ML20073M156

Monthly Operating Repts for Apr 1991 for LaSalle County Nuclear Power Station Units 1 & 2

ML20073M156
Person / Time
Site:	LaSalle
Issue date:	04/30/1991
From:	Cialkowski M, Diederich G COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation
References
NUDOCS 9105140262
Download: ML20073M156 (27)

Text

_ _ -.

~

Commonwnith Edison

=

LaSahe County Nuclear Station

,- /

Rural Route *1, Box 220

,V Marce Ues, llLnnis 61341 s

Telepone 815!35747c1 L

May 10, 1991 Director of Nuclear Reactor Regulation United States Nuclear Regulatory Commission Mail Station PI-137 Hashington, D.C.

20555 ATTN:

Document Control Desk l

Gentlemen:

Enclosed for your information is the monthly performance report covering LaSalle County Nuclear Power Station for April 1991.

Very truly yours, D

[8g. J. Diederich G

Station Manager 1

LaSalle County Station GJD/MJC/djf Enclosure xt:

A. B. Davis, NRC, Region III T. M. Tongue, NRC Resident Inspector LaSalle J. L. Roman, IL Dept. of Nuclear Safety i

J. B. Hickman, NRR Project Manager D. P. Galle, CECO i

D. L. Farrar, CECO l

INPO Records Center l

D. R. Eggett, NED l

J. E. Kuskey, GE Resident l

T. J. Kovach, Manager of Nuclear Licensing W. F. Naughton, Nuclear fuel Services Manager J. E. Lockwood, Regulatory Assurance Supervisor J. H. Gieseker, Technical Staff Supervisor M. M. Servoss 0A/NS Off Site Review Station File 910514o262 910430 PDR ADOCy 0500 3

ICADTS/S

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I LASALLE NUCLEAR POWER STATION UNIT 1 MONTHLY PERFORMANLE REPORT APRIL 1991 COMMONHEALTH EDISON COMPANY NRC DOCKET NO. 050-373 LICENSE NO. NPF-11 l

i ZCADTS/5

TABLE OF CONTENTS (UNIT 1)

I.

INTRODUCTION II.

REPORT A.

SUMHARY OF OPERATING EXPERIENCE D.

AMENDMENTS TO FACILITY LICENSE OR TECHNICAL SPECIFICATIONS C.

HAJOR CORRECTIVE MAINTENANCE TO SAFETY-RELATED EQUIPMENT 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.

Major Changes to Radioactive Haste Treatment System l

5.

Indications of Failed fuel Elements l

l l

ZCADTS/5

_,~ _ _, _

i

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1.

INTRODUCTION (Unit 1)

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.

j Unit One was issued operating license number NPF-II on April 17, 1982.

t 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. Cialkowski, telephone number (815)357-6761, extension 2427.

1 ZCADTS/5

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_- - =

. -.- - - - -=

II. HONTHLY REPORT i

A.

SUMMARY

OF OPERATING EXPERIENCE (Unit 1) day lLml Event 1

0000 Reactor _subtritical, generator off line, LIR04 in progress.

30 2400 Reactor subcritical, generator off line, L1R04 in

progress, I

i l

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ZCADTS/5

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

B.

AMENDHENTS TO THE FACILITV LICENSE OR TECHNICAL SPECIFICATION Technich! Specification Amendment for Management Title changes and elimination of Station Control Room Engineer turnover for Shif t Technical Advisor (Amendment #78).

C.

HAJOR CORRECTIVE HAINTENANCE TO SAFETY-RELATED EQUIPMENT (including SOR differential pressure switch failure reports).

(See Table 1)

D.

LICENSEE EVENT REPORTS (Unit 1) 1 LER Number QAlg Descriotion 91-004-00 04/01/91 Partial Group II Primary Containment isolation due to blown fuse.

91-005-00 04/10/91 Hissed Technical Specification surveillance for the Primary Containment.

E.

DATA TABULATIONS (Unit 1) 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)

ZCADTS/5 l

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TABLE 1.(Unit 1) 4 j

MAJOR CORRECTIVE MAINTENANCE TO SAFETY-RELATED EQUIPMENT-I HORK REQUEST RESULTS AND EFFECTS d'

NUMBER-COMPONENT CAUSE OF MALFUNCTION ON SAFE PLANT OPERATION CORRECTIVE ACTION LOO 776 Hydrogen Recombiner Valve motor.

