ML20133H411

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Monthly Operating Repts for Sept 1985
ML20133H411
Person / Time
Site: LaSalle  Constellation icon.png
Issue date: 09/30/1985
From: Diederich G, Peters J
COMMONWEALTH EDISON CO.
To:
NRC OFFICE OF ADMINISTRATION (ADM), NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
NUDOCS 8510170166
Download: ML20133H411 (33)
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,I' s LASALLE NUCLEAR POWER STATION UNIT 1 MONTHLY PERPORMANCE REPORT SEPTEMBER, 1985

, COfMONWEALTH EDISON COMPANY NRC DOCKET NO. 050-373 LICENSE NO. NPF-ll s

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8510170166 850930 PDR ADOCK 05000373 R pm Doctament 0043r/0005r Q tI v  ;

s 1 I. INTRODUCTION The LaSalle County Nuclear Power Station is a two-unit i facility owned by Comunonwealth Edison Comapny and located near Marseilles, Illinois. Each unit is a Boiling Water Reactor with a designed net electrical output of 1078 Megawatts. Waste heat is rejected to a man-made cooling pond using the Illinois River for make-up and blowdown. The architect-engineer was Sargent and Lundy, and the primary construction contractor was Comunonwealth Edision Company.

Unit one was issued operating license number NPF-ll on April 17, 1982. Initial criticality was achieved on June 21, 1982, and comunercial power operation was comumenced on January 1,1984.

This report was compiled by James P. Peters, telephone number (815)357-6761 extension 325.

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s TATLE OF CONTENTS s

I. INTRODUCTION II. MONTHLY REPORT FOR UNIT ONE 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. 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

3 II. MONTHLY REPORT FOR UNIT ONE A. SUP9ERY OF OPERATING EXPERIENCE FOR UNIT ONE September 1-31, -

Sept. 1, 0001 Hours. The unit entered September with the reactor critical at 90%

power and generator on-line at 960 MWe-net.

Sept. 5, 0808 Hours. Reactor Power Reduced to 74%

(800 MWe-net) per E.G.C. Test.

Sept. 5, 0940 Hours. Began increasing reactor power.

Sept. 7, 1500 Hours. Reactor Power steady at 87% (934 MWe-net) limited by Fuel consumption.

Sept. 14, 1300 Hours. Reactor Power Reduced to 850 MWe-net to check "B" Flow control valve.

Sept. 20, 0800 Hours. Reactor Power coasting down at 81% (876 MWe-net).

Sept. 28, 0050 Hours. Reactor Power Reduced to 736

-MWe-net (68%) for control valve

, surveillance.

Sept. 28, 0150 Hours. Began increasing reactor power.

Sept. 28, 0700 Hours. Reactor Power coasting down at 78% (840 MWe-net), Limited by fuel consumption.

Sept. 30, 2400 Hours. Reactor Power at 77% (830 MWe-net), coasting down.

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B. PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS AND SAFETY RELATED 4 .

MAINTENANCE.

1. Amendments to facility licer.se or Technical Specification.

Amendment 24 - Extention of a limited number of 18 month surveillances for first fueling cycle.

2. Facility or procedure changes requiring NRC approval.

Yes, the LaSalle Emergency Procedures (LGA-01 through 05 and LGA-ATWS-01 through 05) were written from guidelines developed at LaSalle based on the BWROG Emergency Procedure Guidelines.

3. Tests and Experirents requiring NRC approval.

There were no tests or experiments requiring NRC approval during this reporting period.

4. Corrective maintenance of safety related equipment.

The following table (Table 1) presents a sununary of safety-related maintenance completed on Unit One during the reporting period. The hee. dings indicated in this summary include: Work Request number, Component Name, Cause of Malfunction, Results and Effects on Safe Operation, and Corrective Action.

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  • o CORRECTIVE MAINTENANCE OF SAFETY RELATED EQUIPMENT ,

WORK REQUEST COMPONENT CAUSE OF MALFUNCTION RESULTS AND EFFECTS CORRECTIVE ACTION ON SAFE PLANT OPERATION L45618 RCIC Level Switches Dirty Seats and Disc. Unable to Calibrate Level Switch Cleaned Seating Surface Isolation Valve at Operating Pressure & Reassemble.

