ML20135B269

Monthly Operating Rept for June 1985

ML20135B269
Person / Time
Site:	LaSalle
Issue date:	06/30/1985
From:	Rohrer R COMMONWEALTH EDISON CO.
To:
References
NUDOCS 8509100497
Download: ML20135B269 (16)

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i LABALLE NUCLUR POWER STATION UNIT 2 MONTHLY PERP3RftANCE REPORT JtNE 1985 C09990NWEALTH EDISON COMPANY NRC DOCKET No. 0$0-374 e

LICENSE NO. NPF-18 l

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TABLE OF CONTENTS 1.

INTRODUCTION II.

MONTHLY REPORT FOR UNIT TWO A.

sumary of operating Experience B.

PLANT OR PROCEDURE CHANGES, 'tRSTS, EXPERIMENTS, AND BAFETY 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 REPCRTING REQUIREMENTS 1.

safety / Relief valve operations 2.

scCs system Outages i

3.

Off-site Dose Calculation Manual Changes 4.

Major changes to Radioactive vaste Treatment i

system

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1.

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 not electrical output of 1078 Megawatts. Vaste heat is rejected to a man-made cooling pond using the Illinois River for make-up and blowdown. The architecht-engineer was Sergent and Lundy, and the Primary construction contractor was comanonwealth Edison Company.

Unit two was issued operating license number WPF-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 (615)357-6761 extension 175.

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4 II.

M0MLY REPORT FOR WIT TWO A.

SUlt9JtY OF OPERATING EXPERIENCE FOR UNIT WO JUNE 1-30 The reactor was subcritical, and the generator was off-line for the entire Inonth of JUNE, Unit Two is in a scheduled outage for maintenance, testing, and j

modifications.

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8.

PUWT OR PROCEDURE QUWGES, TESTS, EXPERIMENTS MD SAFETY RELATED MAINTEWlufCE.

1.

Amendments to facility license or Technical Specifications.

Amendment 12 was made to the unit two Technical speciafications.

incorporating a revision to the system response time specification for Main steam Line 1.ow Pressure Isolation.

2.

Facility or procedure changes requiring NRC approval.

There were no facility or precedure 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 squipment.

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

TABLE 1 nnemarTIVE nnittragusCE OF g

SAFETY BEATED SQUIPemfr idQERK ttEQUEST 000W ctMBff CAUSE OF SthLFLEICTICIf BESULTS ARID EFFMCTS ODERSCTIVE ACTICIf CIf SAFE PEAT lT OPelEATICII L38868 Elet "B"

& "C" Faulty Bearings Could not lubricate Motor.

Replaced bearings.

Area Fan stotor.

LC5362 Suppression Pool Leaking Squalizing Valve False indications.

Cleaned equalizing valve asarrow Atange Level and Out-of-tolerance and recalibrated samrder.

Instrument.

Instruments.

Ld7064

• A" BIER Pump Minimum Packing leaked.

Urasanted leakage.

Replaced packing.

Flow Valve.

LC~7218 Outboard Peedwater Leaky Solenoid valves.

Check Valve could not be held Tested and replaced check valve "a*.

in the closed position.

solenoid valves.

LC 7284 seat "A" Service Oil needed to be changed.

Oil leak in bearing.

Changed oil.

Water Puer.

LCa162 Diesel Generator "A" Out-of-tolerance.

Imcal indication wa:: incorrect. Recalibrated meter, watt meter.

LCS299 Itte Pump Minimum Jamnsd Equalizing valve Could not calibrate instrument. Replaced Equalizing valve bypass flow switch, on 5-valve-manifold.

stem.

LC892$

Average Power Range Blonsa Fuse.

Half of dcastscale lights were Replaced fuse.

Igonitor F.

out.

LC9040 DIPCS Puup Boom Faulty plunger interlock Fan did not autostast uhen HPCS Replaced plunger i

Cubicle Fan.

on HPCS Breaker.

started.

interlock.

LC9047 Circuit Breaker Broken Reset Button on Could not reset breaker.

Replaced thermal for valve 2821-F071.

thermal overload device.

overload device.

LC9049 Circuit areaker Faulty thermal overload Could not reset breaker.

Replaced thermal for valve device.

overload device.

2B21-F073.

