ML20071F063

Monthly Operating Rept for Jan 1983

ML20071F063
Person / Time
Site:	LaSalle
Issue date:	02/02/1983
From:	Ullrich J COMMONWEALTH EDISON CO.
To:
Shared Package
ML20071F050	List: ML20071F047 ML20071F063
References
NUDOCS 8303150426
Download: ML20071F063 (14)

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

8303150426 830203 PDR ADOCK 05000373 R PDR

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TABLE OF CONTENTS f

l. INTRODUCTION l

ll.

SUMMARY

OF OPERATING EXPERIENCE FOR UNIT ONE Ill. 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 l V. DATA TABULATIONS A. Operating Data Report B. Average Daily Unit Power Level C. Unit Sisutdowns and Power Redtetions VI. Unique REPORTING REQUIREMENTS i

j 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-i t

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1. 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.

This report was compiled by John Ullrich, telephone number (815)357-6761, extension 481.

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II.

SUMMARY

OF UNIT OPERATING EXPERIENCE FOR UNIT ONE January 1-31 The' unit was shutdown due to the "B" RHR Pump'being declared inoperative due to excessive pump vibrations.

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i Ill. PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS AND SAFETY RELATED MAINTENANCE A. Amendments to Facility License or Technical Specifications.

There were no amendment to facility license or technical specification during the reporting period.

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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RESULTS Allu EFFECTS CORitLCi lVi, ACil0li WORK REQUEST LER CollP0llEllT CAUSE CF MALFullCTI0li ON SAFE OPERATI0li .

. 1 L15388 --

VC 'B' Train Steam Bad hsating element St.eam generator will not Replaced heating Generator Start-up trips breaker, element.

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,L20676 - '0B' VC Odor Eater Bad upper seal in Damper would not close. Replaced upper seal.

- Inlet Damper actuation

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L20716 --

Charcoal Filter Inlet Bad 'O' ving on solenoid Damper indicates open at Replaced 'O' ring Damper extension all times L20994 --

A VC Air intake Rad input coupling capacitor Rad moni tor failed down- Replaced input

.. . Monitor D and input discriminator scale coupling capacitor

!l5 chip A101 defective and discriminator chip J

L21028 l 82-174/03L-0 'B' IRM Loose high vol'tage I nd,i ca t ion is erratic Replaced high connector voltage connector

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L21215 --

+20 VDC APRM Power Bad SCR in power supply Power supply does not work Replaced SCR Supply ,

L21414 --

'A' IRM Bad pre-regulator IRMreadinghighonranhh Replaced pre-one, regulator L21436 82-173/03L-0 Outboard Reactor Dirty valve and solenoid Solenoid valve inter- p Cleaned valve Water Sample Isola- mittently sticks in the and solenoid tion Valve open position L21438 --

'B' Rx Recirc Suction Bad valve Valve won't cycle Replaced valve Valve L21460 --

Pressure Transmitter Bad transducer Readings from pressure Replaced trans-for OPL58JA Flow .

transmitter and pressure ducer Sensing indicator do not agree t

L21461 --

Pressure Transmitter Bad transducer Readings from pressure Replaced transducer

, for OPL58JB Flow transmitter and pressure l Sensing indicator do not agree i

L21474 --

Make-;p and Blowdown Lines plugged Not available for NPDES Cleaned lines Sample Lines sampling and daily radio-activi ty measurements 9

VORT, REQUEST LER C0llP0llEllT CAUSE OF HALFullCTI0li RESULTS Afl0 EFFECTS CORRECTIVE ACTl0ll Oil SAFE OPERATIO!!

I VC Rad Monitor B Bad G-it tube B PRM won't stay reset Replaced G-H tube L21557 --

kPR 'A' inboard Dry- Bad packing Valve packing leaks Replaced packing L21690 --

well Spray Valve Drywell Particulate Bad low "voltage connector input signal cable has a Replaced low L21726 --

Rad Monitor loose connector voltage connector

'lB' D/G Governor Bad cams, micro switch Speed could not be con- Replaced cams, L21768 --

arm and sync motor trolled either locally or micro switch and t .'

remotely using the raise / sync motor

. lower switch L21861 J

D/G 1B Motor-Driven Bad Valve Valve lifts at low Replaced valve l

Air Compressor Dis- pressure charge Relief Valve

'B' Air Compressor Bad 'M' contactor Placing control switch Replaced 'M' L21865 --

for 2A D/G

- to off does not stop the contactor air compressor

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A*VC Filter Train Out Upper piston' seal bad Does not close from Replaced upper L21892 --

control room p piston seal L21945 --

Control Room HVAC Fuse pulled Damper did not close Reinstalled fuse Charcoal Filter Bypass Damper L21947 --

Aux Electric Room Fuse pulled D;amper did not open Reinstalled fuse HVAC Exhaust Air Outlet Damper L21949 --

Control Room HVAC Fuse pulled Damper did not open Reinstalled fuse 0.A. Damper L21950 --

Aux Electric Room Actuator limits out-of- Dual position indication Set limits on Charcoal Filter adjustment actuator inlet Damper OVE07YA I - - _ _ _ _ _ _ _

LER C0llP0llEllT CAUSE CF MALFullCTI0li RESULTS AtID EFFECTS C01l REC IIVI: AC TI0li L'ORK REQUEST Oil SAFE OPERATI0li .

L21951 --

Auz Electric Room . Bad seals on piston shaft Dual position indication Replaced seals Charcoal Filter inlet Damper OVE09YA L21952 --

Aux Electric Room Fuse pulled Damper did not open Reinstalled. fuse HVAC Outside Air Isolation Damper L21962 # --

Main Steam Line Drain Torque switch contacts Can't seal-in close posi- Cleaned contacts (7 Valve . dirty tion L22014 --

Safety Relief Valve Solenoid valve was Positive ground on Div 11 Replaced solenoid grounded power supply could cause valve f valve to go open G

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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, occurring during the reporting period,' January 1, to January 31, 1983 This information i

is provided pursuant to the reportable occurrence reportino require-ments as set forth in section 6.6.B.1 and 6.6.B.2 of the Technical Specifications.