L49738 VC Emergency Make-up Temperature out of Spec Different Temperature Loop Calibrations OVC105 &.

Train "A" Inlet Temp. High. Indications Recieved. OVC106 and LIP-GM-28 Completed Satisfactorily. j L50684 "lB" RHR Heat Scaled Tubes on Service Could not obtain desired Service Chemically Cleaned Exchanger Water Side Water Flow Tubes.

L51342 "lA" RHR Heat Scaled Tubes on Service Could not obtain Desired Chemically Cleaned Exchanger. Water Side. Service Water. Flow. Tubes.

! 1 L51371 RHR B Minimum Flow Flow Switches IE12-N010BA/ The Valve does not always open Recalibrated Pressure Valve IE12-P064B. BB Found out of Tolerance when above minimum Flow Alarm. Switches IE12-N010BA/BB, Low. and verified no Air in

l. Sensing Lines.

L51372 HPCS Water Leg Pump Under Investigation, Could not maintain system Duplicate Work Request IE22-C003 suspect problem with pressure per Tech. Spec. 3.5.1. for Futher investigation.

impellar.

L51410 "A" VC Air Leaking oil at Seals and Could Cause Possible Internal Replaced Seal.

Conditioning Unit Motor. Damage.

OVC05CA.

l l L51410 Drywell Air and Bad Chart Drive Motor. Loss of Temperature Record Replaced Drive Motor.

l Suppression Pool Water for_Drywell and Suppression ,

Temp. Recorder Pool.

ITR-CM037 l

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TABLE 1 s

CORRECTIVE MAINTENANCE OF  ;

i SAFETY RELATED BQUIPMENT ,

J COff0NENT CAUSE OF MALFUNCTION RESULTS AND EFFECTS CORRECTIVE ACTION WORK REQUEST ON SAFE PLANT OPERATION L51442 HPCS Pump Low Suction . Pressure Switch IE22-N015 Failed Surveillance LIS-HP-303 Recalibration of IE22-N015

Pressure Alarm out of calibration.

l l L51513 DG "lA" Air Compressor Pressure Switch IPS-DG043 Control Room Alarm Annunciated. Recalibration of IPS-DG043 Starting Switch out of Calibration.

.IPS-DG043.

"lD" RHR Service Water Packing Follower Cocked Loss of Service Water for Loosened Valve Follower

, LS1606 Cooling. and Adjusted Evenly.

Pump Suction Valve on Valve.

IE12-F330D l Continuity Lamp Burned No indication on Squib Valve Replace Lamp.

l L51613 SBLC "A" Squib Valve Continuity Light out. continuity.

l j IC41-F004A.

I Circuitry units loose in Conflicting instrumentation. Retightened all cir-L51749 Stack WRGM Recorder cuitry units.

Downscale OD18-R521. sockets.

valve Leaks by at steam. Potential effect to CRD Replaced damaged L51869 1Cll-D001-111 on Stem Packing and 0-HCU 46-27, Instrum- Instrumentation.

Rings.

ent Block Stop Valve.

l Failed Surveillance LIS-NR-305. Replaced 2nd Level L51990 RBM "B" IC51-K60SGV Bad Second Level Multi- Multiplexer Card.

plexer Card.  ;

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C. LICENSEE EVENT REPORTS t

{ The following is a tabular sumunary of all licensee event reports for F

j LaSalle Nuclear Power Station, Unit One,. logged during the reporting i . .

{ period,. September 1 through September 30, 1985. This information is i provided pursuant to the reportable occurrence reporting requirements as set forth in 10CFR 50.73.

Licensee Event Report Number Date Title of Occurrence 85-058-00 8/17/85 Scram on Turbine Trip.

85-059-00 8/7/85 Spurious chlorine Detector Alarm.  ;

85-061-00 8/14/85 Failu(e to run lA DG within 1 1 Hours of 2A going IMOP. l 85-062-00 8/23/85 chlorine Trip of "B" VC/VE

, Train.

