ML20207M444

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Monthly Operating Repts for Dec 1986
ML20207M444
Person / Time
Site: LaSalle  Constellation icon.png
Issue date: 12/31/1986
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 8701130181
Download: ML20207M444 (32)
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LASALLE NUCLEAR POWER STATION UNIT 1 MONTHLY PERFORMANCE REPORT DECEMBER 1986 COMMONWEALTH EDISON COMPANY NRC DOCKET NO. 050-373 LICENSE NO. NPF-ll f

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8701130181 DR 861231 "

ADOCK 05000373 PDR ,

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6 DOCUMENT ID 0043r/C005r <7& l) 2

t TABLE OF CONTENTS s

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
5. Completed Safety Related Modifications.

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
5. Indications of Failed Fuel Elements DOCUMENT ID 0043r/0005r

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I. INTRODUCTION q

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 Bciling 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 NPF-ll 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.

t DOCUMENT ID 0043r/0005r

t s II. MONTHLY REPORT FOR UNIT ONE A.

SUMMARY

OF OPERATING EXPERIENCE FOR UNIT ONE December 1-31 December 1, 0000 Hours. The Unit Entered December the Reactor Critical and On-line at 93.9% Power (1033 MWe).

December 4, 1617 Hours. Reactor Scram due to "B" MSL PRM Spurious Spike while another 1/2 Scram was already present during LIS-NR-303.

December 6, 2020 Hours. Reactor Achieved Criticality.

December 7, 0500 Hours. Turbine Generator Synchronized to the Grid.

December 7, 0815 Hours. Reactor Power Holding at 10% (110 MWe) due to Scram Time Surveillance, s

December 7, 1115 Hours. Reactor Power Increasing at 11MWe/hr to 36%

(405 MWe) then Upshifting to 63% (700 MWe).

December 8, 0015 Hours. Reactor Power Increasing 8 MWe/hr to 82%

(907 MWe).

December 8, 2100 Hours. Reactor Power Decreasing 150 MWe/hr to 51%

(560 MWe) due to control Rod Manipulations.

December 9, 0300 Hours. Reactor Power Increasing 120 MWe/hr to 65%

(720 MWe).

December 9, 0415 Hours. Reactor Power Increasing 10 MWe/hr to 93%

(1030 MWe).

December 12, 0215 Hours. Reactor Power Decreasing 50 MWe to 89% (980 MWe) for control Rod Manipulations.

December 16, 0815 Hours. Reactor Power Increasing 6 MWe/hr to 97%

(1085 MWe).

December 20, 1135 Hours. Reactor Power Decreasing 50 MWe to Cycle Intermediate Control Rods.

December 20, 1215 Hours. Reactor Power Increased at 30 MWe/hr to 92%

(1015 MWe) then 5 MWe/hr to 97% (1080 MWe).

December 24, 0900 Hours. Reactor Power Decreasing 40 MWe to 93% (1035 MWe) due to TCV Oscillation.

DOCUMENT ID 0043r/0005r

II. MONTHLY REPORT FOR UNIT ONE A.

SUMMARY

OF OPERATING EXPERIENCE FOR UNIT ONE December 1-31 (Continued)

December 25, 0300 Hours. Reactor Power Decreased to 88% (980 MWe) due to TCV Oscillations.

December 26, 0230 Hours. Reactor Power Decreasing 50 MWe to 84% (935 MWe) due to control Rod Manipulations.

December 31, 2400 Hours. Reactor and Generator On-line and Holding at 92% (1010 MWe).

i DOCUMENT ID 0043r/0005r

B. -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 Procedural 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 sununary include:

Work Request number, Component Name, Cause of Malfunction, Results and Effects on Safe Operation, and Corrective Action.

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5. Completed Safety Related Modifications.

The following Table (Table 2) presents a list of completed

-Modifications during this reporting period. Each entry will have a-4 short synopsis explaining details involved with each modification.

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TABLE 1 CORRECTIVE MAINTENANCE OF SAFETY RELATED EQUIPMEh?

UNIT #1 WORK REQUEST COMPONENT CAUSE OF MALFUNCTION RESULTS AND EFFECTS CORRRCTIVE ACTION ON SAFE PLANT OPERATION L47423 SBGT Low Flow Alarm M-1-1-85-027 The new switch will have a Replaced and rewired Switch IFS-VG036 dual set point and low flow switch, alarm contacts OFF switch.

L63515 IB IRM IC51-K601B Bad voltage regulator and IRM spiking, downscale Replaced voltage regulator amplifier attentuator chattering on drawer. and amplifier attentuator cards, cards.

