Text

Monthly Operating Repts for June 1984
	ML20093J565
Person / Time
Site:	LaSalle
Issue date:	06/30/1984
From:	Diederich G, Dus R; COMMONWEALTH EDISON CO.
To:	; NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
	NUDOCS 8407300183
	Download: ML20093J565 (31)
	v • d • e

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LASALLE NUCIAAR POWER STATION I

UNIT 1 MONTHLY PERFORMANCE REPORT JUNE 1984 i

ColGIONWEALTH EDISON COMPANY NRC DOCKET No. 050-373 LICENSE NO. NPF-11 i

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8407300183 840630 PDR ADOCK 05000373 l

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TABLE OF CONTENTS I.

INTRODUCTION II.

MONTHLY REPORT FOR UNIT ONE A.

Susunary of Operating Experience B.

PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS, AND SAFETY RELATED MAINTENANCE 1.

Amendments to Facility License or Technical Specifications 2.

Facility or Procedure Changes Requiring NRC Approval 3.

Tests and Experiments Requiring NRC Approval 4.

Corrective Maintenance of Safety Related Equipment C.

LICENSEE EVENT REPORTS D.

DATA TABULATIONS 1.

Operating Data Report 2.

Average Daily Unit Power Level 3.

Unit Shutdowns and Power Reductions E.

UNIQUE REPORTING REQUIREMENTS 1.

Main Steam Relief Valve Operations 2.

ECCS System Outages 3.

Off-Site Dose Calculation Manual Changes 4.

Major Changes to Radioaci.ive Waste Treatment System l

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INTRODUCTION The LaSalle Nuclear Power Station is a Two Unit Facility Located in Marsellies, Illinois. Each Unit is a Bolling Water Reactor with a designed electrical output of 1078 MWe net-The Station is owned by Commonwealth Edison Company. The Architect / Engineer was Sargent & Lundy,

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and the primary construction contractor was Commonwealth Edison Company.

The condenser cooling method is a closed cycle cooling pond. Unit One is subject to License Number NPF-11, issued on April 17, 1982. The date of initial criticality was June 21, 1982. Unit Two is subject to license nurber NPF-18, issued on December 16, 1983. The date of initial criticality was March 10, 1984.

This report was complied by Randy S. Dus telephone number (815)357-6761, extension 324.

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MONTHLY REPORT FOR UNIT ONE A.

SUMMARY

OF OPERATING EI?ERIENCE FOR UNIT ONE June 1 The Unit started the reporting period shutdown due to a loss of condenser vacuum and a subsequent reactor scram.

June 2-24 The reactor went critical at 1125 hues on June 2.

At 0100 hours0.00116 days 0.0278 hours 1.653439e-4 weeks 3.805e-5 months on June 3, the Main Generator was synchronized to the grid. At 0645 hours0.00747 days 0.179 hours 0.00107 weeks 2.454225e-4 months on June 3, reactor power was raised to 15%. At 1500 hours0.0174 days 0.417 hours 0.00248 weeks 5.7075e-4 months on June 3 reactor power was raised to 33%. At 0100 hours0.00116 days 0.0278 hours 1.653439e-4 weeks 3.805e-5 months on June 4, reactor power was raised to 62%.

At 1500 hours0.0174 days 0.417 hours 0.00248 weeks 5.7075e-4 months l

on June 5, reactor power was raised to 80%. At 0020 hours2.314815e-4 days 0.00556 hours 3.306878e-5 weeks 7.61e-6 months on June 9, reactor power was lowered to 27% for the Unit Two " Loss of Offsite Power Test".

At 0700 hours0.0081 days 0.194 hours 0.00116 weeks 2.6635e-4 months on June 9, reactor power was raised to 76%. At 0000 hours0 days 0 hours 0 weeks 0 months on June 11, reactor power was raised to 90%.

At 1330 hours0.0154 days 0.369 hours 0.0022 weeks 5.06065e-4 months on June 11, reactor power was reduced to 48% due to a Reactor recirc pump trip. At 0000 hours0 days 0 hours 0 weeks 0 months on June 12, reactor power was raised to 76%. At 0700 hours0.0081 days 0.194 hours 0.00116 weeks 2.6635e-4 months on June 13, reactor power was raised to 90%. At 0000 hours0 days 0 hours 0 weeks 0 months on June 14, reactor power was raised to 97%. At 0700 hours0.0081 days 0.194 hours 0.00116 weeks 2.6635e-4 months on June 23, reactor power was reduced to 74%

for a rod sequence change. At 0820 hours0.00949 days 0.228 hours 0.00136 weeks 3.1201e-4 months on June 24, a reactor scram occurred as a result of a reactor feed pump flow control problem. The reactor was critical for 524 hours0.00606 days 0.146 hours 8.664021e-4 weeks 1.99382e-4 months and 55 minutes.

