ML20211K156

Monthly Operating Repts for Oct 1986

ML20211K156
Person / Time
Site:	LaSalle
Issue date:	10/31/1986
From:	Diederich G COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF ADMINISTRATION (ADM), NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
NUDOCS 8611170059
Download: ML20211K156 (29)

Text

__

A 1

i LASALLE NUCLEAR POWER STATION UNIT 1 MONTHLY PERFORMANCE REPORT OCTOBER 1986 COMMONWEALTH EDISON COMPANY i NRC DOCKET NO. 050-373 LICENS3 NO. NPP-ll l

l l

l i

l i

i l

1 l

l l

0611170059 861 g 73 l

DR ADOCK 050 R $

nt Document 0043r/0005r

4 l

TABLE OF CONTENTS l l

1

1. INTRODUCTION l II. MONTHLY REPORT FOR UNIT ONE A. Sumary 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

5. Indications of Failed Fuel Elements Document 0043r/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 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.

l l

l l

1

! Document 0043r/0005r l

l

s' l l

-= l II. MONTHLY REPORT FOR UNIT ONE J A.

SUMMARY

OF OPERATING EXPERIENCE FOR UNIT ONE October 1-31 October 1, 0001 Hours. The Unit entered October with the Reactor Critical and on-line at 55.9% Power (615 MWe).

October 3, 2200 Hours. Began Decreasing Power 25 MWe/hr. to 27.3%

(300 MWe) due to drywell entry.

October 4, 1052 Hours. Began Increasing Power 16 MWe/hr. to 80.9%

(890 MWe).

October 6, 0000 Hours. Began Decreasing Power to 53.6% (590 MWe) for Control Rod Manipulations.

October 6, 0600 Hours. Began Increasing Power at 7.7 MWe/hr to 90%

(990 MWe).

October 10, 0200 Hours. Began Decreasing Power 50 MWe for Control Rod Manipulations.

October 10, 0245 Hours. Began Increasing Power at 15 MWe/hr to 90%

(990 MWe).

October 15, 1600 Hours. Began Decreasing Power 50 MWe to 85.5% (940 MWe) due to Control Rod Manipulations.

October 15, 1710 Hours. Began Increasing Power at 10 MWe/hr to 90%

(990 MWe).

October 18, 0115 Hours. Began Decreasing Power 120 MWe to 79.1% (870 MWe) for MSIV and TCV Surveillance Testing.

October 18, 0900 Hours. Began Decreasing Power 260 MWe to 55.5% (610 MWe) due to maintenance needed on MSIV Limit Switch.

October 18, 1245 Hours. Began Increasing Power at 10 MWe/hr to 90.1%

(995 MWe).

October 24, 0550 Hours. Began Decreasing Power 20 MWe to 75% (835 MWe) to swap FW 1B TDRFP with MDRFP.

October 24, 0600 Hours. Began Increasing Power at 10 MWe/hr to 82.8%

(911 MWe).

October 25, 0140 Hours. Began Increasing Power at 7.7 MWe/hr to 96.5% (1062 MWe).

October 31, 2400 Hours. Reactor and Generator on-line and holding at 96% (1060 MWe).

Document 0043r/0005r

I

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

. MAINTENANCE.

l. Amendments to facility license or Technical Specification. l 1

Amendment 46 - Incorporate changes to reporting requirements for Iodine Spiking from a short term report to an item included in Annual Report, for Report Requirements on Primary Coolant Iodine Spikes.

2. Facility or procedure changes requiring NRC approval.

There were no procedure changes requiring NRC approval during this reporting period.

The following facility changes which required NRC Approval were made up to this reporting period.

MODIFICATION NUMBER DESCRIPTION 1-1-82-263 Redundant Vent and Drain Valves and diverse and redundant scram instrumentation.

1-1-82-290 Redundant Fault protection in power circuits of electrical penetration circuits.

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.

i l

l l

l i

l i

Document 0043r/0005r l

TABLE 1 o .