Licensee Event Report Number Date Title of Occurrence 82-180/03L-0 12/30/82 Mechanical Snubbers not Installed 83-002/03L-0 1/21/83 Failure to Perform F:nctional LIS-HP-09 83-003/03L-0 1/18/83 Missed Calibration and Functional Test of LIS-MS-06 83-004/03L-0 1/21/83 Overdue Calibration of Unit 2 Hydrogen Recombiner instrumentation l

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{ V. DATA TABULATIONS The following data tabulations are present-d in this report: ,

i A. Operating Data ?.eport i

B. Average Daily Unit Power Level C. Unit Shutdowns and Power Reductions  ;

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1LTP-300-7 Rav!sion 2 ATTAChEiT D

.' - November 13,.1979 S

• OPERATING DATA REPORT

- DOCKET NO. 050-374 UNIT LaSalle One DATE

- COMPLETED BY John UIIeich

• TELEPHONE (815) 357-6761 x-481 ' ,

OPERATING STATUS .

January 198'3 ' GROSS HOURS IN REPORTING PERIOD:

1. REPORTING PERIOD:

1002 MAX, DEPEND. CAPACITY (MhNet): 0 l

2. CURRENTLY AUTHORIZED POWER LEVEL (MW)ig  ;

DESIGN ELECTRICAL RATING IMWo. Net): 10

3. POWER LEVEL TO WHICH RESTRICTED (IF ANY) (MWo. Net):

1

'. 4. REASONS FOR RESTRICTION (lF ANY1:

' - THl3 MONTH YR TO DATE ' CUMULATIVE ,

l O O 2747.4

, 5. NUM8ER OF HOURS REACTOR WAS CRITICAL . . . . . . . . . . . . . . .

l 0 0 0 l E. REACTOR RESERVE SHUTDCWN HOURS . . . . . . . . . . . . . . . . . . .

0 0 18N.6 J

7. HOURS GEN ER ATOR ON LIN E . . . . . . . . . . . . . . . . . . . . -. . . . . .

0 0_ 0

8. UNIT RESERVE SHUT 00WN HOURS ,.....................

0 0 2140579 .

9. GROSS THERMAL ENERGY GENER ATED (MWH1 L 0 0 8320399

10. GROSS ELECTRICAL ENERGY GENERATED (MWH) . . . . . . . . . . . . .

0 '

0 46077's

11. NET ELECTRICAL ENERGY GENERATED (MWH) . .............

NA NA NA

12. R EACTOR SE RVICE F ACTOR . . . . . . . . . .. . . . . . . . . . . . . . . . . .

NA NA NA

13. REACTOR AVAILASILITY F ACTOR . . . . . . . . . . . . . . .'. . . . . . . .

NA NA NA

14. UNIT SE RVICE F ACTO R . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

NA NA NA

15. UNIT AVAILABILITY F ACTOR . . . . . . . . . . . . . . . . . . . . . . . . . .

' NA NA NA l

16. UNIT CAPACITY FACTOR (Using MDC) .....................

NA NA NA

17. UNIT CAPACITY FACTOR (Using Design MWel . . . . . . . . . . . . . . . . .

NA NA NA

18. UNIT FOR CE D OUTAG E M ATE . . . . . . . . . . . . . . . . . . . . . . . . . . s I

19. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE. DATE, AND OURATION OF EACHl:

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

2/2/83

21. UNITS IN TEST STATUS (PRIOR TO COMMERCIA(.OPER ATION): FORECAST ACHIEVED 6/21/82 , y INITIAL CRITICALITY

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. - LTP-300-7 Revision 2 '

. , November 13, 1979 5

ATTACHMENT A AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 050-373-U' NIT LaSalle One

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• DATE Feb uary 2. 1983 COMPLETED BY Joh'n Ullrich

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TELEPHONE (8'15) 357-6761 x481

" MONTH January 1983 ,

DAY AVERAGE DAILY POWER LEVEL . DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Ne t)

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. n 3 0 19 0 -

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12. o 28. O fl3 .

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Rr.visien 2 ' l Nov:mber 13,, 1979 l 6 .

. ATTACiltlENT B '*

UNIT SHUTDOWNS AND POWER REDUCTIONS

• DOCKET NO. 050-373 I

UNIT NAME LaSalle One DATE Feb. 2, 1983 REPORT HONTH January 1983 ,

COMPl.ETED BY _

John UlIrich l

TELEPil0NE (815) 357-6761,'

x-481 NETil0D OF SilVTTING DOWN

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TYPE THE REACTOR OR F: FORCED DURATION REDUCING POWER.(2) CORRECTIVE ACTIONS / COMMENTS li S: SCHEDULED (HOURS) REASON (I) l' NO. CATE 1:

A 4 Normal shutdown due to 1 12-31-82* F 744.0 " Unusual Event" due.to "B"  !:

RHR Pump being inop. because [

of high vibration ll l

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• Refer to the December 1982 report.

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-e VI. _ Unique REPORTING REQUIREMENTS 1

A. Main Steam Relief Valve Operations for Unit 1 There were no main steam relief valve operations during this '

1 reporting period.

4 B. ECCS Systems Outages I

j There were no ECCS System Outages during this reporting period.

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C. Of f-Site Dose Calculation Manual There were no changes to the Off-Site Dose Calculations Manual i

during this reporting period.

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

E. Process Control Program l There were no changes to the Process Control Program during this reporting period.

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