June 25-30 The reactor went critical at 0531 hours0.00615 days 0.148 hours 8.779762e-4 weeks 2.020455e-4 months on June 25.

At 1414 hours0.0164 days 0.393 hours 0.00234 weeks 5.38027e-4 months on June 25, the main generator was synchronized to the grid. At 1500 hours0.0174 days 0.417 hours 0.00248 weeks 5.7075e-4 months on June 25, reactor power was raised to 44%.

At 0700 hours0.0081 days 0.194 hours 0.00116 weeks 2.6635e-4 months on June 25, reactor power was raised to 63%. At 0000 hours0 days 0 hours 0 weeks 0 months on June 28, reactor power was raised to 90%. The reactor was critical for 138 hours0.0016 days 0.0383 hours 2.281746e-4 weeks 5.2509e-5 months and 29 minutes.

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PLANT OR PROCEDURE CHANGES, TESTS, RKPERIMEhTS AND SAFETY RELATED MAINTENANCE.

1.

Amendments to facility license or Technical Specification.

There were no amendments to the facility license or Technical Specification.

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Facility or procedure changes requiritg NRC approval.

There were no facility or procedure changes requiring NRC

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approval, i

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Tests and Erp9einents requiring NRC approval.

There were no tests or experiments requiring NRC approval.

4.

Correctivo maintenance of safety related equipment.

The following tsble (Table 1) presents a susunary of safety-related maintenance completed on Unit One during the reporting period. The headings indicated in this summary include: Work Request numbers, LER numbers, Component Name, cause of Malfunction, Results and Effects on Safe Operation, and Corrective Action.

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LTP-300-7 TABLE 1 Revision 4 F;br try 29, 1984 CORRECTIVE MAINTENANCE OF 6

SAFETY RELATED EQUIPMENT I

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WDRE REQUEST LER COMPONENT CAUSE OF MALFUNCTION RESULTS AND EFFECTS CORRECTIVE ACTION ON SAFE OPERATION I

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l L36832 Drywell temp-Faulty pinion and cluth None. Redundant channel Repaired drive mechanism rature recor-on drive mechanism.

operable.

der.

L36849 Fipe Tunnel HI Instrumentation delft out RCIC Isolation from DIV II Recalibrated A T Isol, of calibration.

Instrumentation.

L37213 HPCS water Leg Defective bearing Potential loss of line Replaced pump.

Pump pressure.

L37300 Drywell vent-Damper failed CLOSED.

No effect on safe operation. Wired damper OPEN.

ilation damper L37905 SBCT WBGM Faulty plug connector Causes intermit *.ent spiking. Repaired grounding causing high resistance Problem.

ground.

L38085 RCIC Steam Valve Packing Leak.

No effect on operation.

Repaired leak.

7 Supply Isol.

ALARA concern.

valve.

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LICENSEE EVENT REPORTS The following is a tabular summary of all licensee event reports for LaSalle Nuclear Power Station, Unit One, occurring during the reporting period, June 1 through June 30, 1984. 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 84-025-00 5/17/84 Lack of Positive Control on Entry into high radiation area.

84-026-00 5/17/84 Electrical Cable Penetrations Inoperable 84-027-00 5/20/84 Missed Off Cas Hydrogen Sample 84-028-00 5/13/84 RCIC Isolation Inboard System 84-029-00 5/31/84 Rx Scram from low vacuum trip of turbine generator.

84-030-00 5/31/84 Rx Water Cleanup high differential flow isolation.

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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 l

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LTP-300-7 R;visics 3 March 1, 1983 7

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OPERATING DATA REPORT DOCKET NO. 050-373 UNIT LaSalle One DATE July 10. 1984 COMPLETED BY Randy S. Dus TELEPHONE (815)357-6761 OPERATING STATUS 1.

REPORTING PERIOD: June 1984 GROSS HOURS IN REPORTING PERIOD: 720 2.

CURRENTLY AUTHORIZED POWER LEVEL (MWt):3323 MAK 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):

THIS MONTH YR TO DATE CUMULATIVE 5

NUMBER OF HOURS REACTOR WAS CRITICAL 663.4 3257.8 3257.8 6.

