ML20091F139

Monthly Operating Repts for Mar 1992 for LaSalle Nuclear Power Station

ML20091F139
Person / Time
Site:	LaSalle
Issue date:	03/31/1992
From:	Cialkowski M, Diederich G COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation
References
NUDOCS 9204160133
Download: ML20091F139 (28)

Text

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3 Commonw=lth Edison C aSalle County Nuclear Station 7601 N. 21st. Rd.

lAarseilles, ll!!nola 61341 Telephor.e 615/35T 0761 April 10, 1992 Director of Mc: lear Reactor Regulation United Statu Nuclear Regulatory Conunission Mail Station P1-137 Washington, D.C. 2055d ATTN: Document Control Desk Gentlemen:

Enclosed for your information is the monthly performance report covering LaSalle County Nuclear Power Station for March, 1992.

Very truly yours, fhk h i G. J. Diederich 6

Station Hanager .

LaSalle County Station GJD/HJC/djf Enclosure  ;

xt: A. B. Davis, NRC, Region III D. E. Hills, NRC Resident Inspector .8aSalle J. L. Roman, IL Dept. of Nuclear Safety B. Siegel, NRR Project Manager D. P. Galle, CECO D. L. Farrar, CECO INPO Records Center D. R.-Eggett, NED P. D. Doverspike, GE Resident T. J. Kovach, Manager oi' Nuclear Licensing '

W. F. Naughton, Nucicar Fuel Services Manager J. E. Lockwood, Regulatory Assurance Supervisor J. H. Gieseker, Technical Staff Supervisor H. H. Servoss, QA/NS Off Site Review Station File 9204266i33 970333 gDR ADOCK 05000373 ZCADTS/5 eDR

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lASALLE NtRLEAR POWER STATION UNIT 1 PCNTHIY PERF'ORMANCE REPORI HARCH 1992 00HHONHEALTH EDISON COMPANY NRC DOCKET NO. 050-373 LICENSE NO. NPT-11 ZCADIS/S

I TABLE OF CONTENTS l (UNIl 1) l I. INTRODUCTION l

II. REPORT  ;

A. SUMKARY OF OPERATING EXPERIENCE ,

B. AMENDMENTS TO FACILI1Y LICENSE OR TECHNICAL SPECIFICATIONS C. KAJOR CORRECTIVE MAINTENANCE TO SAFETY-RELATED EOUUHENT 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. Main Steam Relief Valve Operations

2. ECCS System Outages

3. Off-Site Dose Calculation Manual Changes

4. Hajor Changes to Radioactive Haste Treatment System

5. Indications of failed fuel Elements l

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ZCADTS/S

4 I, INTRODUCTION (Unit 1)

The LaSalle County Nuclear Power Station is a two-unit facility owned by Commonwealth Edison Company and located near Marsellies, Illinois, Each unit is a Bolling Water Reactor with a designed net electrical output of i 1078 Hegawatts. Haste heat is reje:.ted to a man-made cooling pond using the Illinois River for make-up and blowdown. The architect-tngineer was Sargent and Lundy and the primary construction contractor was Commonwealth Edison Company, Unit One was issued operating license number NPT-11 on April 17, 1982.

Initial criticality was achieved o's June 21, 1982 and comercial poser operation was comenced on January 1,1984. 1 This report was compiled by Michael J. Ciallowski, telephone number (815)357-6761, extension 2427.

p ZCADTS/S

II. MONTHLY REPORT A. SUMKARY Of OPERATING EXPERIENCE (Unit 1)

. Day ILme EY.enL _.

1 0000 Reactor critical, Generator on-line at 1130 Hve. ,

1640 Reactor scram due to loss of Main Condenser vacuum.

4 0610 Reactor critical.

5 1455 Generator on-line.

6 0645 Increased power level to 470 Hwe.

0700 Increased power level to 700 Hve.

1100 Incteased power IcVel to 850 Hve.

7 0900 Increased power level to 930 Hve.

