ML20043E020

Monthly Operating Repts for May 1990 for LaSalle County Nuclear Station.W/900610 Ltr

ML20043E020
Person / Time
Site:	LaSalle
Issue date:	05/31/1990
From:	Diederich G, Thunstedt J COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9006110386
Download: ML20043E020 (22)

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i, l * ' ' ",V , . Commonwealth Edison-LaS:lle County Nucl:ar Station

, Rural Route a1. Dox 220

, Marsolltes. Illinois 61341 Telephone 815/357 6701 June 10, 1990

)

1 Olroctot of Nuclent Iteactor Regulation ,

tinit ed States Nuclear itegulat ory Commisalon Hall' titat,lon P1-137  :

Washington, D.C. 20$$$

ATTil Document Control Denk Unntlement Enclosed for your informntion is the monthly performance report coveting 14nfiolle County Nuclear Power Station f or Hay,1990. - i Very truly yours, a

G .

/Station

. J. Diedorich Hanager j

LaSalle County Station i

GJD/JWT/msh EncloBut0 j act A. IN Davir., NRC, Region !!!

tiltC Ronideut Inspector LaSalle '

i ill. Dept- of Nuclent Snfety H, l'ulalter, NRH Project Haneger I D. P. Onlle, Cf:Co D. L. Carrar, CECO IllPO Hocords Cont er D. R. Eggett, f1ED J. E. Kunkey GE Henident T. J. r,ovech. Hannget of fluclear Licensing W. P. Ilaughton, Nuclear Tuel Services Manager C. r. D111on, Senior financial Coordinator, LaSalle Terry Novotney, IllPO Coot dinator , LaSal)e Station T.-A. Hammerich, Regulatory Assurance Gupervisor J. H. Gloseker, Technlcal Staff Supervisor Centrar rlle

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TABLE OT CONTENTS

-(UNIT.1)- '

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.1. IIITRODUCTION ,

!  !!. REPORT ,

A.

SUMMARY

Or.0PERATING EXPERIENCE'- , 'f it . - PLANT OR PROCEDURE. CHANGES, TESTS, EXPERIMENTS, AND SAFETY RELATED

~

MAINTENANCE .

3.- knendments: to racility License or Technical Specifications 1 1 24 . Changes'to procedutos which are described'li the, Safety Analysis Report

3. Tests.andEsperimentsnotcovered'inthe!SafetyAnalysis.Rhportj  :

4. Corrective Maintenance of Safety-Related rquipnent

5. Completed Safety-Related Modifications  ;

! L. .LICEllSEE EV'NT E REPORTS D. DATA TABULATIONS '  :!

1. Operating Data Report

2. Average Delly Unit Power. Level-

3. Unit Shutdownn and Power Reductions.  !

E. UNIQUE REPORTIllG REQUIREMENTS

1. Main Steam Rslief Valve Operations '

2. ECCS System Outa['as .

3. Off-Site Dose Ct1culation Manual: Changes

4. Major ChangJs to Radioactive Nante Treatment-Syntom, . ,

5. Indications of Falled ruel1 Elements- 3 U

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1. INTRODUCTION (Unit 1) '

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The LaSalle-County Nuclear Power Station-is n'two-unit facility owned'byc j Cormonwealth Edison Company and-located near Marsellies, Ill',nois..'Each.

unit- is a Bolling Water' Reactor with a designed net electric'.1 Output' of ~ -]

.j 1078 Megawatts.- Waste heat is rejected.to a man-made;coollrg pond using  ;

the Illinois R!ver-for'make-up and-blowdown. .The architet'-engineer c was ,j .

Sargent and Lundy and the primary construction contractot was '

Commonwealth Edison Company.

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Unit One was.lssued operating license--number HPF-11.on Apr.1-17,-1982. l Initial criticality was achieved"on June 21,11982-and' commercial p6werl operation was commenced on January-1,.1984.,

This report was. compiled by John W.-Thunstedt, telephonef ntunbst..

(815)357-6761, extension 2463.

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' i'II. MONTilLY REPORT

'- A.

SUMMARY

OF.CPERATING EXPEPIENCE (Unit 1) .

Day Time TJ.tAL_. _. .

1- 0000 Eeactor critical, generator on-line at 3113 MWT, CRD exercleing in progress 1200 Returned to full-power.

6 0430 Reduced' power to 3079 MWT for "B" Main Turbine Control' Valve work.