REACTOR RESERVE SHUTDOWN HOURS 56.6 1076.3 1076.3 7.

HOURS GENERATOR ON LINE 641.1 3097.7 3097.7 8.

UNIT RESERVE SHUTDOWN HOURS 0.0

_.1. 0 1.0 9.

GROSS THERMAL ENERGY GENERATED (MWH) 1806185 8574125 8574125 10.

GROSS ELEC. ENERGY GENERATED (MWH) 583251 2813123 2813123 11.

NET ELEC. ENERGY GENERATED (MWH) 557739 2677044 2677044 12.

REACTOR SERVICE FACTOR 92.1%

74.6%

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REACTOR AVAILABILITY FACTOR 100%

99.2%

14.

UNIT SERVICE FACTOR 89.0%

70.9%

15.

UNIT AVAILABILITY FACTOR 89.0%

70.9%

16.

UNIT CAPACITY FACTOR (USING MDC) 74.8%

59.2%

17.

UNIT CAPACITY FACTOR (USING DESIGN MWe) 71.9%

56.9%

18.

UNIT FORCEO OUTAGE RATE 11.0%

24.5% _

24.5%

19.

SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, ALo DURATION OF EACH)

On October 1, 1984 there will be a four week outage to inspect the drywell and perform scheduled surveillances.

20.

IF SHUT DOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP:Same 21.

UNITS IN TEST STATUS (PRIOR TO COMMERCIAL OPERATION):

FORECAST ACHIEVED INITIAL CRITICALITY 6/21/82 INITIAL ELECTRICITY 9/04/82 COMMERCIAL OPERATION 1/1/84 l

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LTP-300-7 R;visics 3 March 1, 1983 3

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2. AVERAGE DAILY UNIT POWER LEVEL DOCKET NO: 050-373 UNIT: LASALLE ONE DATE: JULY 10. 1984 COMPLETED BY: Randy S. Dus TELEPHONE: (815) 357-6761 MONTH: June 1984 DAY AVERAGE DAILY POWER LUVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1.

0 17.

1027 2.

0 18.

1044 3

197 19.

1046 4.

623 20.

1009

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783 21.

1013 6.

916 22.

1002 7.

918 23.

712 8.

799 24.

281 9.

650 25.

127 10.

846 26.

657 11.

729 27.

786 12.

864 28.

960 13.

1028 29, 1044 14.

1049 30.

1041 15.

1060 31.

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INSTRUCTIONS On this form list the average daily unit power level in MWe-Net for each day in the reporting month. Compute to the nearest whole megawatt.

These figures will be used to plot a graph for each reporting month.

Note that when maximum dependable capacity is used for the net electrical rating of the unit there may be occasions when the daily average power level exceeds the 100% line (or the restricted power level line.)

In such cases the average daily unit power output sheet should be footnoted to explain the apparent anomaly.

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LTP-300-7 R;visics 3 March 1, 1983 9 (Final) 3.

UNIT SH;'. DOWNS AND POWER REDUCTIONS DOCKET NO. 050-373 UNIT NAME LeSalle One DATE July 10 1984 REPORT MONTH JUNE 1984 COMPLETED BY Randy S.

Dus TELEPHONE (815)357-6761 METHOD OF TYPE SHUTTING DOWN F: FORCED DURATION THE REACTOR OR CORRECTIVE NO.

DATE S: SCHEDULED (HOURS)

REASON (1)

REDUCING POWER ACTIONS / COMMENTS 13 840531 F

49.0 A

4 Continuation of outage from previous month.

Blown loop seals resulting in loss of condenser vacuum.

14 840624 F

29.9 A

3 Rx scram on low water level resulting from the loss of a 8.x feed pump.

Problem stemmed from a malfunction in the Ex water lavel control logic. Work performed under work request L38185.

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LTP-300-7 R;vicits 3 March 1, 1983 9 (Final) 3.

UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 050-373 UNIT NAME LaSalle One DATE July 10. 1984 REPORT MONTH MAY 1984 COMPLETED BY Randy S. Dus TELEPHONE (815)357-6761 METHOD OF TYPE SHUTTING DOWN F: FORCED DURATION THE REACTOR OR CORRECTIVE NO.