CORRECTIVE MAINTENANCE OF ,

SAFETY RELATED EQUIPMENT -

UNIT #1 WORK REQUEST COMPONENT CAUSE OF MALFUNCTION RESULTS AND EFFECTS CORRECTIVE ACTION ON SAFE PLANT OPERATION L61873 DG 1A Compressor Pressure Switch out of The Compressor does not Recalibrated Pressure Start /Stop Pressure calibration, cycle. Switch.

Switch IPS-DG043A L61894 Post Loca Primary Pen Bound up. Red Pen for O2 Recorder Cleared and Lubricated containment O2 was sticking. Recorder.

Recorder LAIR-CM048 L,61946 E-APRM APRM E HI set out of APRM E generates APRM Hi and Replaced and recalibrated IC51-K605GS tolerance. Rod out block alarms when trip unit.

not bypassed.

L62026 Suppression Pool Bad circuit card and Failure of LIS-CM-104 Replaced circuit card Temperature Recorder connector. and connector.

ITR-CM037 L62340 DIV-II, Suppression Bad Amplifier Assembly All points read approximately Replaced Amplifier Pool Temperature 30 degrees low Assembly.

Recorder ITR-CM038 L62561 IB21-F028D Outbd Limit Switch was out of Upon re-opening, Limit Switch Readjusted Limit Switch Limit Switch #4 adjustment. would not make (K3G would not #4.

re-energize).

L62562 IB21-F028A Outbd. Limit Switch was out of Upon slow closing, limit switch Readjusted Limit Switch Limit Switch #4 adjustment. would not reopen (K3A does not #4.

de-energize).

L62772 DIV-I Post Loca 02 Found bad regulators, O2 Division I read about 2-3 times Replaced regulators R1, Monitor LAIR-CM047 Cell, Vacuum Pump, and less than DIV.II. R2 and R4, O2 cell, various leaks. Vacuum Pump and Repair leaks at panel.

Document 0043r/0005r

a 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, October 1, through October 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 86-039-00 10/16/86 Residual Heat Removal Shutdown Cooling Suction High Flow Isolation Switch was lock wired Closed, instead of Open during LIS-RH-312 due to personnel error.

i l

l l

l l

Document 0043r/0005r '

o 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 a

i l

I t

I I

(

i Document 0043r/0005r l

l

_ . _ _ . _ . _ _ _ . . . _ , , _ _ _ _ _ . _ , . _ . _ . _ _ - . , _ . _ = _

_ _ . _ _ _ _ _ , - _ . . . . ~ .._,

, 1. OPERATING DATA REPORT DOCKET NO. 050-373 UNIT LaSalle One DATE November 10, 1986 COMPLETED BY James P. Peters TELEPHONE (815)357-6761 OPERATING STATUS

1. REPORTING PERIOD: October, 1986 GROSS HOURS IN REPORTING PERIOD: 745

2. CURRENTLY AUTHORIZED POWER LEVEL (MWt):3323 MAX DEPEND CAPACITY (MWe-Net): 1036 DESIGN ELECTRICAL 2ATING (MWe-Net): 1078

3. POWER LEVEL TO WHICH RESTRICTED (IF ANY) (MWe-Net): 1035

4. REASONS FOR RESTRICTION (IP ANY): Administrative THIS MONTH YR TO DATE CUMULATIVE 5 NUMBER OF HOURS REACTOR WAS CRITICAL 745 984.65 13023.65

6. REACTOR RESERVE SHUTDOWN HOURS 0.0 0.0 1642.0

7. HOURS GENERATOR ON LINE 745 928.62 12570.62

8. UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 0.0

9. GROSS THERMAL ENERGY GENERATED (MWH) 2077296 2325576 34539226

10. GROSS ELEC. ENERGY GENERATED (MWH) 688665 761199 11260593

11. NET ELEC. ENERGY GENERATED (MWH) 662943 638846 10643303

12. REACTOR SERVICE FACTOR 100% 13.5% 52.4%

13. REACTOR AVAILABILITY FACTOR 100% 13.5% 58.9%

14. UNIT SERVICE FACTOR 100% 12.7% 50.6%

15. UNIT AVAILABILITY FACTOR 100% 12.7% 50.6%

16. UNIT CAPACITY FACTOR (USING MDC) 85.9% 8.5% 41.3%

17. UNIT CAPACITY FACTOR (USING DESIGN MWe) 82.5% 8.1% 39.7%

18. UNIT FORCED OUTAGE RATE 0.0% 0.0% 16.4%

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.

