Text

Monthly Operating Repts for Apr 1985
	ML20117N731
Person / Time
Site:	LaSalle
Issue date:	04/30/1985
From:	Diederich G, Rohrer R; COMMONWEALTH EDISON CO.
To:	; NRC OFFICE OF ADMINISTRATION (ADM), NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
	NUDOCS 8505170641
	Download: ML20117N731 (32)
	v • d • e

.

- f,n .

s , hh * $ b LASALLE NUCLEAR POWER STATION UNIT 1 MONTHLY PERFORMANCE REPORT APRIL 1985 COfMONWEALTH EDISON COMPANY NRC DOCKET NO. 050-3~13 LICENSE NO. NPF-ll B505170641 850430 PDR ADOCK 05000373 -

R pop l

rt g'

Document 0043r/0005r

i

'/ W d TABLE OF CONTENTS I. INTRODUCTION j II. MONTHLY REPORT FOR UNIT ONE l

A. Summary of Operating Experience l

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

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 .

1 C. LICENSEE EVENT REPORTS l 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

P '* e I. INTRODUCTION The LaSalle County Nuclear Power Station is a two-unit facility owned by commonwealth 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 an artificial cooling pond using the Illinois River for make-up and blowdown. The architecht-engineer was sargent and Lundy, and the primary construction contractor was commonwealth Edision company.

Unit one was issued operating license number NPF-11 on April 17, 1982. Initial criticality was achieved on June 21, 1982, and commercial power operation was commenced on January 1, 1984.

This report was compiled by Richard J. Rohrer, telephone number (815)357-6761 extension 575.

Document 0043r/0005r

1

f. ., .

II. MONTHLY REPORT FOR UNIT ONE A. SUtttARY OF OPERATING EXPERIENCE FOR UNIT ONE l Boril 7-11 )

l April 7, 1515 hours0.0175 days 0.421 hours 0.0025 weeks 5.764575e-4 months - Reactor Critical '

April 8, 0830 hours0.00961 days 0.231 hours 0.00137 weeks 3.15815e-4 months - Generator Synchronized to the grid i I

April 10, 2300 hours0.0266 days 0.639 hours 0.0038 weeks 8.7515e-4 months - Reactor power at 81%.

April 11, 2235 hours0.0259 days 0.621 hours 0.0037 weeks 8.504175e-4 months - Reactor scram on turbine trip due to high vibration on bearing number 11.

The reactor had been critical for 103 hours0.00119 days 0.0286 hours 1.703042e-4 weeks 3.91915e-5 months and 20 minutes in April.

April 13-20 April 13, 0212 hours0.00245 days 0.0589 hours 3.505291e-4 weeks 8.0666e-5 months - Reactor Critical.

April 13, 0900 hours0.0104 days 0.25 hours 0.00149 weeks 3.4245e-4 months - Generator Synchronized to the grid.

April 14, 2300 hours0.0266 days 0.639 hours 0.0038 weeks 8.7515e-4 months - Reactor power at 71%

April 15, 0345 hours0.00399 days 0.0958 hours 5.704365e-4 weeks 1.312725e-4 months - Reactor power reduced to 57% in order to manipulate control rods.

April 17, 0700 hours0.0081 days 0.194 hours 0.00116 weeks 2.6635e-4 months - Reactor power at 93%.

April 21, 1130 hours0.0131 days 0.314 hours 0.00187 weeks 4.29965e-4 months - Reactor power reduced to 75% in order to manipulate control rods.

April 22, 2300 hours0.0266 days 0.639 hours 0.0038 weeks 8.7515e-4 months - Reactor power at 99%.

April 28, 0140 hours0.00162 days 0.0389 hours 2.314815e-4 weeks 5.327e-5 months - Reactor power reduced to 53% in order to manipulate control rods.