DATE S: SCHEDULED (HOURS)

REASON (1)

REDUCING POWER ACTIONS /COBRENTS lla 840506 S

0.0 H

5 Power reduction 4' 1r a rod sequence change.

12e 840527 F

0.0 A

5 Power reduction due to a TDRFP trip.

132*

840531 F

7.7 A

3 Loss of condenser vacuum as a result of blown SJAE & S.P.E. Loop Seals resulted in Turbine trip & Reactor scram.

Procedure revisions in proEress to ensure loop seals remain filled.

a Add 2d July 10, previously omitted.

n* Was outage No. 9.

DOCUMENT 0044r/0005r

LTP-300-7 Revicion 3 Mar h 1, 1983 9 (Final) 1 3.

UNIT SHUTDOWNS AND POWER REDUCTIONS j

DOCKET NO. 050-373 UNIT NAME LaSalle One i

i DATE Ju17 10. 1984 REPORT MONTH APRIL 1984 COMPLETED BY Randy S. Dus j

TELEPHONE (815)357-6761 r

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METHOD OF TYPE SHUTTING DOtti F: FORCED DURATION THE REACTOR OR CORRECTIVE NO.

DATE 3: SCHEDULED (HOURS)

REASON REDUCING POWER ACTIONS /C005 TENTS On 840407 S

0.0 H

5 Power reduction for rod sequence change.

I 1G23 840414 F

34.3 G(1) 3 Procedures were changed to more clearly define l

the operational setpoints, j

(1) The operator changed the setpoint of the reactor water level control below the operational level allowed by existing j

procedures for paralleling an additional feedwater pump. This resulted in a low reactor water level scraa.

I a Added July 10, previously omitted.

I j ca Wa3 outage No. 8.

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LTP-300-7 Revicion 3 March 1, 1983 ATTACHMENT E 9 (Final)

UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 050-373 UNIT NAME LaSalee One DATE July 10. 1984 REPORT MONTH MARCH 1984 COMPLETED BY Randr S. Dus TELEPHONE (815)357-6761 METHOD OF TYPE SHUTTING DOWN F: FORCFD DURATION THE REACTOR OR CORRECTIVE NO.

DATE S: SOMEDULED (HOURS)

REASON (1)

REDUCING POWER ACTIONS / col 9 TENTS 6

840213 S

156.5 B

4 Condenser Boot Seal and extraction steam expansion joint repaired.

7 840308 F

286.7 F

1 Temporary drywell vent-ilation ductwork evaluated for loading on containment structrual members.

Analysis O.K.

No corrective action taken.

Remained shutdown to perform electrical cable butt splices inspection required by NRC.

88 840328 F

0.0 A

5 Power reduction as a result of feedwater heater string isolations.

AddOd July 10, 1984, previously omitted.

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UNIQUE REPORTINC REQIIIREMENTS 1

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Safety /Felief valve operations for Unit One.,

There were no rollef valve operations for Unit one for this enporting period.

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ECCS Systems Outag00 The following outages were taken on ECCS Systems during the reporting period.

OUTAGE NO.

EQUIPMENT PURPOSE OF OUTAGE 1-491-84 HPCS Water Leg Install new pump Pump 1-509-84 LPCS Water Leg General Maintenance Pump 1-518-84 RHR Water Les Pump Repair Valve Motor Min Flow Bypass Stop 1-519-84 RHR Water Les Pump Repair Valve Notor Min Flow Bypass Stop 1-537-84 RHR Water Les Pump Repair Valve Motor Min Flow Bypass Stop 1-538-84 RHR Water Les Pump Repair Valve Motor Min Flow Bypass Stop i

1-542-84 HPCS D/G Petter General Maintenance Diesel Air Compressor 1-545-84 LPCS Water Leg Pump Lubricate Coupling 1-558-84 RHR Service Water Replace Outboard Bearing Pump Casket 3.

Off-site Dose calculation Manual There were r.a changes to the off-site dose calculations 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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LASALLE Nt' CLEAR POWER STATION UNIT 2 1

MONTHLY PERFORMANCE REPORT j

JUNE 1984

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Cole 00NWEALTH EDISON COMPANY 4

NEC 00 CERT No. 050-374 LICENSE NO. NPF-18 4

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TABLE OF CONTENTS I.

INTRODUCTION II.

MONTHLY REPORT FOR UNIT TWO A.

Susunary of Operating Experience R.

PLANT OR PROCEDURE CHANCES, TESTS, EEPERIMENTS, AND SAFETY RELATED MAINTENANCE J

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 i,

3.

Off-site Dose Calculation Manual Changes 4.

