ML20082S039

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Monthly Operating Repts for Aug 1991 for LaSalle County Nuclear Power Station
ML20082S039
Person / Time
Site: LaSalle  Constellation icon.png
Issue date: 08/31/1991
From: Cialkowski M, Diederich G
COMMONWEALTH EDISON CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation
References
NUDOCS 9109170005
Download: ML20082S039 (26)
v • d • e


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LaSalle County Nuclear Stabon

) Ruralnouto #1, Dbx 220  !

t v' Mat 6eilles,lilinois 61341 7

Telephone 815/357 6701 l

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Septembcr 11, 1991 i i

Director of Nuclear Reactor Regulation United States Nuclear Regulatory Commission Mail Station PI-137 ,

-Hashington, D.C.- 20555 AT1N: Document Control Desk Gentlemen:

l Enclosed for your information is the monthly performance report covering LaSalle County Nuclear Power Station for August, 1991. j Very truly yours, s

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'M C G. J. Diederich Y Station Manager ,

LaSalle County Station

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GJD/MJC/djf Enclosure xc: A. B.-Davis, NRC, Region III T. M. Tongue, NRC Resident Inspector LaSalle J. L. Roman, Il Dept. of Nuclear Safety J. B. Hickman, NRR Project Manager D. P. Galle CECO D. L. Farrar, t,ECo-INPO Records Center D. R. Eggett, NED J. E. Kuskey, GE Resident T. J. Kovach, Manager of Nuclear Licensing H. F. Naughtor, Nuclear fuel Services Manager J. E. Lockwood,-Regulatory Assurance Supervisor J. M. Gieseker, Technical Staff Supervisor

- M. M. -Servoss, 0A/NS Off Site Review '

Station File <

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s l.ASALLE NUCLEAR POWER STATION UNIT I MON 1HLY PERf0RMANCE REPORT AUGUST 1991 C0l#40NHEALTH EDISON COMPANY NRC DOCKET NO. 050-373 LICEtiSE NO. - NPF-11 ZCADTS/5

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TABLE Of CONTENTS (UNIl 1) l I. INTRODUCTION II. REPORT A.

SUMMARY

Of OPERATING EXPERIENCE B. AMENDMENTS TO FACILITY LICENSE OR TECHNICAL SPECIFICATIONS g C.

MAJOR CORRECTIVE MAINTENANCE TO SAFETY-RELATED EQUIPHENT D. LICENSEE EVENT REPORTS E. DATA TABULATIONS

1. Operating Data Report
2. Average Daily Unit Power Level
3. Unit Shutdowns and Power Reductions F. UNIQUL 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 S. Indications of Failed Tuel Elements i

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ZCADTS/S

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I. INTRODUCTION (Unit 1)

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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 Bolling Mater Reactor with a designed net electrical output of l 1078 Megawatts. Haste heat is rejected to a man-made cooling pond using the Illinois River for make-up and blowdown. The architect-engineer was .

Sargent and Lundy and the primary r.onstruction contractor was  !

Commonwealth Edison Company. j P

Unit One was issued operating Ilcense number NPF-11 on April 17, 1982. l Initial criticality was achieved on June 21, 1982 and commercial' power I operation was- commenced on January 1,1984.  ;

This report was compiled by Michael J. Cla1Lowski, telephone number .l (815)357-6761, extension 2427.  :

i L

ZCADTS/S-

II. MONTHLY REPORT A. Sl> MARY OF OPERATING EXPERIENCE (Unit 1)

Qu Ilma Event 1 0000 Reactor critical, generator on-line at 1110 Hve 0600 Reduced power level to 950 Hwe due to system load.

1130 Increased power level to 1100 Hve.

5 0100 Reduced power level to 850 Hve due to system load.

1000 Increased power level to 1108 Hwn.

2200 Reduced power level to 1010 Hve, power level held due to probles with the Core Monitoring Code.

6 0100 Reduced power level to C50 Hwe due to system load.

