ML20107B445

Monthly Operating Repts for Dec 1984

ML20107B445
Person / Time
Site:	LaSalle
Issue date:	12/31/1984
From:	Diederich G, Dus R COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF ADMINISTRATION (ADM), NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
NUDOCS 8502200400
Download: ML20107B445 (29)

Text

A a

h LASALLE NUCLEAR POWER STATION UNIT 1 MONTHLY PERFORMANCE REPORT DECEMBER 1984 COtm0NWEALTH EDISON COMPANY NRC DOCKET NO. 050-373 LICENSE NO. NPF-ll i

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INTRODUCTION The LaSalle Nuclear Power Station is a Two Unit Facility Located in Marceilles, Illinois. Each Unit is a Boiling Water Reactor with a designed electrical output of 1078 MWe net. The Station is owned by Comunonwealth Edison Company. The Architect / Engineer was Sargent & Lundy, and the primary construction contractor was Coaumonwealth 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, 1082. Unit Two is subject to license ntusber 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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TABLE OF CONTENTS I.

INTRODUCTION II.

MONTHLY REPORT FOR UNIT ONE A.

Summary of Operating Experience B.

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

Amendments to Facility License or Technical Specifications 2.

Facility or Procedure Changes Requiring NRC Approval 3.

Testa 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 Maste Treatment System i

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MONTHLY REPORT FOR UNIT ONE A.'

SUIMARY OF OPERATING EXPERIENCE FOR UNIT ONE December 1-31 The Unit started the reporting period at 60% power. At 0000 Hours on December 4, Reactor Power was raised to 80%. At 2300 hours0.0266 days <br />0.639 hours <br />0.0038 weeks <br />8.7515e-4 months <br /> on December 5, reactor power was lowered to 63% per the load dispatcher. At 0800 hours0.00926 days <br />0.222 hours <br />0.00132 weeks <br />3.044e-4 months <br /> on December 7, reactor power was raised to 80%. At 0700 hours0.0081 days <br />0.194 hours <br />0.00116 weeks <br />2.6635e-4 months <br /> on December 19, reactor power was lowered to 66% for repairs to the MSIV limit switches.

At-1500 hours on December 19, reactor power was reduced to 45% to reduce radiation exposure during MSIV limit switch repairs. At 2300 hours0.0266 days <br />0.639 hours <br />0.0038 weeks <br />8.7515e-4 months <br /> on December 19, Reactor power was raised to 65%, At 2300 hours0.0266 days <br />0.639 hours <br />0.0038 weeks <br />8.7515e-4 months <br /> on December 21, reactor power was raised to 80%. At 0700 hours0.0081 days <br />0.194 hours <br />0.00116 weeks <br />2.6635e-4 months <br /> on December 22, reactor power was raised to 94%. At 0115 hours0.00133 days <br />0.0319 hours <br />1.901455e-4 weeks <br />4.37575e-5 months <br /> on December 23, reactor power was reduced to 80%

to adjust the flow control line. At 0700 hours0.0081 days <br />0.194 hours <br />0.00116 weeks <br />2.6635e-4 months <br /> on December 24, reactor power was raised to 90%. At 0400 hours0.00463 days <br />0.111 hours <br />6.613757e-4 weeks <br />1.522e-4 months <br /> on December 27, Reactor power was reduced to 80%

due to the #2 and #4 control valve failure to fast close during a scheduled surveillance. ~ At 0000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> on December 28, reactor power was reduced to 60% for maintenance work on the #2 and #4 control valves. At 0000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> on December 31, reactor pcwer was raised to j

90% power. The reactor was critical for 744 hours0.00861 days <br />0.207 hours <br />0.00123 weeks <br />2.83092e-4 months <br />.

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

1.

Amendments to facility license or Technical Specification.

Ther 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 i

approval.

3.