i l

l l

Document 0043r/0005r i

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

1. 583 17. 956

2. 577 18. 753 3 570 19. 861

4. 452 20, 986

5. 790 21. 1036

6. 672 22. 1008

7. 842 23. 1016

8. 956 24. 911

9. 946 25. 964

10. 939 26, 1028

11. 961 27. 985

12. 965 28. 985

13. 965 29. 989 t

14. 963 30. 1024 l

l 15. 954 31. 1019 t

l 16, 964 l

l l

i l

t l

l l

I Document 0043r/0005r l

wg w --y wi - -,w-, -

,.ce-4---% , -- .w ---4 -- -r,,- -----,-- w- - e--w-

ATTACHMENT E

3. UNIT SHUTDOWNS AND POWER REDUCTIONS .

DOCKET NO. 050-373

• UNIT NAME LaSalle One DATE November 10, 1986 REPORT MONTH OCTOBER, 1966 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 / COMMENTS

4. 10/18/86 S 0.0 H 5 MSIV and TCV Surveillance Testing Document 0043r/0005r

4 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 0043r/0005r

.~ 2. ECCS Systems Outtg:s i

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

OUTAGE NO. EOUIPMENT PURPOSE OF OUTAGE 0-204-86 OD$0lP Fuel Oil Replace Contactor at Transfer Pp. MCC 135Y-2, F3.

0-205-86 0 DG Maintenance Change Filters Switch 0-210-86 0 DG Air Dryer Repair Drain Trap "B" Drain Trap 1-1512-86 IB D/G Lubrication and Filter Change 1-1513-86 lE22-D310 HPCS Clean Sightglass Sightglass 1-1556-86 lE12-C003 Repair Leaks 1-1557-86 lE12-C003 Replace Contactor Document 0043r/0005r

. 3. Off-Site Dose 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 system during this reporting period.

5. Indications of Failed Fuel Elements There were no indications of Failed Fuel Elements from January 1, 1986 through October 31, 1986.

(

Document 0043r/0005r

LASALLE NUCLEAR POWER STATION UNIT 2 MONTHLY PERFORMANCE REPORT OCTOBER, 1986 COMMONWEALTH EDISON COMPANY NRC DOCKET NO. 050-374 LICENSE NO. NPF-18 2

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 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 Sarge.',t 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.

l DOCUMENT ID 0036r/0005r

,1,I . MONTHLY REPORT FOR UNIT TWO A.

SUMMARY

OF OPERATING EXPERIENCE FOR UNIT TWO October 1-31 October 1, 0001 Hours. The Unit entered October with the reactor critical and on-line at 84.1% (925 MWe).

October 3, 0030 Hours. Began decreasing power 50 MWe to 79.5% (875 MWe) due to control rod manipulations.

October 3, 0040 Hours. Began increasing power at 15 MWe/hr to 84.1%

(925 MWe).

October 9, 2330 Hours. Began decreasing power at 150 MWe/hr. to 48.4% (532 MWe) due to control rod manipulations.

October 10, 0330 Hours. Began increasing power at 7.5 MWe/hr. to 90%

(990 MWe).

October 17, 0005 Hours. Began decreasing power 50 MWe to 81.8% (900 MWe) due to control rod manipulations.

October 17, 0125 Hours. Began increasing power at 12 MWe/hr. to 90.3% (995 MWe).

October 24, 0000 Hours. Began decreasing power 50 MWe to 81.8% (900 MWe) due to control rod manipulation.

October 24, 0215 Hours. Began increasing power at 10 MWe/hr. to 90%

(990 MWe).

October 29, 2330 Hours. Began decreasing power at 150 MWe/hr. to 51.8% (570 MWe) due to load dispatcher.