8 1500 Increased power level to 1000 Hve (1evel held due to feedwater controller problems).

1930 Reduccd power level to 800 Hwe to place the 'A' Turbine Driven Reactor feed Pump on-line.

2100 Increased power level to 1050 Hwe.

9 0000 Increased power level to 1115 Hve.

2300 Reduced power level to 1000 Hwe to perform Reactor Protection monthly sJrveillances and Control Rod Drive exercising.

10 0830 Increased power leve' to 1130 #4we.

18 1940 Reduced power level to 1115 Hwe due to low Condensate liooster Pump suction pressure.

19 1100 Increased power level to 1130 Hwe.

20 1800 Reduced power level to 1100 Hvo to place the 'C' Condensate Pump on-line.

21 0500 Increased power level to 1130 Hwe.

l 23 2330 Reduced power level to 850 Hwe to perform a rod set

! and to perform a heater bay entry to isolate the '16A' Hetter emergency drain valve due to a yhlve leak.

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I II. HONTHLY REPORT (CONTINUiD)

/. . SUHHARY Of OPERATING EXPERIENCE (Unit 1)

Qay Ilme trent ._

24 1000 Increased porer level to 1130 Hwe.

25 0130 Reduced power level to 1000 Hve due to system load.

1000 Increased power level to 1130 Hwe.

26 0200 Reduced power level to 850 Hwe due to system load.

1000 Increased power level to 1130 Hwe.

31 2400 Reactor critical, Generator on-line at 1130 Hwe.

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l; D. AMENDr.ENTS TO THE FACILITY LICENSE OR TECHNICAL SPECIFICATION l l

(None.)

)

l C. MAJOR CORRECTIVE KAINTENANCE TO SAFETY-RELATED E()UIPHENT (including SOR differential pressure switch failure reports).

(See Table 1)

D. LICENSEE EVENT REPORTS (Unit 1)

LflLEUm_hgr 03..tr Description 92-002-00 03/11/92 Auto trip of the '10' Heater Drain System pump causing a voltage spike that was transmitted to the site electrical distribution system.

92-003-00 03/01/92 Automatic reactor scram cau ed by the loss of Hain Condenser vacuum.92-004 00 03/10/92 A fire Protection system surveillance was not completed in the required time.

E. DATA TABULATIONS (Unit 1) i

1. Operating Data Report (See Table 2)

2. Average Daily Unit Power L.. ' (See Table 3)

3. Unit Shutdowns and Significant Power Reditctions (See Table 4)

ZCADTS/5

C. TABLE 1 (Unit 1)-

MJOR COR2ECTIVE MAINTENANCE TO SAFETY-RELATED EQUIPMENT HORK REQUEST RESULTS AND EFFECTS NLHSER COMPONENT CAUSE OF MALFUNCTION ON 3AFE PLAN 1 OPEPATION CORRECTIVE ACTION L13G37 IB Diesel Generator Pressure gauges broken. Inproper Indication. Replaced gauges.

Fuel Filters L13938 Hydraulic Control Directional control valve. Multiple control rod notcn outs. Replaced valve.

Unit 14-51 L13957 Extraction Steam Valve stem separated from Resulted in 1/2 main steam Replaced stem and disc Instrument Root Valve disc. isolation, assembly.

1ES065 (No SOR Failures this month.)

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TABLE 2 E.1 OPERATING DATA REPORT

• DOCKET NO. OS( ,73 UNIT LASALLE OllE DATE April 10,1992 COMPLETED BY M.J.CIALKOWSKI TELEPlIONE ('115) 3 57-6761 -

OPERATING STKIUS

1. EEPORTIllG PERIOD: March 1992 GROSS liOURS IN REPORTING PERIOD: 744

2. - CURRENTLY AUTilORI'4 ED POWER LEVEL (Hwt): 3,323 MAX DEPENDAllLE CAPACITY (Mwe-Net.): 1,036 DESIGN ELECTRICAL RATING (Mwe-Wet): 1,078 I l

