Text

Monthly Operating Repts for Aug 1984
	ML20093G485
Person / Time
Site:	LaSalle
Issue date:	08/31/1984
From:	Diederich G, Dus R; COMMONWEALTH EDISON CO.
To:	; NRC OFFICE OF ADMINISTRATION (ADM), NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
	NUDOCS 8410150510
	Download: ML20093G485 (30)
	v • d • e

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i LASALLE NUCLEAR POWER STATION UNIT 1 MONTHLY PERFORMANCE REPORT AUGUST 1984 CopMONNBALTH EDISON COMPANY NRC DOCKET NO. 05r 373 LICENSE NO. NPF-11 I

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3 Document 0043r/0005r

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TABLE OF CONTENTS I.

INTRODUCTION II.

MONTHLY REPORT FOR UNIT ONE A.

Sumunary of Operating Experience B.

PLANT OR PROCEDURE CHANGbS, 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 TABUIATIONS i

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 Document 0043r/0005r

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.I.

INTRODUCTION The LaSalle Nuclear Power Station is e Two Unit Facility Located in Marseilles, Illinois. Each Unit is a Boiling 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, 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-ll, issued on April 17, 1982. The date of initial criticality was June 21, 1982. 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.

l Document 0043r/0005r

II.

MONTHLY REPORT FOR UNIT ONE A.

SUlemRY OF OPERATING EXPERIENCE FOR UNIT ONE AUGUST 1-31 The Unit started the reporting period at 92% power. At 2300 hours0.0266 days 0.639 hours 0.0038 weeks 8.7515e-4 months on August 3, power was reduced to 80% power

'for a high pressure heater out of service. At 0700 hours0.0081 days 0.194 hours 0.00116 weeks 2.6635e-4 months on August 6, reactor power was increased to 91%.

At 1510 hours0.0175 days 0.419 hours 0.0025 weeks 5.74555e-4 months on August 8, power was reduced to 70% to reduce conductivity and chloride levels in the reactor water. At 1500 hours0.0174 days 0.417 hours 0.00248 weeks 5.7075e-4 months on August 13, power was increased to 94%. At 0842 hours0.00975 days 0.234 hours 0.00139 weeks 3.20381e-4 months on August 25, power was decreased to 85% due to a reactor recire pump trip during the performance of LIS-NB-09.

At 0800 on August 27, power was increased to 98%. At 0000 hours0 days 0 hours 0 weeks 0 months on August 31, power was reduced to 81% per the load dispatcher. The reactor was critical for the entire month of August totalling 744 hours0.00861 days 0.207 hours 0.00123 weeks 2.83092e-4 months .

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PLANT OR PROCEDURE CHANGES, TE3TS, EXPERIMENTS AND SAFETY RELATED MAINTENANCE.

1.

Amendments to facility license or TechnJcal Specification.

Amendment No. 18. - This amendment revised the Unit 1 Technical Specification to reflect the changes that were previously approved for the Unit 2 Technical Specifications. This aumendment affects the entire Unit 1 Technical Specification.

2.

Facility or procedure changes requiring NRC approval.

There were no facility or procedure changes requiring NRC approval.

3.

Tests and Experiments requiring NRC approval.

There were no tests or experiments requiring NRC approval.

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 numbers, LER numbers Component Name, cause of Malfunction, Results and Effects on Safe Operation, and Corrective Action.

Document 0043r/0005r

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TABLE 1 L7P-300-7 Eevicion 4 CORRECfIVE MAINTENANCd OF F;bruary 29, 1984' y.

SAFETY RELATED EQUIPMENT 6

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I WORK REQUEST LER' COMONENT CAUSE OF MALFUNCTION RESULTS AND EFFECTS CORRECTIVE ACTION.

ON SAFE OPERATION i

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I L24803 DIV I SWGR Damper actuator Leaking Damper Still functional Repaired actuator re-Room Vent oil and will not position manually, turned to service.

]

damper, damper.

L38733 RHR Heat Ex-Stake the setscrew in the Preventative Maintenance.

Reinstalled setscrew

{

changer by-Anti-rotation stem to with locktite.

pass viv.

prevent loosening t

L39207 Suppression Chart drive broke paper Recorder still prints Replaced high speed pool temp-does not advance correctly.

clutch.

erature re-I corder.

l L39374 ADS Continuity Continuity lights not lit. All circuits verified to be Tightened loose j

monitor Potential loss to ads operable.

socket corutection.

