Text

Monthly Operating Repts for Sept 1984
	ML20108A063
Person / Time
Site:	LaSalle
Issue date:	09/30/1984
From:	Diederich G, Dus R; COMMONWEALTH EDISON CO.
To:	; NRC OFFICE OF ADMINISTRATION (ADM), NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
	NUDOCS 8411140455
	Download: ML20108A063 (28)
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l LASALLE NUCLEAR PCh'ER STATION i

i UNIT 1 MONTHLY PERFORMANCE REPORT SEPTEMBER 1984 CON 90NWEALTH EDISON COMPANY i

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NRC DOCKET NO. 050-313 LICENSE NO. NPF-ll i

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8411140455 840930 i

PDR ADOCK 05000373 p

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INTRODUCTION J

The LaSalle Nuclear Power Station is a Two Unit Facility I

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 Comunonwealth Edison Company. The Architect / Engineer was Sargent & Lundy, and the primary construction contractor was comunonwealth 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 contpiled by Randy S. Dus telephone number (815)357-6761, extension 324.

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4 TABLE OF CONTENTS I.

INTRODUCTION

- II.

MONTHLY REPORT POR 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 Approva) 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 t

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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MONTHLY REPORT FOR UNIT ONE A.

SUIWUutY OF OPERATING EXPERIENCE FOR UNIT ONE SRPTEMBER l-22 The Unit started the reporting period at 83% power. At 0730 hou,on September 3 power was reduced to 60% per the Load Dispatcher. At 1500 hours0.0174 days 0.417 hours 0.00248 weeks 5.7075e-4 months on September 4, reactor power was increased to 86%. At 0200 hours0.00231 days 0.0556 hours 3.306878e-4 weeks 7.61e-5 months on September 5 power was increased to 86%. At 0200 hours0.00231 days 0.0556 hours 3.306878e-4 weeks 7.61e-5 months on September 5 power was reduced to 75% per the Load Dispatcher. At 2300 hours0.0266 days 0.639 hours 0.0038 weeks 8.7515e-4 months on September 14 power was reduced to 55%. At 0700 hours0.0081 days 0.194 hours 0.00116 weeks 2.6635e-4 months on September 17, reactor power was 74%. At 0700 hours0.0081 days 0.194 hours 0.00116 weeks 2.6635e-4 months on September 19 power was reduced to 25% to troubleshoot the main generator voltage inbalance due to pot transformer fuses. At 1522 hours0.0176 days 0.423 hours 0.00252 weeks 5.79121e-4 months on September 19 the turbine generator was removed from the grid for OAD work. At'2040 hours0.0236 days 0.567 hours 0.00337 weeks 7.7622e-4 months on September 19 the turbine-generator was synchronized to the grid.

At 1500-hours on September 20, reactor power was increased to 67%. At 1440 hours0.0167 days 0.4 hours 0.00238 weeks 5.4792e-4 months on September 21 the reactor scrassed due to performance of instrument surveillance, LIS-MS-01, Group I Isolation. The reactor was critical for 494 hours0.00572 days 0.137 hours 8.167989e-4 weeks 1.87967e-4 months and 40 minutes.

SEPTEMBER 23-30 At 2000 hours0.0231 days 0.556 hours 0.00331 weeks 7.61e-4 months on September 23, the reactor was critical. At 0505 hours0.00584 days 0.14 hours 8.349868e-4 weeks 1.921525e-4 months on September 24, the main generator was synchronized to the grid. At 1030 hours0.0119 days 0.286 hours 0.0017 weeks 3.91915e-4 months

-on September 24, reactor power was increased to 25%. At 1500 hours0.0174 days 0.417 hours 0.00248 weeks 5.7075e-4 months on September 24, reactor power was increased to 52%. At 2300 hours0.0266 days 0.639 hours 0.0038 weeks 8.7515e-4 months on September 28, power was decreased to 36% for the outage. At 0345 hours0.00399 days 0.0958 hours 5.704365e-4 weeks 1.312725e-4 months on September 29 the generator was taken off line. At 1245 hours0.0144 days 0.346 hours 0.00206 weeks 4.737225e-4 months on September.29, the reactor mode switch was put in shutdown for the outage. The reactor was critical for 136 hours0.00157 days 0.0378 hours 2.248677e-4 weeks 5.1748e-5 months and 45 minutes.

