ML20211E131

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Monthly Operating Repts for May 1986
ML20211E131
Person / Time
Site: LaSalle  Constellation icon.png
Issue date: 05/31/1986
From: Diederich G, Peters J
COMMONWEALTH EDISON CO.
To:
NRC OFFICE OF ADMINISTRATION (ADM), NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
NUDOCS 8606130237
Download: ML20211E131 (33)
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4 e-LASALLE NUCLEAR POWER STATION 2

UNIT 1 MONTHLY PERFORMANCE REPORT MAY, 1986 COMMONWEALTH EDISON COMPANY NRC DOCKET NO. 050-373 LICENSE NO. NPF-ll 8606130237 860531 PDR ADOCK 05000373 R PDR

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9 TABLE OF CONTENTS l l

r 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

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4 s 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-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.

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t s II. MONTHLY REPORT FOR UNIT ONE A. SUffUWY OF OPERATING EXPERIENCE FOR UNIT ONE May 1 - 31 May 1, 0001 Hours. The Unit entered May with the reactor subcritical and Off-Line in cold shutdown for first refueling outage.

May 30, 2400 Hours. Reactor in cold shutdown for first refueling outage.

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

MAINTENANCE.

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1. Amendments to facility license or Technical Specification.

AMENDMENT 39 - Change to CRD Accumulator Alarm Action /Setpoint.

AMENDMENT 40 - Unit #1 Reload Submittal AMENDMENT 41 - Degraded Voltage to Technical Specification 3.3.3 AMENDMENT 42 - Primary Containment Overcurrent Protection to Technical Specification 3.8.3.2 Revision

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 l safety-related maintenance completed on Unit one during the reporting period. The headings indicated in this summary include: Work Request number, Component Name, Cause of

! Malfunction, Results and Effects on Safe Operation, and Corrective Action.

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TABLE 1 CORRECTIVE MAINTENANCE OF

  • SAFETY RELATED EQUIPMENT WORK REQUEST COMPONENT CAUSE OF MALFUNCTION RESULTS AND EFFECTS CORRECTIVE ACTION ON SAFE PLANT OPERATION - s 4

L21531 MSIV (K3) and TSV (K10) M-1-1-84-015 Added additional Completed modification for single MSIV and TSV not package.

"Not Full Open" full open indication in Control Alarms. Room.

L27306 "A" RHR Pump M-1-1-83-135 Replace old shaft with new Completed modification IE12-C002A short shaft. package.

L35150 S/D Cooling Inbd Bad internal components High S/D Header Pressure Alarm Repaired Valve internals Suction valve in valve. Up in Control Room. and completed on-site lE12-F009. review per administrative replacement.

L43757 Odor Eater Bypass Bad Microswitch on The damper drifts closed. Replaced mirco-switch Damper OVCl3YA Actuator. and installed.

L51627 "A" Rx. Recirc. Pump Failed #2 Seal. The #2 seal failed allowing Replaced with new seal.

  1. 2 Seal. the #1 seal seeing increased 3

pressure.

L56528 Unit #1, Division Batteries were discharged Division III Batteries Replaced all cells except 1

III Batteries and left open circuited. inoperable. for dummy cell 28-30.

1822-S001.

. L56666 Mechanical Snubber Damaged Snubber. Failure of LTS-500-14. Replaced Snubber.

1 ILC09-1031S.

L56667 Mechanical Snubbers Damaged Snubbers. Failure of LTS-500-14. Replaced Snubbers.

ILC01-1058S/1051S L57708 Mechanical Snubber Damaged Snubber. Failure of LTS-500-14. Replaced Snubber.

M-1302-22-102 L57754 RBCCW Isolation Valve Warped Bonnet Gasket. Failure of LTS-100-30. Repacked new packing LWR 179 and new bonnet gasket. ,

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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
  • L57755 O/L Relay for LPCI Bad overload device. O/L relay wouldn't manually Replaced overload device.