1 circuit.

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L39549 ESF Annun-Spurious alarm occurrance Computer verified spurious Replaced digital j

ciator panel. Which could not be reset. alarm.

logic card.

L39553 D/G Cooling Pressure gauge reading Pump pressure gauge verified Recalibrated i

Water pump low, suspect inadequate to be out of calibration.

pressure gauge.

]

cooling to diesel.

i L39619 RHR Supp-Valve trips on thermals Fully operational in open Cleaned torque ression pool when going closed, direction, switch contacts.

{

spray viv.

L39701 Reactor scram Switch does not return Still able to scram reset.

Cam on actuator was reset switch fully to the mid position, sticking, replaced j

actuator.

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l DOCUMENT 0044r/0005r

TABLE 1 LTP-300-7 Revision 4

^

CORRECTIVE MAINTENANCE OF February 29, 1984

~ SAFETY RELATED EQUIPMENT 6

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I If0RK REQUEST LER COff0NENT CAUSE OF MALFUNCTION RESULTS AND EFFECTS CORRECTIVE ACTION ON SAFE OPERATION I

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L39976 RHR service

. Bearing assembly Redundant service water

' Removed bearing water pump assembled wrong.

pumps operable.

housing and re-assembled.

L40341 Rod block "B" Channel not properly None. Redundant channels Replaced defective monitor decoding the LPRM string operable.

multiplexer card.

for the rod selected.

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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, occurring during the reporting period, August I through August 31, 1984. This information is provided pursuant to the reportable occurrence reporting requirements as set forth in 10CFR 50.~l3.

Licensee Event Report Number Date Title of Occurrence 84-045-00 Reactor Water Cleanup High Differential Flow Isolation.

84-046-00 Reactor Water Cleanup High Differential Flow Isolation.

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'l Doctanent 0043r/0005r

1 D.

DATA TABULATIOtfS The following data tabulations are presented in this report:

1.

Operating Data Report 2.

Average Daily Unit Power Level 3.

Unit Shutdree-and Power Reductions E

. Document 0043r/0005r

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1.

OPERATING DATA REPORT DOCKET NO. 050-373 UNIT LaSa11e One DATE September 6, 1984 COMPLETED BY Randv S. Dus TELEPHONE (815)357-6761 OPERATING STATUS 1.

REPORTING PERIOD: August 1984 GROSS HOURS IN REPORTING PERIOD: 744 2.

CURRENTLY AUTHORIZED POWER LEVEL (MWt):3323 MAX DEPEND CAPACITY (MWe-Net): 1036 DESIGN ELECTRICAL RATING (MWe-Net):1078 3.

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

N/A 4.

REASONS FOR RESTRICTION (IF ANY):

THIS MONTH YR TO DATE CUMULATIVE 5

NUMBER OF llOURS REACTOR WAS CRITICAL 744.0 4746 4746 6.

REACTOR RESERVE SHUTDOWN HOURS 0.0 1076 1076 7.

HOURS GENERATOR ON LINE 744.0 4586 4586 8.

UNIT RESERVE SHUTDOWN HOURS 0.0 1.0 1.0 9.

GROSS THERMPL ENERGY GENERATED (MWH) 2223602 13126524 13126524 10.

GROSS ELEC. ENERGY GENERATED (MWH) 713445 4283229 4283229 11.

NET ELEC. ENERGY GENERATED (MWH) 677248 4080111 4080111 12.

REACTOR SERVICE FACTOR 100%

81.0%

81%

13.

REACTOR AVAILABILITY FACTOR 100%

99.4%

14.

UNIT SERVICE FACTOR 100%

78.3%

15.

UNIT AVAILABILITY FACTOR 100%

78.3%

16.

UNIT CAPACITY FACTOR (USING MDC) 87.9%

67.3%

17.

UNIT CAPACITY FACTOR (USING DESIGN MWe) 84.4%

64.6%

18.

UNIT FORCED OUTAGE RATE 0.0%

18.0%

19.

SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE AND DURATION OF BACH)

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:N/A 21.

UNITS IN TEST STATUS (PREOR TO COfGEERCIAL OPERATION):

PORECAST ACHIEVED INITIAL CRITICALITY 6/21/82 INITIAL ELECTRICITY 9/04/82 COI99ERCIAL OPERATION 1/1/84 Document 0043r/0005r J

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

(MWe-Net) 1.