Tes'ts 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 sununary 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 i

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 OPERATION-L26314 Main Steam Low Install Pressure Snubbers Could cause Unit trip due-to Performed work per pressure Isolation spurious pressure pulsations.

modification package switches.

.#1-1-83-41.

L31235 RHR Min Flow Bypass Modify bypass valve thermal May cause bypass valve to open Revised wiring to con-

Valves, overload bypass circuit.

on ECCS Actuation.

form to other ECCS Logic.

L31539 Aux. Elec. Equip.

Fan motor casing is Redundant Ventilation Train Replaced fan motor.

I room air cooled.

cracked.

still operable.

condensing Fan.

L43100 Diesel Generator Air Start Motors have 43 Per G. E. Recommendatior.s, Air start. motors air start motor..

starts on them. Need to number of motor starts should were changed out.

be replaced.

not exceed 50.

L43894 Drywell/ Suppression Recorder Sometimes Stops Still Provides temperature Changed pinion motor,,

Pool temperature driving.

indication but cannot trend adjusted clutch and recorder.

changes in temperature.

drive belt.

L44008 Post Loca Monitor Excessive Oscillations Rad Chem Technicians sampling Found Slight zero noted causing alarm drywell atmosphere to assure shift at analyzer.

for HI O2 to come up.

correct 02 &H2 con-centration.

L44239 Core Plate DP Calibrate Core differential Core Plate DP close to exceeding Recalibrated per Recorder.

. pressure recorder.

Tech Spec. Limits.

LIP-NB-05.

Instrument Loop.

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=L44304 Drywell Equipment.

Relief Valve suspected of Excessive heat inputs to RBEDT. Bench tested relief i

drain sump heat ex-leaking.

valve at settpres-changer relief valve.

sure and verified no leaks.

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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 OPERATION

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Hydrogen Recomb-Recalibrate flow loop.

Failed to meet required flow.

Completed LIS-HG-102 L44318 iner inlet flow satisfactorily.

loop.

L44614 "B" Outboard MSIV Limit switch out of ad-Failed to generate a half scram Reset limit switch justment.

during the performance of.

to proper setpoint LOS-RP-MI.

cycled valve 4 times and verified proper-operation.

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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, cccurring during the reporting

. Period, December 1 through December 31, 1984. This information is provided pursuant to the reportable occurrence reporting requirements as set-forth in 10CPR 50.73.

Licensee Event Report Number Date Title of Occurrence 84-073-00 11/6/84 PCIS Group 1 Isolation Signal on Turbine Reset.

84-074-00 11/7/84 RWCU Isolation 84-075-00 11/11/84 1B RR Pump Suction Temperature RTD well leak 84-076-00 11/11/84 Unit 1 & 2 VR Isolation i-84-077 11/15/84 - Auto Start of B control room emergency makeup train.

1 84-078-00 11/17/84 Ammonia Chlorina ESF Actuation.

84-079-00 11/14/84 High. Rad Door Open Without positive control.

84-080-00 11/20/84 Potential failure of safety related battery rack.

84-081-00 11/23/84 HI Suppression pool level HPCS suction swap.

84-082-00 11/24/84 RWCU Hi A Flow Isolation.

84-083-00 11/24/84 Ur. secured Hi Rad. Area.

84-084-00 11/30/84 Control Room HVAC Ammonia' Detector Spurious Actuation.

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84-085-00 11/29/84 Loss of feedwater heating procedure nonconservative with respect to analysis.

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DATA TABULATIOtiS 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 1

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OPERATING DATA REPORT DOCKET Nu. 050-373 UNIT LaSalle One DATE January 10, 1984 COMPLETED BY Randy S. Dus TELEPHONE (815)357-6761 OPERATING STATUS 1.

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

CURRENTLY AUTHORIZED POWER LEVEL (MWt):3323 MAX DEPEND CAPACITY (We-Net): 1036 DESIGN ELECTRICAL RATIkG (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 744.0 6280 6280 6.