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D. DATA TABULATIONS a

The following data tabulations are presented in this report: ,

< l. Operating Data Report

2. Average Daily Unit Power Level
3. Unit shutdowns and Power Reductions i

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l. OPERATING DATA REPORT DOCKET NO. 050-373 UNIT LaSalle One DATE October 10, 1985 COMPLETED BY James P. Peters TELEPHONE (815)357-6761 OPERATING STATUS
1. REPORTING PERIOD: September 1985 GROSS HOURS IN REPORTING PERIOD: 720 i 2. CURRENTLY AUTHORIZED POWER LEVEL (MWt):3323 MAX DEPEND CAPACITY (MWe-Net): 1036 DESIGN ELECTRICAL RATING (MWe-Net): 1078
3. POWER LEVEL TO WHICH RESTRICTED (IP ANY) (MWe-Net): N/A
4. REASONS FOR RESTRICTION (IF ANY): Fuel Consumption.

THIS MONTH XR TO DA,TE . CUMULATIVE . ,

5 NUMBER OF HOURS REACTOR WAS CRITICAL 720 5333.5 11615

6. REACTOR RESERVE SHUTDOWN HOURS 0.0 476.2 1642
7. HOURS GENERATOR ON LINE 720 5165.7 11223
8. UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 0.0
9. GROSS THERMAL ENERGY GENERATED (MWH) 1971144 14401441 31224730
10. GROSS ELEC. ENERGY GENERATED (MWH) 638896 4710775 10181418
11. NET ELEC. ENERGY GENERATED (MWH) 613489 .4527276 9722338
12. REACTOR SERVICE FACTOR 100% 81.4% 75.6%
13. REACTOR AVAILABILITY FACTOR 100% 88.6% 86.3%
14. UNIT SERVICE FACTOR 100% 78.9% 73.1%
15. UNIT AVAILABILITY FACTOR 100% 78.9% 73.1%
16. UNIT CAPACITY FACTOR (USING MDC) 82.2% 66.7% 61.1%
17. UNIT CAPACITY FACTOR (USING DESIGN MWe) 79% 64.1% 58.7%
18. UNIT FORCED OUTAGE RATE 0% 18.5% 17.9%
19. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH)

> An outage for refueling, maintenance, surveillance and modifications is scheduled to begin October 18, 1985 and will last 26 weeks.

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

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I 2 AVERAGE DAILY UNIT POWER LEVEL DOCKET NO: 050-373 UNIT: LASALLE ONE DATE: October 10, 1985 COMPLETED BY: Jasses P. Peters TELEPHONE: (815) 357-6761 MONTH: SEPTEMBER 1985 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net)

1. 924.6 17. 852.8
2. 911.8 18. 847.4
4. 907.3 20. 835.4
5. 860.6 21. 831.9
6. 864.9 22. 826.0
7. 878.4 23. 823.6
8. 877.4 24, 822.5
9. 870.0 25. 818.7
10. 869.0 26. 812.3
11. 868.0 27, 808.8
12. 867.5 28. 798.6
13. -

864.7 29. 800.5

14. 859.7 30. 796.5 15.__ 857.9 31. N/A
16. 854.9 Docussent 0043r/0005r o

ATTACISEDfT E *

3. WIT SHUTDOWS AND POWER CEDUCTIONS

-DOCKET NO. 050-373 '

UNIT NAME LaSalle One

,DATE OCTOBER 10. 1985 REPORT N0 NTH SEPTIDesR 1985 *

' COMPLETED BY James P. Peters TELEPHONE (815)357-6761

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METHOD OF i TYPE SHUTTING DOWN ;

F: FORCED DURATION THE REACTOR OR , CORRECTIVE NO. DATE S: SCHEDULED (HOURS) REASON REDUCING POWER ' ACTIONS /COf9 TENTS I r I .

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E. UNIQUE REPORTING R8QUIREMENTS l

1. Safety / Relief valve operations for Unit One.

VALVES NO & TYPE PLANT DESCRIPTION DATE ACTUATED ACTUATION _ CONDITION OF EVENT There were no Safety Relief Valves Operated for Unit One during this reporting period.

