATION L35151 S/D Cooling Outboard Valve leaks by seat. S/D cooling suction header HI Repaired valve internals.

Valve IE12-F008 pressure alarm present.

L387% LPC3 Discharge Alarm M-1-1-84-088. Split up high and low pressure Completed under ECN-ED-147 Switches alarms on LPCS pump discharge and PFL-172 within pressure. M-1-1-84-088.

L48950 B SBLC Pump Discharge Check valve would not Failure of LOS-SC-M1, check Disassembled, cleaned and' check valve seat-properly. valve leaks. reassembled check valve, IC41-F033B also seal welded bonnet.

L50629 B RHR Testable Bad air cylinder. Valve would not cycle from Replaced air cylinder and Check Valve control switch. relubed.

IE12-F041B L51401 A RHR Full Flow Considerable leakage Failure of LTS-300-7. Repacked valve.

Test Stop Valve through valve packing.

IE12-F024A L51995 D Main Steam Line Component drawer was out D Rad monitor is reading low. Repaired internal Rad Monitor of tolerance low. circuitry.

1D18-K610D L52565 VE Damper DVE-03YA Damper actuator discon- During LIS-VC-053, damper Reconnected linkage and nected and wired open. would not stroke. unwired the damper.

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TABLE 1 CORRECTIVE MAINTENANCE OF SAFETY RELATED EQUIPMENT e d

WORK REQUEST COMPONENT CAUSE OF MALFUNCTION RESULTS AND EFFECTS CORRECTIVE ACTION ON SAFE PLANT OPERATION a

L53920 A D/W Spray Upstream Valve had excessive leak- Failure of LTS-100-43. Machined valves disc and isolation stop valve age through seat. Seat seats and reassembled..

IE12-F016A full of scratches.

L55044 C RHR WS Pump Motor burned up. WS pump inoperable. Rewound motor and rein-IE12-C300C stalled.

L55546 Mechanical snubbers snubbers found broken. Failed during functional Replace with new snubbers.

HP20-15075, testing.

HP20-14025 and MS14-10485 L555'l3 B RHR Steam Line Bad motor. During LES-EQ-112 found Replaced motor.

Isolation valve motor grounded.

IE12-F052B L55596 A RHR Valve Failed motor during Valve inoperable. Installed new motor.

IE12-F068A testing.

L55~109 B RHR Full Flow Test Considerable leakage Packing leaks when volve Repacked valve.

Stop Valve through valve packing. strokes.

IE12-F024B i

L55920 B VC Refrigeration Bad flair coupling on Trips on low suction pressure. Repaired flaired coupl-Unit OVC05CB hot gas bypass valve. ings on hot gas bypass valves.

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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 L56101 HPCS Min Flow Valve Bad motor. Valve won't cycle from control Replaced motor.

IE22-F012 switch.

L56142 B RHR HX Vent Valve Torque switch close Valve will not completely Changed torque switch IE12-F074B setting to low. close, close setting from 1 to 2-1/2.

L56231 Mechanical Snubber Failed snubber. Failed LTS-500-14, functional Replaced with new snubber.

HP08-10245 test.

L56353 B RHR Testable Check Disc is not traveling Valve will not seat to allow Repacked and Valve IE12-F041B into seat due to packing pressurization for LLRT. reassembled.

gland binding.

L56467 Control Room HVAC Bad flowswitch and No indication on flow lamp with Replaced flowswitch and Detector OXY-VC-1258 broken wires. appropriate flow present, repaired broken wires.

L56583 H2 Recombiner Bad packing. Valve is binding when manually Repacked valve.

Valve IHG001B stroked and high amps when electrically stroked.

L56670 D/W Humidity Mon- Bad terminal block and No indication when valve is Replaced cable, lugs and itored Suction valve damaged field wires, full closed. terminal block.

ICM017A L56890 H2 Recombiner Bad packing. Valve hard to turn manually Repacked valve.

Valve lHG001A and draws high amperage when electrically stroked.

L56913 HPCS Standby Water Bad breaker. Pump breakers trip on magnetics. Replaced breaker.

Leg Pump IE22-C003 L57132 A RHR Injection Burned overload relay. Valve has no light indication Replaced burned valve IE12-F042A. and cannot be cycled from overload relay.

control room.

Document 0043r/0005r

o 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, March I through March 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 86-005-00 02/17/86 ESF actuation from VR due to 80 not completing procedure step by step.

86-006-00 02/18/86 Reactor water conductivity monitor inoperable due to no sample taken.

86-007-00 02/26/86 Missing 0-ring on VQ valve due to improper installation during construction.