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PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS AND SAFETY RELATED

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j MAINTENANCE.

1.

Amendments to facility license or Technical Specification.

There were no facility license or Technical Specification 4

Amendments during the reporting period.

2.

Facility or procedure changes requiring NRC approval.

There were no facility or procedure changes requiring NRC 1

approval.

3.

Tests and Experiments requiring NRC approval.

i 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, l

Cause of Malfunction, Results and Effects on Safe Operation, and I

Corrective Action.

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TABLE 1 LTp-300-7 R?tition 4 CORRECTIVE MAINTENANCE OF February 29, 1984 SAFETY RELATED EQUIPMENT 6

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.IdORK REQUEST LER COMPONENT CAUSE OF MALFUNCTION RESULTS AND EFFECTS CORRECTIVE ACTION ON SAFE OPERATION l

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L35938 Drywell/Sup points 1 & 2 currently Drywell and suppression pool Recalibrated alarm pression pool in an alarm state due temperatures are monitored points 1 & 2 to come temperature to low alarm setpoint.

at all times, up @ 50*F.

L36087 RHR heat exch Valve does not fully close Valve handwheel must be Readjusted torque anger vent to with handswitch in closed cranked an additional 1/2 switch setting.

suppression

position, turn to stop flow completely pool valve.

L37095 HpCS Full Stake the setscrew in the preventative maintenance Removed, cleaned, lubricated setscrew flow test Anti-rotation stem clamp measure.

t valve to cy to prevent loosening with locktite and tank due to vibrations.

reinstalled.

L38320 Suppression pT #13 reads downscale Suppression pool water Replaced defective chamber water temperature monitored at all wire and connections.

temperature times via redundant channels recorder L39495 2B D/G The Starters for the Technical specification 3.8.1 Replaced air start diesel generator need limits the number of starts motors.

to be changed out.

for each starter.

L40480 Suppression Recorder printing false pool level verified to be Recalibrated narrow pool narrow suppression pool level within limits via local range portion of range re-indications.

sight glasses.

LIS-CM-01.

order L40709 HpCS Relief Relief valve leaks badly potential loss of containment Removed valve, valve integrity rebuilt and sat-isfactorily leak tested.

L40896 Main Steam Valve does not seal in Valve still fully closes cleaned torque line drain closed from the control when handswitch is held switch contacts,

switch, closed.

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LICENSEE EVENT REPORTS The following is a tabular stmunary of all ' licensee event reports for LaSalle Nuclear Power Station, Unit One, occurring during the reporting period, September 1 through September 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 84-047-00 8/7/84 RWCU High Differential Flow Isolation 84-048-00 8/10/84 Missed Noble Gas Sample from U-l SBGT & Particulate & Iodine Samples Counted Late 84-049-00 8/24/84 VR Isolation During Testing LES-RP-102 84-050-00 8/28/84 RWCU Isolation on High Delta Flow 84-051-00 8/29/84 SRV's Lifting l

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

1 1.

Operating Data Report

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Average Daily Unit Power Level 3.

Unit Shutdowns end Power Reductions N

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i. OPERATING DATA EEPORT DOCKET NO. 050-373 UNIT LaSalle One DATE October 10. 1984 COMPLETED BY Randy S. Dus _

TELEPHONE [815)357-6761 OPERATING STATUS 1.

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

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

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

N/A 4.

REASONS FOR RESTRICTION (IP ANY):

THIS MONTH YR TO DATE CUMULATIVE 5

NUMBER OF HOURS REACTOR WAS CRITICAL 631.4 5377.4 5377.4 6.

REACTOR RESERVE SHUTDOWN HOURS 88.6 1165 1165 7.

HOURS GENERATOR ON LINE 608.0 5194 5194 8.