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. 2. ECCS Sy::tems Outtge3 The following outages were taken on ECCS Systems during the reporting period.

OUTAGE NO. EQUIPMNT PURPOSE OF OUTAGE I 1-743-85 "1A" RHR Hx Chemical Cleaning.

(Shell Side) 1-744-85 "1A" RHR Hx Chemical Cleaning.

! (Tube Side) 1-747-35 "1A" RHR Hx. Chemical Cleaning.

1 *l52-85 "1B" HHR Hx Chemical Cleaning.

(Shell side)-__. _

.{ 1-753-85 "1B" RHR Hx Chemical Cleaning.

(Tube side) i 1-754-85 "1B" RHR Hx Chesatcal Cleaing.

1-755-85 "1B" RHR WS Repair Valve 1E12-F0148

1-760-85 NCIC Valves Repair Valves j 1E51-F331/332 1-766-85 1E22-F012 LIS-HP-105 i 1-767-85

i 1-770-85 1D001PA Polarization Index.

1-773-85 "1A" RHR Hx Draining Heat Exchanger 1-779-85 1812-F064C Valve Bad Switch 1-781-85 1HP08D Remove Section of Pipe.

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3. Off-Sito Dose Calculction Manual There were no changes to the off-site dose calculation Manual during this reporting period.
4. Radioactive Waste Treatment Systems.

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

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LASALLE NUCLEAR POWER STATION UNIT 2 MONTHLY PERFORMANCE REPORT SEPTEMBER 1985 COlm0NWEALTH EDISON COfWANY ,

WRC DOCKET NO. 050-374 LICENSE NO. NPF-18 [

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t DOCUMENT ID 0036r/000Sr L._. _- __ _ ________ _ _ - _ . _ _ _ - - _ - _ _ _ _ _ - _ _ - - - _ - - _ _ - - _ _ - - - - - - - - . _ - - - - - - . - . - --- -

I. INTRODUCTION l

The LaSalle County Nuclear Power Station is a two-unit facility owned by Commonwealth Edison Company and located near Marseilles, Illinois. Each unit is a Boiling Water Reactor with a designed net electrical output of 1078 Megawatts. Wacte heat is rejected to a 4 man-made cooling pond using the Illinois River for make-up and blowdown. The architect-engineer was Sargent and Lundy, and the primary construction contractor was Ceaumonwealth Edison company.

Unit two was issued operating license number NPF-18 on December 16, 1983. Initial criticality was achieved on March 10, 1984, and commercial power operation was ccommenced on June 19, 1984.

i This report was compiled by James P. Petern, telephbtie ' ~+ - - - -

number (815)357-6761 extension 325.

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TABLE OF CONTENTS I. INTRODUCTION II. MONTHLY REPORT FOR UNIT TWO A. Suussary of Operating Experience B. PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS, AND SAFETY RELATED MAINTENANCE

? 1. Noendments 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

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C. LICENSEE EVENT REPORTS D. DATA TABULATIONS 1

l 1. Operating Data Report

2. Average Daily Unit Power Level
3. Unit shutdowns and Power Reductions i 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

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II. AONTHLY REPORT POR UNIT TWO A. SUtnutY OF OPERATINC EXPERIENCE FOR UNIT TWO September 1-31 Sept. 1, 0001 Hours. The Unit entered September with

the Reactor critical at 100% Power i

and generator on-line at 1089 We-net.

Sept. 1, 0345 Hours. Bottomed out at 86% Power (929 We-net) Per Load Dispatcher.

Sept. 1, 2300 Hours. Reactor Power Steady at 100%, 1086 We-net.

Sept. 2, 0515 Hours. Power Decension stopped at 85%,

920 We-net.

Sept. 2, 1930 Hours. Power Acension Complete to 100%,

1087 MWe-net.

Sept. 4, 0230 Hours. Power leveled off at 89%, 960 We-net.