86-008-00 02/26/86 HPCS DG start from instrument pressure surge due to air in SBLC injection line.

86-009-00 02/25/86 VR outboard Group IV isolation due to alligator clip falling off terminal during RPS bus transfer.

86-010-00 03/04/86 Group IV PCIS isolation due to short to groun<1 from jumper falling off terminal.

Document 0043r/0005r

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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

,I. OPERATING DATA REPORT DOCKET NO. 050-373

. UNIT LaSalle One DATE 3/10/86 COMPLETED BY James P. Peters TELEPHONE (815)357-6761 OPERATING STATUS

1. REPORTING PERIOD: March 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 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) -11041 -25470 9978987
12. REACTOR SERVICE FACTOR 0.0% 0.0% 61.0%
13. REACTOR AVAILABILITY FAC'IOR 0.0% 0.0% 69.3%
14. UNIT SERVICE FACTOR 0.0% 0.0% 59.0%
15. UNIT AVAILABILITY FACTOR 0.0% 0.0% 59.0%
16. UNIT CAPACITY FACTOR (USING MDC) -1.4% -1.1% 48.8%
17. UNIT CAPACITY FACTOR (USING DESIGN MWe) -1.4% ,-1.1% _46.9%
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 into May, 1986.

20. IF SHUT DOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP: May 3, 1986 Document 0043r/000$r

,2. AVERAGE DAILY UNIT POWER LEVEL

. DOCKET NO: 050-373 UNIT: LASALLE ONE DATE: 3/10/86 COMPLETED BY: James P. Peters TELEPHONE: (815) 357-6761 MONTH: MARCH 1986 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net)

1. -15 17. -15
2. -14 18. -16 3 -13 19. -16
4. -15 20. -16
5. -16 21. -16
6. -13 22. -16
7. -16 23. -16
8. -16 24. -16
9. -14 25. -15
10. -14 26. -15
11. -14 27. -15
12. -14 28. -15
13. -15 29. -14
14. -16 30. -14
15. -15 31. -14
16. -15 Document 0043r/0005r

ATTACIWWINT E ,

3. UNIT SHUTDOWNS AND PONER REDUCTIONS DOCKET NO. 050-373 ,

UNIT MAME LaSalle One DATE 3/10/86 REPORT MONTH MARCH 1986 COffLETED BY J_ asses P. Peters TELEPHONE (815)357-6761 METHOD OF TYPE SHUTTING DONN 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 the refuel outage in progress.

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

Document 0043r/0005r

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

OUTAGE NO. BOUIPMENT PURPOSE OF OUTAGE 0-64-86 O DG Lube coupling and clean injection screen 0-65-86' O DG Fix cylinder temperature sensor 0-67-86 O DG Cooling Water Lube Coupling 0-68-86 O DG Replace K55 Relay 1-424-86 IB DG Clean Ejector Screen 1-425-86 IB DG Relay Calibration 1-426-86 B RHR HX Hydro 1-429-86 IE22-F010 LES-FQ-ll2 1-431-86 IE12-F068A Test Thermal Overloads 1-432-86 IE12-F090A Keep closed 1-433-86 IE12-F092A Keep Closed 1-437-86 IE12-F063C Fill Suppression Pool 1-440-86 IE12-F009 Remove Packing 1-441-86 B/C RHR Seal Coolers Isolate For Hydro 1-442-86 LPCS Waterleg Pump Prevent Filling A HHR l-445-86 IE12-F041B Repair 1-450-86 IE51-F013 LES-BQ-ll2 1-456-86 IE12-F372C Clean Sight Glass 1-460-86 IB12-F063C To Fill Reactor Well 1-471-86 IE51-F031 LES-BQ-ll2 1-472-86 IE12-F026A Install Limiter Plate 1-477-86 B RHR PRM Isolate till MOD Complete 1-486-86 IE12-F073A Valve Position Indication 1-489-86 IE22-C003 Lubricate 1-490-86 1E22-F010/23 LES-BQ-112 1-493-86 1E12-F063C Add Water to Supp. Pool 1-495-86 HPCS Suction Relief Hydro Bound.