1400 Incieased power level to 1118 Hve.

9 0030 Reduced power le*/e1 to 900 Hwe due to system load.

1000 Increased power level to 1115 Hve.

11 0200 Reduced power level to 850 Hwe due to system load.

1400 Increased power level to 1110 Hve.

13 0030 Reduced powei level to 850 Hve due to system load.

1330 Increased power level to 1105 Hve.

14 0100 Reduced power level to 850 Hve due to system load.

1130 Increased power level to 1105 Hve.

15 0400 Reduced power level to 850 Hve due tc system load.

1000 Increased power level to 1105 Hve.

2300 Reduced power level to 850 H.te due to systes load, removed the 'A' Turbine Driven Reactor Feed Pump from service and placed the Motor Driven Reactor Feed Pump in service.

16 1000 Increased power level to 1010 Hve (e ximum power level with the Motor Driven Reactor Feed Pump in service).

17 2100 Reduced power level to 950 Hve due to systes load.

18 0400 Reduced power level to 850 Hwe due to system load.

ZCADTS/5 .

c II. MONTHLY REPORT t V .  ;

A. SlM4ARY Of OPERATING EXPERIENCE (Unit 1) (Continued)

Day ling Event ,

0815 Removed the Motor Driven Reactor feed Pump from service and placed the 'A' Turbine Driven Reactor  !

Feed Pump in service. l 1900 Increased power level to 1102 Hve.  :

2330 Reduced power level to 1000 Mwe due to system load.

19 0230 Reduced power level to 900 Mwe due to system load.

1300 Increased power level to 1115 Hve.

20 0030 Reduced power level to 880 Mwe due to system load. -

1000 Increased power level to 1115 Mwe, 1100 Reduced power level to 1050 Mwe for entry into the Heater Bay.

21 0100 Reduced power level to 850 Mwo due to system load and to repair the '15A' feedwater Heater normal e drain valve.

1100 Increased power level to 1115 Mwe. '

24 0400 Reduced power level to 850 Mwe due to system load. ,

1130 Increased power level to 1110 Mwe. j 25 0500 Reduced power level to 850 Mwe due to system load, ';

performed weekly, monthly and quarterly surveillances. ,

2100 Increased power level to 1105 Mwe. [

27 0200 Reduced power level to 850 Mwe due to system load, performed wetkly and monthly surveillances.

t 1100 Increased power level to 1105 Mwe.

t i 31 2400 Reactor critical, generator on-line at 1090 Mwe.

l. (power level restricted due to condenser backpressure ,

concerns) l I

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ZCADTS/5 t

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

1

. - B. AMENDMENTS TO THE FACILITY LfCENSE OR TECHNICAL SPECIf! CATION (None)

C. . MAJOR CORRECTIVE MAINTENANCE TO SAFETY-RELATED EQUIPMENT (including SOR differential pressure switch failure reports).

(See Table 1)

D. LICENSEE EVENT REPORTS (Unit 1) i LIILhatter Ddt Dian.idion 91-013-00 08/07/91 Actuation of 'B' Aux Electric Equipment Room i Ventilation Charcoal Absorber due to a Defective  ;

lon12ation Detector. -,

l E. DATA-IA80LATIONS (Unit 1)  ;

1. Operating Data Report (See Table 2) f i
2. Average Daily Unit Power Level (See Table 3)' ,
3. Unit Shutdowns and Significant Power Reductions (See Table 4)  !

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MUOR CORRECTIVE MAINTENANCE TO SAFETY-RELATED EQUIPMENT- -

MORK REQijEST RESULTS AND EFFECTS NUMBER COMPONENT CAUSE OF MALFUNCTION ON SAFE Pl. ANT OPERATION CORRECTIVE ACTION LO7090 Aux. Electric Equip- 'A' Train Prefilter Mone. Replaced filter.

ment Room Ventilation l LO8994 Control Room HVAC Evaporator cooling coil Mone. Replaced valves.