None.

Replaced motor.

l-Cooling Hater Valve 1E12-F312A' LOO 931 Suppression Pool Inproper level switch Failed to alarm on high level.

Lowered level switch.

Level Switches (High) location.

1E22-N002A,1E22-N0028 LO3779 Division 1 Post LOCA Solenoid valve.

Erratic operation.

Replaced solenoid valve.

Hydrogen Monitor 1

1AIT-CM009 LO4008 Main Steam Tunca' Relay failed testing.

None.

Replaced relay.

Differential Temper-I ature Relay 1E31-K3B LO5088 Control Room Horn diaphragm.

Unable to calibrate pressure Replaced pressure i

Emergency Make-Up Fan indicator.

Indicator.

Differential Pressure Indicator OPDI-VC029 1

LO5245 Division III Low individual specific Degraded operation.

Replaced cells.

l Batteries, Cell #9, gravities.

I 16 and 24' l

LO5380 Hydraulic Control Drain stop valve leaking.

Degraded control rod operation. Replaced disk assembly j

Unit 38-11 and valve stem.

i LO5541 Low Power Range Amplifier card.

None.

Replaced amplifier card.

j Monitor 16-57A LO5861 Reactor Hater Clean Thermal overload relay.

None.

Replaced thermal overload Up Inboard Suction relay.

l Valve 1G33-F001 (See attached SOR Failure Report.)

i ZCADTS/5+

l j

t

[

t

C TABLE 1 (Unit i)

MAJOR CORRECTIVE MAINTENANCE TO SAFETY-RELATED EQUIPMENT

(

HORK REQUEST RESULTS AND EFFECTS h

NUMBER COMPONENT CAUSE OF MALFUNCTION ON SAFE PLANT OPERATION CORRECTIVE ACTION L

LO5910 Residual Heat Removal Torque switch.

Valve failed to seal completely. Replaced torque switch.

Shut-Down Cooling Failed leak rate test.

i Testable Check l

Equalizing Valve lE12-F0998 j

LO5962 Average Power Range Averaging card cracked.

None.

Replaced averaging card.

Monitor, Channel D I

IC51-K605GR LO6392 Hydraulic Control Failure of directional Degraded control rod operation. Replaced solenoid valve.

Unit 58-31 control solenoid valve.

LO6393 Hydraulic Control Instrument block valve Degraded control rod operation. Replaced valve cartridge.

Unit 38-31 leaking.

l i

LO6520 IB Diesel Generator Governor booster leaking.

Diesel failed to start when hot. Replaced shutdown solenoid, Governor sync. motor.

LO6532 Inboard Main Steam Torque switch.

Valve failed to seat completely. Replaced torque switch.

Isolation Valve Drain Failed leak rate test.

Valve IB21-F019 F

LO6546 Hydraulic Control Unit Instrument block valve Degraded control rod operation. Replaced valve cartridge.

14-07 leaking.

LO6551 Inboard Main Steam Limit switch failed to Improper indication.

Replaced limit switch.

i Line Isolation Valve reset.

1821-F0228 1

LO6591 Hydraulic Control Unit Instrument block valve Degraded control rod operation. Replaced valve.

r 58-35 leaking.

t l

ZCADTS/5+

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i

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C TABLE 1 (Unit 1)

MAJOR CORRECTIVE MAINTENANCE TO

~

l SAFETY-RELATED EQUIPMENT HORK REQUEST RESULTS AND EFFECTS l

NUMBER COMPONENT CAUSE OF MALFUNCTION ON SAFE PLANT OPERATION CORRECTIVE ACTION

_ ~

i LO6682 Hydraulic Control Instrument block valve Degraded control rod operation. Replaced valve.

Unit 42-15 leaking.

LO6633 Hydraulic Control Instrument block valve Degraded control rod operation. Replaced valve cartridge.

Unit 50-31 leaking.

5 LO6844 250 Volt Charger Ammeter and signal Improper indication.

Replaced ammeter and signal converter failed converter.

calibration.

t LO6952 Reactor Core Isolation Pump matcr brushes worn.

None.

Replaced brushes.

[

Cooling Pump 1E51-C004 L80708 Low Power Range LPRM feiled test.

None.

Replaced LPRM.

i-Monitor 40-41D L82004 Standby Liquid Valve leaking.

None.

Replaced valve.