UNIT ESERVE SHUTDOWN HOURS 0.0 1.0 1.0 9.

GROSS THERMAL ENERGY GENERATED (MWH) 3455185 14581709 14581709 10.

GROSS ELEC. ENERGY GENERATED (MWH) 456560 4739789 4739789 11.

NET ELEC. ENERGY GENERATED (MWH) 432697 4512808 4512808 12.

REACTOR SERVICE FACTOR 97.M 81.8%

81.8%

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REACTOR AVAILABILITY FACTOR 100%

99.5%

14.

UNIT SERVICE FACTOR 84.4%

79.0%

~79.0%

15.

UNIT AVAILABILITY FACTOR 84.4%

~79.0%

~79. 0%

16.

UNIT CAPACITY FACTOR (USING PE)C) 58.0%

66.2%

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UNIT CAPACITY FACTOR (USING DESIGN MWe) 55.%

63.%

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UNIT PORCED OUTAGE RATE 10.0%

17.1%

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: November 1._1984 21.

UNITS IN TEST STATUS (PRIOR TO COftlERCIAL OPERATION):

FORECAST ACHIEVED INITIAL CRITICALITY 6/21/82 INITIAL ELECTRICITY 9/04/82 COf9tERCIAL OPERATION 1/1/84 I

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2. AVERAGE DAILY UNIT POWER LEVEL DOCKET WO: 050-373 UNIT: LASALLE ONE DATE: OCTOBER 10, 1984 COMPLETED BY: Randy S. Dus TELEPHONE: (815) 357-6~161 MONTH: SEPTEMBER 1984 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1.

878 17.

767 2.

958 18.

811 3

628 19.

174 4.

811 20.

572 5.

798 21.

265 6.

748 22.

0 7.

895 23.

0 8.

%0 24.

271 9.

883 25.

654 10.

869 26.

562 11.

871 27.

564 12.

837 28.

527 13.

850 29.

6 14.

846 30.

0 15.

517 31.

0 16.

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INSTRUCTIO*lS On this form list the average daily unit power level in MWe-Net for each day i

l 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 l

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 l

anomaly.

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ATTACHMENT E 3.

UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 050-374 UNIT NAME LaSa11e One DATE October 1984 REPORT MONTH SEPTEMBER 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 /COf9 TENTS 16 84/09/03 S

0.0 H

5 Reduced power per Load Dispatcher 17 84/09/14 S

0.0 H

5 Reduced power per Load Dispatcher J

18 84/09/19 F

5.3 B

1 Reduced power.to troubleshoot main generator voltage imbalance due to pot 4

transormer fuses 1

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19 84/09/21 F

62.4 B

3 Reactor scram caused by IM Surveillance LIS-MS-01.

20 84/09/29 S

44.3 H

1 Turbine off line for scheduled outage.

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UNIQUE REPORTING REQUIREMENTS 1

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Safety / Relief valve operations for Unit One.

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

There were no relief valve actuations during the month of September.

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ECCS Sy;tems Outige3 The following outages were taken on ECCS Systems during the reporting period.

OUTAGE NO.

BOUIPMENT PURPOSE OF OUTAGE l-680-84 1822-F023 Prevent Rupture of discharge relief diaphragm.

1-699-84 IB D/G Motor Driven Replace Head Gasket Air Compressor 1-731-84 1C RHR pump Remove Motor 1-736-84 1C RHR Pump Blank Flange Pump Suction Line 1-741-84 1C RHR Pump Change Pump Shaft 1-747-84 IB D/G 18 Month Inspection i

1-754-84 lE12-F009 Remove Motor 1-755-84 IE12-F008 Repairs to IE12-F009 1-757-84 lE12-F009 Repair Limitorque 1-758-84 IE22-F028 ASTM UT-1 Visual Inspection 1-764-84 IB D/G Recalibrate Instrumentation 3.

Off-Site Dose Calculation Manual There were no changes to the off-site dose calculations manual during this reporting period, t

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Radioactive Waste Treatment Systems.