Sept. 4, 0500 Hours. Reactor Power Bottomed out at 70%,

750 MWe-net per load dispatcher.

Sept. 4, 2300 !!ours. Reactor -Ps'.Jer-at-974. - 10W -- -

MWe-net.

Sept. 5, 0200 Hours. Power Leveled out at 71%, 770 MWe-net.

Sept. 5, 0445 Hours. Bottomed out at 62% Power, 670 MWe-net.

Sept. 5, 0700 Hours. Reactor Power at 85%, 920 MWe-net.

Sept. 5, 2300 Hours. Reactor Power at 94%, 1025 MWe-net.

Sept. 9, 0245 Hours. Reactor Power comunenced to 100%, j 1073 HWe-net.

Sept. 9, 0445 Hours. Reactor Power at 72%, 775 MWe-net.

Sept. 9, 0635 Hours. Reactor Power at 88%, 950 MWe-net.

Sept. 9, 1500 Hours. Reactor Power at 98%, 1060 MWe-net.

Sept. 10, 0230 Hours. Reactor Power at 83%, 900 MWe-net.

Sept. 10, 1000 Hours. Reactor Power at 98%, 1060 MWe-net, Held for Tip Traces.

Sept. 10, 2000 Hours. Reactor Power at 100%, 1097 MWe-net.

Sept. 12, 2105 Hours. Reactor Power at ~11%, 760 MWe-net due to TDRFP Failure.

Sept. 12, 2200 Hours. Reactor Power at 81%, 850 MWe-net Held for Radiation Work.

1 Sept. 13, 1630 Hours. Comumenced Load Drop at 120 MWe/hr. For Entry into Steam Tunnel.

Sept. 13, 1835 Hours. Reactor Power at 56%, 600 MWe-net. '

Sept. 13, 2030 Hours. Reactor Power at 70%, 750 MWe-net Held For Load Dispatcher.

Sept. 14, 0100 Hours. Reactor power at 79%, 850 MWe-net Per Load Dispatcher.

DOCUMENT ID 0036r/0005r

Sept. 14, 0500 HourO. R: actor Power ct 63%, 675 MWe-net.

. Sept. 14, 0900 Houra. R:act r Power ct 79%, 850 MWe-net Per Load Dirp tch2r.

Sept. 15, 0600 Hours. Reactor Power Commenced to 76%,

820 MWe-net Per Load Dispatcher.

Sept. 17, 0700 Hours. Reactor Power at 96%, 1060 MWe-net.

Sept. 17, 2300 Hours. Reactor Power at 56%, 600 MWe-net.

Sept. 18, 0700 Hours. Reactor Power at 65%, 700 MWe-net and Held for Tip Traces.

Sept. 20, 1500 Hours. Reactor Power at 100%, 1100 MWe-net.

Sept. 21, 0500 Hours. Reactor Power at 96%, 1038 MWe-net Per Load Dispatcher.

Sept. 22, 0430 Hours. Reactor Power at 100%, 1075 MWe-net Per Load Dispatcher.

Sept. 22, 0500 Hours. Reactor Power Commenced to 82%,

880 MWe Per Load Dispatcher.

Sept. 22, 1850 Hours. Reactor Power at 100%, 1080 MWe-net.

Sept. 23, 2300 Hours. Reactor Power at 99%, 1096 MWe-net.

Sept. 24, 0330 Hours. Reactor Power Commenced to 79%,

.. . . , __ , 850 MWe-net per EGC Test.

Sept. 27, 0600 Hours ~ Reactor Power at 100%, 1112

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MWe-net.

Sept. 27, 1930 Hours. Reactor Power at 96%, 1040 MWe-net for control Rod Manipulation.

Sept. 30, 2400 Hours. Reactor Power at 100%, 1112 MWe-net.

DOCUMENT ID 0036r/000$r

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

1. Amendments to facility license or Technical Specifications.

Amendment 13- Extension of Diesel "lA" 18 Month Surveillance to First Fueling Cycle.

Amendment 25- Extension of One 18 Month Surveillance to First Fueling Cycle.