Major Changes to Radioactive haste Treatment System i

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INTRODUCTION l

The LaSalle Nuclear Power Station is a Two Unit Facility Located in Marsellies Illinois. Each Unit is a Bolling Water Reactor with a designed electrical output of 1078 MWe net. The Station is owned by Commonwealth Edison Company. The Architect /Ingineer was Sargent & Lundy, i

and the primary construction contractor was commonwealth Edisen Company.

The condenser cooling method is a closed cycle coollas pond. Unit One is subject to License Number NPF-11, issued on April 17, 1982. The unit commenced commercial generation of power on January 1, 1984. Unit Two is subject to license number NPF-18, issued on December 16, 1983. The date of initial criticality was March 10, 1984.

This report was compiled by Randy S. Dus, telephone number (815)357-6761, extension 324.

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MONTHLY REPORT FOR UNIT TWO A.

SUMMARY

OF OPERATING EXPERIENCE FOR UNIT TWO June 1-6 The unit startad the reporting period at 25%

power with the main generator synchronized to the grid.

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At 0330 hours0.00382 days 0.0917 hours 5.456349e-4 weeks 1.25565e-4 months on June 1, reactor power was raised to I

45%. At 1307 hours0.0151 days 0.363 hours 0.00216 weeks 4.973135e-4 months on June 5 reactor power was reduced to 24% because of feedwater chemistry problems. At 0530 hours0.00613 days 0.147 hours 8.763227e-4 weeks 2.01665e-4 months on June 6, a reactor scram occurred while performing an instrument maintenance surveillance. The reactor was critical for 125 hours0.00145 days 0.0347 hours 2.066799e-4 weeks 4.75625e-5 months and 30 minutes.

June 6-10 At 2150 hours0.0249 days 0.597 hours 0.00355 weeks 8.18075e-4 months on June 6 the reactor was critical. At 0515 hours0.00596 days 0.143 hours 8.515212e-4 weeks 1.959575e-4 months on June 7 the main generator was synchronized to the grid. At 1400 hours0.0162 days 0.389 hours 0.00231 weeks 5.327e-4 months on June 7 reactor power was raised to 24%. At 0700 hours0.0081 days 0.194 hours 0.00116 weeks 2.6635e-4 months on June 8 reactor power was raised to 44%.

At 1700 hours0.0197 days 0.472 hours 0.00281 weeks 6.4685e-4 months on June 8, reactor power was reduced to 24% due to feedwater chemistry problems. At 2325 hours0.0269 days 0.646 hours 0.00384 weeks 8.846625e-4 months on June 8, a reactor scram occurred as a result of the " Loss of Offsite Power" test. The reactor was critical for 49 hours5.671296e-4 days 0.0136 hours 8.101852e-5 weeks 1.86445e-5 months and 35 minutes.

June 11-16 At 1100 hours0.0127 days 0.306 hours 0.00182 weeks 4.1855e-4 months on June 11, the reactor was critical. At 0400 hours0.00463 days 0.111 hours 6.613757e-4 weeks 1.522e-4 months on June 12, the main generator was synchronized to the grid. At 0700 hours0.0081 days 0.194 hours 0.00116 weeks 2.6635e-4 months on June 12, reactor power was raised to 39%. At 2300 hours0.0266 days 0.639 hours 0.0038 weeks 8.7515e-4 months on June 4

12, reactor power was raised to 50%. At 1500 hours0.0174 days 0.417 hours 0.00248 weeks 5.7075e-4 months on June 15, reactor power was reduced to 12% for maintenance work. At 2000 hours0.0231 days 0.556 hours 0.00331 weeks 7.61e-4 months on June 15, the main generator was removed from the grid. At 0200 hours0.00231 days 0.0556 hours 3.306878e-4 weeks 7.61e-5 months on June 16 the reactor was shutdown for maintenance work on the condensate booster system. The reactor was critical for 111 hours0.00128 days 0.0308 hours 1.835317e-4 weeks 4.22355e-5 months and 0 minutes.