3. POWER LEVEL TO WHICH RESTRIC'ILD (IF ANY): N/A l

4. . REASON FOR RESTRICTION (IY ANY):

TilIS MONTH YEAR-TO-DATE CUMULATIVE

5. REACTOR CRITICAL TIMI.(llOURS) 682.5 2,1?.2.5 49,479.0

,- 6. REACTOR RESERVE SHUTDOWN TIME (HOURS) 0.0 0.0 1,641.2 ,

7. GENERATOR ON-LINE TIME (llOURS) 649.8 2,089.8 48,468.1

8. UNIT RESERVE SIIVTDOWN TIME (!!OURS) 0.0 0.0 1.0

9. THERMAL ENERGY GENERATED (MWilt) 2,066,741 6,739,752 141,896,731

10. ELECTRICAL ENERGY GENERATED (MWile-Groris) 702,763 2,301,84'- 47,391,615 i

11. ET.ECTRICAL ENES.GY GCNERATED (MWHe-Net) 679,927 2,234,351 45,429,496 [

12. REACIOR SERVICE FACTOR (%) 91.i 97.2 68.4 13.. REACTOR AVAILABILITY FACTOR (%) 91.7 97.2 70.7 y 14. UNIT SERVICF. FACTOR (%) 87.3 95.7 67.0 [

15. UNIT AVAILAtsII.ITY FACTOR (%) 87.3 -95.7 67.0.

-16. UNIT CAPACITY FACTOR (USING MDC) (%) .88.2 98.8 60.6  :

'17. UNIT CAPACITY FACTOR (USING DESIGN MWo) 84.8 94.9 58.3 ,

18. UNIT FORCED OUTAGE FACTOR (%) 8.6 2.9 7.4 1

19. SHUTDOWNS SCHEDU' LED OVER THE HEXT 6 MONTils (TYPE, DATE AND DURATION OF EAC}l) : Refuel Outege, 09/26/92, 12 Weeks i

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

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TABLE 3 E.2 AVERAGS DAILY (MIT FOWER LEVEL (HWe-Net)

DOCKET NO. 050-373 UNIT LASALLE Ot1E DATE April- 10,1992

,.. COMPLETED !!Y H.J.CIALK0WSKI TELEPHONE (815) 357-6761 REPORTING PERIOD March 1992 i

DAY POWER DAY POWER 1 754 17 1,101 2 -10 18 1,100 3 +11 19 1,096 1 4 -13 20 1,091 5 37 21 1,095 6 622 22 1,090 i

7 860 23 1,099 8 955 24 1,060 t

9 1,090 25 1,080 10 1,070 26 1,076 11 1,099 27 1,096 t-

.12 _ 1,100 28 1,096-13 1,103 29 1,096  !

14 1,103 30 1,096 15- 1,102 31~ 1,093 16 1,099 .

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TABLE 4 E.3 UNIT SHUTDOHNS AND PONER REDUCTIONS > 201 (Unit 1)

HETHOD OF CORRECTIVE '

YEARLY TYPE SHUTTING DONN ACTIONS / COMMENTS SEQUENTIAL DATE F: FORCED DURATION THE REACTOR OR (LER/DVR # if NUMBER (YYM00) S: SCHEDULED (HOURS) REASON REDUCING PONER applicable) ,

1 920301 F 94.25 A 3 Reactor scram due to loss of main condenser vacuum.  !

LER #92-003-00 DVR #1-1-92--0014  :

t SL49%RY OF OPERATION:

i The unit started the month at full power operation. Ist approximately 1640 on 03/01/92 e --actor scram occurred due to l loss of main condenser vacuum. The unit was returr:ed to service on 03/05/92. The unit rer Jaed on line at nigh power for the remainder of the month. Several minar power reductions were required due to system lor'ing rid maintenance activities. '

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F. UNIQUE REPORTING REQUIREMENIS (Unit 1)

1. Safety / Relief valve operations VALVES NO & TYPE PLANT DESCRIPTION D&IE ofl0AILD 6GUAIl0N CEDU10N QE_LYLHT_

03/01/92 2021-F013J Automatic 1 Scram (LER #92-003-00)  ;

2. ECCS ffstem Outages (See table 5) l

3. Changrs to the Off-Site Dose Calculation W 1ual (None.)

4. Major chinges to Radioactive Haste Treatment Sy!tems.

(None.)