I 4

Control Double Block Vent Valve IC41-F312 l

L92248 Main Steam Isolation Valve leaking.

None.

Replaced valve.

f l

Air Valve Assembly j

1B21-F022D j

L94730 Low Power Range LPRM damaged.

None.

Replaced LPRM.

j Monitor 48-418 L95422 ADS Accum Vent Valve Vahe leaking.

None.

Replaced valve disc.

lIN091C i

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ZCADTS/5+

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EQILdpJ. witch railuig._Ilatadhget Equipment Piece 11 umber : 1ER-110090 Model 11 umber: if2-M-D12)L-UX-C1A-JJTTX 6 i

Serial 11 umber:

M-1-212 Application:

Mal h. gam Line HialLFlow Switch Date and Time of Discovery:

21/11/21 0500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br /> Reactor Mode 1(Refue1L Fower Level

__1L Calibration Tolerance:

192A _1RamQ PSID llominal Setpoint:

103.0 rs:D Action Limits:

<98.2 or >107.8 PSID Reject Limits:

(94.8 or >111.2 PSID Technical Specification Limit 11EAPEID As Found Setpoints 103 d lSlD Date and Time of Return to Service; Dd/21/21 hours Model 11 umber of Replacement Switch if2-M-B.ifl -UX-C1A-JJTTX6 Serial 11 umber of Replacement. Switch:

16-12-MH_

DVR 11 umber 1_1.-91-053 Causes SwitI;h_actpoint_ ERA _fnund_itLtO12ranC2_ hut _the_. aesp2iDt__was not re-peatable.

Corrective Action:

The switch was replaced. The f ailed switch was. inspect.gIL

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

5 TAILE 2 E.1 OPERATING MTA FEt0Ri DOCIET NO. 050-373

~

UNil LASALLE ONE

! ATE MAf 10,1991 (MPLETED Pf M.J. CIALt0V!Il

?

TELEPHONE (815)-357-6761 OPERA!! O $1ATUS 1.

RLf0RilNG Pill 0D:

APRIL 1991 GFDSS HOURS IN REFORTING fER10D:

719

2. ' CURRENilf A')1HDillED POWER LEVEL (N(h 3,323 nAX IDEND CATAtlit (MWe-Neth 1,036 KSIM ELECTRICAL PAllN3 (Ne-Neth 1,078 3 FOUER LEVEL 10 UHICH FEilRICIED (IF ANY) (MJr-Net):

N/A 4.

REASONS FOR EESTRIC110N (if ANYh FEFORl!NG FERIOD MTA HIS MONTH YEAR TD-MIL CUMULAi!VE

5. REACTOR ERli! CAL 11hE (HOURS) 0.0 1,100.8 41,718.2 6.

REACIDR RESERVE SHUTICUN ilME (HOURS) 0.0 0.0 1,641.2 7, GENERA 10R ON-LINE ilhE (HOURS) 6.0 1,107.9 40,856.7

8. UN11 RESERVE SHU110WN ilhE tHOURS) 0.0 0.0 1,0

9. THERMAL ENERGY GENERATED (MWHt) 0 3,565,872 117,769,473

.10. ELEC1RICAL ENER6Y BENERATED (MJHe-6tess) 0 1,230,541 39,233,829 11, ELECTRICAL ENERGY GENERATED (MWHe NPt)

-8,183 1,171,607 37,54),60) 12.REACTORSERVICETAC10R(%)

0.0 38.5 64.9

13. REArTOR AVAILAtlllif FAC10R (1) 0.0 38.5 67.5 l-

'. 14. LMIL SERVICE TACTOR (!)

0.0 38.5 63.6 15 UN!! AVAIL!$1LIIT FACIOR (1) 0.1 38.5 63.6

16. UN!1 CAPACITY FACTOR (USINS MDC) (%)

-1.1 39.3

-56.4

-17. UNIT CAFAC11Y fACIOR (USING KSIM MWe) (%)

1,1 37.8 54.2 19 UN11 FORCED OUTA9E FACTOR (!)

0.0 0.0 8.3 l

19. S1fJIIOWNS SCHEDJLED DVER THE NEXT 4 h0 NTH 3 (itrE, MIE, AhD MAT!DN Of EACHh

20. IF SHUTMN AT END OF REPORT PERIOD, ESTIMATED MTE Of STARTUh 05/09/91

,._m..