L63527 Div-III, Batteries Mounting brackets 19-21 No potential effect. Mounting brackets 1E22-S001 and 49-51 are not bolted are bolted correctly.

in place.

L63552 S/P and D/W Temp. Bad pinion gear and drive Paper does not advance. Replaced worn pinion gear

recorder ITR-CM038 belt was out of adjustment. and readjusted chart drive belt.

L63764 "A" RR Flow Unit Inoperable summer card. During LIS-RR-101, the "A" RR Replaced bad summer card.

1B33-K607A comparator trip could not be

, adjusted within allowable tolerances.

L63822 "B" MSL Radiatior. Bad MSL Radiation Drawer. MSL Rad. Drawer spiked Replaced MSL Rad.

Drawer ID18-K610B downscale, drawer.

L63891 "A" RBM IC51-K605GU Bad Power Supply and trip Generate spurious rod blocks. Replaced power supply reference card. and trip reference card.

L63986 Div-I Post L,oca Bad H2 cell. Mismatched swings between Replaced H2 cell.

(Hydrogen) local indicator and recorder.

DOCUMENT ID 0043r/0005r a

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, TABLE 2 COMPLETED SAFETY RELATED MODIFICATIONS 1

MODIFICATION NUMBER: A brief synopsis of incorporated modification objectives with final design resolution. Also, state reviewed or unreviewed safety. questions.

=-.

The following list below has all the Safety Related Modifications completed from December 1, 1986 through December 31, 1986.

M-1-0-81-025 - This modification replaced the low level alarm and pump autostart setpoints for the day tank level switch with a 40 minute time delay in the alarm circuit. There was no unreviewed safety question.

M-1-1-85-027 - This modification replaced the high flow alarm switch 1FS-VG036 with dual set point model switch and have low flow alarm contacts off of this switch and not the heater trip relay. There was no unreviewed safety question.

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DOCUMENT ID 0043r/0005r

C. LICENSEE EVENT REPORTS i

The following is a tabular summary of all licensee event reports for LaSalle Nuclear Power Station, Unit One, logged during the reporting period, December 1, through December 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 86-042-00 12/04/86 Failure of the HPCS waterleg pump discharge check valve due to magnetite on check valve

[ disc.

86-043-00 12/04/86 Main Steamline PRM spurious \

spike with half scram present caused from unknown sources.

f DOCUMENT ID 0043r/00C5r

i 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 I

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1. OPERATING DATA REPORT
  • DOCKET NO. 050-373 UNIT LaSalle One DATE January 10, 1987 COMPLETED BY James P. Peters TELEPHONE (815)357-6761

' OPERATING STATUS

1. REPORTING PERIOD: December, 1986 GROSS HOURS IN REPORTING PERIOD: 744
2. CURRENTLY AUTHORIZED POWER LFVEL (MWt):3323 MAX DEPEND CAPACITY (MWe-Net): 1036 DESIGN ELECTRICAL RATING (MWe-Net): 1078
3. ' POWER LEVEL TO WHICH RESTRICTED (IF ANY) (MWe-Net): 1050
4. REASONS FOR RESTRICTION (IF ANY): Administrative THIS MONTH YR TO DATE CUMULATIVE 5 NUMBER OF HOURS REACTOR WAS CRITICAL 691.95 2396.6 14435.6
6. REACTOR RESERVE SHUTDOWN HOURS 0.0 0.0 1642.0
7. HOURS GENERATOR ON LINE 683.28 2331.9 13973.9
8. . UNIT RESERVE SHUTDOWN HOURS 0.0 0.0- 0.0
9. GROSS THERMAL ENEPGY GENERATED (MWH) 2027808 6541992 38755642
10. GROSS ELEC. ENERGY GENERATED (MWH) 689692 2191283 12690677
11. NET ELEC. ENERGY GENERATED (MWH) 664209 2018117 12022574
12. REACTOR SERVICE FACTOR 93% 27.4% 54.8%
13. REACTOR AVAILABILITY FACTOR 93% 27.4% 61.0%
14. UNIT SERVICE FACTOR 91.8% 26.6% 53.1%
15. UNIT AVAILABILITY FACTOR 91.8% 26.6% _ 53.1%
16. UNIT CAPACITY FACTOR (USING MDC) 86.1% 22.2% 44.0%
17. UNIT CAPACITY FACTOR (USING DESIGN MWe) 82.8% 21.3% 42.4%
18. UNIT FORCED OUTAGE RATE 8.2% 2.5% 15.3%
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:

N/A.