5. Indications of failed fuel Elements.

(None.)

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4 (Unit 1)

Table 5 f.2 ECCS System Outaget Note: The year and unit data has been removed from the outage number.

OMIAGU10 LOW 1MENI [MBLML (U-0) 0155 00G01K Lubrication.

0160 ODG01A Install interposing relay in 0161 ACB 1413.

(U-1) 0164 IE51-C004 Notor inspection.

IE5i-C005 0180 lE22-C001 Megcer motor.

0183 1E22-S001 Lubrication.

0187 IE22-C001 Inspection and calibration. .

0194 IDG01K Lubricattori.

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LASALLE NUCLEAR P0HER STATION UNIT 2 WATl!LY PERFORMANCE REPORT MARCH 1992 COMh0NHEALTH EDISON COMPANY ,

f-B i

NRC DOCKET NO. 050-374 LICENSE NO. NPF-18 .

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lABLE Of LONTENTS (Unit 2) i l

I. INTRODUCTION l

l 1

II. REIORT A. SUMARY OF OPERATING LXPERIENCE i D. AMENDHENTS TO FACILITY LICENSE OR TECHNICAL SPECIFICATIONS C. MA30k CORRECTIVE MAINTENANCE TO SAFETf-RELATED EQ!!PHENT

0. LICENSEE EVENT REPORTS E. IIATA TABULATIONS

l. Operating Data Report

2. Average Cally Unit Power f.evel

3. Unit Shutdowns and Power Reductions F. UNI @lE klPORTING REQUIREMENTS

1. Safety / Relief Valvo Operations

2. ECf.S System Outages

3. Off-Site Ibse Calculation Manual Changes '

4. Major thanges to Radioactive Waste Treatment System

5. Indications of failed Fuel Elemer.ts l

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i I. INTRODUCTION (Unit 2) )

The LaSalle County Nuclear Power Station is a two-unit facility owned by l Comonwealth Edison Company and located near Marsellies, Illinois. Each i unit is a Boiling Hater Reactor with a designed net electrical output of  !

1078 Megawatts. Haste heat is rejected to a man-made cooling pond using the Illinois River for make-up and blowdawn. The architect-engineer was Sargent and Lundy and the primary construction contractor was Commonwealth Edison Company.

linit Two was issued operating license number NPT-18 ou December 16.

1983. Initial criticality was achieved on March 10, 1984 and comercial power operation was commenced on June 19, 1981.

This report was complied by Michael J. Clatkowski, telephone number (815)357-6761 extension 2427.

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II. HONTilLY REPORT A. SUHHARY Of OPERATING EXPERIENCE (Unit 2) i day Iin Cytst .

1 0000 Reactor subtritical, Generator off-11ne RefucI outage (L2R04) in progress. I l

31 2400 Reactor subcritical, Generator off-lino, Refuel outage (L2kO4) in progress.  ;

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B. AMENDHENTS TO THE TACILI1Y LICENSE OR TECHNICAL SPECIf!CATIO (None.)

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

(See Table 1) l D. LICENSEE EVf.NT REPORTS (Unit 2)  !

LIR_hitmber Orte D.c.sstb.iton i 92-003-00* 03/22/92 During performance of the Reactor Instrument ,

Line High Pressure Excess flow Check Valve Test an actuation of Reactor water level switches I caused the '28' HPCS Diesel Generatcr to auto start, j

,92-005 00 03/72/92 Initiation of the *28' and '2C' Low Pressure Core Injection system and a '2A' Diesel Generator auto start due to a instrument line pressure spike.

• LER #92-003-00, Unit 2 output breaker (ACB 2413) failed to close, as reported in the February 1992 report was, upon further investigallon, determined to be a non-reportable item.