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

=

2 j

DOCKET NO. 050-373 l

1AILE 3 UNil LALAllE ONE l

E.2 AVEkAC( NILY 'MT PMR LEVEL (NeNet)

MIE MAY 10,1991 l

COnPLETED BY n.J. CIAtt0VEtt i

IELEfHDNC (B15)-357-6761 l

t I

r l

AEF051 rit!Dlh Ati!L 1991 i

IAY PMR DAY F0VER j

l 1

-11 17

-11 2

11 18

-11 i

3 19

-12 i

9

-11 20

-12 5

11 21

-12 l

6

-11 22

-11 i

7

-11 23

-12 l

0

-11 24

-12 l

9

-11 25

-12 li

-11 26 12 I

11 27

-12 L.

l 12

-11 28

-12 I

13

-11 29

-12 i

i 14

-11 30

-12 15

-11 31 i.

16

-11 t

I i

a i

I

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TABLE 4 E.3 UNIT SHUTDOWNS AND POWER REDUCTIONS > 201 (Unit 1) l METHOD OF CORRECTIVE SHUTTING DOWN ACTIOi4S/ COMMENTS YEARLY TYPE SEQUENTIAL DATE F: FORCED DURATION THE REACTOR OR (LER/DVR # if NUMBER (YYMMED) S: SCHEDULED (HOURS)

REASON REDUCING P0HER applicable) 01 910216 S

719.0 C

1 Refueling outage L1R04.

l l

SUMMARY

OF OPERATION:

The unit entered a scheduled refueling outage on 02/16/91.

ZCADTS/S

F.

UNIQUE REPORTING REQUIR[HCNTS (Unit 1)

I 1.

Safety / Relief valve operations VALVES NO & TYPE PLANT DESCRIPTION DAIL ACIUAILD ACIUAROM C0!!DlH03 OL.LYL!il (None) 2.

ECCS System Outages (See Table 5) 3.

Changes to the Off-Site Dose Calculation Manual (None) 4.

Major changes to Radioactive Waste Treatment Systems.

(None) 5.

Indications of failed fuel Elements.

(None)

ZCADTS/5

(Unit 1)

Table 5 f.2 ECCS System Outages Note:

The year and unit data has been removed from the outage number.

DulhGERA MfhWI PURPOSE (U-0) 127 ODG01K Replaced cooling water relief valve.

6 128 ODG01K Replaced crankcase switch and oil pressure gauge.

(U-1) 1162 1E51-F084 Disassemble and inspect check valve.

1191 1DG034 Test relief valve.

1194 1E22-5001 Replaced relays.

1229 1E22-C003 Replaced water leg pump.

1232 lE51-f045 Inspection.

ZCADTS/5+

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LASALLE NUCLEAR POWER STATION UNIT 2 MONTHLY PERFORMANCE REPORT APRIL 1991 COMMONHEALTH EDISON COMPANY NRC DOCKET NO. 050-374 LICENSE NO. NPF-18 ZCADTS/7

~ _ _ _ _.

TABLE Of CONTENTS (Unit 2)

I.

INTRODUCTION II. REPORT A.

SUMMARY

OF OPERATING EXPERIENCE B.

AMENDHENTS TO FACILITY LICENSE OR TECHNICAL SPECIFICATIONS C.

MAJOR CORRECTIVE MAINTENANCE TO SAFETY-RELATED EQUIPMENT 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.

Off-Site Dose Calculation Manual changes 4.

Major Changes to Radioactive Haste Treatment System S.

Indications of failed fuel Elements I

ZCADTS/7

1.

INTRODUCTION (Unit ?)

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 Boiling Water 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.

Unit Two was issued operating license number NPF-18 on December 16, 1983.

Initial criticality was achieved on March 10, 1984 and commercial power operation was commenced on 3une 19, 1964.

This report was compiled by Michael J.

Cialkowski, telephone number (815)357-6761 extension 2427.

l l

l ZCADTS/7

)

II. HONTHl.Y REPORT l

A.

SUMMARY

Of OPERATING EXPERIENCE (Unit 2)

Day Ilme Event 1

0000 Reactor critical, generator on line at 1134 MHE.

3 0100 Reduced power to 1065 MHE for weekly surveillances.

0700 Increased power tr 1133 MHE.

10 0100 Reduced power to 1075 MHE for weekly surveillances.

1000 increased power to 1133 MHE.