920 17.

955 2.

939 18.

943 3

%6 19.

938 4.

733 20.

994 5.

770 21.

1023 6.

916 22.

1026 7.

947 23.

1033 8.

802 24.

1031 9.

778 25.

899 10.

639 26.

921 11.

688 27.

1008 12.

825 28.

1007 13.

932 29.

970 14.

944 30.

956 15.

914 31.

794 16.

%9 INSTRUCTIONS On this form list the average daily unit power level in MWe-Met 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.

Document 0043r/0005r

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UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO, 050-374 UNIT NAME LaSalle One DATE Septernber 1984 REPORT MONTH AUGUST 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 15 84/08'04 S

0 H

5 Reduced power to repair steam leaks on high pressure heater i

DOCUMENT 0044r/0005r

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UNIQUE REPORTING RBQUIREMENTS l

1.

Safety / Relief. valve operations for Unit One.

VALVES NO & TYPE PLANT DESCRIPTION DATE ACTUATED ACTUATION CONDITION OF EVENT l

8/28/84 IB21-F013S. 1 Auto 981 psig Grounded on "C" Solenoid.

8/29/84 IB21-F013S 4 Auto 981 psig Grounded on "C" Solenoid.

t Document 0043r/0005r

2.

ECCS Cystems Outtge3 4

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

OUTAGE NO.

BOUIPPENT PURPOSE OF OUTAGE 1-63~1-84

~HPCS Diesel / Gen and Change oil in pump Cooling Water Pump 1-654-84 1C RHR Service Water Inspect pump bearings.

Pump.

1-629-84 1A Diesel / Gen Lubrication System Inspection.

3.

Off-site Dose Calculation Manual There were no 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 NUCLEAR POWER STATION UNIT 2 MONTHLY PERFORMANCE REPORT AUGUST 1984 CON 90NWEALTH EDISON COMPANY NRC DOCKET NO. 050-374 LICENSE NO. NPF-18 DOCUMENT ID 0036r/0005r

TABLE OF CONTENTS v

I.

INTRODUCTION II.

MONTHLY REPORT FOR UNIT TWO A.

Susumery 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 REQUIREMNTS l.

Safety / Relief valve Operations 2.

BCCS System Outages 3.

Off-Site Dose Calculation Manual Changes 4.

Major Changes to Radioactive Weste Treatment System

)

i t

DOCUMNT ID 0036r/0005r

t I.

INTRODUCTION The LaSalle Nuclear Power Station is a Two Unit Facility located in Marseilles Illinois. Each Unit is a Boiling Water Reactor with a designed electrical output of 1078 MWe net. The Station is owned by cr==nrnsealth Edison Company. The Architect / Engineer was Sargent E Lundy, and the primary construction contractor was en==nansealth Edison Company.

The condenser cooling method is a closed cycle cooling pond. Unit One is subject to License Number NPF-ll, 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.

DOCUMENT ID 0036t/0005r

II.

MONTHLY LEPORT FOR UNIT TWO A.

SINSEUtY OF OPERATING EXPERIENCE FOR UNIT WO August 1-5 The Unit started the reporting period shutdown for steam leak repairs to the moisture seperator reheater. At 1200 hours0.0139 days 0.333 hours 0.00198 weeks 4.566e-4 months on August 1, the reactor went critical. -At 0550 hours0.00637 days 0.153 hours 9.093915e-4 weeks 2.09275e-4 months on August 2, the main generator was synchronized to the grid. At 0700 hours0.0081 days 0.194 hours 0.00116 weeks 2.6635e-4 months on August 2 reactor power was raised to 18%. At 1400 hours0.0162 days 0.389 hours 0.00231 weeks 5.327e-4 months on August 2, reactor power was raised to 4M.

At 0230 hours0.00266 days 0.0639 hours 3.80291e-4 weeks 8.7515e-5 months on August 3 reactor power was decreased to 25% to repair steam leaks on the second stage reheater drain tank. At 2300 hours0.0266 days 0.639 hours 0.0038 weeks 8.7515e-4 months on August 3, reactor power was raised to 60%. At 1400 hours0.0162 days 0.389 hours 0.00231 weeks 5.327e-4 months on August 4, reactor power was raised to 7M. At 1900 hours0.022 days 0.528 hours 0.00314 weeks 7.2295e-4 months on August 5 the reactor scrammed due to an unauthorized person lifting leads at the turbine control panel. The reactor was critical for 193 hours0.00223 days 0.0536 hours 3.191138e-4 weeks 7.34365e-5 months .