1-497-86 LPCS/CY Spool Piece Remove Spool Piece 1-500-86 IB DG Replace Upper Head Gasket 1-503-86 IE12-F041A/B/C Replace Cable 1-504-86 IE12-F092A Replace Cable 1-527-86 IE51-N010 Replace Level Switch 1-528-86 IE51-N010 Support Level Switch Replacement 1-530-86 HPCS Waterleg Pump Troubleshoot 1-539-86 IE22-F023 LES-SQ-ll2 1-543-86 RCIC Interlocks Revise Wiring 1-556-86 lE21-C001 Inspect coupling 1-565-86 A HHH WS Relocate PRM Probe 1-569-86 IE12-F016A Packing Leak 1-574-86 1821-8003 Repair Wire in Breaker 1-579-d6 IE12-F041C Repair Sealtite at Limit Switch Document 0043r/0005r

-. OUTAGE NO, BOUIPMENT PURPOSE OF OUTAG7

+ l-580-86 IE12-F008 Hydro 1-581-86 IE12-F0998 Install Redundant Fault Protection 1-589-86 RHR S/D Cool Flcm Switch LST-86-47 1-602-86 IE12-F040A Repair Ground Wires 1-603-86 IE12-F073A Repair Conduit 1-604-86 IE12-F074A Repair Conduit 1-606-86 IE12-F042B "epair Contactor 1-608-86 IE51-F080 ripack Valve 1-622-86 IE12-F042A Replace Thermal O/L I-623-86 IE12-F332B Admin. Control 1-625-86 IE51-F086 Repack Valve 1-633-86 IB12-C300A Install Motor Document 0043r/0005r

, '3. Off-Site Dose calculation Manual There were no changes to the ODCM during this reporting period.

4. Red.ioactive Waste Treatment Systems.

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

Document 0043r/0005r

LASALLE NUCLEAR POWER STATION UNIT 2 MONTHLY PERFORMANCE REPORT MARCH 1986 COfMONWEALTH EDISON COMPANY NRC DOCKET NO. 050-374 LICENSE NO. NPF-18 i

DOCUMENT ID 0036r/0005r

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. TABLE OF CONTENTS o.

-I. INTRODUCTION II. MONTHLY REPORT POR UNIT TidO A. Summary of Operating Experience B. PLANT OR PROCEDURE CHANGES, TESTS, EXPhMIMENTS, AND SAFETY RELATED MAINTENANCE

1. Amendmer.ts to Pacility 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 Equipmarat 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 i

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DOCUMENT ID 0036r/0005r

r-I. INTRODUCTION The LaSalle County Nuclear Power Station is a two-unit facility owned by Comunonwealth 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 Rdison 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 comunenced on June 19, 1984.

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

DOCUMENT ID 0036r/0005r

_II.. MONTHLY REPORT FOR UNIT TWO

,, 'A. SUpWERY OF OPERATING EXPERIENCE FOR UNIT TWO

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March 1-31 March 1, 0001 Hours. The Unit entered March with the Reactor critical at 98% power and Generator on line at 1097 MWe.

Also, power is being reduced to 89% (985 MWe) for surveillance testing.

March 1, 0815 Hours. Reactor power reduced to 78% (850 MWe) due to BGC testing.

March 2, 1000 Hours. Reactor Power increased to 100%

(1122 MWe).

March 2, 2100 Hours. Commenced Reactor shutdown to repair reactor water clean-up isolation valve IG33-F001.

March 3, 0543 Hours. Reactor scram on IRM HI-HI.

March 5, 1340 Hours. Reactor critical.

March 5, 2135 Hours. Generator synchronized to the grid, began increasing power.

March 8, 0400 Hours. Reactor power increased to 78%

(870 MWe).

March 8. 0600 Hours. Reactor power reduced to 51% (570 MWe) due to control rod manipulations.

March 8, 1212 Hours. Reactor power reduced to 38% (456 MWe) due to spurious RR pumps down shift.

March 8, 1305 Hours. Reactor power increased to 57%

(625 MWe) due to upshifting RR pumps and continued power ascension.

March 9, 2200 Hours. Reactor power decreased to 54%

(605 MWe) for control rod manipulations.

March 10, 0030 Hours. Final rod pattern set and began power ascension.

March 12, 1800 Hours. Reactor power increased to 98%

(1081 MWe) limited by flow control line.

DOCUMENT ID 0036r/0005r

II. MONTHLY REPORT 16 UNIT TWO (Continued)

,. A. .SUMARY OF OPERATING EXPERIENCE FOR UNIT TWO March 1-31 March 16 0720 Hours. Reactor power reduced to 74% (835 MWe) for control rod manipulations.

March 18, 0700 Hours. Reactor power increased to 100%

(1108 We) full power.

March 18, 2050 Hours. Reactor power reduced to 95% (1065 MWe) for preconditioning.

March 19, 1000 Hours. Reactor power at 100% (1110 We) limited by Xenon.

March 20, 2400 Hours. Reactor power reduced to 94% (1040 We) for control rod manipulations.