'B' Evaporator thermal expansion valves.

i LO9320 'A' Main Steam Line High voltage power scpply. Spurious high radiation alarm. Replaced power supply.

. Radiation Monitor LO9337 Reactor Core Isolation EG-R valve. Yurbine govenor valve failed to Replaced valve.

Cooling Turbine close during RCIC cold quick Actuator start test.

! LO9338 Reactor Core Isolation Remote Servo. Turbine govenor valve failed to Replaced serve.

Cooling Turbine close during RCIC cold quick Govemr Valve start test.

LO9415 Hydraulic Control Accumulator charging None. Replaced charging Unit 46-39 connection leakage. connector.

j LO9638 Reactor Building Air operating teose. Dasper failed to close. Replaced hose.

Ventilation Isolation Damper IVR04YA.

LO9639 Reactor Building Defective solenoid valve. Damper failed to close. Replaced solenoid valve.

Venti 1ation Isolation j Damper IVR04YA LO9679 Reactor Mater Level Transmitter failed None. Replaced transmitter.

Transmitter.1821-N403A calibration.

(See attached SOR failure report.)

A 4

ZCADTS/5+

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1 SDILdp_Mt.ch_Inilutelat.a_ Sheet Equipment Piece Number: 1E31-N012Ab Model Ntunbor n 103AS-B203-NX-JJTTX6 Serial Number .O 2431._

Applicationi htlR bhutIiQs coolina Suction Hioh Flow Alarm Switch 1

Date and Time of Discovery 08/12./11 1024 hours0.0119 days <br />0.284 hours <br />0.00169 weeks <br />3.89632e-4 months <br /> Reactor Mode __.l._{Eun ) . Power Levels 1.001 Calita a Tolerance: 167.4 - 169.4 "WC Nominal Setpoint: 168.4 "WC Action Limita <163.0 or >173.8 "WC Reject Limits: <158.8 or >L L Q "WC ,

Technical Specification 1,imit: J3.lA "WC As Found Setpoints 180.0."WC Date and Time of Peturn to Service: 08/12/9.1 110_Q hours Model Number of Replacement Switch: 103AS-E203-NX-ddI[X6 ,

Serial Number of Replacement Switch 1Q-8-6436 DVR Number 1-1-91-021 Cause: Switch was found out of calibration. Apparent cause is h trument drift. A failure analysis of the . switch has not been _

_ CDIN'llgted.'

Corrective Action _ The switch was-immediately recalibrated and was later replaced per Work Request LO9569.

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E.3 UNIT SHUTDONNS AND POWER REDUCTIONS > 201 -

(Unit 1)

METHOD OF CORRECTIVE SHUTTING DOHN ACTIONS /Q M4ENTS YEARLY . TYPE THE REACTOR OR (LER/DVR # if F: FORCED DURATION applicable)

SEQUENTIAL DATE REASON REDUCING POWER

{YYMei) S: SCHEDULED (HOURS) l NtRIBER -

I (None) s SUM 4ARY OF OPERATION:

Several minor power reductions were required due to system The Unit remained on-line at high power throughout the month.

loading, survelliances and neintenance activities.

ZCADTS/5

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= k F. UNIQUE REPORTING REQUIREMENTS (Unit 1)

1. Safety / Relief valve operations'  ;

VALVES NO & TYPE PLANT DESCRIPTION  !

Delf ACIMILQ ACTUATION CONDITIO8( Of EVENT _

(None) l

2. ECCS System Outages  !

(See Table 5) l; I

3. Changes to the Off-Site Dose Calculation Manual j (None.)

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4. MajorchangestoRadioactiveMasteTreatmentSystems.  !