0900 Ircreased power to'3277 MWT.

, 0 0130; Reduced power;to 2966 MWT;fer CRD-exercising.

,1100 Returned,to.fu11' power.

15 00" Reduced' power to 3170 MWT!for'CRD exercising.-

0700 Returned to full power.

0300 Reducrid load to 3100 MWT to insert- FCLL rods.

17 0700 keturned to full power.

22 0100 Reduced power to 2910, MWT for CRD _erercising, TH lleater Bay: work, and monthly surveillances.

. 1400 Returned to full power.

29 0000 Reduced' load to 3120 for^CRD exercising.

1000 Returned to full power.

31 2400 Reactor Critical, generatbr un-line at~ full power.

7.C ADTS/ 5 7

1 , , . . . . . . . . . . . . . . . . . . . . . . . . . .

1 D.- PLANT OR PROCEDURE CHANGES,' TESTS, EXPERIMENTS AND' SAFETY 2 ELATED HAINTENANCE.(Unit 1)

+

1 '. Amendments to the Facility License or Technical ~ Specification.

a.- Rev3 sed Snubberisurveillance intervali tolerance.-

2. Changes to procedures which are described in the SafetyL Analysis Report.

a. LaSalle Special-Test, LST-90-053 " Operation.of the IB Reactor Recirc Flow Control Valve without LVDT Feedback". j This procedure will provide the instructions necessary to- j perform initial calibration, Installation tuning, testing,  !

and operation of the special signal card for simulating RR valve _ position based on the RR loop flow signal. This.is necessary due to. erratic feedback signals.Irom the-IB'FCV' LVDT-and still use a flow signal feedback.to allow'.

continued! operation of-the IB FCV.

b. LaSalle Special Test,-LST-90-054 " Control. Room / Auxiliary Electric Room HVAC System Initial Damper Adjustment'. The

~

purpose of this! test is to provide a methodology for; y ensuring that the."A" train Control Room (VC) Land l Auxiliary Electric Room (VE) HVAC' systems ~are opesable .

during the= initial _ adjustment'of' balancing dampers.v'This. i will increase system flowrate to design by. removing-_ excess

. system resistance. .

c. LaSalle_Special Test, LST-90-061:"ManipulationLof the: .

Reactor Recirculation IB Loop's Flow Control Valve. Without '

LVDT Feedback", -

The purpose of the.peocedure is to- .! I provide a method of controlling'the.1B loop's flow control Ij valve and thus change reactor power.without'LVDT feedback '

on the valve.. 'The purpose!is due tolthe' position feedback i signal is unstab3e and the'drywell is inaccessible, j 3.. Tests:and Experiments not described in the Safety Analysis-  :!

Report.

(None) j

4. Major corrective maintenance.to-Safety-Related_ Equipment, including any SOR switch failure reports.-

(None,.See-attached 2 pages for SOR-switch reports)

~

5. Completed Safety-Related Modifications.

(None)

C. LICtNSEE EVENT REPORTS (Unit 1) l 1&R Number D. ate Daggriotion 90-007-00 5/11/90 Failed RCIC Hi Steam Flow DP Switch due to torn diaphram '

90-00B-00 5/25/90 Missed hourly fire watch on Refuel-Floor D. DATA TABULATIONS (Unit 1)

L Operating Data Report (attached)

2. Avetage Daily Unit Power Level (attached)

3. Unit Shutdowns and Significant Power Reductions (none)

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x lAct' ion Limits: -(163,0lor5173.'83WCl ,

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TechnicalISP ecification.

Limits' 186,0'?WC~ "

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As Found Setpoints- ,1L81d 4 WC' 3

Date and Time of Return to Servicet iO5/06/90 0540 houiof

'Model Number of Repbcement:SEitcht;L1D3AS'-BNO NNX-JJTTX6L = '

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• Serial Number ~of Replacement! Switch:

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3 Equipment ^ Piece.Humber: 1E31-H013Aff-.ModelHumbers;103AS-B20?-NX-JJTTX6:

~ESerial Numbers' 85-4 ~

Application: RCIC'Hiah' Flow Isolation Switch-Date and Time.of Discovery - 05/11/907 0240 hour0.00278 days <br />0.0667 hours <br />3.968254e-4 weeks <br />9.132e-5 months <br />s- >