REACTOR RESERVE SHUTDOWN HOURS 0.0 1165 1165 7.

HOURS GENERATOR ON LINE 744.0 6055 6055 8.

UNIT RESERVE SHUTDOWN HOURS 0.0 1.0 1.0 9.

GROSS THERMAL ENERGY GENERATED (MWH) 2017106 16823289 16823289 10.

GROSS ELEC. ENERGY GENERAT3D (MWH) 664254 5470643 5470643

11. N3T ELEC. ENERGY GENERATED (MWH) 638 % 3 5195062 5195062 12.

REACTOR SERVICE FACTOR 100%

71.5%

71.5%

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REACTOR AVAILABILITY FACTOR 100%

84.8%

84.8%

14.

UNIT SERVICE FACTOR 100%

68.9%

68.9%

15.

UNIT AVAILABILITY FACTOR 100%

68.9%

68.9%

16.

UNIT CAPACITY FACTOR (USING MDC) 82.9%

57.1%

57.1%

17.

UNIT CAPACITY FACTOR (USING DESIGN MWe) 79.7%

54.9%

54.9%

18.

UNIT FORCED OUTAGE RATE 0.0 15.1%

15.1%

19.

SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH) 20.

IF SHUT DOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP: N/A l

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

(MWe-Net) 1.

628 17.

966 2.__

641 18.

998 3

772 19.

678 4.

881 20.

742 5,

730 21.

930 6.

736 22.

1020 7.

869 23.

873 8.

879 24.

1004 9.

875 25.

1036 10.

862 26, 1006 11.

881 27.

861 12.

870 28.

613 13.

883 29.

661 14.

946 30.

873 15.

986 31.

979 16.

945 I

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ATTACHMENT E 3.

UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 050-374 UNIT NAME LaSalle One DATE January 10, 1985 REPORT MONTH DECEMBER 1984 COMPLETED BY Randy S. Dus TELEPHONE (815)357-6761

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

-DATE S: SCHEDULED (HOURS)

REASON REDUCING POWER ACTIONS /COMENTS 21 84/12/19 F

0.0 A

5 Load drop for MSr/

limit switch repairs.

22 84/12/28 F

0.0 A

5 Load drop for maintenance on #2 and

1. 4 turbine control' valves.

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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 valve operations during the reporting period.

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

OUTAGE NO.

EQUIPMENT PURPOSE OF OUTAGE 1-1298-84 lE12-C300A Lube Pump Coupling 1-1304-84 lE12-F068A Repack valve 1-1306-84 1E12-C003 Lube Pump Coupling 1-1338-84 1A D/G Replace Air Start Motors 1-1339-84 1A D/G Replace Lube Oil Filters 1-1340-84 1A D/G Instrumentation Calibration.

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 made to the radioactive waste treatment system during this reporting period.

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LASALLE NUCLEAR POWER STATION UNIT 2 MONTHLY PERFORMANCE REPORT DECEMBER 1984 LUMONWEALTH EDISON COMPANY l

NRC DOCKET NO. 050-3'14 LICENSE NO. NPF-18 i

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TABLE OF CONTENTS I.

INTRODUCTION II.

MONTHLY REPORT FOR UNIT TWO A..Susunary of Operating Experience B.

PIJelT 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 4

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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 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 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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II.

MONTHLY REPORT FOR UNIT TWO' A.

SUI 9fARY OF OPERATING EXPERIENCE FOR UNIT TWO December 1-18 The Unit started the reporting period at 95% power. At 1335 hours0.0155 days <br />0.371 hours <br />0.00221 weeks <br />5.079675e-4 months <br /> on December 14, a turbine trip and reactor scram occurred due to high turbine vibrations which was

-caused by a loose card in the turbine supervisory instrumentation cabinet. The reactor was critical for 325 hours0.00376 days <br />0.0903 hours <br />5.373677e-4 weeks <br />1.236625e-4 months <br /> and 35 minutes.