April 30, 2300 hours0.0266 days 0.639 hours 0.0038 weeks 8.7515e-4 months - Reactor power at 98% i The reactor was critical for a total of 532 hours0.00616 days 0.148 hours 8.796296e-4 weeks 2.02426e-4 months and 8 minutes in April.

i

< l l

1 i

l l

Document 0043r/0005r l

1

a

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

1. Amendments to facility license or Technical Specification.

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

2. Facility or procedure changes requiring NRC approval.

There were no facility or procedure changes requiring NRC approval during this reporting period.

3. Tests and Experiments 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 summary of safety-related maintenance completed on Unit One during the reporting period. The headings indicated in this sununary include: Work Request number, Component Name, cause of Malfunction, Results and Effects on Safe Operation, and Corrective Action.

Document 0043r/0005r

TABLE 1 CORRECTIVE MAINTENANCE OF .

SAFETY RELATED BQUIpMENT WaaK REQUEST COMONENT CAUSE OF MALFUNCTION RESULTS AND EFFECTS CORRECTIVE ACTION

ON SAFE OPERATION L48035 Outboard Feed Water Air leak on supply to Possibility to hinder attempts Repaired leak. .

Check Valve "B" solenoid valve. to open this valve using air ,

pressure.

L46617 Diesel Generator "A" Malfunctioning shutdown Could not shutdown diesel. Repaired and adjusted .

solenoid. shutdown solenoid.

L48043 RHR "B" Full Flow Limit switches out of Loss of "Open" indication. Adjusted limit switches Test Valve. adjustment.

L47883 Deluge Valves to Unit Leaking Valve. Water leaked into charcoal Rebuilt deluge valves One SBGT train. causing possibly degraded SBGT and leak tested charcoal.

performance.

L26507 Outboard Feed Water Limit switches out of Improper Valve position Adjusted limit switches.

Check Valve "A". adjustment. indication.

L265% Outboard Feed Water Limit switches out of Improper Valve position Adjusted limit switches.

j Check valve "B". adjustment. indication.

l L47827 ADS Valve Recorder Faulty equipment. Temperature indicated upscale. Repaired faulty l point Number 19. equipment.

, L48158 Division II Post Monitor out of calibration Incorrect indication of Hydrogen Recalibrated Monitor.

I Hydrogen and Oxygen and Oxygen Concentration.

Monitor.

f L48075 Division I Post LOCA Monitor out of calibration Incorrect in61 cation of Hydrogen Recalibrated Monitor Hydrogen and Oxygen and Oxygen concentration.

Monitor.

L48199 Control Rod 22-43. Faulty equipment. Rod periodically tripped. Repaired faulty equipment.

i i

DOCUMENT 0044r/0005r

TABLE 1

~'

mee8CTIVE MRINTENANCE' OF '

SAFETY RELATED BQUIPIENT WORK R8 QUEST C0ff0NENT CAUSE OF MRLPUNCTION RESULTS AND EFFECTS CORRBCTIVE ACTION , . .

ON SAFE OPERATION RHR "B" Flow L48041 Out of calibration. No flow indication. Recalibrated Transmitter. Transmitter.

L48412 Ammonia Detector for Faulty cassette mechanism Alarmed continuously. Repaired cassette "A* Control Room mechanism.

HVAC train.

L48031 Feed Water Stop Fauly Valve. Valve would not close. Repaired valve.

Valve "A" L47804 Outboard Feed Water Faulty seats., Eccessive leakage. Changed seats.

Check valve "B" L48167 NCU Accumulator for Leaking isolation valve. Potential to cause failure to Replaced valve.

CRD 38-55. scram this rod if combined with other events.

L48037 HCU Accumulator for Leaking isolation valve. Potential to cause failure to Replaced valve.

CRD 02-43. scram this rod if combined with other events.

L47803 Inboard Feed Water Faulty Valve. Exessive leakage. Repaired Valve.