LER #92-003-00 was reissued and a sumnnry is included in this report, i E. DATA TABULATIONS (Unit 2)

[.

1. Operating Data Report.

(Sce Table 2)

2. Average Daily Unit Power Level.

! (See Table 3)

3. Unit Shutdouns and Significant Power Reductions.

(See Table 4) l ZCADTS/7

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C. TAB E 1 (Unit 2) l SAFETY-R TED I -

MORK REQUEST RESULTS AND EFFECTS

, NLMBER COMPONENT CAi!SE OF MALFUNCTION CN SAFE PLANT ')PERATION CORRECTIVE ACTION LO3289 ' Automatic Depressur- Valve packing. None. Replaced valve packing.

Ization System Bottle

!.' Pressure Regulator

Stop Valve 2IN090 i

! LO4383 Low Power Range LPRM string reached LPRM string inoperable. Replaced LPRN string.

i Monitor 56 neutronic end of life.

I-l- L0e391 Suppression Pool- RTD input anellfier. Inaccurate temperature Replace RTD icput

[ Temperature' Elements indication. amplifler. ,

j  ;2TE-CM057A-B i

l. 2TE-CM057E-A .!

i 2TE-CM057V-A i I '

i i LO5384 Reactor Core Isolation t'alve pack 1r.g leakage. None. Installed new spring [

l. Cooling. Steam Supply packing.  ;

i Valve 2E51-F008 ,

LO8060 Main Steam Line Drain Torque switch. Torque switch failed when valve Replaced torque switch.  !

Valve 2B21-F019 was closed.

LO8812 250 Volt Battery Cells #77 and 114 had low Mone. Replaced cells #77 & 114.

Cells #77 and 114 ICV. ,

i LO9371 Low Power Range. LPRM string reached LPRM string inoperable. Replaced LPRM string.  !

Monitor 48-41 . neutronic end of life. [

t LO9372 Low Puser Range LPRM string reached LPRM string inoperable. Replaced LPRM string.

Monitor 32-49 neutronic end of life. ,

I l-LO9373 Low Power Range- LPRM string reached LPRM string inoperable. Replaced LPRM string.  !

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' Monitor 32-09 neutronic end of life.

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C. TABLE i (Unit 2) --CC NIClJED MNIOR CGRRECTIVE MAINTENANCE TO

SAFETY'-RELATED EQUIPMENT -

l HORK REQUEST RESULTS AND EFFECTS j

NUMBER COMPONENT _ CAUSE OF mat.FUMCTION OM SAFE PLANT OPERATION CORRECTIVE ACTION l LO9374 Low Power Range LPRM string reached LPRH string inoperable. Replaced LPRM string.  !

Monitor 24-49 neutronic end of life.

109375 Low Power Range LPRM string reached LPRM string inoperable. Replaced LPRM string.

Monitor 24-09 neutronic end of life.  :

LO9376 Low Power Range LPRM string reached LPRM string inoperable. Replaced LPRM string.

Monitor 16-49 neutronic end of Ilfe. '

LO9377 Low Power Range LPRM string reached LPRM string inoperable. Replaced LPRM string.

Monitor 16-41 neutronic end of life.

LO9378 Low Power Range LPRM string reached LPRM string inoperable. Replaced LP24 string.

Monitor 16-25 neutronic end of Ilfe. .

LO9379 Low Power Range LPRM string reached LPRM string inoperable. Peplaced LPRM string.

Monitor 16-17 neutronic end of life. l I LO9380 Low Power Range LPRM string reached LPRM string laoperable. cplaced LPRM string. [

Honitor 08-41 neutronic erd of life. -

i i LO9383 Low Power Range LPRM string reached LPRM string inoperable. Replaced LPRM string.

Monitor 32-57 neutronic end of life. l i

LO9385 Low Power Range LPRM string reached LPRM string inoperable. Replaced LPRM string.  ;

Monitor 32-25 neutronic end of life.  !