(None) t

5. Indications of failed fuel Elements._ f (None)  !

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Table 5 l f.2 ECCS System Outages j i

Note: The year and unit data has been removed from the outage number. I i

WJAGE NO. [QUlftlDE Gil2QSE  !

l' (U-0) 276 ODG01K Lubrication 1

i (U-1) 1454 IE12-F094 Inspection, determ motor 1455  !

i 1461, IDG01K-- Replace relay 1477 IE12-F074A Admin control I i

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h LASALLE NUCLEAR POWER STATION UNIT 2 HONTHLY PERFORMANCE REPORT l

AUGUST 1991 COHHONHEALTH EDISON COMPANY

! NRC DOCKET NO. 050-374 LICENSE NO. NPT-18 1

ZCADTS/7

TABLE OF CDNTENTS '

(Unit 2)

I. INTRODUCTIG4 l II. REPORT A. SUMARY OF OPERATING EXPERIENCE B. AMENDMENTS TO FACILITY LICENSE OR TECHNICAL SPECIFICATIONS ,

C. MAJOR CORRECTIVE MAINTEWANCE TO SAFETY-RELATED EQUIPyr.NT D. LICENSEE EVENT REPORTS E. DATA TABULATIONS

1. Operating Data Report
2. Average Daily Unit Power Level
3. Unit Shutdowns and Power Reductions F. UNIQUE REPORTING REQUIREMENTS ,
1. Safety / Relief Valve Operations
2. ECCS System Outages
3. Oft'-Site Dose Calculation Manual Changes
4. Major Changes to Radioactive Maste Treatment System
5. Indications of failed' Fuel Elements I

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ZCADTS/7

I. 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 Hater Reactor with a designed net electrical output of 1078 Hegawatts. Haste heat is rejected to a man-made cooling pond using the Illinois River for make-up and blowdown. The architect-engineer was Sargent and Lundy and the primary construction contractor was Commonwealth Edison Company.

Il',".t Two was issued operating license nur.ber 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 complied by Michael J. Cialkowski, telephone number (815)357-6761 extension 2427.

ZCADTS/7

II. MONTHLY REPORT A. SlM4ARY Of OPERATING EXPERIENCE (Unit 2)

Du I1m Event.._ .

1 0000 Reactor critical, generator on-line at 1105 Hwo.

2 2300 Reduced power level to 900 Hwe '.< remove the ' A' Turbine Driven Reactor feed Puy from service and to place the Motor Driven Reactor feed Pump in service.

3 0210 Increased power level to 965 Hve (maximum power level due to the Motor Driven Reactor feed Pump in service).

4 1430 Removed the Motor Driven Reactor feed Pump from service and placed the 'A' Turbine Driven Reactor feed Pump in Service.

2015 Increased power level to 1100 Hve.

9 2300 Reduced power IcVel to 750 Hwe to perform rod set and scram timing.

11 0030 Increased power level to 1105 Hwe.

0500 Reduced power level to 850 Hwe due to system load.

0830 Increased power level to 1030 Hwe.

0930 Reduced power level to 965 Hwe to remove the 'B' Turbine Driven Reactor feed Pump from service due to a fire in the feed pump room.

14 0300 Reduced power level to 850 Hve due to system load.

0830 Increased power level 965 Hwe (maximum power level due to the 'B' Turbine Driven Reactor Feed Pump out of service).

16 0130 Placed the 'B' Turbins Driven Reactor feed Pump back in service.

0345 Reduced power level to 920 Hwe to perform rod set.

1130 Increased power level to 1105 Mye.

20 2330 Reduced power level to 1050 Hve for cycling of the Condensate / Condensate Booster pumps.

21 1200 Increased power level to 1110 Hwe.

ZCADTS/7

P l

II. MONTHLY REPORT (CONTINUED)

A. SUMARY Of OPERATING EXPERIENCE (Unit 2)

Day ling Event  !

l 23 1930 Reduced power level to 950 Mwe to repair the 'A'  ;

Heater Drain Pump forward valve.  ;

24 1200 Reduced power level to 930 Hve to perform rod pulls.

25 0630 Increased power level to 1100 Mwe.