2. Facility or procedure changes requiring NRC approval.

Yes, the LaSalle Emergency Procedures (LGA-01 Through 05 and LGA-ATVS-01 Through 05) were written from Guidelines Developed at LaSalle Based on the BWROG Emergency Procedure Guidelines.

3. Tests and experiments requiring NRC approval.

There were no tests or experiments requiring NRC approval during the reporting period.

4. Corrective Maintenance of Safety Related Equipment.

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

DOCUMENT ID 0036r/0005r

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1 TABLE 1 l 00RRECTIVE MAINTENANCE OF SAFETY RELATED SQUIPfEENT ,

UDRK R9 QUEST COWONENT CAUSE OF MALFUNCTION RESULTS AND EFFECTS CORRECTIVE ACTION ON SAFE PLANT OPERATION L51278 Scram Discharge Volume Did Not Close Fully When Redundant Valves In Series, Machined New Spring Button valve 2Cll-F380. Tested. No Loss of System Function. Out of Carbon Steel.

L51346 Rx Vessel Low Pressure Stripped Tubing at Test Rendered Instrument Inoperable. Replaced Valve and LPCS/LPCI Injection Tap. Test Tap Tube Fittings. s Valve Permissive. ,'

L51515 LPRM 40-09A 100VDC Bad Power Supply FailureofLI(-NR-211. Replaced Power Supply.

Power Supply.

L51538 SBGT Manual Deluge Valves Leaking From Packing 7-Day Time Clock for Repairs. Repaired Valves.

Valves. 1 i

l L51672 Torque switch on valve Stripped Screw on Torque Inappropriate lvalveMovement. Replaced Torque Switch. t

'2E12-F049A. Switch.

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L i L51719 Div.-II Post Loca Failed Vacuum Pump. During LOS-AA--iHt Recorder Replaced Vacuum Pump.

02 Monitor 2 AIR- Operated Sporddically.

01048.

LS1802 APRM *F" 2C51-K605GT Bad Power Supplies 4,8,19, APRM "F" Caus4d Spurious 1/2 Replaced Power Supplies 20 and 24. Also Bad Relay Scrams. and Relay.

K12.

L51825 Remote Shutdown Panel Level Difference of 21" Failed Surveillance LOS-RX-M1. "B" Loop Transmitter Post Loca Level tihen Allowable is + 10". 2B21-N026BA was replaced.

l 2821-W026BA. "B" Loop Transmitter l 2B21-N026BA Failed.

l l L51911 Accumulator 42-85 .vsive Leaks by at stem. Depressurizing Accumulator Replaced Damaged Stem Instrtament Block 42-85. Packing and "O-Ring. ,

Valve 2C11-Flll.

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.4 TABLE 1 CORRECTIVE MAINTENANCE OF ,

SAFETY RELATED EQUIPMENT j ,

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WORK REQUEST CONONENT CAUSE OF MALFUNCTION RESULTS AND EFFECTS CORRECTIVE ACTION ON SAFE PLAh OPERATION

! L52040 DG Cooler Upstream Contacts Improperly Wired. When Control Switch is Taken DCR-85-185 issued to Stop. 2DG035. to Open (Valve already open) correct prints.

The Valve Will Close.

L52086 RHR Pump 2C Minimum Broken Tripper Fingers Could not be ' manually operated. Replaced Tripper Fingers.

Flow Bypass Valve to Valve Actuator.

! 2E12-F064C.

  • l L52235 Division II Battery Bad Float Potientiometer. Any Adjustments made on Replaced Float Pot-l Charger 2DC16E. Potientiometer, Charger Does lentiometer.

Not Trip. Current Goes To Zero And Drawa Off Batteries. -

i L52347 ~2B" DG Cooling Water Screws in Breaker handle Breaker Does Not operate with Replaced with app-Pump Breaker 243-1, too Long. no light indication. ropriate screws.

  • Compt.-10.

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, C. ' LICENSEE EVENT CEPORTS The following is a tabular sununary of all licensee event reports for LaSalle Nuclear Power Station, Unit Two, lagged during the reporting period, September 1 through September 30, 1985. This information is provided pursuant to the reportable occurrence reporting requirements as set forth in 10CFR 50.~13.