March 21, 1500 Hours. Reactor power at 100% (1116 MWe) full power.

March 27, 1900 Hours. Reactor power reduced to 71% (800 We) for control rod manipulation.

March 29, 2300 Hours. Reactor power at 100% (1110 MWe) full power.

March 31, 2400 Hours. Reactor power at 99% (1097 MWe) full power.

DOCUMENT ID 0036r/0005r

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s. B.- ' PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS AND SAFETY RELATED MAINTENANCE.
1. Amendments to facility license or Technical Specification.

AMENDMENT 19 - This revised Unit #2 specification for High Radiation Door control.

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 no tests or experiments requiring NRC approval during the reporting period.

4. Corrective Maintenance of Safety Releted Equipment.

The following table (Table 1) presents a summary of safety-related maintenance completed on Unit Two during the reporting period. The headirags 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/000$r

TABLE 1 e

CORRECTIVE MAINTENANCE OF .

SAFETY RELATED EQUIPMENT .

1 WORK REQUEST COMPONENT CAUSE OF MALFUNCTION RESULTS AND EFFECTS CORRECTIVE ACTION ON SAFE PLANT OPERATION L56163 APRM-C Bad ICPS ICPS power is at 20.4 VDC and Replaced ICPS and set at LPRM 24-57B should be at 100 VDC. 100 VDC.

L56188 Div-I Post Loca Bad chart drive circuit Chart drive does not work. Replaced chart drive Chart Recorder board and motor. circuit board and motor.

2B21-R884A L56270 TSV closed scram EQ penetration lead wire Continously blows fuses. Put heat shrink on entire Relay 2C71A-K10,C grounded at limit switch. length of wire.

L56400 RWCU inboard isol- Bound up declutch lever Valve failed to open after Declutched valve operator ation valve isolation and breaker was and opened valve.

2G33-F001 re-energized.

L56409 LPCS min flow valve Flow switch 2E21-N004 Sporadic valve positioning. Recalibrated flow switch 2E21-F0ll out of calibration. 2E21-N004.

L56461 RWCU outlet isol- Dirty contacts and loose Valve does not open Cleaned contacts and ation valve connections on torque electrically. tightened screws on 2G33-F004 switch. torque switch.

L5G537 SBGT damper actuator Bad mA source to Actuator 2FZ-VG003 for damper Installed new mA source.

2FZ-VG003. actuator 2VG002 is cycling open and closed.

L56570 control Room Panel Bad Power Supply. 120 Volt ground on 211Y CB21 Replaced with new power 2PM18J ground supply.

211-CB21.

L56897 SBGT moist. sep. Pressure switch out of Alarm is up when train is in Recalibrated diff. press.

diff. press. alarm tolerance low operation. switch.

2PDS-VG021.

DOCUMENT ID 0036r/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,_ March 1 through March 31, 1986. This information is provided pursuant to the repor table occurrence reporting requirements as set forth in 10CPR 50.73.

Licensee Event Report Number Date Title of Occurrence 86-002-00 02/06/86 RCIC System and IE51-F008 inoperable due to loose contact strip in contact block.

86-003-00 02/17/86 Inadvertently placed mode switch into run due to inattentiveness.

86-004-00 02/16/86 Loss of main transformer due to phase to phase fault on main transformers.

86-005-00 03/03/86 Scram on IRM HI-HI alarm due to instrumentation sensing feedwater regulator valve shut when 15% open.

DOCUMENT ID 0036r/0005r

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.1 i .

D. DATA TABULATIONS 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 4

4 f

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l DOCUMENT ID 0036r/0005r

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.. 1. OPERATING DATA REPORT

  • DOCKET NO. 050-374 UNIT LaSalle Two DATE 3/10/86 COMPLETED BY James P. Peters TELEPHONE (815)357-6761 OPERATING STATUS
1. REPORTING PERIOD: March, 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 M 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 uOURS REACTOR WAS CRITICAL 688.05 2056.59 7445.99
6. REACTOR RESERVE SHUTDOWN HOURS 0.0 29.83 29.83
7. HOURS GENERATOR ON LINE 680.14 2029.44 7265.74
8. UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 0.0
9. GROSS THERMAL ENERGY GENERATED (MWH) 1989000 5953104 21461656
10. GROSS ELEC. ENERGY GENERATED (MWH) 665452 1991323 7101392
11. NET ELEC. ENERGY GENERATED (MWH) 643693 1933582 6756797
12. REACTOR SERVICE FACTOR 92.5% 95.2% 58.5%
13. REACMR AVAILABILITY FACTOR 92.5% 96.6% 58.8%
14. UNIT SERVICE FACTOR 91.4% 93.9 L 57.1%
15. UNIT AVAILABILITY FACTOR 91.4% 93.9% 57.1%
16. UNIT CAPACITY FACTOR (USING MDC) 83.5% 86.4% 51.2%
17. UNIT CAPACITY FACTOR (USING DESIGN MWe) 80.3% 83.0% 49.3%
18. UNIT FORCED OUTAGE RATE 8.6% 6.0% 22.6%
19. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH):

There are no shutdowns scheduled over the next 6 months.