Check Valve "A" DOCUMENT 0044r/0005r

. ,- a 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, April 1 through April 30, 1985. 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 85-027-00 3-13-85 Unsecured High Radiation Area 85-028-00 3-27-85 Three Safety Relief Valves opened and reactor scrammed on low level.

85-029-00 3-21-85 Reactor Scram due to Instrument valving error.

. 85-030-00 3-25-85 Ammonia Detector ESF Actuation.

85-031-00 3-11-85 Discharge of Radwaste Discharge Tank 2WF05T with incorrect Setpoint.

85-032-00 3-28-85 Inboard Feedwater Check Valve Local Leak Rate Test Failure 85-033-00 4-2-85 Missed Noble Gas Sample for Unit One standby Gas Treatment System.

85-034-00 3-30-85 1812-F009 Valve Isolation.

85-035-00 4-11-85 Main Turbine High Vibration Trip and Reactor Scram.

85-036-00 4-3-85 Shutdown Cooling System Isolation on Suction Line High Flow Document 0043r/0005r

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

i

1. Operating Data Report

2. Average Daily Unit Power Level

3. Unit Shutdowns and Power Reductions 2

L 1

i l

l l

f l

l l

l f Document 0043r/0005r i

i t

- - . - -, . . - . - - --. - - . , , , . - , , . . - _ _ -- - , . . . _ -.n.- . .-- , .. , . - . .- - . - , , , -. -- .- - -

~

. f. OPERATING DATA REPORT DOCKET NO. 050-373 UNIT LaSalle One DATE May 9, 1985 COMPLETED BY Richard J. Rohrer TELEPHONE (815)357-6761 OPERATING STATUS

1. REPORTING PERIOD: April, 1985 GROSS HOURS IN REPORTING PERIOD: 719

c. 2. - CURRENTLY AUTHORIZED POWER LEVEL (MWt):3323 MAX DEPEND CAPACITY l (MWe-Met): 1036 DESIGN ELECTRICAL RATING (MWe-Net):1078

3. POWER LEVEL TO WHICH RESIRICTED (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 532.1 2302.2 8583

6. REACTOR RESERVE SHUTDOWN HCUES 27.6 98.6 1265

7. HOURS GENERATOR ON LINE 508.1 2229.4 8285

8. UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 0.0

9. GROSS THERMAL ENERGY GENERATED (MWH) 1407910 6249577 23072866

10. . GROSS ELEC. ENERGY GENERATED (MWH) 460260 2064310 7534953

11. NET ELEC. ENERGY GENERATED (MWH) 443442 1984684 7179746

12. REACTOR SERVICE FACTOR 74.0% 79.3% 73.4%

13. REACTOR AVAILABILITY FACTOR 77.8% 82.% 84.3%

14. UNIT SERVICE FACTOR 70.% 76.8% 70.9%

15. -UNIT AVAILABILITY FACTOR 70.M 76.8% 70.9%

16. UNIT CAPACITY FACTOR (USING MDC) 59.5% 66.0% 59.3%

17. UNIT CAPACITY FACTOR (USING DESIGN 4

MWe) 57.2% 63.4% 57.0%

18. UNIT FORCED OUTAGE RATE 29.3% 15.1% 14.%

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

Unit one is scheduled for a refueling, maintenance, modification, and surveillance outage beginning September 3, 1985 and lasting 26 weeks.

l20. IF SHUT DOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP: N/A 1

4 t

Document 00$3r/0005r

.-....-_,__-,..-_-.._._,u.........._.....,--,, _. - _ _ _ . _ _ , . . , . , _ _ . , _ . _ . _ - - _ .

~

.' f. AVERAGE DAILY UNIT POWER LEVEL DOCKET NO: 050-373 UNIT: LASALLE ONE DATE: May 9, 1985 COMPLETED BY: Richard J. Rohrer TELEPHONE: (815) 357-6761 MONTH: APRIL, 1985 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net)

1. -14 17. 1000

2. -13 18, 995 3 -14 19. 1046

4. -14 20. 1039

5. -15 21. 910

6. -16 22. 1010

7. -15 23. 1073

8. 124 24. 1052

9. 527 25. 1045

10. 787 26. 1028 -

11. 721 27, 1027

12. -14 28. 701 13, 309 29. 876

14. 716 30. 1020

15. 747

16. 836 Doctament 0043r/0005r

ATTAOWEENT E- .,.