"A" Injection Vlv. trip.

IE12-F042A L57804 Mechanical Snubber Damaged Snubber. Failure of LTS-500-14. Replaced Snubber.

IRH40-1506S.

L57805 Mechanical Snubbers Damaged Snubbers. Failure of LTS-500-14. Replaced Snubbers.

, IRHA6-1003S and i IR403-1508S L57806 Mechanical Snubber Damaged Snubber. Failure of LTS-500-14. Replaced Snubber.

i IRH40-1043S.

L57807 Mechanical Snubbers Damaged Snubber. Failure of LTS-500-14. Replaced Snubber.

IRH40-1042S/1572S L57808 Mechanical Snubber Damaged Snubber. Failure of LTS-500-14. Replaced Snubber.

1RH03-1047S -

L57809 Mechanical Snubbers Damaged Snubbers. Failure of LTS-500-14. Replaced Snubbers.

1RH25-H04S/H03S and H06S.

L57810 Mechanical Snubber Damaged Snubber. Failure of LTS-500-14. Replaced Snubber.

IR459-1056S.

L57922 Mechanical Snubber Damaged Snubber. Failure of LTS-500-14. Replaced Snubber.

M-1302-28-76.

L57923 Mechanical Snubber Damaged Snubber. Failure of LTS-500-14. Replaced Snubber.

M-1302-28-74.

L57925 Mechanical Snubber Damaged Snubber. Failure of LTS-500-14. Replaced Snubber.

ILP20-1030S.

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TATLE 1 O

CORRECTIVE MAINTENANCE OF SAFETY RELATED EQUIPMENT ,

WORK REQUEST COMPONENT CAUSE OF MALFUNCTION RESULTS AND EFFECTS CORRECTIVE ACTION ,

ON SAFE PLANT OPERATION L57926 Mechanical Snubber Damaged Snubber. Failure of LTS-500-14. Replaced Snubber.

ILP20-1028S L57927 Mechanical Snubber Damaged Snubber. Failure of LTS-500-14. Replaced Snubber.

ILP02-1054S L57985 Mechanical Snubber Damaged Snubber. Failure of LTS-500-14. Replaced Snubber.

M-1302-23-14.

L57986 Mechanical Snubber Damaged Snubber. Failure of LTS-500-14. Replaced Snubber.

M-1302-36-54.

L57987 Mechanical Snubber Damaged Snubber. Failure of LTS-500-14. Replaced Snubber.

IMS10-1013S L58108 Mechanical Snubber Damaged Snubber. Failure of LTS-500-14. Replaced Snubber.

IRH13-ll61S.

L58135 Mechanical Snubber Damaged Snubber. Failure of LTS-500-14. Repacked Snubber.

IMS00-1041S.

L58136 Mechanical Snubber Damaged Snubber. Failkure of LTS-500-14. Replaced Snubber.

IMS00-1029S.

L58154 Mechanical Snubber Damaged Snubber. Failure of LTS-500-14. Replaced Snubber.

1HG05-1041S.

L58204 "A" VC "B" NH3 Bad Drive Motor and Gear Intermittent Problem with Replaced bad motor and Detector. on Chemcassette assembly. Chemcassette tape causing gear on assembly.

spurious trips.

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TABLE I CORRECTIVE MAINTENANCE OF e

.- SAFETY RELATED EQUIPMENT

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

L58483 "A" VC "B" NH3 Bad Capstan Rolle'r. Tripped and will not reset. Replaced Capstan Roller.

Detector.

L58625 Outboard H2 Recom- Improperly landed wire. Valve opened but would not Relanded wire per biner Isolation close. electrical print.

Valve lHG006B.

LS8685 Excess Flow Check Clogged Check Valve. Valve will not re-open from Disassembled, cleaned and valve IB33-F315C. Control Room. flushed check valve then reassembled.