December 19 - 31 The reactor went critical at 1850 hours0.0214 days <br />0.514 hours <br />0.00306 weeks <br />7.03925e-4 months <br /> on December 19.

At 0830 hours0.00961 days <br />0.231 hours <br />0.00137 weeks <br />3.15815e-4 months <br /> on December 20, the Main Generator was synchronized to the grid. At 1500 hours0.0174 days <br />0.417 hours <br />0.00248 weeks <br />5.7075e-4 months <br /> on December 20, Reactor power was raised to 27%. At 0700 hours0.0081 days <br />0.194 hours <br />0.00116 weeks <br />2.6635e-4 months <br /> on December 21, Reactor power was raised to 55%. At 2300 hours0.0266 days <br />0.639 hours <br />0.0038 weeks <br />8.7515e-4 months <br /> on December 24, reactor power was raised to 80%.

At 2300 hours0.0266 days <br />0.639 hours <br />0.0038 weeks <br />8.7515e-4 months <br /> on December 27, reactor power was raised to 96%. The reactor was critical for 293 hours0.00339 days <br />0.0814 hours <br />4.844577e-4 weeks <br />1.114865e-4 months <br /> and 10 minutes.

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

1.

Amendments to facility license or Technical Specifications.

Amendment No. 6 - This amendment added a reactor scram on Low control rod drive pump discharge pressure as required by license condition 2.c(7).

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 experheents 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 Cae 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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TABLE l' CORRECTIVE MAINTENANCE OF SAFETY RELATED EQUIPMENT s

WORK REQUEST COMPONENT CAUSE OF MALFUNCTION RESULTS AND EFFECTS CORRECTIVE ACTION-ON SAFE OPERATION L43660

-Div 2 Battery Charger. Charger output voltage ad-Could eventually allow bat-Made adjustments to re-justing pot is set for max teries.to drain slowly.

sistors to provide ad-voltage but does not de-equate voltage.

liver' adequate voltage.

L43889 Containment vent &

Valve Failed LLRT Potential Loss of Containment Replaced valve seat purge inlet valve.

Integrity, and reperformed LLRT.

L44078 Main. Steam Tunnel Alarm Setpoint is 28'F Recorder in constant alarm.

Raised setpoint to A T recorder.

and indicated A T is 29'F Higher setpoint acceptable.

32*F per temp. system change.

L44298 CY Tank Suction Valve Valve will not open using Could lose CY supply to HPCS Found wire missing.

to HPCS.

control switch from control pump.

Corrected per' app-room.

licable wiring diagrams.

L44388 VR Exhaust Rad Monitor Rad Monitor is reading up-Redundant monitors still.oper-Replaced defective GM-scale due to defective GM able.

Tube.

Tube.

L44395 RHR full flow test Valve torques out before Valve can not fully close.

Readjusted torque-valve.

it-is fully closed.

switch setting.

~L44501 Shutdown Cooling Valve is difficult to open. Not able to run shutdown cooling Long term corrective suction valve.,

through normal. lineup, action is currently being investigated.

L44505 Div II Post Loca O2 Recorder indicating x 12.5% Rad Chem Technicians verified Found poor solder Monitor.

02 for:several hours.

02 concentration prior to connections on power

'while deinerting drywell.

entry, supply.

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CORRECTIVE MAINTENANCE OF SAFETY RELATED EQUIPMENT l

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' WORK REQUEST COMPONENT CAUSE OF MALFUNCTION RESULTS AND EFFECTS CORRECTIVE ACTION ON SAFE OPERATION F

L44511 Inboard MSIV-LC Valve would not fully open valve required to be operable Repacked valve, depressurization valve during surveillance per Tech. Spec. 3.6.1.4.

adjusted limit switch LOS-MS-Ql.

and performed LLRT.

L44531 LPCI "B"

testable Valve will not cycle Proper operation observed with Replaced valve check valve.

properly.

pump presure present.

operator.