June 17-30 At 0825 hours0.00955 days 0.229 hours 0.00136 weeks 3.139125e-4 months on June 17, the reactor was critical. At 1025 hours0.0119 days 0.285 hours 0.00169 weeks 3.900125e-4 months on June 18, the main generator was synchronized to the grid. At 1500 hours0.0174 days 0.417 hours 0.00248 weeks 5.7075e-4 months on June 18, reactor power was raised to 18%. At 1500 hours0.0174 days 0.417 hours 0.00248 weeks 5.7075e-4 months on June 19, reactor power was raised to 47%. At 1500 hours0.0174 days 0.417 hours 0.00248 weeks 5.7075e-4 months on June 22, reactor power was raised to 62%. At 0700 hours0.0081 days 0.194 hours 0.00116 weeks 2.6635e-4 months on June 24, reactor power was reduced to 54% for flux shaping. At 2300 hours0.0266 days 0.639 hours 0.0038 weeks 8.7515e-4 months on June 26, reactor power was raised to 70%. At 1900 hours0.022 days 0.528 hours 0.00314 weeks 7.2295e-4 months on June 28, reactor power was reduced to 45% for bypass v&lve testing. At 0000 1

hours on June 29, reactor power was reduced to 22% due to feedwater chemictry problems. At 2030 hours0.0235 days 0.564 hours 0.00336 weeks 7.72415e-4 months on June 30, reactor power was raised to 64%. The reactor was critical for 327 hours0.00378 days 0.0908 hours 5.406746e-4 weeks 1.244235e-4 months and 35 minutes.

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PLANT OR PROCEDURE CNANGES, TESTS, EXPERIMENTS AND SAFETY RELATED MAINTENANCE.

1.

Amendments to facility license or Technical Specifications.

There were no amendments to the facility license or Technical Specifications during the reporting period.

2.

Facility or procedure changes requiring NRC approval.

There were no facility or procedure changes 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.

1 The following table (Table 1) presents a susumary of I

safety-related maintenance completed on Unit one during the reporting period. The headings indicated in this suesnary include: Work Request numbers, LER Numbers, Component Name, cause of malfunction, results and effects on safe operation, and corrective action.

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LTP-300-7 TABLE 1 Revicion 4

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February 29, 1984 CORRECTIVE MAINTENANCE OF 6

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SAFETY RELATED EQUIPMENT l

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WORK REQUEST LER COMPONENT CAUSE OF MALFUNCTION RESULTS AND EFFECTS CORRECTIVE ACTION ON SAFE OPERATION I

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I L37604 Er Water Valve does not isolate Potential loss of Contain-Repaired solenoids Sample Valve as required / defective ment integrity Solenoid L37625 Div II Post Instrumentation Drift None. Redundant channel Recalibrated Loca 02 causing false oxygen still available.

Instrument.

I readings in drywell l

l L37026 APRM Flow Power supply was tripped Causes rod block Restored power to Comparators resulting in false Instrument.

reading.

i L37865 HPCS Disch Bellows Assembly v' thin Potentlal loss of containment Replaced failed l

Relief Valve valve body failed.

integrity.

bellows.

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L37937 D/G Immersion Defective Transformer Potential D/G Damage upon Replaced defective Heater heater cannot energize sudden start.

transformer.

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LICENSEE EVENT REPONTS The following is a tabular susunary of all 11consee event reports for LaSalle Nuclear Power station Unit Two, occurring during the reporting period, June 1 through June 30, 1984.

This information is provided pursuant to the reportable occurrence reporting requirements as set forth in 10CFR 50.73.

Licensee Event Resort Number M

Title of Octyrrence 84-018-00 5/17/84 U2 MPCs Pump Breaker Nelfunetton 84-019-00 5/9/84 Missed four hour hydrogen sampling of Off Cas system.

l 84-020-00 5/21/84 U2 Cenerator lockout and reactor scram.

44-021-00 5/15/54 Weactor Water Cleanup high l

differential flow isolation.

j 84-022-00 5/21/84 Loss of positive control on High Rad. Cate.

84-023-00 5/29/84 Reactor water cleanup 1solations.

84-024-00 5/31/84 Loss of RCIC Control and Instrument Power.

z 84-025-00 6/6/84 Rs Scram due to personnel error.

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DATA TA80LA110Ils i

The followtas data tabulations are presented in this report I

1.

Operating Data Report t

2.

Average Dally Unit Power Level r

3.

Unit shutdowns and Power Reductions i

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DOCUIIRIff ID 0036r i

LTP-300-7 Revision 3 March 1, 1983 7

1. OPERAftNC DATA REPORT DOCERT NO. 050-374 UNIT LaSalle Two DATE July 10. 1984 COMPLETED BY Randr 8. Due TELMPHONE (815)357-6761 OPERATING STATUS 1.

REPORTIkG PERIOD: June 1984 CROSS HOURS IN REPORTING PERIOD 720 2.