DOCUMENT ID 0043r/0005r

,2. AVERAGE DAILY UNIT POWER LEVJE

, DOCKET NO: 050-373 UNIT: LASALLE ONE DATE: January 10, 1987 COMPLETED BY: James P. Peters TELEPHONE: (815) 357-6761 MONTH: December, 1986 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net)

1. 999 17. 1050
2. 997 18. 1044 3 994 19. 1042
4. 669 20. 1028
5. -17 21. 1043
6. -18 22. 1039
7. 278 23. 1042
8. 775 24. 1017
9. 790 25. 965
10. 988 26, 954
11. 1029 27. 959
12. 1025 28. 958
13. 1013 29. 997
14. 1016 30, 976
15. 1014 31. 977
16. 1035 DOCUMENT ID 0043r/0005r
3. UNIT SHUTDOWNS AND POWER LEDUCTIONS DOCKET NO. 050-373'-

UNIT NAME LaSa11e One DATE January 10. 198)

REPORT MONTH DECEMBER. 1986 COMPLETED BY James P. Peters TELEPliONE (815)357-6761 METHOD OF TYPE SHUTTING DOWN F: PORCED DURATION THE REACTOR OR CX)RRECTIVE NO. DATE S: SCHEDULED (HOURS) REASON REDUCING POWER ACTIONS /COPMENTS 5 12/04/86 F 00.72 H 3 MSL PRM spiking with 1/2 scram already present caused by unknown reasons.

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DOCUMENT ID 0043r/0005r

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.

DOCUMENT ID 0043r/0005r

2. ECCS Sy;:tems Outage:2 The following outages were taken on ECCS Systems during

, the reporting period.

OUTAGE NO. BOUIPMENT PURPOSE OF OUTAGE 0-1632-86 IE22-F007 Repair Check Valve 0-1643-86 "A" DG Fuel Oil Replace Contactor Transfer Pp.

I l-1644-86 "A" DG Replace Air Start Motor 1-1652-86 RCIC Waterleg Pp. Replace MCC Contactor k

DOCUMENT ID 0043r/0005r

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3. Off-Site Doss Calculation Manual 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 Systems during this reporting period.

5. Indications of Failed Fuel Elements There were no indications of Failed Fuel Elements during this reporting period.

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LASALLE NUCLEAR POWER STATION i

UNIT 2 MONTHLY PERFORMANCE REPORT DECEMBER, 1986 COMMONWEALTH EDISON COMPANY NRC DOCKET NO. 050-374 LICENSE NO. NPF-18 i

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DOCUMENT ID 0036r/0005r

TABLE OF CONTENTS I. 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
5. Completed Safety Related Modifications 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
5. Indications of Failed Fuel Elements DOCUMENT ID 0036r/0005r

- 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.

DOCUMENT ID 0036r/0005r

II . . MONTHLY REPORT FOR UNIT TWO

'A. SUf9fARY OF OPERATING EXPERIENCE FOR UNIT TWO

, December 1-31 December 1, 0000 Hours. The unit entered December with the Reactor Critical and on-line at 67% (756 MWe) and decreasing Power to 64% (715 MWe) for TCV testing.

December 1, 0214 Hours. Reactor Power increasing (fast ramp) to 71%

(790 MWe) then increase at 3 MWe/hr to 74%

(830 MWe).

December 10, 1015 Hours. Reactor Power decreased to 67% (730 MWe) due to TCV oscillations.

December 10, 1320 Hours. Reactor Power increased to 8 MWe/hr to 74%

(926 MWe).

December 10, 2320 Hours. Reactor Power decreased to 32% (360 MWe) due to downshift caused by "B" Steam dome /RR suction delta temperature trip.

December 11, 0035 Hours. Reactor Power increasing (fast ramp) to 63%

(700 MWe) due to "B" RR upshift.

December 11, 0330 Hours. Reactor Power was 64% (710 MWe) then decreased to 29% (325 MWe) due to feedwater low flow reset trip (burned out light indication) resulting from prior "B" RR pump runback.

December 11, 0400 Hours. Reactor Power increased to 57% (630 MWe) then increasing power at 10 MWe/hr to 77%

(848 MWe).

December 27, 1250 Hours. Reactor Power decreased to 70% (755 MWe) due to starting MDRFP for 2-hour run surveillance.

December 27, 1450 Hours. Reactor Power increased to 70% (775 MWe) due to shuting off MDRFP.

C December 31, 2400 Hours. Reactor and Generator On-line and coasting down in power at 68% (755 MWe).

DOCUMENT ID 0036r/0005r

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

u.