~

3. UNIT SHUTDOWNS AND POWER REDUCTIONS .

DOCKET NO. 050-373 ' -

UNIT NAfEt LaSalle One .,

DATE May 9. 1985 REPORT MONTH April 1985 COMPLETED BY Richard J. Rohrer TELEPHONE (815)357-6761 i

METHOD OF TYPE SHUTTING DOWN ,

F: FORCED DURATION THE REACTOR OR CORRECTIVE NO. DATE S: SCHEDULED (HOURS) REASON REDUCING POWER ACTIONS /COf9EENTS 6 850321 F 176.50 G 3 Continuation of outage begun on March 21, 1985. Reactor Scrasumed on Low Vessel Level and High vessel pressure sismals due to a valving error during installation of an Environnental Qualification Modification.

7 850411 F 34.42 A 3 Reactor scram on Turbine trip due to high vibrations in bearing number 11.

8 850428 S 0.00 H 1 Power reduced to manipulate control rods.

DOCUMENT 0044r/0005r

, o .s E. UNIQUE REPORTING REQUIREMENTS

1. Safety / Relief valve operations for Unit One. .

VALVES NO & TYPE PLANT DESCRIPTION DATE ACTUATED ACTUATION CONDITION- OF EVENT 4-11-85 IB21-F013E 1 Automatic 978 psig Actuated to relieve Pressure following reactor scram.

4 i

i f

t J

Doctament 0043r/0005r 4

-, ,-,y-, .....,w.,,,------p,. ,---- - - - - , %. , - - v--,-,m,,--- ,-p-.me----.,-----.- v.,, .- , -,-, +---,. .- , - , - ~,-. --= .

,' 2. ECCS Syh:tems Outtges The following outages were taken on ECCS Systems during the reporting period.

OUTAGE NO. BOUIPMENT Pt'RPOSE OF OUTAGE 0-265-85 Diesel Generator "0" Replace Puffer Pistons.

Feed Breaker 0-266-85 Diesel Generator "0" Inspection 0-267-85 ' Diesel Generator "0" Recalibration 0-268-85 ODOO1P Surveillance 0-269-85 Diesel Generator "0" Lubrication 0-270-85 Diesel Generator "0" Recalibrations 0-272-85 Diesel Generator "0" Lubrication Air Compressors 0-278-85 Diesel Generator "0" Repair Air Start Solenoid 1-319-85 1E12-N010CA/CB Repipe switches 1-320-85 1E22-N012 A/B Repipe Switches 1-326-85 1DG08CB Repair Fitting 1-345-85 1E12-F024B Repair Limit Switches 1-355-85 LPCS Minimum Flow Technical Specification valve Requirement 1-366-85 1812-F053A Technical Specification Requirement 1-367-85 1812-F053A Environmental. Qualification Modification (BQ Mod).

1-377-85 1E21-N004 Rotate Switch 1-378-85 LPCS Minimum Flow Technical Specification valve Requirement.

1-383-85 1E12-C003 Lubrication 1-385-85 Shutdown Cooling Requirement of Special Suction Header Test LTS-85-45.

Document 0043r/0005r

. .' OUTAGE NO. ROUIPMENT PURPOSE OF OUTAGE 1-390-85 RCIC Remove Governor 1-391-85 RCIC 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 significant changes to the radioactive waste treatment system during this reporting period.