LO9387 Low Power Range LPRM string reached LPRM string inoperable. Replaced LPRM string. l Monitor 16-33 neutronic end of life.

LO9388 Low Power Range LPRM string reached LPRM string inoperable. Replaced LPRM string.

Honitor 48-33 neutronic end of life.

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C. TABLE 1 (Unit 2) -C0]TIOJED MAJOR CDRRECTIVE MAINIENANCE TO SAFETY-RELATED EQUIPMENT

! HORK REQUEST RESULTS AND EFFECIS l NUMBER COMPONENr CAUSE OF MALFUNCTION ON SAFE PLANT OPERATION CORRECTIVE ACTION l

I LO9389 Low Power Range LPRM string reached LPRA string inoperable. Replaced LPRM string.

Monitor 48-25 neutronic end of life.

LO9390 Low Power Range LPRM string reached LPRM string inoperab!e. Replaced LPRM string.

Monitor 40-49 neutronic end of life.

LO939i Low Power Range LPRM string reached LPRM string inoperable. Replaced LPRM string.

Monitor 40-09 ncutronic end of life.

LO9392 Low Power Range LPRM string reached LPRM string inoperable. Replaced LPRM string.

Monitor 40-33 neutronic cr-d of life.

L11867 tow Power Range LPRM string reached LPRM string inoperable. Replaced LPRM string.

bnitor 08-33 neutronic end of life.

L12730 Primary Containment Disc and seat leakage. Valve failed local leak rate tapped disc and seat and Ventilation Outboard testing. replaced packing.

Isolation Valve 2VPOS3A L12781 Reactor Building Valve control switch. None. Replaced control switch.

Closed Cooling Hater

, Drywell Isolation Valve 2HR!79 and 2HR180 ,

i L12828 Drywell Equipment Valve seat leakage. Valve failed local leak rate Replaced seat ring and Drain Susap Isolation testing. gasket.  !

Valve 2RE024 L129M Reactor Recirculation Valve seat leakage. Valve failed local leak rate tapped disc and seat. l Pump Seal Cooling testing.  !

Check Valve 2B33-F017A l ZCADTS/7

1 C. . TABLE 1 (Unit 2) --CONTIN'JED _

i MAJOR CORRECTIVE MAINTENANCE TO SAFETY-RELATED EQUIPMENT  !

! NORK REQJEST - RESULTS AND EFFECTS I-

_ NUMBER CONF 9fENT- CAUSE OF MALFUNCTION ON SAFE PLANT OPERATION COR*ECTIVE ACTION  !

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[ L13597 Reactor Vessel Low: Yalve' stem bent.- Valve leakage. Replaccd valve sten. l'

! Pressure Injection Line Stop Valve

[ 2B21-N413A.

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! L13669 .Residu&1 Heat. Removal Valve packing leakage. None. Adjusted packing. l Heat. Exchanger Isolation

, Valve 2E12-F011A i t

l L13815 Hydraulic Control Nitrogen cyclinder leakage. None. Replaced cylinder.

Unit 46-55' L13854 Hydraulic Centrol Scram pilot solenoid valve Mone. Replaced cover gasket.

Unit 34-19 leaking air.

! L13964 Residual Heat Removal Motor contactor. Closed contactor experienced Replaced motor cor. tactor.

L13965 Suction Cooling short circuit current when l- Isolation Valve valve was c;cled.

} 2E12-F009'

L13969 Scram Air Header Regulator valve 2IA186 Outlet header pressure not . Replaced valve.

Pressure maintained during 1/2 scrams.

j L14015 Low Power Range LPRM card. LPRM indicating downstale. Replaced LPRM card.

i Mont tor'16-25C i

L14253 Reactor Core Isolation Valve seat leakage. Valve failed local leat rate tapped disc and seats ar.d i L14254 Cooling Steam Supply testing. Installed a new seal ring.

. Inboard Isolation

Valve 2E51-F063 1

- L14275 Switchgear Heat Damper actuator 2TZ-VX0n88. Damper failed to cycle. Replaced dager actuator.