1. . Amendments to Facility license or Technical Specification.

There were no Amendments to Facility License or Technical Specifications 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 no Tests or Experiments requiring NRC approval during the reporting period.

4. Corrective Maintenance of Safety Related Equipment.

The following table (Table 1) presents a summary of Safety-Related Maintenance completed on Unit Two during the reporting period. The headings indicated in this summary include: Work Request number, Component Name, cause of malfunction, results and effects on safe operation, and corrective action.

t

5. Completed Safety Related Modifications.

The following table (Table 2) presents a list of completed Modifications during this reporting period. Each entry will have i a short synopsis explaining details involved with each

' modification.

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TABLE 1' CORRECTIVE MAINTENANCE OF *j SAFETY RELATED EQUIPMENT Unit #2

, WONK REQUEST COMPONENT CAUSE OF MALFUNCTION RESULTS AND EFFECTS CORRECTIVE ACTION ON SAFE PLANT OPERATION

} L47422 SDGT Low Flow Alarm M-1-2-85-034 The new switch will have Replaced and Rewired Switch 2FS-VG009. a dual setpoint and low flow Switch, alarm contacts OFF switch.

j L63463 D/W and S/P Recorder Defective Love Controller Inaccurate Recorder Points. Replaced Defective Love

2TR-CM038. Control 1er.

< L63495 Rx Vessel Low Water Bad Switch Switch exceeded reject limit Replaced Switch.

l Level ADS Permissive during LIS-NB-206.

2B21-NO38A.

i L63587 RCIC Pump Suction Internal Valve Leakage. 1 GPM leakage to 2RE08 or Dissassembled and lapped i Relief 2E51-F017. approximately 2000 gal / day. Disc & Seat.

L63831 Div-I, D/W and S/P Bad Motor Clutch Assembly. When alarm came in, recorders Replaced Motor Clutch Temperature Recorder stop instead of go to fast Assembly.

2TR-CM037. speed.

i L63893 Div-II, D/W and S/P Defective Slow Speed Chart Recorder does not advance Replaced slow speed chart Temperature Recorder Drive and Clutch Assembly, in slow speed. drive and clutch assembly.

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L63908 RCIC Stm Line High Switch has a blown Inoperable switch. Replaced switch.

Flow Isolation diaphram.

. 2E31-N013BB.

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DOCUMENT ID 0036r/0005r

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TABLE 2 COMPLETED SAFETY RELATED MODIFICATIONS MODIFICATION NUMBER: A brief Synopsis of Incorporated Modification Objectives with final design resolution. Also, state reviewed or unreviewed safety questions.

The following list below nas all the Safety Regulated Modifications completed from December 1, 1986, through December 31, 1986.

l 1

M-1-2-85-034 - This Modification replaced the High Flow Alarm Switch 2FS-VG009 l with a dual set point model switch and have low flow alarm contacts l off this switch and not the heater trip relay. There was no l unreviewed safety question.  !

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DOCUMENT ID 0036r/0005r

'C. LICENSEE EVENT REPORTS The following is a tabular summary of all licensee event reports for l

LaSalle Nuclear Power Station, Unit Two, logged during the reporting l period, December 1 through December 31, 1986. This information is i

i provided pursuant to the reportable occurrence reporting requirements as j set forth in 10CFR 50.~13.

Licensee Event Report Number Date Title of Occurrence i

86-018-00 11/18/86 RCIC Steam Line High Flow Isolation Switch was found inoperable due to a failed (torn) diaphram inside the switch.

86-019-00 11/24/86 Reactor Low Water Level confirmed ADS switch was in access of reject limit due to setpoint drift.

DOCUMENT ID 0036r/0005r

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so 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 k

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l. OPERATING DATA REPORT

- , DOCKET No. 050-374 UNIT LaSalle Two DATE January 10, 1987 COMPLETED BY James P. Peters TELEPHONE (815)357-6761 OPERATING fiTATUS

1. REPORTING PERIOD: December, 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 (IP ANY) (MWe-Net): 985 i 4. REASONS FOR RESTRICTION (IF ANY): Administrative THIS MONTH YR TO DATE CUMULATIVE 5 NUMBER OF HOURS REACTOR WAS CRITICAL 744 6614.05 12003.45
6. REACTOR RESERVE SHUTDOWN HOURS 0.0 29.83 29.83
7. HOURS GENERATOR ON LINE 744 6534.62 11770.92
8. UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 0.0
9. GROSS THERMAL ENERGY GENERATED (MWH) 1790016 18005712 33514264
10. GROSS ELEC. ENERGY GENERATED (MWH) 591254 5951503 11061572