L58686 Excess Flow Check Clogged Check Valve. Valve will not re-open from Disassembled, cleaned j valve IB33-F315D Control Room. and flushed check valve then reassembled.

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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, May 1 through May 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 86-015-00 04/25/86 Full scram signal upon ApRM "lF" trip due to mechanical failure of scram contactor.

86-016-00 04/25/86 Fuel bundle loaded without proper SRM instrumentation due to poor communication techniques.

86-017-00 05/03/86 Reactor Scram on low CRD header pressure due to improper techniques in overseeing Control Room instrumentation.

86-018-00 05/21/86 "A" VC "B" ammonia detector spurious trip due to binding of cassette spool mechanism.

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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 ,

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1. OPERATING DATA REPORT DOCKET NO. 050-373 UNIT LaSalle One DATE 6/10/86 COMPLETED BY James P. Peters TELEPHONE (815)357-6761 OPERATING STATUS
1. REPORTING PERIOD: May 1986 GROSS liOURS 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) -11481 -47918 9956539
12. REACTOR SERVICE FACTOR 0.0% 0.0% 56.8%
13. REACTOR AVAILABILITY FACTOR 0.0% 0.0% 64.6%
14. UNIT SERVICE FACTOR 0.0% 0.0% 54.9%

l!. . UNIT AVAILABILITY FACTOR 0.0% 0.0% 54.9%

16. UNIT CAPACITY FACTOR (USING MDC) -1.5% -1.3% 45.4%
17. UNIT CAPACITY FACTOR (USING DESIGN MWe) -1.4% -1.2% 43.6%

1F. 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 June 18, 1986.

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

Start-up on June 18, 1986 may be postpcaed due to pending decision of NRC due to Static O-Rinq problem.

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2. AVERAGE DAILY UNIT POWER LEVEL

. DOCKET NO: 050-373 UNIT: LASALLE ONE DATE: 6/10/86 COMPLETED BY: James P. Peters TELEPHONE: (815) 357-6761 MONTH: MAY 1986 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net)

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

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ATTACHMENT E ,

3. UNIT SHUTDOWNS AND POWER REDUCTIONS -

LOCKET NO. 050-373 ,

UNIT NAME LaSaj1e One DATE 6/10/86 REPORT MONTH MAY 1986 COMPLETED BY James P. Peters TELEPHONE (815)357-6761 ,

METHOD OF TYPE SHUTTING DOWN F: PORCED DURATION THE REACTOR OR CORRECTIVE NO. DATE S: SCHEDULED (HOURS) REASON REDUCING POWER ACTIONS /COPMENTS Th2re were no Unit shutdowns or power reductions during this reporting period due to the first refueling outage.

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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.

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2. ECCS Systems Outtgis

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

OUTAGE NO. EQUIPMENT PURPOSE OF OUTAGE l-825-86 HPCS System Electrical Maintenance Surveillances.

1-826-86 lE12-F040A Change Thermal O/L setting and test.

1-827-86 lE12-F042A Replace Overload.

1-832-86 lE12-F073A/74A Replace Breakers and O/L.

1-833-86 lE12-F047A Replace Breaker.

1-845-86 "A" RHR/LPCS Technical Staff Testing. '

Manual Injections 1-849-86 250 VDC Bus and RCIC Install Limiter Plate.

1-869-86 lE12-F008 LIS-RH-312 1-870-86 lE12-F009 LIS-RH-312 1-890-86 RCIC Switches Repipe 3-Way Manifold.

1-892-86 lE12-F067C LOP-NB-01 1-893-86 lE12-F098C Reduce "C" RHR Flow.

1-896-86 IE51-F064 Repack Valve.

1-907-86 lE12-F359A/B Repair Valve.

l l-908-86 lE12-F087A License Requirement.