Document 0043r/0005r

T j

LASALLE NUCLEAR POWER STATION UNIT 2 MONTHLY PERPORMANCE REPORT APRIL 1985 i'

COIMONWEALTH EDISON COMPANY NRC DOCKET NO. 050-374 LICENSE NO. NPF-18 1

i DOCUMENT ID 0036r/0005r

TABLE OF CONTENTS I. INTRODUCTION II. MONTHLY REPORT FOR UNIT TWO 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 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 4 3. Off-Site Dose Calculation Manual Changes

4. Major Changes to Radioactive Waste Trestment System l

l l

t l

l l

i DOCUMENT ID 0036r/0005r i ,. . . , . . _ . . -. . . . , . - - . - . , , . . _ . . . _ .. . -. . . - - - . _ _ . , . . - - . - - - _ , . , _ _ _ . - . . . - , ..

I. INTRODUCTION 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. Waste heat is rejected to an artificial cooling pond using the Illinois River for make-up and blowdown. The architecht-engineer was Sargent and Lundy, and the primary construction contractor was connonwealth 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 commenced on June 19, 1984.

This report was compiled by Richard J. Rohrer, telephone number (815)357-6761 extension 575.

t DOCUMENT ID 0036r/0005r

. 1

.- ?. KI. MONTHLY REPORT POR UNIT TWO A. 'SUf91kRYOFOPERATINGEXPERIENCEFORUNITTWO APRIL 1-30

.The reactor was subcritical, and the generator was off-line for the entire month of April. Unit Two is in a schedled outage for maintenance, testing, and modifications.

J l

i t

l l

t i

l

(

DOCUMENT ID 0036r/0005r

, e' * ,

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

1. Amendments to facility license or Technical Specifications.

There were no amendments to the facility operating license or Technical Speciafications during this reporting period.

2. Facility or procedure changes requiring NRC approval. -

There were no facility or procedure changes requiring NRC approval during the reporting period.

3. Tests and experiments requiring NRC approval.

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

4. Corrective Maintenance of Safety Related Equipment.

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.

a DOCUMENT ID 0036r/0005r

i TABLE 1 CORRECTIVE MAINTENANCE OF SAFETY RELATED EQUIPMENT 2 WORK REQUEST COMPONENT CAUSE OF MALFUNCTION RESULTS AND EFFECTS CORRECTIVE ACTION

ON SAFE OPERATION -l L48422 5-Valve manifold for Plugged Equalizing line. Difficulty in calibration or Replaced 5-Valve manifold.

2E12-N010CB. maintenance of 2E12-N010CB. -

L4:202 RHE "B" Heat Exchanger Faulty indicator. Loss of position indication. Repaired indicator.

Vent Valve. .

L47681 Unit Two 250 Volt Gaps between batteries and Possible seismic ha::ard. Placed material batteries. side rails exceeded seismic between batteries specifications. and siderails.

L47325 MSIV Leakage Control Rotor and Finger base Would not operate. Replaced rotors and Valve. cracked. finger base.

L46895 RHR Temperature Dirty selector switch. Points 3,5, and 6 sporadically Cleaned selector switch.

Recorder. printed upscale.

L48304 Diesel Generator "A" Faulty relief valve. Sporadically cycling relief Repaired valve.

Air Compressor "B" valve.

L48026 LPCI Manual Injec- Broken Manual Actuator. Handwheel rotated without Repaired actuator.

tion Valve "A". stroking valve.

L40429 HCU Accumulator Leaking isolation valve Potential to cause failure to Cleaned valve and re-for CRD 22-55. and fitting. scram this rod if combined with placed fitting.

other events.

L43534 2E12-F064C Faulty packing. Valve leaked at packing. Repaired packing.

L46964 Reactor Well Drain Faulty Valve. Excessive leakage. Repaired valve.

Downstream Isolation Valve.

DOCUMENT 0044r/0005r

l

.s,, -

1 C. 5.ICENSEEEVENTREPORTS The following is a tabular sununary of all licensee event reports for 1.aSalle Nuclear Power Station, Unit Two, occurring during the reporting period, March 1 through March 31, 1985. This information h. provided l 1

pursuant to the reportable occurrence reporting requirements as set forth !