] 11. NET ELEC. ENERGY GENERATED (MWH) 566775 5717014 10540229

12. REACTOR SERVICE FACTOR 100% 75.5% 62.1%
13. REACTOR AVAILABILITY FACTOR 100% 75.8% _62.3%
14. UNIT SERVICE FACTOR 100% 74.6% 60.9%
15. UNIT AVAILABILITY FACTOR 100% 74.6% 60.9%
16. UNIT CAPACITY FACTOR (USING MDC) 73.5% 62.9% 52.7%
17. UNIT CAPACITY FACTOR (USING DESIGN MWe) 70.7% 60.5% 50.6%
18. UNIT FORCED OUTAGE RATE 0.0% 25.4% _26.4%
19. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH):

The units first refueling outage began January 4, 1987 and is scheduled

to end May, 1987.
20. IF SHUT DOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP NA 4

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2. AVERAGE DAILY UNIT POWER LEVEL
  • DOCKET NO: 030-374
    • UNIT: LASALLE TWO DATE: January 10, 1987 COMPLETED BY: James P. Peters TELEPHONE: (815) 357-6761_

MONTH: December, 1986 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net)

1. 755 17. 790
2. 793 18. 784 3 792 19. 780 4, 788 20. 774
5. 786 21. 768
6. 781 22. 763
7. 772 23, 757
8. 767 24. 753
9. 765 25. 747
10. 741 26. 743
11. 653 27. 735 ,

12, 790 28. 734

., 13. 781 29. 730

14. 775 30. 726
15. 775 31, 722 4
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, E. UNIQUE REPORTING REQUIREMENTS

1. Safety / Relief Valve Operations for Unit Two.

DATE VALVES NO & T'.T? PLANT DESCRIPTION ACTUATED ACTUAT16^S CONDITION

_ OF EVENT _-

There were no safety relief valves operated for Unit #2 during this reporting period.

DOCUMENT ID 0036r/0005r

2. ECCS Sy;tems Outtge2 o

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

OUTAGE NO. EQUIPMENT PURPOSE OF OUTAGE 2-637-86 2E22-C302A Replace High Pressure Valve Assembly.

2-638-86 "B" DG Change Crankcase Pressure Switch.

2-645-86 "A" DG Pressure Switch Calibration.

2-652-86 RCIC Technical Specifications Compliance 2-656-86 2E51-C003 Lubrication.

2-662-86 2822-F010 Limitorque Surveillance.

2-663-86 2E51-F022 Limitorque Surveillance.

2-664-86 2E12-F093 Limitorque surveillance.

2-665-86 2B12-F040B Limitorque Surveillance.

2-667-86 2E12-F094 Limitorque Surveillance.

2-680-86 2E12-F049B Limitc;que Surveillance.

2-681-86 2E12-F026B Limitorque Surveillance.

l 2-682-86 2B12-F087B Limitorque Surveillance.

2-683-86 2E12-F006B Limitorque Surveillance.

2-684-8f 2E12-F052B Limitorque Surveillance.

2-685-86 2E12-F052A Limitorque Surveillance.

2-688-86 2822-F011 Limitorque Surveillance.

2-689-86 "B" RHR Modification Test 1-2-86-045.

2-692-86 "A" RHR CY FILL Install High Point Vents.

I I

DOCUMENT ID 0036r/0005r 1

, 3. Off-Sita Dos] C31culition Manu21

  • 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 Systems during this reporting period.

5. Indications of Failed Fuel Elements.

There were no indications of failed fuel elements during this reporting period.

4 w

DOCUMENT ID 0036r/0005r

Commonwealth Edison 2 LES:lls County Nucitar Station y'- % Ruril Routa #1, Box 220 v ~ Marseilles, Illinois 61341 Telephone 815/357-6761 January 8, 1987 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 December 1, 1986 through December 31, 1986.

Very truly yours, 4

kb G. J. Diederich Station Manager LaSalle County Station ,

l l GJD/JPP/psk l

l Enclosure xc: J. G. Keppler, NRC, Region III NRC Resident Inspector LaSalle

Gary Wright, Ill. Dept. of Nuclear Safety A. Bournia, NRR Project Manager D. P. Galle, CECO D. L. Farrar, CECO INPO Records Center L. J. Anastasia, PIP Coordinator SNED M. A. Ortin, GE Resident H. E. Bliss, Nuclear Fuel Services Manager 1 C. F. Dillon, Senior Financial Coordinator, LaSalle Central File i

I i \

DOCUMENT ID 0043r/0005r  !

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