1-928-86 lE51-F063 Repack Valve.

l 1-934-86 RCIC Water Leg Pp. LTS-300-4 1-939-86 "C" RHR Serv. Water Reinstall Inbd. Grease l

Pp. lE12-C300C Seal.

l l-942-86 lE51-F086 Change Breaker Ccntacts.

l l-945-86 lE51-F064 Repair Valve Seat.

l-946-86 lE51-F064 Determinate Limitorque.

} 1-947-86 lE12-F063A Fill Suppression Pool.

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3. Off-Site Dose Calculation Manual There were no changes to the ODCM manual during this reporting period.
4. Radioactive Waste Treatment Systems.

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

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LASALLE NUCLEAR PCMER STATION UNIT 2 MONTHLY PERFORMANCE REPORT MAY 1986 l COMMONWEALTH EDISON COMPANY

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

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, 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 Relsted 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. Eafety/ Relief Valve Operations
2. ECCS System Outages
3. Off-Site Dose Calculation Manual Changes
4. Major Changes to Radioactive Waste Treatment System 1

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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)' 57-6761 extension 325.

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, II. MONTHLY REPORT FOR UNIT TWO A.

SUMMARY

OF OPERATING EXPERIENCE FOR UNIT TWO s

- May 1-31 May 1, 0001 Hours. The Unit entered May with the Reactor critical at 72% power and Generator on line at 850 MWe, May 2, 0355 Hours. Reactor Power was at 73% (880 MWe) when a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> time clock was initiated due to containment 02 concentration being too high.

May 4, 0500 Hours. Reactoi Power decreased to 51%

(600 MWe) due to control rod manipulations.

May 7, 1445 Hours. Reactor Power increased to 96%

(1070 MWe).

May 9, 0911 Hours. Reactor Scram on low level due to loss of TDRFP Control Power.

May 10, 2122 Hours. Reactor sustained criticality.

May 11, 0442 Hours. Reactor Power at 10%. The generator was brought on-Line.

May 11, 0443 Hours. Reactor Scram due to Group-I Isolation on high main steam line flow.

May 23, 2005 Hours. Reactor sustained criticality.

May 24, 1625 Hours. Reactor Power at 12%. The Generator was brought on-line.

May 30, 2300 Hours. Reactor Power Decreased to 50%

(575 MWe) due to control rod manipulations.

May 31, 2359 Hours. Reactor Power steady at 91% (1038 MWe).

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l 8 B. PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS AND SAFETY RELATED MAINTENANCE.

1. Amendments to facility license or Technical Specification.

AMENDMENT 21 - Change to CRD Accumulator Alarm Action /Setpoint.

NEENDMENT 22 - Degraded voltage to Technical Specification 3.3.3.

AMENDMENT 23 - Primary Containment Overcurrent Protection to Technical Specification 3.8.3.2 Revision.

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.

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TABLE 1 CORRECTIVE MAINTENANCE OF o SAFETY RELATED EQUIPMENT WORK REQUEST COMPONENT CAUSE OF MALFUNCTION RESULTS AND hPFECTS CORRECTIVE ACTION ON SAFE PLANT OPERATION L55291 2B DG ESP Status Bad Aux. contact lever on Computer Point C504 alarms Replaced Aux. contact Panel 2AP078 74F1 Relay. Intermittently. lever.

L56401 "B" RR Pump Seal Seal is failing. Seal #2 is seeing 800 psig. Replaced seal and

  1. 7, 2B33-C001B. bearing housing.

LS8214 Post Loca Rx Press. Failed chart drive card. Recorder paper does not Replaced chart drive and Lv1. Wide Range advance. card.

Recorder 2B21-R884A.

LS8314 RCIC Barometric Cond- Dirty Commutator and Control Room gets run indica- Cleaned commutator and enser Vacuum Pump. brushes on motor, tion, but pump does not run. inspected brushes.

L58374 C RHR Injection Misadjusted limits. Reverse indication in Control Readjusted limits for J Testable Check Valve Room. proper indication.