! l in 10CFR 50.73.

Licensee Event Report Number M Title of Occurrence 85-012-00 3-31-85 Inadvertant EHR Shutdown cooling Isolation.

85-013-00 3-28-85 Loss of Shutdown Cooling due to Group 6 Division 2 Isolation.

85-014-00 4-9-85 Spurious Division I Isolation of Shutdown Cooling.

85-015-00 4-1-85 Loss of Continuous Conductivity i Indication.

85-016-00 4-18-85 Missed Surveillance of 2551-F091.

85-01*l-00 4-13-85 Group VI Isolation.

85-018-00 4-13-85 Shutdown Cooling Isolation on Blown Fuse.

,i, l

l l

i DOCUMarr ID 0036r/0005r

~

, 1. .

I D. DATA TABULATICIf8 The following data tabulations are presented in this report:

1. Operating Data Report t

2. Average Daily Unit Power Level

3. Unit Shutdowns and Power Reductions t

1

(- ,.

i 4 l 1

4 i

2 DOCUMENT ID 0036r/0005r

, 6, ,

1. OPtRATING DATA REPORT DOCKET NO. 050-374 UNIT LaSalle TWO DATE May 9, 1985 COWLETED BY Richard J. Rohrer TELEPHONE (815)357-6761 OPERATING STATUS ,

1. REPORTING PERIOD: April, 1985 GROSS HOURS IN REPORTING PERIOD:_719

2. CURRENTLY AUTHORIEED POWER LEVEL (Wt):2}2), MAX DEPEND CAPACITY-- ,

(IRfe-Met): 1036 DESIGN ELECTRICAL RATING (MWe-Net):1078

3. PONetR LEVEL TO WICH RESTRICTED (IF ANY) (MWe-Net): N/A

-4. REASONS FOR REETRICTION (IF ANY):

THIS MONTH YR TO DATE CUMULATIVE 5 NUMBER OF HOURS REACTOR WAS CRITICAL 0.0 1399.8 3011.6

6. REACTOR RESERVE SHUTDONN HOUR 8 0.0 0.0 125.3

7. HOURS GENERATOR ON LINE 0.0 1397.3 2934.7

8. UNIT RESERVE SHUTDOW HOURS 0.0 0.0 0.0

9. GROSS THERMAL ENERGY GENERATED (MWH) 0.0 4387385 9894977

10. Gross ELEC. ENERGY GENERATED (MWH) 0.0 1460387 2945373

11. NET ELBC. ENERGY GENERATED (MWH) -8965 1391590.. 2783707

12. REACTOR SERVICE FACTOR 0.0% 48.2% 64.4%

13. REACTOR AVAILABILITY FACTOR 0.0% ,48.2% 67.0%

14. UNIT SERVICE FACTOR 0.0% 48.1% 62.7%

15. UNIT AVAILABILITY FACTOR 0.0% 48.1% 62.7%

16. UNIT CAPACITY FACTOR (USING IWC)_ -1.2% 46.3% 57.4%

17. UNIT CAPACITY FACTOR (USING DESIGN MWe) -1.2% 44.5% 55.2%

18. UNIT FORCED OUTAGE RATE 0.0% 0.0% 5.1%

19. SHUTDOWS SCHEDULED OVEN NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF BACH):

An outage for maintenance and surveillance was begun at 0520 on February 28, 1985.