'I Reactor' Mode: 1 (Run)  : Power Levels 100% i

-i Calibration Tolerance - &65. 4 .16'7. 4 ' ' WC -

Nominal Setpoint:L <S6.4 'WC '

- Action-Limitst <116.0for >lZ1.8 *WC ,

Reject Limits:- <155,6 Lor'>177.0 *WC Technical Speci11 cation +

' Limit: 185.0-"WC

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As Found Setpoint's ---

'WC' ,

Date and Time of Return to Service QELLLL21'122Q hours i

Model Number of Replacement Switch:L 103AS-B203 n JJTTX6+ l Serial Number of Replacement S'v itch 88-6-121' Causes Switch vould not hold pressure durina functional testino. Durina insoection the switch was found to have a teer in the dischram'between-the cylinder disk-outside diameter and 0-rina seatino surface (acorox'3/8'.k.

Corrective Action: Replaced switch. Insoccted failed switch.

DVR Numbers- 1-1-90-040 i l e

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' D.i' OPERATING DATA REPORI LOCKET NO. 950-373 <

UNIT LASALLE ONE'

= DATE June 10,1989'

, COMPLETED BY J.W. THUN3TEDT (TEL& HONE (815)-357-6761l ,

COPERAi!NG STATUS

i.. REPORTING PERIOD: MAT 1990 GROSS HOURS _IN REPORi!NG FERIOD: 744

- 2. CURRuild AUTHORIZED POWER LEVEL ('Mt): 3,322 MAXDEFENDCAPACITY(MWe-Net): l,036 l DESIGN ELECTRICAL RATING (MWe-Net) - 1,078 ' =

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3! POWER LEVEL 10 WHICH RESTRICIED (if ANY) (MWe-Net): (None)

4. REASONS FOR RESTRICTION (IF ANY): (N/A)- .g REPORTINGPERIODDATA d THIS MONTH YEAR-10-DATE CUMULATIVE .I

5. TIME REACM CRiflCAL (HOURS)-

............ ... .. .. ...........- -[

744.0 3,452.0 35,586.1: E!

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6. TIMEREACTORRESERVESHUTDOWN(HOURS) 0.0 . 0.0 11,641'.2 1

7. TIME GENERATOR OF LINE (HOURS) 744.0 .3,325.1 34,743.4 3 1

8. TIME GENERATOR RESERVE SHUTS 0WN (HOURS) 0.0 0.0 1.0 . -- i 2

9. THERMAL ENERGY GENERATED (MWHt-Gross) 2,450,832 110,510,137.4 99,343,705.4

' ie. ELECTRICAL ENERGY GENERATED (MWHe-Gross)- 840,903 3,596,y19 32,645,520 i

ti.ELECTRICALENERGYGENERATED(MWHe-Net)' - 816,957' 3,483,4f6 31,216.118-1

12. REACTOR SERVICE FAC10R (%) 100.0 95.3 63.3-

13. REACIDR AVAILABILITY FACTOR (%) 100.0 95.3 66.2 $

14. SERVICE FACTOR (%) 100.0'- 91.8 61.8 ~{

15. AVAILIBILITY FACTOR (%) 100.0- 91.8 61.8

16. CAPACITY FACTOR (USING MDC) (%) 106.0- 92.8 53.6

17. CAPACliY FACTOR (USING DESIGN MWe) (%) 101.9 89.2 51.5

18. FORCED OUTAGE FACTOR (%) 0.0 3.8' ' 9.6 a - .

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19. SHUIDCWHS SCHEDULED OVER THE HEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH):

(None)

20. IT SHUIDOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP:

(N/A) l 1

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E .1 ' UNIQUE REPORTING REQUIREMENTS (Unit 1)

1. Safety / Relief valve operations.

VALVES NO & TYPE PLANT ~ DESCRIPTION DATE . AC1VAIED AC1VAIJM CQtiDJ112 QF EVENT I

(None)

~

2.. ECCS System. Outages 1

QUIAGEJQt. EQUIPliEHI 2VMQSE (Notes the year and unit numbers hrve been ommitted from the Outage Number)-

LUnLt_Q) lib ODG01P Repair

^

117 ODG08CD Check hold-downs- ..

118 ODGOBCA Check 1 hold-downs

-119 0 D/G Replace ~ air-start motors  !

120 0 D/G -Replace filter- .

LU.nl..t_1 )

221 1E31-H012AA(RH)- Replace switch.

