ML20077A142

Monthly Operating Rept for May 1983

ML20077A142
Person / Time
Site:	LaSalle
Issue date:	06/09/1983
From:	Diederich G, Lin D COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
NUDOCS 8307220200
Download: ML20077A142 (15)

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LASALLE NUCLEAR POWER STATION UNIT 1 MONTHLY PERFORMANCE REPORT May 1983 COMMONWEALTH EDISON COMPANY NRC DOCKET NO. 050-373 LICENSE NO. NPF-11

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TABLE OF CONTENTS I.

INTRODUCTION

.II.

SUMMARY

OF OPERATING EXPERIENCE FOR UNIT ONE III. PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS, AND SAFETY RELATED MAINTENANCE A.

Amendments to Facility License or Technical Specifications B.

Facility or Procedure Changes Requiring NRC Approval C.

Tests and Experiments Requiring NRC Approval D.

Corrective Maintenance of Safety Related Equipment IV.

LICENSEE EVENT REPORTS V.

DATA TABULATIONS A.

Operating Data Report B.

Average Deily Unit Power Level C.

Unit Shutdowns and Power Reductions VI.

UNIQUE REPORTING REQUIREMENTS A.

Main Steam Relief Valve Operations B.

ECCS System Outages C.

Off-Site Dose Calculation Manual Changes D.

Major Changes to Radioactive Waste Treatment System E.

Changes to the Process Control Program 1

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I.

INTRODUCTION The LaSalle Nuclear Power Station Unit One is a Boiling Water Reactor with a designed electrical output of 1078 MWe net, located in Marseilles, Illinois. The Station is owned by Commonwealth Edison Company. The Architect / Engineer was Sargent & Lundy, and the primary construction contractor was Commonwealth Edison Company.

The condenser cooling method is a closed cycle cooling pond. The plant is subject to License Number NPF-11, issued on April 17, 1982. The date of initial criticality was June 21, 1982. The unit has not commenced commercial generation of power.

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This report was complied by Diane L. Lin, telephone number (815)357-6761, extension 499.

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II.

SUMMARY

OF UNIT OPERATING EXPERIENCE FOR UNIT ONE May 1-27 The Unit was shutdown to condenser repairs and the recirculation seals being replaced.

May 28-31 The reactor went critical at 0615 hours0.00712 days <br />0.171 hours <br />0.00102 weeks <br />2.340075e-4 months <br /> on May 28, 1983 At 0805 hours0.00932 days <br />0.224 hours <br />0.00133 weeks <br />3.063025e-4 months <br /> on May 29 the main generator was synchronized to the grid and loaded. At 0705 hours0.00816 days <br />0.196 hours <br />0.00117 weeks <br />2.682525e-4 months <br /> on May 30 power was increased from 15% to 35%.

The. reactor was critical for 95 hours0.0011 days <br />0.0264 hours <br />1.570767e-4 weeks <br />3.61475e-5 months <br /> and 45 minutes.

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

Amendments to Facility License or Technical Specifications.

Amendment 14 - This amendment deletes License Condition 2.C. (26),

and also changes the Technical Specifications to incorporate the alternate Rad / Chem Technical qualifications.

B.

Facility or Procedure Changes Requiring NRC Approval.

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

C.

Tests and Experiments Requiring NRC Approval.

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

D.

Corrective Maintenance of Safety Related Equipment.

The following tables present a summary of safety-related maintenance completed on Unit One during the reported period.

The headings indicated in this summary include: Work Request Numbers, LER Numbers, Component Name, Cause of Malfunctions, Results and Effects on Safe Operation, and Corrective Action.

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l!(llK ItEQUESI LER C0llPolKill CAUSE CF 11AlfullCT1011 RESULTS AllD EITECiS L O M L L i i R lit i I Uii Ott SAFE OPERATI0il MSIV L22273 Valve 1B21-F028B Bad hose Hose leaked Replaced hose L22460 High Side Instrument Bad Manifold Valve leaks by Replaced Manifold Stop Valve on when valve is closed 1021-N044A L22661 RHR "B" Outboard Bad packing Valve leaks at valve stem

' Replaced packing (1

Contalment Spray d

Valve i

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VC Trouble alarm in the Replaced relay L23570 Refrigeration Unit Bad relay Control Room will not clear 250 VDC Damaged amp Battery voltage was down Replaced amp L23785 and firing module.

Battery Charger and firing module L23807 SBGT Radiation Bad pressure transducer Vacuum and digital gauges Replaced pressure Monitor disagree

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transducer.