17 0000 Reduced power to 1066 HWE for weekly surveillances.

0900 Increased power to 1134 HHE.

19 2100 Reduced power to 830 MHE for stran time testing, heater bay work and monthly surveillarces.

20 0400 Reduced power to 716 MHE for rod set.

1800 Increased power to 990 MHE.

21 0800 Reduced power to 900 MHE to remove the motor driven reactor feed pump from service and to place the turbine driven reactor feed pump in service.

22 1800 Increased power to 1130 MWE.

23 2330 Reduced power to 1060 MHE for weekly surveillances.

24 1100 Increased power to 1133 MHE.

28 0400 Reduced power. to 1000 MHE for secondar,i containment leak rate testing.

2100 Reduced power to 980 MHE for outboard main steam isolation valve testing.

29 1600 Increased power to 1126 MHE.

30 2330 Reduced power to 1060 MHE for weeH y surveillances.

2400 Reactor critical, generator on.line at 1060 MHE.

l 1

ZCA0TS/7

B.

AMENDMENTS TO THE FACILITY LICENSE OR TECHNICAL SPECIFICATION Technical Specification Amendment-for Management Title - changes and elimination of Station - Control Room Engineer turnover for Shift Technical Advisor (Amendment #62).

C.

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

(See Table 1)

D.

LICENSEE EVENT REPORTS (Unit 2)

LER Number QAla Descriotion (None.)

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 Pe.. r R >cuctions.

(See Table 4) l l

l ZCADTS/7

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TABLE.1 (Unit 2) l i

MAJOR CORREC nVE MAINTENANCE TO SAFETY-P. ELATED EQUIPMENT I

HORK REQUEST RESULTS AND EFFECTS l

NUMBER COMPONENT CAUSE OF MALFIF# TION ON SAFE PLANT OPFRATION CORRECTIVE ACTION LO6827 Intermediate range Praregulator bad.

None.

Replaced preregulator.

Monitor D

[

f LO7076 Reactor Core Isolation Broken diaphragm.

Switch inoperable.

R201 aced switch.

- Cooling Steam Flow-Isolation-Differential Pressure Switch 2E31-N007AA I

i l

i t

l i

i (See attached SOR Failure Report)

ZCADTS/7 i

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=.m.

m

SCA_dp_S wit.ch.la ilur e_D.a t a _She e t Equipment Piece Number: 2E31-H007M Model Number: 103AS-B203-HX-JJTTX6 Serial Number:

8 6-10-3 8feA Application:

RCIC Hich Steam Line Flow Isolation Switch Date and Time of Discovery:

04/24/91 1945 hours0.0225 days <br />0.54 hours <br />0.00322 weeks <br />7.400725e-4 months <br /> Reactor Mode:

1 (Run)

Power Level: 100%

Calibration Tolerance:

110.4 - 112.4 "WC Nominal Setpoint:

11 M "WC Action Limits:

<106.0 or >116.8 "WC Reject Limits:

<102. 8 or >12D d "WC Technical Specification Limit:

128.0 "WC As Found Setpoint:

"WC Date and Time of Return to Service:

D.,4/26/91 1$11 hours Model Number of Replacement Switch:

1HJAS-B2L3-NX-JJTTX6 Serial Number of Replacement Switch:

90-8-6256 l

DVR Number:

1-2-91-016 Cause:

Switch would not hold pressure durina functional testina.

l Durino insoection the switch was found to have a hole in the diachracmt The_cause 'of the hole could not be determined.

~

1 Corrective Action:

Replaced switch.

Inspected failed switch.

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TAILE 2 E.1 DPERAllNG MTA REPORT Il0CKET NO. 050-374 UNITLASALLE100 DATE haf 10,1991 COMPLE1ED If M,J. CIALK0WWI

-TELEPHONE (015)-357-6761 l OPERATING $1/ 7

' l '. REPORilNG PERIOD:

APRll 1991 SRDSS H0URS IN REPORTING PERIOD:

719

2. CUFREN'LY AUTHORIZED POVER LEVEL (MWth 3,343 MAX KPEND CAPACIT) (MWrNeth 1,036 ESIGN ELECTRICAL RATI$ (MWe-Neth 1,070 lt 3.- POUCR LEVEL TO UHICH RESTRICTED (IF AN1) (MWe-Net):

N/A l

4. REASONS FOR RESTRICTION (If ANYh REPORTINS PERIOD NTA THIS MONTH YEAR-TO-DATE CUNJLA11VE

5..DEACTOR CRITICAL TIME IH0VRS) 719.0 2,079.0 39,369.2

'6.~

REACTOR RESERVE SHUIDOWN TIME (HOURS) 0.0 0.0 1,716,9

-7.