Aueust 6-14 The reactor went critical at 0830 hours0.00961 days 0.231 hours 0.00137 weeks 3.15815e-4 months on August 6.

At 1605 hours0.0186 days 0.446 hours 0.00265 weeks 6.107025e-4 months on August 6 the main generator was synchronized to the grid.,At 2200 hours0.0255 days 0.611 hours 0.00364 weeks 8.371e-4 months on August 6, reactor power was raised to 38%. At 0700 hours0.0081 days 0.194 hours 0.00116 weeks 2.6635e-4 months on August 7, reactor power was raised to 66%. At 0700 hours0.0081 days 0.194 hours 0.00116 weeks 2.6635e-4 months on August 9, reactor power was raised to 90%. At 0750 hours0.00868 days 0.208 hours 0.00124 weeks 2.85375e-4 months on August 10, the reactor scrassed on a closure of a turbine control valve. The reactor was critical for 95 hours0.0011 days 0.0264 hours 1.570767e-4 weeks 3.61475e-5 months and 20 minutes.

Auaust 15-28 At 1200 hours0.0139 days 0.333 hours 0.00198 weeks 4.566e-4 months on August 15, the reactor went critical. AT 2325 hours0.0269 days 0.646 hours 0.00384 weeks 8.846625e-4 months on August 15, the main generator was synchronized to the grid. At 0600 hours0.00694 days 0.167 hours 9.920635e-4 weeks 2.283e-4 months on August 16, reactor power was raised to 2M, at 1550 hours0.0179 days 0.431 hours 0.00256 weeks 5.89775e-4 months on August 16, reactor power was raised to 40%. At 0854 hours0.00988 days 0.237 hours 0.00141 weeks 3.24947e-4 months on August 17, the reactor scrammed due to a 4

main generator exciter failure. The reactor was critical for 44 hours5.092593e-4 days 0.0122 hours 7.275132e-5 weeks 1.6742e-5 months and 54 minutes.

Aueust 29-31 At 2240 hours0.0259 days 0.622 hours 0.0037 weeks 8.5232e-4 months on August 29, the reactor went critical. At 1723 hours0.0199 days 0.479 hours 0.00285 weeks 6.556015e-4 months on August 30, the min generator was synchronized to the grid. At 0700 hours0.0081 days 0.194 hours 0.00116 weeks 2.6635e-4 months on August 31, reactor power was raised to SM. The reactor was critical for 49 hours5.671296e-4 days 0.0136 hours 8.101852e-5 weeks 1.86445e-5 months and 20 minutes.

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I DOCUMENT ID 0036r/0005r

B.

PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS AND SAFETY RRLATED MAINTENANCE.

1.

Amendments to facility license or Technical Specifications.

.There were no facility license or Technical Specification Amendments 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.

l 4.

Corrective Maintenance of Safety Related Equipment.

The following table (Table 1) presents a sumunary of safety-related maintenance completed on Unit one during the reporting period. The headings indicated in this sumanary include: Work Request numbers, LER Numbers, Component Name, cause of malfunction, results and effects on safe operation, and corrective action.

DOCUMENT ID 0036r/000$r

TABLE 1 LTP-300 *1 Revision 4 CORRECTIVE MAINTENANCE OF February.29, 1984 SAFETY RdLATED EQUIPMENT 6

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I if0RK REQUEST LER-00t@ONENT CAUSE OF MALFUNCTICN RESULTS AND EFFECTS CORRECTIVE ACTION ON SAFE OPERATION I

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L39119 RPV Differ-Indicator failed downscale Redundant indication avail-Replaced leaking 3 ential press-able and operable.

way manifold.

ure indicator.

L38622 Drywell Elec-Pressure less than 5#'s.

Containment integrity still Recharged penetra-trical pen-Suspect leak in penetra-maintained.

tion. 1;o Leaks found.

etration.

tion.

L38734 RHR heat ex-Stake the setscrew in the Preventative Maintenance.