, Removal System Dancer 4

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I i -- C. TABLE 1 (Unit 2) J.IMTINUED ,

i 1.

MAJOR CEG ECTIVE HAINTENANCE TO -

SAFETY-PELATED ECNIPMENT 1

RESIAiS AND EFFF/

HORK REQUEST Cet S,aM.PlaiiLQP_Eh. weiRECTIVE Af (ION MtJMilE_R__ CCHPONENT CNFE OF MALFUNCTION Directional control valve Solenoid valve fis a ': laced mienoic valve Hydraulic Coni.rol L14302 i l

Unit 46-15 122. operate. cvil.

Scram pilot solenoid valve None. Rebuilt valve.

L14445 Hydrac11c Control Unit 46-47 leaking air.

Damper - actuatre 2TT VYO23A. Damper actuatar inoperable. Replaced damper actuator.

I L14610 Core Standby Cooling Systems Ventilation l Damper 2VY0lY l

Damper actuator 2TZ-VYu?.38. Damper actuator inoperable. Replaced damper actuator.

L14611 Core Standby Cooling l Systems Ventilation Damper 2VYO2Y IIRH string reached LPRM string inoperable. Replaced t.PRM string.

L97852 Low Power Range Monttor 08-49 neutronic end of life.

Direc tional conttu. valve None. Replaced directional L99035 Hydraulic Control control valve.

Unit 34-43 120.

i Reactor Core Isciation Valve packing. Seal leak off temperature Replaccd valve packin3 l L99622 reached alarm point.

Cooling Valve Inbcard Isolation Valve 2E51-F063 (ik W Failures tMs month.)

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-TABLE-2 E.1 OPERATING DATA REPORT a: .-

DOCKET NO. 050-373 UNI 1 LASALLE TWO DATE April 10,1992' COMPLETED BY M,J.CIALKOWSK1 TELEPHCHE (815) 357-6761 OPERATING STATUS

1. REPORTING-PERIOD: March 1992 GROSS HOURS IN REPORTING PERIOD: 744

2. CURRENTL'i AUTHORIZED POWER LEVE! (Mwt): 3,323 MAX DEPENDADLE CAPACITY (Mwe-Net): 1,036 DESIGN. ELECTRICAL. RATING (Mwe-Net): 1,078

'3.  : POWER LEVEL TO WHICH RESTRICTED (IF ANY): N/A

4. REASON FOR RESTRICTION'(IF ANY):

THIS MONTH YEAR-TO-DATE CUMULATIVE

5. REACTOR CRITICAL TIME (HOURS)- 0.0 84.0 45,019.8'

6. REACTOR- RESERVE SHUTDOWN TIME (HOURS) 0.0 0.0 1,716.9

. 7. GENCRATOR ON-LINE TIME (HOURS) 0.0 73.9 44,278.5 8 .' ~ UNIT' RESERVE' SHUTDOWN TIME (HOURS) 0.0 0.0 0.0

= 9. THERMAL. ENERGY. GENERATED (MWHt). 0.0 180,986 132,423,385.

F

'10. ELECTRICAL ENERGY GENERATED (MWHe-Gross) 0.0 64,274 43,954,024 j

- 11.' ELECTRICAL ENERGY GENERATED (MWHe-Net) -8,759 37,720 42,169,224-l12. REACTOR SERVICE FACTOR (%) 0.0 3.8 68.9

~

13. REACTOR AVAILABILITY FACTOR'(%) 0.0 3.8- 71.5 14.' UNIT SERVICE FACTOR (%) 0.0 3.4 67.8:

, - 15.. UNIT AVAILABILITY FACTOR (%) 0.0 3.4 67.8

16. UNIT CAPACITY FACTOR-(USING MDC) (%) -1.1 1.7 62.3 h

'17 $ . UNIT CAPACITI FACTOR . (USING DESIGN NWe) -- 3 .1 .6 59.0 18.-UNIT FORCED _ OUTAGE FACTOR (%)' O.0 0.0 13.1

- 19. SHUTD0HNS SCHEDULED OVER THE NEXT 6 MONTHS'(TYPE, DATE AND DURATION OF

, EACH):'