2E12-F041C L58375 MSIV-LCS OUTBD Valve Dirty Torque Switch con- Valve would not cycle per Cleaned open torque 2E33-F009 tacts and misadjusted LOS-MS-Ql. switch contacts and limits. reset limits.

L58376 MSIV-LCS INBD. Valve Dirty Torque Switch con- Valve would not cycle per Cleaned torque switch 2E32-F002A. tacts and misadjusted LOS-MS-Ql. contacts and reset limits.

L58388 2A LPCI Suction Valve Bad key in declutch lever. Valve went closed, but would Replaced key in de-2E12-F004A. not open tripping M.O. thermals, clutch lever.

L58426 Mechanical Snubber Damaged Snubber. Failed LTS-500-14. Replaced Snubber.

2RH14-H04S.

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CORRECTIVE MAINTENANCE OF ..

SAFETY RELATED EQUIPMENT ,

WORK REQUEST COMPONENT CAUSE OF MALFUNCTION RESULTS AND EFFECTS CORRECTIVE ACTION ON SAFE PLANT OPERATION L58455 Mechanical Snubber Damaged Snubber. Failed LTS-500-14. Replaced Snubber, 2VQ05-2025S.

L58530 "B" RHR Return to RR Misadjusted Closed Limit Valve does not cycle per Readjusted Closed Testable check valve Switch. LOS-RH-93. Limit Switch.

2E12-F0508.

L58535 RCIC Barometric Failed 74 Control Relay. Auto Trip light is energized. Replaced 74 Control Condenser Pump. Relay.

L58599 Mechanical Snubber Damaged Snubber. Failed LTS-500-14. Replaced Snubber.

2HP02-2813S.

I L58627 Mechanical Snubber Damaged Snubber. Failed LTS-500-14. Replaced Snubber.

2RR59-2038S.

L58665 HCU 26-31 Instrument Packing Leak. Accumulator will not hold Replaced valve.

Block 2C11-2001-111 charge for more than hour.

reset limits.

L58376 MSIV-LCS INBD. Valve Dirty Torque Switch con- Valve would not cycle per Cleaned torque switch 2E32-F002A. tacts and misadjusted LOS-MS-Ql. contacts and reset I

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P C. LICENSEE EVENT REPORTS The following is a tabular summary of all licensee event reports for j LaSalle Nuclear Power Station, Unit Two, logged during the reporting period, May 1 through May 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 to be submitted during this reporting period.

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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 k

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, *l. OPERATING DATA REPORT

. DOCKET NO. 050-374 UNIT LaSalle Two DATE 6/10/86 COMPLETED BY James P. Peters TELEPHONE (815)357-6761 OPERATING STATUS

1. REPORTING PERIOD: May, 1986 GROSS HOURS IN REPORTING PERIOD: 744 l 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): N/A 4.

REASONS FOR RESTRICTION (IF ANY): N/A THIS MONTH YR TO DATE CUMULATIVE 5 NUMBER OF HOURS REACTOR WAS CRITICAL 404.4 3179.99 8569.39

6. REACTOR RESERVE SHUTDOWN HOURS 0.0 29.83 29.83
7. HOURS GENERATOR ON LINE 379.6 3128.04 8364.34
8. UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 0.0
9. GROSS THERMAL ENERGY GENERATED (MWH) 928320 9099936 24608488
10. GROSS ELEC. ENERGY GENERATED (MWH) 303616 3035547 8145616
11. NET ELEC. ENERGY GENERATED (MWH) 287500 2938837 7762052
12. REACTOR SERVICE FACTOR 54.4% 87.8% 60.4%
13. REACTOR AVAILABILITY FACTOR 54.4% 88.6% 60.6%
14. UNIT SERVICE FACTOR 51.0% 86.3% 58.9%
15. UNIT AVAILABILITY FACTOR 51.0% 86.3% 58.9%
16. UNIT CAPACITY FACTOR (USING MDC) 37.3% 78.3% 52.8%
17. UNIT CAPACITY FACTOR (USING DESIGN MWe) 35.8% 75.2% 50.8%
18. UNIT FORCED OUTAGE RATE 49.2% 13.7% 22.9%
19. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF BACH)

! The Units First Refuel is scheduled to start November 1, 1986.