SENERATOR ON-LINE TIME (HOURS) 719.0 2,879.0 38,726.2

- 8. UNIT RESERVE SHUTil0WN TIME (HOURS) 0.0 0.0

1. 0

9.. THEAGAL ENER6Y BENERATED (MLIHt) 2,340,360 9.457,632 114,896,607 l --10. ELECTRICAL ENERGY 6ENERATED (MWHe-Gross) 795,004 3,213.417-38,097,249 f11.- ELECTRICAL ENERGY 6ENERATED (MWHe-Net) 771,733 3,118,387 36,537,477

~12. SEACTOR SERVICE FACTOR (1) 100.0 100.0 69.8

13. REACTOR AVAILABILITY FACTOR (%)

100.0 100.0 71.7

14. UNIT SERVICE FACTOP (%)

100.0 100.0 67,6 L 15. UNIT AVAILIEILITY FACTOR (%)

100.0 100.0 67.6

16. UNIT CAPACITY FACTOR (USING HDC) (1) 103.6 104.6 61.6 l 17. UNIT CAPACITY FACTOR (USING KSIGN MWe) (%).

99.6 100.5 59.2 l

18, UNIT FORCED OUTA6E FACTOR (%)

0.0 0.0 13.9-

- 19. SHUTDOWNS SCHEl!ULED DVER THE NEXT 6 MONTHS (TYPE, MIE, AhD DURATION OF EACHh (N3NE)

20. IF SHUTDOWN AT END OF REPORT FERIOD, ESTIMATED MIE Of STARTUP:

i:.,,

,...,.-_..a 1

~

- IOCKET N0, 050-374 1AILE 3 UN11 LASALLE TWO E,2 AVERAGE MILY UNii POWER LEVEL (MWe-Net)

MIE HAY 10,1991 00nPLETEl) EY M.J. CIAlf0V$ti TELEPHONE (815)-357-6761 REPORT PERIOD:

APRIL 1991 NY POWER MY POWER 1

1,077 17 1,082 2

1,098 18 1,994 I

3 1,089 19 1,048 4

1,099 20 B66 l

l 5

1,100 21 96-l 6

1,100 22 1,963 1

7 1,054 23 1,087 l

8 1,097 24 1,078 i

f.

9 1,095 25 1,097 i

l t

10 1,088 26 1,089 i

11 1,696 27 1,089

' -1,096 28 988

-l 13 1,095 29 1,043 l

-- 14 1,697 30 1,087 i

15 1,096 31 16 1,096

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

(UNIT 2)

METHOD OF CORRECTIVE SHUTTING DOWN ACTIONS / COMMENTS YEARLY TYPE THE REACTOR OR (LER/DVR # if SEQUENTIAL DATE F: FORCED DURATION NUMBER (YYMMDD)

S: SCHEDULED (HOURS)

REASON REDUCING POWER applicable)

(None)

SUMMARY

OF OPERATION:

The unit remained On line at high power thrOughout the month.

Several minor power reductions were required for routine surveillances, heater bay work and testing.

ZCADTS//

f.

UNI @ E REPORTING REQUIREMENTS (Unit 2) 1.

Safety / Relief Valve Operations VALVES NO & TYPE PLANT DESCRIPTION R&If ACTUATED ACTUATIONS CONDITION Of EVENT (None) l 2.

ECCS System Outages (See Table 5) 3.

Changes to the Off-Site Oose Calculation Manual.

(None) 4.

Major changes _to Radioactive Haste Treatment Systems.

(None) j 5.

Indications of Failed fuel Elements.

(None) i I

ZCADTS/7 1

'8*

(Unit 2)

Table 5 F.2 ECCS System Outages Note:

The year and unit data has been removed from the outage number.

DUTAGE NO.

EQUIPMENT PURPOSE 94 2E21-C002 Lubricate coupling.

96 2E12-N413B Replace fitting on vent valve.

103 2E22-5001 Lubrication.

112 1E51-F064 Administrative control, lE51-F091 ZCADTS/7 l

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