L23856 "B" IRM Recorder Bad MSA Unit Recorder was pegged upscale Replaced MSA Unit L23922 83-040/03L-0 Stack WRGH Mid Range Loose connector to Recording giving Reconnected Recorder

.? power supply unusual readings loose connector

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"A" RHR Pump Zero out-of-adjustment Control room indication Readjusted zero L24083

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Discharge Pressure reads high Indicator L24119 83-039/03L-0 Mechanical Snubber Bad Snubber Snubber locked up Replaced-Snubber s

UOllK REQUEST LER C0llP0llEllT CAUSE OF HAl.rullCTI0li RESULTS AllD EFFECTS C0ltitLLilVI. hLilull DN SAFE OPERATI0li L24.183 83-037/03L-0 Radwaste PRM PRM dirty PR'M failed source check Cleaned PRM AP RM ' F ' Powe r Bad SCR-1 Power Supply could not Replaced SCR-1

'L24243 1

Supply be adjusted to spec.

L24310 "A" RHR Service Bad pump and motor Pump will not maintain Replaced pump water process a set flow when operating and motor Radiation Monitor I.9 Sample Pump L24317 l

VR Exhaust PRM "D" Bad relay board PRM does not work.

Replaced relay

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board L24560 Cycled condensate Bad Switch Swit.ch won't operate Replaced switch Storage Tank Level Switch ll L24561 RWCU Flow Transmitte Bad Flow T'ransmitter No ef fect Replaced flow transmitter L24798 Unit 1 Div ll Bad PCV; oxygen instrument ' indicates low Replaced PCV,

Drywell Oxygen analyzer cell and oxygen analyzer Concentrater ampli fier board cell and amplifier board

' Bad overload relay Overload won't work Replaced overload L24840 Valve IB21-F067B relay sl s'

MSIV IB21-F022A Bad limit switches Limit switches have bent Replaced L24876 operating shafts limit switches j

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W0ilVs REQUEST LER C0llPO!!EllT CAUSE OF HALFullCTIO!!

RESULTS AllD EFFECTS C0llRECTIVE ACTI0li ON SAFE OPERATI0li L24900 MSIV 1821-F022A Bad limit switch No effect Replaced limit breaker switch breaker L24922 "A" SBGT Train Flow Bad multiplexer chip indication reads 200 cfm Replaced __

when A VG train is shut-multiplexer chip down Bad DC voit meter Meter out-of-tolerance Replaced meter L24943 5

125 VDC Battery

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1821-F022A Breaker Bad limit ssitch Limit switch borken Replaced limit L24967 l

Close Indication internally.

switch Limit Switch i

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Primary Containment Upper limils Valve shows dual Adjusted upper L24968-Vacuum Breaker out-of-adjustment indication when open,!

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"B" Inboard HSIV Defective Limit Dual Indication

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Replaced Limit L24971 Limit Switch Switch Switch L24993 Shutdown Cooling Bad Overload Unit With the Thermal Replaced Warm-up Valve and Control Overload bypassed, the overload unit Transformer

' valve tripped on a and control thermal overload trans former i

t L24997 Reactor Building Motor winding Breaker for valve Replaced motor to Drywell Purge were shorted to trips when control e'

Valve ground switch is taken to open or close.

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IV.

LICENSEE EVENT REPORTS The following is a tabular summary of all licensee event reports for LaSalle Nuclear Power Station, Unit One, occuring during the reporting period, May 1 to May 31, 1983 This information is provided pursuant to the reportable occurence reporting require-ments as set forth in section 6.6.8.1 and 6.6.B.2 of the Technical Specifications.

Licensee Event Report Number Date Title of Occurrence 83-034/03L-0 4-8-83 Reactor Vessel Water Level High HPCS Injection Valve Closure 83-035/03L-0 4-6-83 Off-Gas Hydrogen Analyzers Inop 83-036/03L-0 4-14-83 Inadequate Welding Procedures 83-037/03L-0 4-21-83 Radwaste PRM i

83-038/03L-0 2-7-83 HPCS Low Water Leg Line Pressure Switch Out of Tolerance l-83-039/03L-0 4-18-83 Inoperable Mechanical Snubber I;

83-040/03L-0 4-12-83 Stack WRGM Mid Range Noble i

Gas Recorder 83-041/03L-0 4-14-83 Steam Leak 83-042/03L-0 4-23-83 MSIV Failure of Leak Rate Test

!j 83-043/03L-0 4-27-83 Unit 1, Division I, 125 VDC lj Charger Failure

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83-044/03L-0 5-5-83 Chemistry Out of Tech Spec Limit

l-j-83-045/03L-0 5-6-83 Reactor Vessel Water Level High HPCS Injection Valve Closure j.

83-046/03L-0 5-8-83 Tech Spec Weekly Surveillance j

Frequency Exceeded 1

V.