20. IF SHUT LOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP N/A 4

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2. AVERAGE DAILY UNIT POWER LEVEL e

,- DOCKET NO: 050-374

  • UNIT: LASALLE TWO DATE: 6/10/86 COMPLETED BY: James P. Peters TELEPHONE: (815) 357-6761 MONTH: May 1986 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net)
1. 834 17. -16
2. 948 .18. -16 3 1033 19. -16
4. 680 20. -15
5. 808 21. -16
6. 934 22. -15
7. 1024 23. -14
8. 1007 24, 32
9. 325 25. 170
10. -14 26. 340
11. -15 27. 733
12. -13 28. 819
13. -14 29. 833
14. -14 30, 736
15. -14 31. 931
16. -16 l

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i DOCUMENT ID 0036r/0005r

ATTACHMENT E

3. UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 050-3~13 0 UNIT NAME LaSa11e Two
  • DATE 6/10/86
  • REPORT MONTH MAY 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 /COf9 TENTS 19 5/4/86 s 0.0 F 5 Dropped Load at 150 MWe/Hr until 600 MWe due to control rod manipulations.

20 5/9/86 F 43.5 H 3 Reactor Scram on low level due to loss of TDRFP's control power.

21 5/11/86 F 320.9 H 3 Reactor Scram due to Group-I isolation on high main steam line flow.

DOCUMENT ID 0036r/0005r

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  • 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 j period.

DOCUMENT ID 0036r/0005r t

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. 2. ECCS Systtms Outcg s .

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

OUTAGE NO. EQUIPMENT PURPOSE OF OUTAGE 2-206-86 28 DG Motor Driven Air Compressor Repairs 2-208-86 2E12-F024A Reset Torque Switches 2-218-86 RCIC Barometric Condensor Repair Pump Vacuum Pp.

2-219-86 "2A" DG "B" Air Compressor HPCS Discharge Valve 2-228-86 "2A" DG "B" Air Compressor Repair HPCS Discharge Valve 2-252-86 HPCS SWGR. 243 Check 2432 Circuit Brk.

Contacts.

2-256-86 RCIC Barometric Condensor Inspect Motor Vacuum Pp.

2-259-86 RCIC Barometric Condensor Replace 74 Relay.

Condensate Pp.

2-278-86 DIV-I RHR S/D Cooling LIS-NB-411 2-279-86 DIV-II RHR S/D Cooling LIS-NB-411 2-281-86 "2A" DG "B" Air Compressor Repair Relief Valve.

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DOCUMENT ID 0036r/0005r l

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e 3. Off-Site Do 3 Calculation Manual 6 There were no changes to the ODCM manual during this reporting period.

4. Radioactive Waste Treatment Systems.

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

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DOCUMENT ID 0036r/0005r

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6 .

[a Commonwe:Ith Edison LaSalle County Nuclear Station f

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s ) Rural Route #1, Box 220 Marseilles, Illinois 61341 g N Telephone 815/357-6761 June 10, 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 May 1, 1986 through May 30, 1986.

Very truly yours, f S. h .

h G.Station J. Diedericn' Manager LaSalle County Station GJD/JPP/jdp Enclosure xc: J. G. Keppler, NRC, Region III NRC Resident Inspector LaSalle Gary Wright, Ill. Dept. of Nuclear Safety D. P. Galle, CECO D. L. Farrar, CECO INPO Records Center L. J. Anastasia, PIP Coordinator SNED J. E. Ellis, GE Resident H. E. Bliss, Nuclear Fuel Services Manager C. F. Dillon, Senior Financial Coordinator, LaSalle 9

7 f Document 0043r/0005r

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