Licensee Event Report Number Date Title of Occurrence There were no Licensee Event Reports Logged for this reporting period.

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! D. DATA TA8ULATIONS l 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 f i 4 ,

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' 1. OPERATING DATA REPORT DOCKET NO. 050-374 UNIT LaSalle Two i

DATE October 10, 1985 COMPLETED BY James P. Peters TELEPHONE (815)357-6761 OPERATING STATUS 4

1. REPORTING PERIOD: September,1985 GROSS HOURS IN REPORTING PERIOD: 720
2. CURRENTLY AUTHORIZED POWER LEVEL (MWt):3323 MAX DEPEND CAPACITY j (Nde-Net): 1036 DESIGN ELECTRICAL RATING (MWe-Net): 1078
3. POWER LEVEL TO WHICH RESTRICTED (IF ANY) (MWe-Net): N/A
4. REASONS FOR RESTRICTION (IF ANY)
N/A THIS MONTH YR TO DATE CUMULATIVE 5 NUMBER OF HOURS REACTOR WAS CRITICAL 720 3066.3 4678.1
6. REACTOR RESERVE SHUTDOWN HOURS 0.0 64.1 189.4
7. HOURS GENERATOR ON'LINE 720 3015.3 4552.7

! 8. UNIT RE3ERVE SHUTDOWN HOURS 0.0 0.0 0.0

! 9. GROSS THERMAL ENERGY GENERATED (MWH) 2161656 8956486 13464078 l' 10. GROSS ELEC. ENERGY GENERATED (MWH) 712742 2949289 4434275

11. NET ELEC. ENERGY GENERATED (MWH) 686191 27 % 091 4188408 e L._____ 12. . REACTOR SERVICE FACTOR 100% 46.8% ^.

56.0%

l 13. REACTOR AVAILABILITY FACTOR 100% 47.84 ~58.2C ~ ~ ~~"~ ~~ ~~ '

14. UNIT SERVICE FACTOR 100% 46% 54.5%

l 15. UNIT AVAILABILITY FACTOR 100% 46% 54.5%  ;

16. UNIT CAPACITY FACTOR (USING MDC) 91.9( 41.2% 48.4%

3

17. UNIT CAPACITY FACTOR (USING DESIGN __88.4% __39.6% 46.5%

Nde)

18. UNIT FORCED OUTAGE RATE 0.0% 2.5% 6.5%

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

l An Outage is scheduled on November 30, 1985 for 2 weeks to complete l unfinished EQ (Enviromental Qualification) Modifications and Limitorque i Upgrade.  !

20. IF SHUT DOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP N/A 1

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{ DOCUMENT ID 0036r/0005r

2. AVERAGE DAILY UNIT POWER LEVEL DOCKET NO: 050-374 UNIT: LASALLE'NO DATE: October 10. 1985 COMPLETED BY: James P. Peters TELEPHONE: (815) 357-6761 MONTH: August 1985 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net)
1. 987.25 17. 1022.4
2. 1003.1 18. 695.1 3 1049.8 19. 887.8
4. 941.8 20. 1029.6
5. 899.3 21. 999.4
6. 1019.3 22. 991.7

.y,-.---~ -1016.2- - -

-23. -

%7.0 ._. ..

8. 1026.3 24, 953.3
9. 991.8 25. 863.9
10. 993.9 26. 936.75
11. 1039.4 27. 104b.1
12. 1004.8 28. 1038.5
13. 775.6 29. 1033.5
14. 782.2 30. 1038.1
15. 724.8 31. N/A
16. 832.9 i

DOCUMENT ID 0036r/0005r

ATTACHMENT E ,

3. UNIT SHUTDOWNS AND POWER REDUCTIONS
  • DOCKET NO.- 050-374 '*

UNIT NAME LaSalle Two Dr.TE October 10. 1985 REPORT MONTH SEPTEMBER 1985 COMPLETED BY James P. Peters TELEPHONE (815)357-6761 METHOD OF TYPE SHUTTING DOWN F: PORCED DURATION THE REACTOR OR CORRECTIVE NO. DATE S: SCHEDULED (HOURS) REASON REDUCING POWER ACTIONS /COfMENTS 8 850912 F 0.0 A 5 'oss of "A" TDRFP.