28 0330 Reduced power level to 1000 Mwe due ta a trip of the

'B' Circulating Mater pump.

0630 Increased power level to 1025 Mwe. (maximum power level due to condenser backpress'Jre) 1400 Increased power level to 1095 Hwe.

31 2400 Reactor critical, generator on-line at 1100 Mwe.

l ZCADTS/7

B. AMENDMENTS TO THE FACIL11Y LICENSE OR TECHNICAL SPECIFICATION

-(None).

C. MAJOR CORRECTIVE MAINTENANCE TO SAFETY RELATED E0JIPMENT (including SOR differential pressure switch failure reports).

(See Table 1)

D. LICENSEE EVENT REPORTS (Unit 2) '

LULHusttrI Date Reis.tiniloa 91-008-00 08/11/91 '28' lurbine Driven Reactor feed Pump 011 Fire due to Leakage through a Flange Gasket.

E. DATA TABULATIONS (Unit 2)

1. Operating Data Report.

(See Table 2)

2. Average Daily Unit Power Level.

(See Table 3)

3. Unit Shutdowns' and Significant Power Reductions.

(See Table 4)

V' 2CADTS/7

C. TABLE li~tJnit ZI _

1- ItVOR CORRECTIVE MAINTDIAIICE TO SAFETY-RELATED E7JIPMENT

, MORK REQJEST ' RESULTS AND Ef tt.us

!' IIUMBER COMPONENT CAUSE OF MALFUNCTION ON SAFE PLAllT OPERATICII CORRECTIVE ACTION

LO9275 Control Room HVAC Flow meter OKY-VC165A- No indication of flow. Replaced flow meter.
j. Ammonia Detector 3

j LO9493 Residual Heat Removal Binding of recorder Failure of recorder to provide Calibrated recorder.

4 Inlet / Outlet indication. full span capability.

j. Temperature Recorder j 2E12-RC01 i

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I' (No SOR Failures this month.)

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'24 ." ? l,f54 14  ?!B 30 1.!!5- I 15 Vii 31- 1,s54 -

If 1322' i

I t

l-r, .

TABLE 4 o 3 ,

E.3 UNIT SBUTDONNS AND POWER REDUCTIONS >2M (UNIT 2)

METHOD OF CORRECTIVE TEARLT TYPE SBUTTING DONE ACTIONS /CopeeNTS SEQUENTIAL DATE Fs FORCED DURATION THE REACTOR OR (LER/DTR f if WUMBER (YYDSOD) 5: SCBEDULED (BOURS) .. REASOE REDUCING PONER asolicable)

(None)

SUBS 4 ART OF OPERATION:

The unit remained on line at high power throughout the month. Several minor power reductions were required due to systen loading and routine surveillances.

ZCADTS/7

f. l'NIQUE REPORTING REQUIREMENTS (Unit 2)
1. Safety / Relief Valve Operations VALVES NO & TYPE PLANT DESCRIPTION OF EVENT I DALE ACTUATED 8CTUAT10NS CWQ11LM (None)
2. ECCS System Outages (See Table 5.) t
3. Changes to the Off-Site Dose Calculation Manual.

(None.)

4. Major changes to Radioactive Raste Treatment Systems.

(None) ,

Indications of failed fuel Elements.

5.

(None) l f

ZCADTS/7

i,

, t -

i l'

(Unit 2) .

Table 5  !

i F.2 ECCS System Outages l l

Note: --The year and unit data has been removed from the outage number.  !

QUJAGE.NO< EQUIPMENT hiftEGSE  ;

I>

352 2DG08CA Inspection. j L

362 2E22-5001 Inspection and calibrations. [

363 j 389 2E12-F047A Perform EQ inspection.

390 391 2E12-r003A Perform EQ inspect 1on. .

392 i

409 2E12-C002C Meggar motor and lubrication. }

r k

i f

1 I

E t

f ZCADTS/7 l ,

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l l

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x.

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