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

f A.

Operating Data Report B.

Average Daily Unit Power Level C.

Unit Shutdowns and Power Reductions A

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November 8,.1979

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OPERATING OATA REPORT OCCXET NO.

090 t7 t LaSalle One UNIT Ane 9,1983 OATE COMPLETED BY _ dim I ~ f In 815-357.-6761 x499 I TELEPHONE l

OPERATING STATUS 74k May 1983 GROSS. Hours IN REPORTING PER100:

1. REPORTimo PERIOD:

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2. CURRENTLY AUTHORIZEO POWER LEYEL (MWt)I DES 4GN ELECTRACAL AATING IMWo. Net): 107

3. POWER LEVEL TO WMtCM RESTRICTED (IF ANY) (MWeNet):

A. REASONS FOR RESTRICTION (IF ANY1:

THis MowrH YR To DATE ',CUMULATIV E

s. NUMBER OF HOURS REACTOR WAS CRITICAL............... 95. 8 1157.0 4794.4 _

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s. REACTOR RESERVE snuTooWN Hours..........'.........

1027.48 2886.18

7. MOURS GENER ATOR ON LINE........................ 71. 9 0

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O. UNIT RESERVE SMUT 00WN Hour $......................

S. GROSS THER' MAL ENERGY GENER ATED (MWH)

............ 54158 1256641 3397220 I

le. GROSS ELECTRICAL ENERGY GENERATED IMWM)...~......... 11860 349308 869707

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11. NET ELECTRDCAL ENERGY GENER ATED (MWHI NA NA

12. REACTOR SERVICE FACTOR.......................... N A

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13. REACTOR AVAlt.AssuTY F ACTOR.....'..........'........ NA NA NA

14. UNIT SERvlCE F ACTOR..... '........................ NA NA NA 1

UN.T Avan.AsiurY,ACToA.......................... N A NA NA 1& UNIT CAPACITY FACTOR IU#g MOC3..................... NA

17. UNIT CAPACITY FACTOR tues DW MWel................, NA M

NA

18. UNIT PORCEO QUTAGE RATE......................... NA hA NA

19.,$MUTDOWNS SCHEDULEO QVER NEXT S MONTHS ITYPE. DATE. AND DURATION OF EACHl:

20.. lF SHUT DOWN AT ENO OF REPORT PEM600. ESTIMAT20 OATE OF STARTUP:

21. UNITS IN TEST STATUS (PRIOR TO COMMERCIAL OPERATIONI:

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, November 13, 1979

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AVERAGE DALLY' UNIT POWER LEVEL DOCKET NO.

050-373 U'N IT LaSalle One

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COMPLETED BY Diane L. Lin TELEPHONE 8'15-357-6761 X499 HOWTH Hav 1981

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DAY AVERAGE ' DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Met)

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ATTActulENT B UNIT SNUTD0VNS AND POWER RiDUCTIONS DOCKET No.

050-373 UNIT NAME LaSalle One DATE June 9.

1983 REPORT HONTH hav 1982

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COMPLETED BY Diane L. Lin.

TELEPHONE 815-357-6761 HETH00 0F j

SilUTTING DOWN

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TYPE THE REACTOR OR

' F: FORCED DURATION NO.

DATE S: SCHEDULED (HOURS)

REASON (1)

REDUCING POWER.(2)

CORRECTIVE ACTIONS /COHHENTS i

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VI.

UNIQUE REPORTING REQUIREMENTS A.

Main Steam Relief Valve Operations for Unit 1 4

There were no main steam relief valve operations for the reporting period.

B.

ECCS Systems Outages There were no ECCS Spstem Outages during this reporting period.

C.

Off-Site Dose Calculation Manual There were no changes to the Off-Site Dose Calculations Manual during this reporting period.

D.

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

d E.

Process Control Program Ij' There were no changes to the Process Control Program during i

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this reporting period.

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'N Commonwkith Edison

). LaSalle County Nuclear Station c

Rural Route #1, Box 220

.,7 uarseiiies.iiiinois 6334i Telephone 815/357-6761 June 9, 1983 Director, Office of Management Information and Program Control United States Nuclear Regulatory Commission Washington, D.C.

20555-ATTN:

Document Control Desk Gentlemen:

Enclosed for your information is the monthly performance report covering LaSalle County Nuclear Power Station, Unit One, for the period covering May 1 through May 31, 1983 Very truly yours, G J. Diederich Station Superintendent GJD/JRU/bej Enclosure xc:

J.G. Keppler NRC, Region 111 NRC Resident inspector LaSalle Gary Wright. lli. Dept. of Nuclear Safety D.P. Galle CECO D.L. Farrar CECO INPO Records Center p

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