Reinstalled set j

changer by-Anti-Rotation stem to pre-screw with locktite.

pass vlv.

vent loosening.

L38919 Post Loca Recorder does not drive Recorder still functional Replaced chart drive gross gamma in slow speed.

in fast speed.

circuit board and recorder motor assembly.

s -

L39019 LPCI Low Low Header Pressure alarm Verified adequate pressure Recalibrated header pres-always up.

in system.

pressure switch, sure alarm.

L39714 Suppression Recorder occassionaly Recorder still prints but Replaced pinion gear, pool temp-stops driving.

does not drive. Redundant motor & clutch.

erature re-division still operable.

corder.

l L40159 RCIC Cond-Run Light energized but Commutator very dirty and Cleaned commutator enser vacuum pump does not run.

slightly burnt.

and rescated brushes.

j pump.

J l

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DOCUMENT 0044r/0005r i

TABLE 1 LTP-300 ~1 ReviOion 4 CORRBCTIVE MAINTFMANCE OF February 29, 1984 SAFETY RELATED EA'IPMENT 6

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I WORK RBQUEST LER COff0NENT CAUSE OF MALFUNCTION RESULTS AND EFrak,TS 00RRECTIVE ACTION ON SAFE OPERATION I

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L40218 Main Steam Valve will not seal in Valve still operable but not Cleaned torque line drain closed.

able to seal in, switch contacts.

valve Verified seal in feature operable.

L40255 Wide range Defective amplifier Fails downscale with Replaced amplifier suppression circuit board.

adequate level present.

circuit board.

pool level indicator.

L403"l8 LPCS Pull Valve Does not cycle from Still functional manually.

Cleaned defective flow test control room.

torque switch valve.

contacts.

L40447 RHR Injection Not able to cycle. Valve Valva still functional with Installed new air testable check due to leaking air system flow and pressure.

cylinder.

Viv.

operator.

L40340 RHR Full Flow Disc. Misalignment Redundant RHR Loop still Disc skirt installed Test Viv.

to body guide operational DOCUMENT 0044r/0005r

C.

LICENSEE EVENT REPORTS The following is a tabular sumanary of all licensee event reports for LaSalle Nuclear Power Station, Unit two, occurring during the reporting period. August I through August 31, 1984.

This information is provided pursuant to the reportable occurrence reporting requirements as set forth in 10CFR 50.*l3.

Licensee Event Report Number Date Title of Occurrence 84-036-00 Reactor Water Cleanup High Differential Flow Isolation.

84-037-00 Reactor Water Cleanup High Differential Flow Isolation.

84-038-00 Unsecured High Radiation Area Door.

84-039-00 Reactor Low Pressure RCIC Isolation.

84-040-00 Drywell crane circuits not on Tech Spec Surveillance.

84-041-00 Reactor Water Cleanup High Differential Flow Isolation.

84-042-00 Unit 2 Manual Scram Shutdown 64-043-00 Violation of Tech Spec 3.6.1.8 Action Statement (VQ in Drywell Ventilation) 84-044-00 Reactor Water Cleanup High Differential Flow Isolation.

84-045-00 Low CRD Header Pressure Scram 84-046-00 Reactor Water Cleanup Isolation-Leak Detection High Ambient Temperature.

l 84-04~1-00 Scram due to vendo error 84-048-00 Reactor Scram Initiation-Reactor Instrumentation line valved in.

84-049-00 Unsecured high Radiation Area j

Door.

DOCUMENT ID 0036r/0005r m-e-

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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 c

4 e

i DOCUMENT ID 0036r/0005r a.---

l

.). OPERATING DATA REPORT DOCKET NO. 050-374 i

UNIT LaSalle Two DATE September 1984 00frLETED BY Eggdy S. Dus TELEPHONE (815)357-6761 l

OPERATING STATUS 1.

REPORTIIIG PERIOD: August 1984 GROSS HOURS IN REPORTING PERIOD: 744 2.

CURRENTLY AUTHORIBED PONER LEVEL (MWt):))2], MAX DEPEND CAPACITY (IRde-Met): 1036 DESIGN ELECTRICAL RATING (MWe-Net):1078 3.

PO NR LEVEL TO W ICH RESTRICTED (IF ANY) (MWe-Net):

N/A 4.