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

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LASALLE NUCLEAR POWER STATION UNIT 2 MONTHLY PERFORMANCE REPORT SEPTEMBER 1984 COfMONWEALTH EDISON COMPANY NRC DOCKET NO. 050-374 LICENSE NO. NPF-18 l

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TABLE OF CONTENTS I.

INTRODUCTION II.

MONTHLY REPORT FOR UNIT TNO A.

Sunusary of Operating Experience B.

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

Amendments to Facility License or Technical Specifications 2.

Facility or Procedure Changes Requiring NRC Approval 3.

Tests and Experiments Requiring NRC Approval 4.

Corrective Maintenance of Safety Related Equipment C.

LICENSEE EVENT REPORTS D.

DATA TABULATIONS 1.

Operating Data Report 2.

Average Daily Unit Power Level 3.

Unit Shutdowns and Power Reductions E.

UNIQUE REPORTING REQUIREMENTS 1.

Safety / Relief Valve Operations 2.

ECC3 System Outages 3.

Off-Site Dose Calculation Manual Changes 4.

Major Changes to Radioactive Waste Treatment Systen k

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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 l

MWe net. The Station is owned by Commonwealth Edison Company. The Architect / Engineer was Sargent & Lundy, and the primary construction contractor was Comunonwealth Edison Company.

i 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 comunenced comunercial 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 I'EPORT FOR UNIT TWO A.

SUf9EARY OF OPERATING EXPERIENCE FOR UNIT TWO September 1-8 The Unit started the reporting period at 70% power. At 2200 hours0.0255 days 0.611 hours 0.00364 weeks 8.371e-4 months on September 3 reactor power was increased to 95%. At 0700 hours0.0081 days 0.194 hours 0.00116 weeks 2.6635e-4 months on September 5 power was reduced to 54% for STP-30 Reactor Recirculat!on Pump Trip. At 0000 hours0 days 0 hours 0 weeks 0 months on September 6, reactor power was increased to 91%. At 0515 hours0.00596 days 0.143 hours 8.515212e-4 weeks 1.959575e-4 months on September 6, the reactor scrammed due to STP-25, MSIV closure. The reactor was critical for 125 hours0.00145 days 0.0347 hours 2.066799e-4 weeks 4.75625e-5 months and 15 minutes.

September 9-13 The reactor went critical at 0040 hours4.62963e-4 days 0.0111 hours 6.613757e-5 weeks 1.522e-5 months on September 9.

At 1312 hours0.0152 days 0.364 hours 0.00217 weeks 4.99216e-4 months on September 9, the main generator was synchronized to the grid. At 1845 hours0.0214 days 0.513 hours 0.00305 weeks 7.020225e-4 months on September 9 reactor power was increased to 25%. At 2300 hours0.0266 days 0.639 hours 0.0038 weeks 8.7515e-4 months on September 9 reactor power was increased to 66%. At 2200 hours0.0255 days 0.611 hours 0.00364 weeks 8.371e-4 months on September 12, reactor power was increased to 95%. At 2300 hours0.0266 days 0.639 hours 0.0038 weeks 8.7515e-4 months on September 12, the reactor scrammed due to STP 27-2, Turbine Control Valve Fast Closure. The reactor was critical for 94 hours0.00109 days 0.0261 hours 1.554233e-4 weeks 3.5767e-5 months and 20 minutes.

September 14-30 The reactor went critical at 0800 hours0.00926 days 0.222 hours 0.00132 weeks 3.044e-4 months on September 14.