20. IF SHUT DOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP 5-30 4 1

i 4

J DOCUMENT ID 0036r/0005r

1, $. AVERAGE DAILY UIIIT POWER LEVEL DOCKET NO: 050-374 UNIT: LASALLE TWO DATE: May 9. 1985 COMPLETED BY: Richard J. Rohrer TELEPHONE: (815) 357-6761 MONTH: April 1985 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net)

1. -14 17. -13

2. -12 18. -12 3 -13 19. -12

4. -13 20. -13

5. -14 21. -13

6. -15 22. -12

7. -14 23. -12

8. -14 24. -11

9. -12 25. -11

10. -12 26. -11

11. -13 27. -11

12. -13 28. -10

13. -13 29. -13

14. -13 30. -11

15. -13

16. -12 l

1 i DOCUMENT ID 0036r/0005r

1 ATTAC3SEENT E

3. UNIT SHUTDatets AIS POWER REDUCTIcefS ,,

DOCKET NO. 050-374 .

L2 FIT MAfE LaSa!Ie Ttso ..

DATE PmY 9, 1985 REPORT MutfTH APRIL 1985 CofFLETED BY Richard J. Rohrer TELEPH00sE (815)357-6761 IEETHOD OF TYPE SHUTTING DotAt F: PORCED DURATION THE NEAC' LOR OR CORMt1TIVE NO. DATE S: SCIIEDULED (IIOURS) REASON REDUCING POWER ACT10NS/COf99RNTS 3 850228 S 719.00 B 2 Maintenance and Surveillance Outage begun 2-28-85 continues DOCUIEDff 0044r/0005r

.A. .

o E. UNIQUE REPORTING REQUIREMENTS

1. Safety / Relief Valve Operations for Unit Two.

DRIE VALVES NO E TYPE PLANT DESCRIPTION ACTUATED ACTUATIONS CONDITION OF EVENT l

There were no safety relief valves actuated during this reporting period.

i DOCUMENT ID 0036r/0005r I

~-

? 2. BCCS Systems outcges The following outages were taken on ECCS Systems during the reporting period.

OUTAGE No. BOUIPMENT PURPOSE OF OUTAGE 2-487-85 RCIC Trip and Throttle Repack Limit Switch Valve.

2-515-85 2E12-N010B and Environmental Qualification 2E12-N015B Modification (EQ Mod).

2-516-85 2E12-N015C and BQ Mod 2E12-N010C 2-517-85 2B12-N016B and EQ Mod 2B12-N019B 2-518-85 2E12-N016 C and BQ Mod 2E12-N019C 2-519-85 Division II. Equipment Protection and Technical Specification Requirement.

2-528-85 RCIC transmitter. EQ Mods.

2-532-85 2E12-F065A Reposition Solenoid.

2-533-85 2E12-F065B Replace Solenoid.

2-534-85 2E51-F054 Reposition Solenoid 2-535-85 2E12-F064C Repack Valve.

2-536-85 Residual Heat Removal Change Oil.

"C" 2-537-85 Diesel Generator "A" Calibration.

2-538-85 Diesel Generator "A" Inspection 2-539-85 Disel Generator "A" Inspection 2-540-85 Diesel Generator "A" Replace Puffer Piston.

Feed to Bus 242Y.

2-541-85 Diesel Generator "A" Lubrication.

DOCUMENT ID 0036r/0005r

. _ _ . _ . .. . _ _ _ . _ . . . _. _ __ _ _ _ _ _ _ _ ~ _ . _ . . . - .. _ _

., QUTAGE NO.

50UIPimff PURPOSE OF QUTAGE [

2-542-85 Residual Heat Removal Cleaning "B" Service Water

!' Process Radiation

. Monitor 2-543-85 2R12-F006 A and B Verify Jumpers 2-544-85 Diesel Generator "A" Surveillance

, Fuel Oil Transfer Pump !

. 2-545-85 Diesel Generator "A" Lubrication l, Cooling Water Pump 2-547-85 Residual Heat Removal Repair Limitorque "B" Full Flow Test 1 valve.

3 2-548-85 Residual Heat Removal Repair Limitorque "B" Full Flow Test Valve.

2-553-85 2B22-F005 and 2R51-F066 Reposition Solenoids.

2-568-85 Division III Batteries. Paint battery rack.