REASONS FOR RESTRICTION (IF ANY):

THIS MONTH YR TO DATE CUMULATIVE 5

NUIBER OF HOURS REACTOR WS CRITICAL 292.6 2811 2811

6.

REACTOR RESEltVE SHUTDOW HOURS 451.4 1380 1380 7.

HOURS GENERATOR ON LINE 237.0 1942 1942 1

8.

UNIT RESERVE SHUTDOW HOURS 0.0 0.0 0.0 9.

GROSS THEINEL ENERGY GENERATED (MWH) 475310 3289078 3289078 10.

GROSS ELEC. ENEltGY GENERATED (MWH) 137874 915324 915324

11. NET ELEC. ENERGY GENERATED (MWH) 130211 860720 860720 12.

REACTOR SERVICE FACTOIt N/A N/A N/A 13.

REACTOR AVAIIABILITY FACTOIt N/A N/A N/A 14.

UNIT SERVICE FACTOIt N/A N/A N/A 15.

UNIT AVAILABILITY FACTodt N/A N/A N/A 16.

UNIT CAPACITY FACT 00t (USING IWC)

N/A N/A N/A

17. UNIT CAPACITY FACTOR (USING DESIGN PRde)

N/A N/A N/A 18.

UNIT F00tchtD OUTAGE RATE N/A N/A N/A 19.

SHUTDONNS SCHEDULED OVElt NEAT 6 MONTHS (TYPE, DATE, AND DURATION OF RACH) 20.

IF SHUT DOW AT END OF REPORT PRItIOD, ESTIMATED DATE OF STAltTUP 21.

UNITS IN TEST STATUS (PRICIt TO C0fEWICIAL OPEltATIOli):

PCItECAST ACHIEVED INITIAL CRITICALITY 3/10/84 INITIAL isL9CTRICITY 4/20/84-COIMEltCIAL OPIIItATION Aug. 84 l

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L DOCUMENT ID 0036r/0005r i

2. AVERAGE DAILY UNIT POWER LEVEL DOCKET NO: 050-374 UNIT: LASALLE TWO DATE: September 1984 COMPLETED BY: Randy S. Dus TELEPHONE: (815) 357-6761 MONTH: August 1984 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1.

0 17.

152 2.

181 18.

0 3

287 19.

0 4.

684 20.

0 5.

615 21, 0

6.

98 22.

0 7.

605 23.

0 8.

737 24.

0 9.

934 25.

0 10.

329 26.

0 11.

0 27.

0 12.

0 28.

0 13.

0 29.

0 14.

0 30.

36 15.

1 31.

514 16, 253 INSTRUCTIONS On this form list the average daily unit power level in MWe-Net for each day i

in ths 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 cccasions 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.

DOCUMENT ID 0036r/0005r

. -, ~,. -,

7;_

ATTACPMENT E 3.

UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 050-374 UNIT NAfEt _LaSalle Two DATE Septeseber 1984 REPORT MONTH AUGUST 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 /COfftENTS 25 840tGB F

13.5 G

3 Unauthorized person incorrect 1y connected DVM resulting in a turbine trip.

26 840810 F

124.1 B

3 Closure of 81 turbine control valve resulted in high reactor i

pressure.

(

27 240817 F

301.8 A

3 Loss of excitation to U-2 Generator caused a turbine trip.

a 2

DOCUMENT 0044r/0005r

E.

UNIQUE REPORTING REQUIREMENTS 1.

Safety / Relief Valve Operations for Unit Two.

DA_TE VALVES NO & TYPE PLANT DESCRIPTION ACTUATED ACTUATIONS CONDITION OF EVENT i

8/5/84 2B21-F013D 1 Auto 981 psig Rx Scram 8/5/84

-2B21-F013S 1 Auto 981 psig Rx Scram.

8/5/84 2B21-F013V 1 Auto 981 psig Rx Scram.

8/15/84 2821-F013A 1 Auto 981 psig SRV Cycling for MOD 1-2-84-120 8/15/84 2B21-F013B 1 Auto 981 psig SRV Cycling for MOD l-2-84-120-8/15/84 2821-F013C 1 Auto 98l psig SRV Cycling for MOD l-2-84-120 8/15/84 2821-F013D 1 Auto 981 psig SRV Cycling for MOD 1-2-84-120 8/15/84 2821-F013E 1 Auto 981 psig SRV Cycling for MOD 1-2-84-120 8/15/84 2B21-F013F 1 Auto 981 psig SRV Cycling for i

MOD 1-2-84-120 8/15/84 2B21-F013G 1 Auto 981 psig SRV Cycling for i

MOD l-2-84-120 l

8/15/84 2B21-F013H 1 Auto 981 psig SRV Cycling for l

MOD l-2-84-120 8/15/84 2B21-F013I 1 Auto 931 psig SRV Cycling for MOD l-2-84-120 8/15/84 2821-F013J l Auto 981 psig SRV Cycling for l

t-l l

..... ~.