9 850913 S 0.0 F 1 Allow Personnel Entry Into Steam Tunnel.

10 850918 S 0.0 F 1 Power Reduction Ordered by Load Dispatcher.

i

! DOCUMENT 0044r/0005r

, ' E. UNIQUE REPORTING REQUIREMENTS Safety / Relief Valve Operations for Unit Two.

'l.

l DATE VALVES NO & TYPE PLANT DESCRIPTION

! ACTUATED ACTUATIONS CONDIT7.O_N OF EVENT 4

There were no Safety Relief Valves operated for Unit #2 during this reporting period.

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'. s DOCUMENT ID 0036r/0005r

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

OUTAGE NO. EOUIPMENT PURPOSE OF OUTAGE 2-1162-85 2E12-F049A Environmental Qualification (EQ Mcd) 2-1164-85 2E12-F026B EQ Mod 2-1165-85 HPCS D/G Peiter Diesel Repair Valve 2-1171-85 2E12-F003B EQ Mod 2-1173-85 PS 2B21-N413B Fix Test Tap Valve 2-1174-85 PS 2B21-N413D Fix Test Tap Valve 2-1175-85 PS 2B21-N413B Replace Valve 2-1176-85 PS 2B21-N413D Replace Valve i 2-1178-85 2E21-F011 EQ Motor Replace 2-1179-85 2B12-F047B EQ Motor Mod 2-1180-85 2E12-F006A/64A EQ Mod 2-1182-85 2E22-F0ll Remove Section of Pipe 2-1184-85 2E12-F004 EQ Motor Mod 2-1189-85 2E12-F064C EQ Mod 2-1190-85 2E12-F064C Repair Engaging Lever 2-1191-85 2E22-C002 Polarization Check.

j 2-1192-85 2DG01P Polarization Check 2-1193-85 2E12-F006B Replace Motor 2-1194-85 2E12-F064B Replace Motor 2-1195-85 2E12-F004B Replace Motor 2-1196-85 2E12-F027B Replace Motor 2-1208-85 LPCS Pump Change Oil

.2-1209-85 "2A" DG Change 1st Stage B Compressor Relief Discharge Valve.

DOCUMENT ID 0036r/0005r

t'

. $-1210-85 "2A" DG 3 WIy solcnoid RLplEca Solinoid

.* 2-1211-85 "2A" DG B Compressor Relief Repair Relief 1218-85 2B12-F012 Replace Motor 2-1219-85 2B DG Troubleshoot Alarm

Circuit.

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I DOCUIENT ID 0036r/0005r

4

, 3. Off-Sito Dos 3 C31culation Manu21

6 There were no changes to the off-site dose calculation manual during 4

this reporting period.

4. Radioactive Waste Treatment Systems.

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

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1 DOCUMENT ID 0036r/0005r l l

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1 Commonwealth Edison

/ _._

') LaSalle County Nuclear Station l -

4 RuralRoute #1, Box 220

\ -

/ Marseilles, Illinois 61341

( / Telephone 815/357 6761 October 10, 1985 Director, Office of Management Information and Program Control United States Nuclear Regulatory Comission Washington, D.C. 20555 ATTN: Docu:;ent Control Desk Centlemen:

Enclosed for your information is the monthly performance report covering LaSalle County Nuclear Power Station for the period August 1 through August 31, 1985.

Very truly yours,

,9'l A N' Gl J. Diederich Station Manager LaSalle County Station GJD/RJR/cth Enclosure xc: J. G. Keppler, NRC, Region III NRC Resident InFpector 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 J. E. Ellis, GE Resident J. M. Nowicki, Asst. Comptroller H. E. Bliss, Nuclear Fuel Services Manager C. F. Dillon, Senior Financial Coordinator, LaSalle Document 0043r/0005r (1

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