o 20'. 1F SHUTDOWN AT END OF REPORT PERIOD, EF'"IMATED DATE OF STARTUP: 04/09/92

{ ~s

, , - , , - ~ ,,

-TABLE.3 E.2 AVERAGE DAILY UNIT P_OWER LEVEL (MWe-Net) s.-. ,* -

• i DOCKET NO. 050-373 _ l UNIT LASALLE TWO-DATE April 10,1992-COMPLETED BY M.J.CIALKO'fSKI TELEPHONE (815) 357-6761 i REPORTING PERIOD March 1992 2

DAY POWER- DAY POWER 1 -11 17 -11 2 -10 18 -11 3 -11 19 -12.

~

4- -13 20 -12 '

.5 -13 . 21 -12 .

6 -12 22 -12

.7 -12 ~ 23 -12 3 -12 24 -12

,_ 5F .12 25- ~12

-10 -12 26 -12 11 -12 27 -12

_12 -12 26 -12 13 -12f 29 -12' >

14- -11" 30' -12 L: 15 31 -12 n,

J 16' -11 Ni 1 I

I' l[

V;

(.

l L

41 i o......., -

, . . . . . . - _.i

TABLE 4 E.3 '- UNIT SHUTDOWNS AND POWER REDUCTIONS >20%

(UNIT 2}

l METHOD OF CCERF~'"IIVE YEARLY TYPE SHUITING DOWN ACTIONS /COPMENTS SEQUENTIAL.DATE F: FORCED DURATION THE REACTOR OR (TJR/DVR # if N_JLMBER (YTHMDD) S: SCHEDULED { HOURS) REASON REDUCING POWER applicable) i 01 920104 S 744,0 C 1 Refueling outage L2R04..

SUMMARY

OF OPERATION:

The unit , ' red a scheduled refueling outage 01/04/92.

ZCADTS/7

9 F. UNIQUE REPORTING REQUIREMENTS (Unit 2)

1. Safety / Relief Valve Operations (None.)

2. ECCS System Outages (See Table 5.)

3. Changes to the Of f-Site Dose Calcolation Hai.ual.

(None.)

4. Hajor changes to Radioactive Haste Treatment Systems.

(None.)

5. Indications of failed fuel Elements.

(None.)

l i

t i

I l

l iCADTS/7 l

~. .. -. - .. . . . . ~ . ... _ . - .

(Unit 2)

Table 5 F.2 ECCS System Outages Note: The year and unit has been removed from the outage number.

DUIAGE.RO, ECFJ11M1MT IVEl'OSS 1075 2E51-F076 Perform VOTES diagnostic testing 1178 2E51-F059 Remove blank flange for modification support.

1200 2E22-F031 Removal of flushing water spool piece.

1320 2DG01K Calibrations.

1381 2E12-F4118 Valvo disassenhJy and repair.

1383 2E12-C300A Pump seal repulr.

1391 2E12 7024H Performance of operational testing.

2E12-F027H 1424 2E12-F0598 Install valvo packing.

1440 2DG01K Change soakback oil filter.

1441 2E5i-F063 Valve disassembly and repair.

1442 1444 2DG01K Inspection of the 'A' pbese 6vercurrent l relay.

l 1449 2E53-F360 Inapection and repair.

1406 2E51-F065 Valve disassembly and repair, 1463 2E51-Y063 Admanistrative DOS fr: the backfilling of the main steam lines.

1480 2E12 "024A Ths 'A' 9eridual Haat Removal system la shutdown cooling mode.

l-1487 2E22-F077- Valve disasrembly and repair.

1495 2E51-F010 valve testJng.

l 1498 2E51-F046 2E51 -F059 L

l 1530 2E12-F024B Valve testing.

2E12-F027B 1