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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 Two, occurring during the reporting period, December 1 through Deceder 31, 1984.

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

Licensee Event Report Numbe'r Date Title of Occurrence 84-073-00 11/12/84 Reactor. Water Cleanup Isolation on A T.

84-074-00 11/16/84 Reactor Water Cleanup Hi Area temperature isolation.

84-075-00 11/12/84 Loss of a RPS Bus.

84-076-00 11/20/84 Main Turbine Bypass Valve Inop.

84-077-00 11/15/84 2A Primary Containment Vacuum Breaker Cycling.

84-078-00 11/17/84 HPCS Suction Swap on the Hi suppression pool level.

J 84-079-00 11/21/84 Reactor Water Cleanup Isolation on Hi A Flow.

84-080-00 11/21/84 Suppresssion Pool to Drywell Vacuum Breakers Open.

84-081-00 11/27/84 2A Primary Containment Vacuum d

Breaker Cycling.

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DATA TABULATIONS The following data tabulations a.. presented in this report:

1.

Operating Data Report 2.

Average Daily Unit Power Level 3.

Unit Shutdowns and Power Reductions J

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1. OPERATING DATA REPORT DOCKET NO. 050-374 UNIT LaSalle Two DATE January 10, 1984 COitPLETED BY Rantiv o----

i OPERATING STATUS i

1.

REPORTING PERIOD: December 191 2.

CURRENTLY AUTHORIZED POWER Li (MWe-Net): 1036 DESIGN ELEC 3.

POWER LEVEL TO WHICH RESTRICT 4.

REASONS FOR RESTRICTION (IP A 5

NUMBER OF HOURS REACTOR WAS C1 DATA TABULATIONS 6.

REACTOR RESERVE SHUTDOWN HOUR 1 D*

resented 7.

HOURS GENERATOR ON LINE The following data tabulations are P 8.

UNIT RESERVE SHUTDOWN HOURS 9.

GROSS THERMAL ENERGY GENERATED 10.

GROSS ELEC. ENERGY GENERATED (I 11.

NET ELEC. ENERGY GENERATED (MWI, Operating Data Report t,

12.

REACTOR SERVICE FACTOR 13.

REACTOR AVAILABILITY FACTOR Unit POWef Level 14.

UNIT SERVICE FACTOR Average Daily 2*

15.

UNIT AVAILABILITY FACTOR 16.

UNIT CAPACITY FACTOR (USING MDC Unit Shutdowns and power Reduction 17.

UNIT CAPACITY FACTOR (USING DESI(

3.

MWe) 18.

UNIT FORCED OUTAGE RATE 19.

SHUTDOWNS SCHEDULED OVER NEXT 6 i There is an outage scheduled to ;

and surveillances. This outage ;

weeks.

20.

IF SHUT DOWN AT END OF REPORT PEE 4

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1. OPERATING DATA REPORT DOCKET NO: 050-374 UNIT LaSalle Two DATE January 10, 1984 COMPLETED BY Randy S. Dus TELEPHONE (815)357-6761 OPERATING STATUS 1.

REPORTI Ki PifRIOD: December 1984 GROSS HOURS IN REPORTING PERIOD: 744 2.

CURREisTLY AUTHORIZED POWER LEVEL (MWt):3323 MAX DEPEND CAPACITY

{

(MWe-Net): 1036 DESIGN ELECTRICAL RATING (MWe-Not):1978 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 618.8 1611.8 1611.8 6.

REACTOR RESERVE SHUTDOWN HOURS 125.3 125.3 125.3 7.

HOURS GENERATOR ON LINE 605.1 1537.4 1537.4 8.

UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 0.0 i

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GROSS THERMAL ENERGY GENERATED (MWH) 1781736 4512592 4512592 10.

GROSS ELEC. ENERGY GENERATED (MWH) 586372 1484995

,1484995 11.