At 1810 hours0.0209 days 0.503 hours 0.00299 weeks 6.88705e-4 months on September 14, the main generator was synchronized to the grid. At 2300 hours0.0266 days 0.639 hours 0.0038 weeks 8.7515e-4 months on September 14, reactor power was increased to 25%. At 0700 hours0.0081 days 0.194 hours 0.00116 weeks 2.6635e-4 months on September 15, reactor power was increased to 50%. At 0000 hours0 days 0 hours 0 weeks 0 months on September 16, reactor power was increased to 75%. At 1400 hours0.0162 days 0.389 hours 0.00231 weeks 5.327e-4 months on September 17, reactor power was increased to 90%. At 0540 hours0.00625 days 0.15 hours 8.928571e-4 weeks 2.0547e-4 months on September 18, reactor power was increased to 100%. At 1540 hours0.0178 days 0.428 hours 0.00255 weeks 5.8597e-4 months on September 25, power was reduced to 75% due to FCV operation without LVDT feedback. At 0156 hours0.00181 days 0.0433 hours 2.579365e-4 weeks 5.9358e-5 months on September 27, the turbine tripped on high vibration, reactor power was reduced to 20%. At 1900 hours0.022 days 0.528 hours 0.00314 weeks 7.2295e-4 months on September 27, the main generator was synchronized to the grid. At 2200 hours0.0255 days 0.611 hours 0.00364 weeks 8.371e-4 months on September 27, reactor power was increased to 42%. At 0700 hours0.0081 days 0.194 hours 0.00116 weeks 2.6635e-4 months on September 28, reactor power was increased to 65%. At 1400 hours0.0162 days 0.389 hours 0.00231 weeks 5.327e-4 months on

~ September 29, reactor power was increased to 88%. The reactor was critical for 400 hours0.00463 days 0.111 hours 6.613757e-4 weeks 1.522e-4 months .

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4 B.

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

1.

Amendments to facility license or Technical Specifications.

Amendment No.4-This Amendment vacates Amendment No.3 and Reinstates License Condition 2.c.(~1).

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.

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.

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TABLE 1 LTP-300-7 s

R; vision 4 CORRECTIVE MAINTENANCE OF February 29, 1984

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a ON SAFE OPERATION I

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i L19912 Post 14CA Annunciators Do Not con-System still operational.

Rewired alarm logic to H2 &O2 form to " Black Panel" correct per modification monitor ann, concept.

package.

L28462 ITT Actuators Fuses in control wiring Only a problem whenever 3 Replaced existing 6 for ventila-logic too small to support actuators are in parallel.

amp fuses with 10 i

tion dampers full starting current.

amp fuses per mod-ification package.

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L37864 VR Exhaust Damper shows dual in-None Damper physically Adjusted limit damper dication. Discovered verified to be closed.

switch to show 4

i IVR05YB during Surveillance closed indication.

1 IDS-CS-Q1.

i L38689 2A D/G Lubricating Oil Samples

. Lubricating oil still within Tightened all fuel showed signs of fuel oil acceptable limits..

line connections.

j Resampled oil.

L39495 2B D/GT The starters for the Technical Specification Replaced air

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diesel generator need 3.8.1 limits the number start motors.

j to be changed.out.

of starts for each starter L39898 Div I Post Recorder pen cycling back Local O2 indication still Changed out servo 1

Loca 02 and forth resulting in showed acceptable 02 drive gears and j

recorder false indication.

concentration.

recalibrated.

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TABLE 1 LTP-3dO-7 Reviolon 4 CORRECTIVE MAINTENANCE OF February 29, 1984 6

SAFETY RELATED BQUIPMENT 6

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I WORK REQUEST LER COMPONENT CAUSE OF MALFUNCTION RESULTS AND EFFECTS CORR 8CTIVE ACTION ON SAFE OPERATION I

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40472 Drywell Recorder frequently Temperature indication still Replaced defective drive temperature stops driving.

correct but recorder does clutch.

recorder not drive. Redundant channell still operable.

L40872 VY Fan motor Fan motor bearings are No effect on safe operation Replaced motor worn and need re-bearings.

placement.

L40980 IB D/G motor Headgasket blown so unable Unable to air start the IB Installed new gasket driven air to maintain air reciever and verified com-compressor pressure greater than pressor operability.

220 psig.

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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, September 1 through September 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 84-050-00 8/10/84 Reactor Scram from RPV High Pressure.

84-051-00 8/23/84 RWCU High Ambient Temperature Isolation.

84-052-00 8/17/84 Reactor Scram due to Turbine Trip.