E.

UNIQUE REPORTING REQUIREMENTS (CONT'D) 1.

Safety / Relief Valve Operations for Unit Two.

DATE VALVES NO & TYPE PLANT DESCRIPTION ACTUATED ACTUATIONS CONDITION OF EVENT 8/15/84 2821-F013K 1 Auto 981 psig SRV Cycling for MOD l-2-84-120 8/15/84 2B21-F013L 1 Auto 981 psig SRV Cycling for MOD 1-2-84-120 8/15/84 2B21-F013M 1 Auto 981 psig SRV Cycling for MOD l-2-84-120 8/15/84 2B21-F013N 1 Auto 981 psig SRV Cycling for MOD l-2-84-120 8/15/84 2B21-F013P 1 Auto 981 psig SRV Cycling for MOD l-2-84-120 8/15/84 2B21-F013R 1 Auto 981 psig SRV Cycling for MOD 1-2-84-120 8/15/84 2B21-F013S 1 Auto 981 psig SRV Cycling for

-MOD 1-2-84-120 8/15/84 2B21-F013U 1 Auto 981 psig SRV Cycling for MOD 1-2-84-120 8/15/84 2B21-F013V 1 Auto 981 psig SRV Cycling for MOD l-2-84-120 l

DOCUMENT ID 0036r/0005r

2.

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

OUTAGE NO.

BOUIPMENT PURPOSE OF OUTAGE 2-948-84 2B DG Air Compressor Replace Gasket 2-971-84 2E12-F322A/B STP 71 2-981-84 HPCS D/G Air Start Replace Relief Motor Comp.

2-997-84 2E12-F0243 Troubleshoot M.O.

2-998-84 2E12-F024B Troubleshoot M.O.

2-1002-84 2512-F024B Repair Valve 2-1010-84 2E12-D300B/RHR Repair Strainer Gasket / Seal.

SW Strainer 2-1012-84 SF & RHR Install SF Spool Pieces.

2-1039-84 HPCS D/G 18 Month Inspection 2-1049-84 B RHR W/L Pump Lubrication.

2-1050-84 2A O/G 18 Month Sury.

2-1051-84 2A D/G Air Syst.

Repair Leaking Valve.

2-1056-84 U-2 LPCS Lube.

2-1073-84 Suppression Pool Remove Spool Pieces.

Cleanup

(

2-1087-84 2812-F001A Repair Operator 2-1090-84 2E12-F05A Troubleshoot & Repair l-i 2-1092-84 2B12-F074A T.S. Action Item.

I f

2-1098-84 2E12-F003B Set Limit SW's.

l 3.

Off-Site Dose Calculation Manual l

There were no changen to the off-site dose calculations manual I

during this reporting period.

f 4.

Radioactive Waste Treatment Syrtems.

There were no changes to the Radioactive Waste Treatment System during this reporting period.

DOCUMENT ID 0036r/0005r L

I

F' y;-

Comm:nwrith Edison LaSall;s County Nuclear Station Rural Route #1, Box 220 Marseilles, Illinois 61341 Telephone 815/357 6761 l

September 10, 1984 Director, Office of Management Information and Program Control United States Nuclear Regulatory Comm),ssion Washington, D.C.

20555 i

ATTN: Document Control Desk Gentlemen:

i Enclosed for your information is the monthly performance report covering LaSalle County Nuclear Power Station for the period covering August I through August 31, 1984.

Very truly yours,

/

M G. J. Diederich #/'O Superintendent LaSalle County Station l

GJD/RSD/cth 1

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, CBCo INPO Records Center Ron A. Johnson, PIP Coordinator SNED W. R. Jackson, GB Resident J. M. Nowicki, Asst. Comptroller d

M 1.t l

Document 0043r/0005r

. _.

ML20093G485

Text

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