October 30, 0405 Hours. Began increasing power at 11 MWe/hr. to 90%

(990 MWe).

October 31, 2400 Hours. Reactor and generator on-line and holding at 91% (1000 MWe).

i DOCUMENT ID 0036r/0005r l

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

. MAINTENANCE.

1. Amendments to facility license or Technical Specification.

'l Amendment 25 - Incorporate the replacement of 8 - 26 inch and 2 -

,8 inch Vent and Purge Isolation Valves by Clow Corp. that meet all vent and purge requirements.

' Amendment 26 - Incorporate the instruments for suppression Pool Water Level and Water Temperature Monitoring Instrumentation at ,

the Remote Shutdown Panel.

Amendment.2*7 - Incorporate the Modification of Automatic Depressurization System Logic required by License Conditior.

2.C.(18)(d)(1).

Amendment 28 - Incorporate changes to reporting requirements for Iodine Spiking from a short term report to an item included in Annual Re x>rt, for reporting requirements on Primary Coolant Iodine Spikes.

2. Facility or procedure changes requiring NRC approval.

There were no facility or procedure change requiring NRC approval 1

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.

I i

l c

DOCUMENT ID 0036r/0005r

TABLE 1 . .

, COR.IECTIVE MAINTENANCE OF SAFETY RELATED EQUIPMENT Unit #2 WORK REQUEST COMPONENT CAUSE OF MALFUNCTION RESULTS AND EFFECTS CORRECTIVE ACTION I

ON SAFE PLANT OPERATION e

1 L61246 RCIC Turb. Trip and Dirty Limit Switch During testing the 2TTV would Cleaned Limit Switch Throttle Valve 2TTV. Contactors. not trip from the Control Room. Contactors.

2 L61247 IRM B Loose connection at Sporadic operation at Erratic Adjusted loose connection.

i 2C51-K601B Voltage Regulator Card. time intervals.

, L61977 RCIC Water Leg Pp. Worn Pump and Intervals. Pump is extremely loud with Installed new pump and 2E51-C003 excessive vibration. seal.

L62291 Ion Chamber Power Defective Power Supply. Incomplete Surveillance Replaced Power supply.

Supply LIS-NR-211 L62465 "B" VC Ammonia Bad optic cell board. Detector will not reset. Replaced optic cell Detector OXY-VC165B board.

L62622 Reactor Pressure Incorrect Gain Setting Erratic Indication. Adjusted gain on Recorder 2C34-R609 on Recorder. Recorder.

i L62683 DIV-III, 125 VDC Shorted Ground Detector. DIV-III has a 125 Volt Ground. Replaced Ground Detector.

Ground Detector i.

l 4

I i

I i

i DOCUMENT ID 0036r/0005r

1 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, October 1 through October 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 There were no Licensee Event Reports for this unit during this reporting period.

l l

DOCUMENT ID 0036r/0005r

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 f

n DOCUMENT ID 0036r/0005r

e

l. OPERATING DATA REPORT DOCKET NO. 050-374 UNIT LaSalle Two DATE November 10, 1986 COMPLETED BY James P. Peters TELEPHONE (815)357-6761 OPERATING STATUS

1. REPORTING PERIOD: October, 1986 GROSS HOURS IN REPORTING PERIOD: 745

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): 982

4. REASONS FOR RESTRICTION (IF ANY): Administrative THIS MONTH YR TO DATE CUMULATIVE 5 NUMBER OF HOURS REACTOR WAS CRITICAL 745 5150.05 10539.45

6. REACTOR RESERVE SHUTDOWN HOURS 0.0 29.83 29.83

7. HOURS GENERATOR ON LINE 745 5070.62 10306.92

8. UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 0.0

9. GROSS THERMAL ENERGY GENERATED (MWH) 2107104 14329560 29838112 4 10. GROSS ELEC. ENERGY GENERATED (MWH) 696253 4734546 9844615

11. NET ELEC. ENERGY GENERATED (MWH) 669984 4548344 9371559

12. REACTOR SERVICE FACTOR 100% 70.6% 42.4%

13. REACTOR AVAILABILITY FACTOR 100% 70.9% 42.5%

14. UNIT SERVICE FACTOR 100% 69.5% 41.4%

15. UNIT AVAILABILITY FACTOR 100% 69.5% 41.4%

16. UNIT CAPACITY FACTOR (USING MDC) 86.8% 60.2% 50.7%

17. UNIT CAPACITY FACTOR (USING DESIGN MWe) 83.4% 57.8% 48.7%

18. UNIT FORCED OUTAGE RATE 0.0% 30.5% 29.0%

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

A refueling outage is scheduled to begin January 2, 1987.