224- '1E12-D300B (RH) Lubricate

.226 1E12-F011D-(RH) ~(Administrative, per T.S. 3.6'.3.)

229 1E51-F008 (RI) (hdmlnistrative,~-per T.S.)

230 1E51-P038'(RI) Repack .. valve 234 x JE21-C002 (LP) Lubricate 235 1E22-C302A (HP) Repair head-gasket

3. Changos to the Off-Site Dose Calculatioa " nual (None).

4. Major - changes to. Radioactive Waste Treac- Systems.

(None)

5. Indications of Falled fuel Elements.

(Hone)

ZCADTS/S i

-. I

e

' , , ;1

,, . i -- .-' -

I i 4 LASALLE-NUCLEAR POWER STATION UNIT 2

'MONTMLY.PERTORMANCE-REPORT, 11AY , 1990 ,

COMMOtlWEALTH EDlSON COMPANY i

NRC DOCKET NO. 050-374 LICENSE NO. HPF-1B'-

ZCADTS/7

l s.

1 >

3

.a -:

V: ,

4 TABLE OF CONTENTS (Unit 2)

1. INTRODUCTION 5,

II. REPORT A.

SUMMARY

OF OPERATING EXPERIENCE t

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

, l '. Amendments to Facility License .or Technical Specifications

2. Changes to procedures which are described in the' Safety AnalysissReport.

3. Tests and Experiments not covered in the Safety Analysis Report.

4. Corrective Maintenance of Safety-Related Equipment- '

5. Completed Safety Related Modifications 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

3. Off-Site Dose Calculation Manual Changes-

4. Major Changes to Radioactive Waste Treatment System

5. Indications of Failed Fuel' Elements' '

i i

ZCADTS/7

1. INTRODUCTION (Unit 2)

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 '

1078 Me,tawatts. Weste heat is rejected to a man-made cooling pond using -

the Illinois River for m:ake-up and blowdown. The architect-engineer was Sargent and Lundy and the primary constru'. tion contractor was

]

Commonwealth Edison Cc pony.

Unit Two was issued operating license number NPF-18 on December 16, 1983. Initial criticelity was achieved on March 10 1984 and commercial power operation was commenced on Juno 19, 1984.

This report was compiled by John W. Thunstedt, celephone number (815)357-6761 extension 2463. l

.mi i '

R W

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5 5

a ZCADTS/7

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,, , ,- 1I .14 MC21THLY . REPORT -c s .-

.e A.

SUMMARY

OF OPERATING EXPERIENCE -(Unit 2)

Day - I.itMt Eyent w -

1 0000 Reactor suberitical, generator off-line, L2R03 in progress.

31 2400 Reactor subcritical, " generator- of f-line,.s L2R03 in' progre ss.

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

• MAINTENANCE.(Unit 2): -

1. -Amendments to the_ Facility License or:Technica.1 3pecification.

a.. ' Revised Snubber surveillence interval tolerance.

~2. Changes to procedures which are described in the Safety Analysis Report.

(Hone)

3. . Tests'Qnd Experiments not' described in the Safety' Analysis-' '

=Repw t.

(P no) d

4. Mejorscorrective maintenance. to Safety-Related - Equipmbnt,_

including any SOR switch failures.

(See Table 1)' ,

5. Completed Safety-Related Modifications.

(Hone).

4-2 1.

M 5

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t 6 'ZCADTS/7 -

4

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• B.4 ?A3LE 1 ' Unit 2) v L MAJCd CORRECTIVE MAINTENANC2 Tu SAFETY-RELATED EQUIPMENT

[

I WORK REQUEST RE54TS AND EFFECTS COMPGiENT C)USE OF MALFt'NCTION ON SAFE PLANT OPERATION CORRECTIVE ACTION f NUMBER w - _ _ _ _ . _ _ _ _ _ __. -_

?

n

=

Fore ign mater i.'s1 i r. Test loop pressure low Ren:oved obstruction

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LEIL thWDhN1 Data I2tt ECXiPLWA.____ . __ __. .._.. . _ . . _ _ . . . . _

10-006-90 05.'02/90 ESP A.:ttstion of the Cotit1 ol J octa U l'morgency Circuit Venti lation linkettp I'atr/Procedur al Do riciency.

90-009-00 05/10/90 RWCU Ictilat ter, du r ing Svr vieil lance Tes t a rq.

D. D UA TABU LX7) GN S (Unit 2!

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