84-053-00 8/16/84 Missed Off Gas H2 Sample.

84-054-00 8/18/84 RWCU Isolation on High j

Differential Flow.

84-055-00 8/18/84 Failure of 'B' RHR Pull Flow Test to Close.

84-056-00 8/27/84 RWCU Isolation on High Pump i

Room Vent Differential Temperature.

84-057-00 9/6/84 Spurious RWCU High Differential Flow Isolation.

84-058-00 8/26/84 RWCU Room High Delta l

Temperature Isolation.

84-059-00 8/28/84 LIS-RD-403 Monthly Punctional Missed Two consecutive Times.

84-060-00 8/28/84 CRD Charging Water Header Pressure Time Delay Greater Than Ten Seconds.

84-061-00 8/30/84 RWCU High Differential Flow Isolation.

84-062-00 8/27/84 Division II Isolation on RHR Shutdown Cooling.

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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 I

h 3.

Unit Shutdowns and Power Reductions

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1. OPERATING DATA REPORT DOCKET NO. 050-374 UNIT LaSalle Two DATE October 10, 1984 CODE *LETED BY Randy S. Dus j

TELEPHONE (815)357-6761 OPERATING STATUS 1.

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

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

POWER LEVEL TO WICH RESTRICTED (IF ANY) (MWe-Met):

N/A 4.

REASONS FOR RESTRICTION (IF ANY):

THIS MONTH YR TO DATE CUBRJLATIVE 5

NUfERER OF HOURS REACTOR WAS CRITICAL 619.6 3430.6 3430.6 5.

REACTOR RESERVE SHUTDOW HOURS 100.4 1480 1480 7.

HOURS GENERATOR ON LINE 579.8 2521.8 2521.8 8.

UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 0.0 9.

GROSS '"HERMAL ENEftGY GENERATED (MWH) 1515746 4804824 4804824 10.

GROSS ELEC. ENERGY GENERATED (MWH) 502128 1417452 1417452 11.

NET ELEC. ENERGY GENERATED (MWH) 482895 1343615 1343615 12.

REACTOR SERVICE FACTOR N/A N/A N/A 13.

REACTOR AVAILABILITY FACTOR N/A N/A N/A 14.

UNIT SERVICE FACTOR N/A N/A N/A 15.

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

UNIT CAPACITY FACTOR (USING PE)C)

N/A N/A N/A 17.

UNIT CAPACITY FACTOR (USING DESIGN Infe)

N/A N/A N/A 18.

UNIT FORCED OUTAGE RATE N/A N/A N/A j

19.

SHUTDOWS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF BACH) 20.

IF SHUT DOW AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP N/A 21.

UNITS IN TEST STATUS (PRIOR TO COf94ERCIAL OPERATION):

FORECAST ACHIEVED INITIAL CRITICALITY 3/10/84 k

INITIAL ELECTRICITY 4/20/84 i

C009EutCIAL OPERATION Oct. 84 5

I r

i I

i 1

l DOCUMENT ID 0036r/0005r

, _ ~ _ -. _ _

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

(MWe-Net) 1.,

818 17.

927 2.

831 18.

1050 3

935 19.

1047 4.

1005 20.

1044 5.

820 21, 1040 6.

215 22.

1042 7.

0 23.

1041 8.

0 24.

1036 9.

116 25.

959 10.

725 26.

779 11.

844 27.

62 12.

0 28.

688 13.

0 29.

920 14.

36 30.

872 15.

536 31.

16.

733 INSTRUCTIONS On this form list the average daily unit power level in MWe-Net for each day i

in the reporting month. Compute to the nearest whole megawatt.

These figuren 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 l

the unit there may be occasions when the daily average power level exceeds the l

100% line (or the restricted power level line.)

In such cases the everage l

daily unit power output sheet should be footnoted to explain the apparent l

anomaly.

l l

DOCUMENT ID 0036r/0005r

ATTACHMENT E 3.

UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 050-374 UNIT NAM LaSalle Two DATE Ojc ober 1984 REPORT MONTH SEPTEMBER 1984 COMPLETED BY Randy S. Dus TELEPHONE (815)357-6761 METHOD OF TYPE SHUTTING DOWN F: FORCED DURATION THE REAC*DR OR CORRECTIVE NO.

DATE S: SCHEDULED (HOURS)

REASON (1)

REDUCING POWER ACTIONS /COMENTS 28 840905 S

0.0 B

5 Reduced power for STP-30, Reactor Recirculation Pump Trip 29 840906 S

80.0 B

3 Reactor Scram for STP-25 MSIV Closure 30 840912 S

43.2 B

3 Reactor Scram for STP 27-2 Turbine control Valve Fast Closure.

A 5

Reduced power due to 31 840925 F

0.0 FCV operation w/o LVDT Feedback.

32 840927 F

17.0 A

9 Turbine Trip on high vibration.

DOCUMNT 0044r/000*;r

j E.

UNIQUE REPORTING REQUIREMENTS 1.

Safety / Relief Valve Operations for Unit Two.

DATE VALVES NO & TYPE PLANT DESCRIPTION ACTUATED ACTUATIONS CONDITION OF EVENT 9/6/84 2B21-F0135 1 Auto 90% Power STP-25/RX Scram 9/6/84 2B21-F013U 1 Auto 90% Power STP-25/RX Scram 9/6/84 2B21-F013D 1 Auto 90% Power STP-25/RX Scram 9/11/84 2B21-F0135 1 Auto 95% Power STP-27-2/RX Scram 9/11/84 2B21-F013S 1 Auto 95% Power STP-27-2/RX Scram 9/11/84 2B21-F013D 1 Auto 95% Power STP-27-2/RX Scram 9/11/84 2B21-F013U 1 Auto 95% Power STP-27-2/RX Scram j

i s

i l

i DCCUMENT ID 0036r/0005r I

2.

BCCS Systems Outage]

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

OUTAGE Wo.

BOUIMENT PURPOSE OF OUTAGE 2-1087-84 2E12-F041A Repair Operator 2-1090-84 2512-F003B Repair Operator 2-1092-84 2512-F074A Tech Spe: Action Statement 2-1098-84 2E12-F003B Set Limit Switch 2-1103-84 2B D/G Replace Air Start Motor 2-1113-84 2E22-F023 Maintenance on 2E22-F035.

2-1117-84 HPCS System Install cy spool piece.

2-1123-84 LPCS Pump Replace Lower Guide Bearing Thermocouple 2-1129-84 28 D/G Recalibrate Instrumentation 2-1142-84 2B D/G Immersion Replace Control Power Heater Transformer 2-1153-84 28 D/G Motor Driver Clean Moisture Trap Air compressor 2-1174-84 i m System Relief Valve Inspection f

2-1177-24 HPCS Relief Valve Repair Relief Valve 3.

Off-Site Dome Calculation Manual There were no changes to the off-site dose calculations manual during this reporting period.

4.

Radioactive WaJte Treatment Systems.

There were no changes to the Radioactive Waste Treatment System during this reporti.19 period.

DOCUMENT ID 0036r/0005r

1"9 5

4 October 10, 1984 Director Office of Management Information and Program Control United States Nuclear Regulatory Commission Washington, D.C.

20555 ATTW: Document Control Desk Gentlemen:

Enclosed for your information is the monthly performance report covering i

LaSalle County Nuclear Power Station for the period covering September i through September 30, 1984.

Very truly yours,

]

A i

G J. Diederich Superintendent LaSalle County Station

]

GJD/RSD/cth Enclosure xc:

J. G. Keppler, NRC, Region III NRC Resident Inspector LaSalle Gary Wright, Ill. Dept. of Nuclear Safety D. P. Galle, CBCo D. L. Farrar, CBCo INPO Records Center Ron A. Johnson, PIP Coordinator SNED W. R. Jackson, GE Resident J. M. N wicki, Asst. Comptroller 1

Document 0043r/0005r

ML20108A063

Text

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