Docustkatt 0044r/0005r I

CassicCTIvec MAItfretRascat OF SAFETY EIELATED W IP9EBrF M IuB9UtiST C OI W otsubrF CAUSN OF 90kLPUtfCTIOtf RESULTS AtID eft 10 CTS CORRECTIVE ACT10tf 000 SAFE PLAbff OpttRATICBf LC9078 Ebst Shutdcase Cooling ran=a set scretes in gears. Local valve indication alweys Adjusted indicator Outboard Isolation at 100% open.

and tightened set scretes.

Valve.

LC9106 3rCS Puer discharge Out-of-tolerance.

Indicated pump discharge secalibrated float esas too low.

floes meter.

flow meter.

LC9117 W W "A" Ninimum Floor Out-of-Tolerance.

Minimum floes valve did not open Recalibrated switch.

edeen it h Id have.

Valve Floes Switch.

LC9419 acIC steam line drain Faulty spring and cracked Valve leaked.

Replaced spring and retaining ring.

valve.

retaining ring.

LC9428 Scram discharge Mispositioned actuating Incorrect position indication.

Adjusted and tightened actuating arm.

volume isolation arm.

valve.

LC9443 seactor Vessel Level High and Imes side sensing Instrument inoperable.

Retouted sensing lines I

Switch.

lines installed on the to the correct ports.

j wrong ports of the 1

instrument.

LG9541 seactor au11 ding afvac aroken limit se# itch.

Limit seeltch would not pick up, sepaired limit switch, thus preventing supply fans supply deeper.

from starting.

LG9%$

• a" Outboard peSIV.

Broken limit switch.

Improper position indication.

Replaced 11mit switch.

LG9801

• C Inboard psSIV.

Broken limit switch.

Improper position indication.

Replaced limit switch.

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. Doctsester 0044r/000$r L-

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LICENSEE EVENT REPORTS

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The-fol. lowing is a tabular sununary of all licensee event reports for j

LaSalle Nuclear Power station Unit T w, logged during the reporting period, June 1 through June 30, 1985. This information is provided pursuant to the reportable occurrence reporting requirements as set forth in 10CFR 50.73.

Licensee Event Report Number gita Title of Occurrengi 85-023-00 5-23-85 Spurious safety Relief valve Actuation.

85-024-00 5-31-85 Group I Isolation from Low condenser vacuum.

85-025-00 5-6-85 Reactor scrams from Las-RP-02.

85-026-00 5-22-85 Diesel Generator Start Failure.

85-027-00 5-27-85 HPCs OY Return Line Rupture.

85-028-00 6-4-85 CRD Low Header Pressure scram.

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DATA TABULATIcel8 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 i

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E.

UNIQUE REPORTING REQUIREMENTS 1.

Safety / Relief Valve Operations for Unit Two.

9821 VALVES NO & TYPE PLANT DESCRIPTION ACTUATED SCTUATIONS CONDITION OF EVENT There were no safety relief valves operated during this reporting period.

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2.

8005 Systems Outages The following outages were taken on ECCS Syster.s during the reporting period.

OUTAGE WO.

pDUIPffENT PURPOSE OF CUTAGE 2-834-85 HPCS Pump Suetion v31ven.

anvirnnmental sal t fication Modification.

Moc).

2-841-85 B/C RHR Cubicle Cooler.

Replace Bearings.

2-842-85 "B" RHR Pump.

Repair puffor piston.

2-843-85 Valve 2E12-F0518 Adjust valve.

2-844-85 Division II RHR 8ervice Relocate Suction.

hter Drceear Radiation Monitor.

1 2-845-85 "B" RHR Service Water Repair leak.

Strainer.

2-846-85 "B" RHR Shutdown Co311ng Repack Valve.

f Testable Check valve.

2-847-85 2DOO3P.

. Testing.

2-855-85 "A" Diesel Generator.

Equipment Protection.

2-860-85 MPC5 Suction from Cycled Isolate pipe break, condensate and full flow test valve.

2-86*t-85 "B" Diesel Generator Maintenance.

Air compressor, l

2-866-85 "B" and "C" RNR Prevent injection to reactor vessel.

2-869-85 "B" RHR Bervice Water.

Hydrostatic Test.

l 2-8'11-85 "B" Diesel Generator.