NET ELEC. ENERGY GENERATED (MWH) 562402 1392117 1392117 12.

REACTOR SERVICE FACTOR 83.2%

90.8%

90.8%

13.

REACTOR AVAILABILITY FACTOR 100%

97.8%

97.8%

14.

UNIT SERVICE FACTOR 81.3%

86.6%

86.6%

15.

UNIT AVAILABILITY FACTOR 81.3%

86.6%

86.6%

16.

UNIT CAPACITY FACTOR (USING MDC)_

73.0%

75.7%

75.7%

17.

UNIT CAPACITY FACTOR (U3ING DESIGN MWe) 70.1%

72.7%

72.7%

18.

UNIT FORCED OUTAGE RATE 18.7%

13.5%

13.5%

19.

SHUTDOWNS SCHEDULliD OVER NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH):

There is an outage scheduled to begin on March 1, 1985 for maintenance and surveillances. This outage is expected to last approximately nine weeks.

20.

IF SHUT DOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP N/A l

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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

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2. AVERAGE DAILY UNIT POWER LEVEL DOCKET NO: 050-374 UNIT: LASALLE TWO DATE: January 10,1984 COMPLETED BY: Randy S. Dus TELEPHONE: (815) 357-6761 ISONTH: December 1984 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1.

1030 17.

0 2.

1025 18.

0 3

1032 19.

0 4.

1041 20.

176 5.

1039 21.

538 6.

1037 22.

714 7.

1042 23.

775 8.

1043 24.

865 9.

1041 25.

857 10.

1044 26.

930 11.

1049 27, 968 12.

1049 28.

901 13.

1044 29.

823 14.

587 30.

889 15.

0 31.

980 16.

0 l

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ATTACHMENT E 3.

UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 050-374 UNIT NAME LaSalle Two DATE JANUARY 10, 1984 REPORT MONTH DECEMBER 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 REDUCING POWER ACTIONS /COfMENTS 5

84/12/14 F

138.9 A

3 Turbine trip due to a loose card in the turbine' supervisory panel.

DOCUMENT 0044r/0005r

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1 E.

UNIQUE REPORTING REQUIREMENTS 1.

Safety / Relief Valve Operations for Unit Two.

DATE VALVES NO & TYPE PLANT DESCRIPTION ACTUATED ACTUATIONS CONDITION OF EVENT 12/14/84 2B21-F013C 1 Automatic 1086 PSIG RX Scram 12/14/84 2B21-F013D 1 Automatic 1086 PSIG RX Scram.

12/14/84 2B21-F013E 1 Automatic 1086 PSIG RX Scram 12/14/84 2B21-F013K 1 Automatic 1086 PSIG RX Scram.

12/14/84 2B21-F013S 1 Automatic 1086 PSIG RX Scram 12/14/84' 2B21-F013U

l. Automatic 1086 PSIG RX Scram.

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3 2.

ECCS Syrtems Outcge3 The following outages weto taken on ECCS Systems during the reporting period.

OUTAGE NO.

BOUIPMENT PURPOSE OF OUTAGE 2-1293-84.

2822-C002 Lube Pump Coupling 2-1297-84 2B D/G Change Oil 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 made to the radioactive waste treatment system during this reporting period.

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7 Commonwe~_Ith Edison LaSalle County Nucitar Station Rural Route #1, Box 220 Marseilles, Illinois 61341 Telephone 815/357 6761 January 7, 1985 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 December 1 through December 31, 1984.

Very truly yours,

/)/

G.' J. Diederich I

superintendent LaSalle County Station GJD/RSD/crh Enclosure xc:

J. G. Keppler, NRC, Region III NRC Resident Inspector LaSalle Gary Wria. Ill. Dept. of Nuclear Safety D.

P A.e, CECO

/arrar, CECO It<0 Records Center Ron A. Johnson, PIP Coordinator SNED W. R. Jackson, GE Resident J. M. Nowicki, Asst. Comptroller

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