20. IF SHUT DOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP NA DOCUMENT ID 0036r/0005r

2 AVERAGE DAILY 'JNIT POWER LEVEL e

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

1. 883 17. 946

2. 874 18, 942 3 873 19. 936

4. 889 20. 929

5. 882 21. 923

6. 878 22. 914

7. 874 23, 909

8. 870 24. 931

9. 870 25. 931

10. 691 26. 963

11. 852 27. 918

12. 940 28. 912 13, 951 29, 907

14. 947 30. 7'9

15. 942 31. 924

16. 936 I

r l

l DOCUMENT ID 0036r/0005r

ATTACHMENT E e' .'

3. UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 050-374 o UNIT NAME LaSa11e Two DATE November 10, 1986 REPORT MONTH OCTOBER, 1986 COMPLETED BY James 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 / COMMENTS'

12. 10/10/86 S 0.0 H 5 Control Rod Manipulations i

DOCUMENT ID 0036r/0005r

3-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. .

I DOCUMENT ID 0036r/0005r i

, , 2. ECCS Syatens Outtgaa The following outages were taken on ECCS Systems during the reporting period.

OUTAGE NO. EQUIPPENT PURPOSE OF OUTAGE 2-575-86 RCIC Steam Drain Pot Troubleshoot Level Switch.

2-576-86 RCIC System Set limits on trip and throttle valve.

2-577-86 RCIC Water Leg Pp. Replace Pump.

2-578-86 2E51-F010 Replace 74 Relay.

2-580-86 RCIC Water Leg Pp. Rebuild Motor.

2-581-86 Condenser Vacuum Pp. Repair Vacuum Pp.

2OG03P 2-611-86 2A DG Change Soak Back Filters.

2-614-86 2B DG Change Soak Back Filters.

DOCUMENT ID 0036r/0005r l

t

o

, 3. Off-Sits Dos 2 Calculstion Manusi 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.

5. Indications of Failed Fuel Elements.

There is currently one suspected Fuel failure (one rod) on Unit #2 from the time period of January 1, 1986 to October 31, 1986. The reason for this suspected failure is that during January 20, 1986, the summation of 6 Nuclide activities at the Steam Jet Air Ejector increased approximately 450 uci/sec. to 3000 uci/sec. No unusual power maneuvers were occurring at the time, and we suspect an undetectable manufacturing flaw or just a " weak spot" in the Cladding that gave away.

DOCUMENT ID 0036r/0005r

i[

~

[c*.

l m v

J Commonwealth Edison LaSzile County Nuclear Station Rural Route #1, Box 220

Marseilles, Illinois 61341 Telephone 815/357-6761 '

l f

November 10, 1986 4

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 October 1, 1986 through October 31, 1986.

Very truly yours, 4

f* J/ W G. J. Diederich i ation Manager LaSalle County Station GJD/JPP/jdp Enclosure l xc: J. G. Keppler, NRC, Region III d NRC Resident Inspector LaSalle Gary Wright, Ill. Dept. of Nuclear Safety i A. Bournia, NRR Project Manager D. P. Galle, CECO

! D. L. Farrar, CECO INPO Records Center i

L. J. Anastasia, PIP Coordinator SNED M. A. Ortin, GE Resident j H. E. Bliss, Nuclear Fuel Services Manager C. F. Dillon, Senior Financial Coordinator, LaSalle Central File lg dl Document 0043r/0005r

_ - . _ _ _ _ _ _ _ _ . _ _ . - _ _ _ - . - - ,