20. IF SHUT DOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP N/A L

DOCUMENT ID 0036r/0005r

2. AVERAGE DAILY UNIT POWER LEVEL

.. DOCKET NO: 050-374

  • UNIT: LASALLE TWO DATE: 3/10/86 COMPLETED BY: James P. Peters TELEPHONE: (815) 357-6761 MONTH: March 1986 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net)
1. 928 17. 983
2. 1021 18. 1063 3 29 19. 1060
4. -14 20. 1062
5. -6 21. 1051
6. 480 22. 1063
7. 744 23. 1058
8. 661 24. 1053
9. 760 25. 1049
10. 761 26. 1045
11. 943 27. 996
12. 1025 28, 896
13. 1026 29, 1029
14. 1020 30. 1064
15. 1015 31. 1058
16. 897 DOCUMENT ID 0036r/0005r

ATTACHMENT E

3. UNIT SHUTDOWNS AND POWER REDUCTIONS ,

DOCKET NO. 050-373 *.

UNIT NAME LaSa11e One.

DATE 3/10/86 REPORT MONTH MARCII 1986 COMPLETED BY James P. Peters TELEPHONE (815)357-6761 METHOD OF TYPE SifUTTING DOWN F: FORCED DURATION THE REACTOR OR CORRECTIVE NO. DATE S: SCHEDULED (HOURS) REASON REDUCING POWER ACTIONS / COMMENTS 17 3/3/86 F 64.27 A-Feedwater Reg. 3 Reactor scram on IRM valve instrumentation HI-HI out of calibration.

1 DOCUMENT ID 0036r/0005r

  • E. UNIQUE REPORTING REQUIREMENTS
1. Safety / Relief Valve Operations for Unit Two.

DATE VALVES NO & TYPE- PLANT DESCRIPTION ACTUATED ACTUATIONS CONDITION OF EVENT There were no safety relief valves operated for Unit #2 during this reporting period.

DOCUMENT ID 0036r/0005r

, 2. ECCS Sy0tems Outtge2 0 The following outag(s were taken on ECCS Systems during the reporting period.

OUTAGE NO. BOUIPMENT PURPOSE OF OUTAGE 2-89-86 HPCS Petter DG Air Compressor. Replace high pressure valves.

2-93-86 2E21-F011. Inoperable per Tech. Spec.

2-103-86 2B DG Air Compressor. Replace belts.

2-109-86 RHR S/D Cooling System. LIS-RH-412.

2-124-86 2B HPCS DG. Change filter and lube.

2-125-86 2B HPCS DG. Change location of sensor.

2-126-86 2B HPCS DG. Lubing and filter changes.

2-138-86 2E51-C003. Adjust impeller.

2-139-86 A RHR WS strainer backwash Change wiring.

control.

2-148-86 RCIC. Inspect water leg pump min.

flow orifice. -

2-149-86 RCIC. Calibrate RCIC pump disch, flow instrument.

2-150-86 RCIC. Calibrate drain pot level switch.

2-156-86 2E12-F023/99A/99B/53A LIS-NB-411.

53B/8/9.

t DOCUMENT ID 0036r/0005r

-e 3. Off-Sit @ Dosa C11culgtion Manuel O There were no changes to the ODCM during this reporting period.

4. Radioactive Waste Treatment Systems.

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

L i

2 DOCUMENT ID 0036r/0005r

/ N Commonwealth Edison

[ ^

') LaS:lle County Nuclear Station Rural Route #1, Box 220 (g '-

7 Marseilles, Illinois 61341 N / Telephone 815/357-6761 r

l April 8, 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 Power Station for the period March 1, 1986 through March 31, 1986.

Very truly yours,

,b W:

G. . Diederich / //4 S ation Manager LaSalle County Station GJD/RJR/bke 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, GB Resident H. E. Bliss, Nuclear Fuel Services Manager C. F. Dillon, Senior Financial Coordinator, LaSalle l

I C%

fV Document 0043r/0005r / )

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