Repair Lccal and Control

' Room Meters.

2-873-85 "B" RHR Service Water Modification.

Process Radiation Monitor.

2-874-85 RCIC Drain Valve.

Repair weld.

2-879-85 RCIC Drain Valve.

Repair weld.

2-884-85 2E51-F063.

Inspect Limit Switches.

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OUTAGE No.

800lP W T PURPOSE OF OUTAGE t

2-886-85 KPCS Fump.

Install Bracket.

2-892-85 "B" Diesel Generator Replace Transformer.

immersion Heater.

2-899-45 acic Turbine.

change oil.

2-900-85 RCIC Turbine.

Flush oil.

2-912-85 2t$1-F063.

Inspect Limit Switches.

2-920-85 2E12-F053A.

Replace Motor.

4-vst-co g.to av reso to owlten squapmens rrotecsaan.

gear 23'lX and 237Y.

2-956-85 HPc5 Pump Breitker.

Repair Auxiliary contactor.

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3. Off-site Dose calculation Manut!

There were no changes to the off-site dose calculation manual during this reporting period.

b'T ilT. ${ lM g,3-4.

Radioactive Weste Treatment systems.

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

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1. OPERATING DATA REPORT DOCKET NO. 050-374 UNIT L(Salle Two DATE July 10. 1985 COMPLETSD BY Richard J. Rohrer TELRPHONE (8151357-6761 OPERATING ETATUS 1.

REPORTING PERIOD: June. 1985 GROSS HOUR 8 IN REPORTING PERICO: 720 2.

CURRENTLY AUTHORIEED POWER LEVEL ( W t):122], MAX DEPEND CAPACITY 1036 DESIGN ELECTRICAL RATING (MWe-Net)t1078 (We-Met):__

3.

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

N/A 4.

REA90NS FOR RESTRICTION (IF ANY):_y/&

THIS MONTH YR TO DATE CUMULATIVE 5

NUMBER OF HOURS REACTOR WAS CRITICAL 0.0 1399.8 _

3011.6 125.3 6.

REACTOR RESERVE SHUTDOW HOURS 0.0 0.0

_ 2934.7 7.

HOURS OENERATOR ON LINE 0.0-1397.3 0.0 0.0 __

0.0 8.

UNIT RESERVE SHUTDOWN HOURS

~ 0.0 M

8894971 9.

GROSS THERMAL WERGY GENERATED (MWH) 10.

GROSS ELEC. ENERGY GENERATED (MWH) 0.0 1460387 2945373

11. MET ELEC. ENERGY GENERATED (MWH)

-8557 1373636 2765953

12. REACTOR SERVICE FACTOR 0.0%

32.1%

49.0%

13.

REACTOR AVAILABILITY FACTOR 0.0%

32.1%

51.1%

14. UNIT SERVICE FACTOR 0.0%

32.0%

47.8%

15. UNIT AVAILABILITY FACTOR 0.0%

32.0%

47.8%

16. UNIT CAPACITY FACTOR (USING MDC)_.

-1.1%

30.4%

43.5%

17.

UNIT CAPACITY FACTOR (USING DESIGN Me)

-1.1%

29.2%

41.8%

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WIT FORCED OUTAGE RATE

, 0.0%

0.0%

3.9%

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19. EMUTDOWS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF RACN):

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

20. IF SHUT DOW AT END OF REPORT PERIOD, ESTINATED DATE OF STARTUP July 12, IIII l

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2. AVERAGE DAILY UNIT POWER LEVEL DOCKET No: 050-374 UNIT: 1ASALLE TWO DATE: July 10. 1985 COMPLETED BYt Richard J. Rohrer TELEPHONE (815) 357-6761 MONTH: June 1985 i

DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (19fe-Net)

(Itle-Net) 1.

~5 17.

-13 2.

-6 18.

-13

-14 3_

-5 19..

20.

-15 4.

-5 5.

-7

21..

-15 6.

-9 22.

-14 7.

-6 23.

-14

8. __

-6 24.

-14 9.

-7 25.

-15 10.

-14

26..

-14 11.

-15 27.

-14 12.

-14

?8.

-15 13.

-14 29.

-15 14.

-14 30.

-16 15.

-13 16._

-14 l

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