CURRENTLY AUTHORIZED POWER LEVEL (NWt)t}}, NAX DEFEND CAPACITY (NWe-Net) 1036 DESIGN ELECTRICAL RATINC (NWe-Net) 1078 3. POWER LEVEL TO WHICH RESTRICTED (IF ANY) (NWe-Net) N/A 4. REASONS FOR RESTRICTION (IF ANY) THIS NONTH YM TO DATE CUNULATIVE 5 NUMBER OF HOURS REACTOR WAS CRITICAL 113.7 1910.5 1910.5 6. REACTOR RESERVE SHUTDOWN HOURS 106.3 792.3 192.3 7. HOURS CENERATOR ON LINE }57.3_ 1138.4 1138.4 8. UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 0.0 9. CROSS THERNAL ENERCY CENERATED (NWH) 892493-1488958 lits 9)(_ 10. CROSS ELEC. ENERCY CENERATED (NWM) 249632 }]ill), 2))516 ]

11. NET ELEC. ENERCY CENERATED (MWH) 735000

}i8093__ 2M093 12. REACTOR SERVICE FACTOR N/A N/A N/A 13. REACTOR AVAILA51LITY FACTOR N/A N/A N/A

14. UNIT SERV 1CE FACTOR N/A N/A N/A

15. UNIT AVAILABILITY FACTOR N/A N/A N/_A 16.

UNIT CAPACITY FACTOR (USING NDC) F/A N/A N/A

17. UNIT CAPACITY FACTOR (USINC DESIGN NWe)

N/A N/A N/A 18. UNIT FORCED OUTACE RATE N/J MfA N/A

19. SHUTDOWNS SCHEDULED OVER NEXT 6 NONTHS (TYPE. DATE. AND DURATION OF EACH) 20.

IF SHUT DOWN AT END OF RSPORT PERIOD, ESTINATED DATE OF STARTUP N/A 21. UNITS IN TEST STATUS (PRIOR TO COMMERCIAL OPERATION): FORECAST ACHIEVED INITIAL CRITICALITY 3/10/84__ INITIAL ELECTRICITY 4/20/84 COMMERCIAL OPERATION Aust_84 DOCUMENT ID 0036r

LTP-300-7 Revision 3 March 1, 1983 6

2. AVERACE DAILY UNIT POWER LEVEL DOCKET NO: 050-374 UNIT LASALW_IMO DATKt July _10. 1984 COMPLETED EY: pandy S. Dvs TELEPHONE: 1915) 357-6761 NONTH: June 1984 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWNE LEVEL (NWe-Net)

(NWe-Net) 1. 401 17. 0 2. 427 18, 60 3 419 19. 268 4. 413 20. 41S 5. 268

21. _

448 6. 41 22. 510 7. 164 23. 535 8. 345 24. 522 9. 0 25. $13 i 10. 0 26. 610 11. 0 27. 104 12. 273 28. 650 13. 436 29. 180 i 14. 463 30. 394 15. 334 31, 16. 0 INSTRUCTIONS on this form list the average daily unit power level in NWe-Net for each day in the reporting month. Compute to the nearest whole megawatt. These figures will be used to plot a graph for each reporting month. Note that when mastnum dependable espacity is used for the not electrical rating of the unit there may be occasions when the daily average power level escoede the 100% line (or the resteleted power level line.) In such cases the average dally unit power output sheet should be footnoted to esplain the apparent anomaly. DOCUMENT 10 0036r

l LTP-300-7 Bewicion 3 march 1. 1983 9 (Flaal) ATTAcumur E 3. IMilT SMUTD0 TBS AND PCMER REDUCTIONS DOCKET Mo. 050-374 INIT Mm LaSalle 7tse DATE July 10. 1904 i REPORT MONTM J W 1984 COWLETkD BY Raadr 3. Des TELEPuoWE 1915)357-6761 ^ ) i 1 IET1800 OF TYPE SBUTTINC D0tM F: POSCID DURATION THE REACTOR OR C mmerTIVE 30. DATE 3: SCMEDULED (MOURS) REASON (I) REDUCIBC POWER ACTIONE/crummmTS l l 13 340605 F 0.0 a 5 Poeser Beduction as a l resmit of Rs Wai.er i l Nigh Conductivity [ 17 840606 F 23.8 C 3 Personnel error askile workinE os as esoter level instrumentation. System upset resulted la i l turbine trip & Rs scram i (me: LER mo. 84-025-00) l DOCWWET 0044r/0005r . _ _ _,, _. _ _ -... _ _ ~ -. _. _ _ _ _. _. _. _. - - _ -. _ _ _.. _. _