4 i 2-579-85 Safety Relief Valve "B". Replace Valve 2-580-85 Safety Relief Valve "B" Replace Valve 2-581-85 Safety Relief Valve "R" Replace Valve.

2-582-85 Safety Relief Valve "R" Replace Valve.

2-587-85 Residual Heat Removal Surveillance "B" and "C" 2-588-85 Residual Heat Removal Lubrication I

"B" and "C" Water Leg i Pump.

t 2-590-85 Diesel Generator "A" Limit cycling.

Air Compressor "B" Relief Valve. 7 2-597-85 Diesel Generator "A" Repair Valve.

Air Compressor "B"

~

Relief Valve i

4 2-601-85 Residual Heat Removal Calibration '

"B" Minimum Flow Valve 2-606-85 HPCS Pump Inspect Coupling DOCUIENT ID 0036r/0005r

- - . _ . . . . . _ - . - . . _ _ . . . . ~ .. _ _ _ - _ _ , , _ . . . . ~ , _ _ . . , . _ _ _ _ _ _ , , , _ _ _ _ _ _ , _ , _ , , , , - _

.a , ,

CUTAGE NO.. EQUIPMENT PURPOSE OF OUTAGE 2-611-85 Diesel Generator "A" Repair Relief Valve Air Compressor "B" 2-623-85 Residual Heat Removal Surveillance "B" and "C" 2-639-85 2512-N010CB Replace 5-Valve Manifold 2-640-85 2E12-F064B Surveillance 2-647-85 Residual Heat Removal Replace Valve Manifold "C" Flow Transmitter 2-650-85 Shutdown Cooling Surveillance 2-652-85 2E12-F041C Replace Control Switch 2-664-85 2E21-F006 Reposition Solenoid l

2-667-85 LPCS Pump Repair Puffer Piston 2-668-85 2E12-N001 and BQ Mod 2E12-N009 2-669-85 2B12-N016A and EQ Mod 2E12-N019A 2-670-85 2E21-N004 50 Mod 2-674-85 2E12-N010A EQ Mod 2-676-85 Residual Heat Calibrations.

Removal "A" Shutdown Cooling.

2-677-85 Residual Heat Removal BQ Mod "A" Minimum Flow Valve 2-678-85 LPCS Minimum Flow EQ Mod Valve.

2-689-85 Residual Heat Removal Sample Oil Pump "A" 2-691-85 Diesel Oenerator "A" Repair relief valve Air Compressor "B" i

DOCUMENT ID 0036r/0005r

m .

et. . o*

[

3,. Off.-Sito Dose C01culCtion Manual l

l There were no changes to the off-nite dose calculations manual during this reporting period.

! [

4. Radioacttve Waste Treatment systems.

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

l l

E l

P l

l l

l t

f 1

l i

[

l DOCUMENT ID 0036r/0005r l_

~ -

o. - Co'mmon'w ealth Edison LaSalle County Nuclear Statcn Rural Route #1, Box 220 Marseilles, Illinois 61341 Telephone 815/357 6761 May 9, 1985 Director, Office of Management Information and Program Control United States Nuclear Regulatory Comission Washington, D.C. 20555 ATTN: Document Control Desk Centlement Enclosed for your information is the monthly performance report covering LaSalle County Nuclear Power Station for the period covering April 1 through April 30, 1985.

Very truly yours,

. Ab o J. Diederich Station Manager LaSalle County Station OJD/RJR/cth Enclosure Mc: J. G. Keppler, NRC, Region III WRC Resident Inspector LaSalle Gary Wright, Ill. Dept. of Nuclear Safety D. P. Galle, CRCo D. L. Farrar, CRCo IN19 Records Center Ron A. Johnson, PIP Coordinator UNED J. R. Ellis, OR Resident J. M. Nowicki, Asst. Comptroller // *f H. R. Bliss, Nuclear Fuel Services Manager ,P I

Document 0043r/000$r

ML20117N731

Text

Navigation menu

Search