LTF-300-7 Bowieles 3 March 1. 1983 9 (Final) ATT N E 3. UNIT SarTDetes AM POWE R. EDUCTIONS DOCERT 50. 050-374 UNIT E m LaSalle Fue DATE July 10. 1984 REPOET MONTE JUNE 1984 C N BY Seeds S. Des T N (815)357-4761 WTN00 0F TTFE SMFTTIBC D0hm F: PoeCID DURATION T M EEACTOR OR COGESCT!YE E0. DATE 3: SCEEDULID (BOURS) BEA505 (1) BEBUCIBC PO W E ACTIONS /t m mmTS IS S4060s 3 76.6 3 3 Unit Shutdessa as a result of the " Loss of Offsite Posser" Test. (STP-31-2) 10 840615 3 62.4 3 1 Unit shutdoun to pectore malatemance merk 20 840629 F 0.0 E 5 Posser toduetios as a result of Rs asster h!Sh conductivity. j anemmm; C044r/0005r t

+ E. UNIQUE REPORTING REQUIREMENTS 1. Safety / Relief Valve Operations for Unit Two. DATE VALVES NO & TYPE PLANT DESCRIPTION ACTUATED ACTUATIONS CONDITION, OF EVENT 6/8/84 2B21-F013S 27 AUTO 1140 psig Rx Scram for STP-31-2 6/13/84 2B21-F013A 1 MANUAL 960 psig STP-26-2 6/13/84 2B21-F013B 1 MANUAL 960 psig STP-26-2 6/13/84 2B21-F013F 1 MANUAL 960 psig STP-26-2 6/13/84 2B21-F013G 1 MANUAL 960 psig STP-26-2 6/13/84 2B21-F013H 1 MANUAL 960 psig STP-26-2 6/13/84 2B21-F013J 1 MANUAL 960 psig STP-26-2 6/13/84 2B21-F013K 1 MANUAL 960 psig STP-26-2 6/13/84 2821-F013L 1 MANUAL 960 psig STP-26-2 6/13/84 2B21-F013M 1 MANUAL 960 psig STP-26-2 6/15/84 2B21-F013N 1 MANUAL 960 psig STP-26-2 6/15/84 2BL'l-F013P 1 MANUAL 960 psig STP-26-2 6/15/84 2821-F013C 1 MANUAL 960 psig STP-26-2 6/15/84 2B21-F013D 1 MANUAL 960 psig STP-26-2 6/15/84 2B21-F013E 1 MANUAL 960 psig STP-26-2 6/15/84 2B21-F013R 1 MANUAL 960 psig STP-26-2 6/15/84 2B21-F013S 1 MANUAL 960 psig STP-26-2 6/15/84 2B21-F013U 1 MAFUAL 960 psig STP-26-2 6/15/84 2B21-F013V 1 MANUAL 960 psig STP-26-2 DOCUMENT ID 0036r

i 2. ECCS Systems Outcsse The following outages were taken on ECCS Systems during I_ the reporting period. l 6 OUTAGE NO. EQUIPMENT PURPOSE OF OUTAGE 2-729-84 2A RHR Pump General Maintenance 2-731-84 RHR HI Shell Side Adjust Limit Switch Vent Downstream Stop 2-762-84 HPCS Discharse Repair Ruptured Bellows Line Relief Valve 2-777-84 RHR Water Leg General Maintenance Pump Check Valve 2-789-84 2C RHR Pump Sample Oil 2-799-84 LPCS Pump Lubrication 2-800-84 RHR Pump Lubrication 3. Off-Site Dose Calculation Manual There were no changes to the off-site dose calculations manual during this reporting perled. 4. Radioactive Waste Treatment Systems. There were no changes to the Radioactive Waste Treatment System during this reporting period, a i l DOCUMENT ID 0036r p-9-,-y ,v,w,w. ,_yyw,,,-,, -wy .---9 m y g qs. w gw -,-g ,_-m,w-=g.yy,-,,-7%.w-w,,,,-,y,m,.%,,,e --.m-wy.ey-m-g-y.

( -/,, ,3 - Commonwealth Edison LaSall] County Nuct nr Station Rural Route #1, Box 220 Marseilles, Illir.ois 61341 Telephone 815/357-6761 l July 6, 1984 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 covering June 1 through June 30, 1984. Very truly yours, ,// G J. Diederich Superintendent LaSalle County Station CJD/RSD/cch =. 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 Ron A. Johnson, PIP Coordinator SNED W. R. Jackson, GE Resident i sgjt? ,y Document 0043r/0005r}}

ML20093J565

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