ML20067E552

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

ML20067E552
Person / Time
Site:	LaSalle
Issue date:	01/31/1991
From:	Cialkowski M, Diederich G COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation
References
NUDOCS 9102150117
Download: ML20067E552 (24)

Text

.... _. _... _ _ _ _.

C'N ' CommonweaHh Edison l-

['

) RuralRoute #1 Box 220 LaSalle County Nuclear Station

=

-(

-v

' Marseilles, filinois 61341

(

Telephone 816/357 6761 -

l 1

February 10, 1991 Director of Nuclear Reactor Regulation United States Nuclear Regulatory Commission Hail Station P1-137 Washington, D.C.

20555

~ ATTN: Document Control Desk Gentlemen:-

Enclosed for your information -is the monthly performance report covering I

.LaSalle County Nuclear. Power Station for January, 1991.

-r Very truly yours, 74 ko h

/

t q G. J. Diederich y Station Hanager LaSalle County Station GJD/HJC/djf Enclosure i

xt:

.A. B. Davis,'NRC, Region III

-NRC, Resident' Inspector LaSalle Ill. Dept. of Nuclear Safety R.-- Pulsifer, NRR Project Manager LD. P. Galle, CECO D. L. Farrar, CECO

-INPO Records Center D.

R.' Eggett._NED J. E. Kuskey, GE Resident T. J. Kovach,- Manager-of Nuclear Licensing

-HD F. Naughton,-Nuclear Fuel Services Manager

~

C.:F. Dillon Senior Financial Coordinator, LaSalle T. R. Novotney, INP0 Coordinator, LaSalle Station J. E. Lockwood, Regulatory Assurance Supervisor J.'W. Gieseker, Technical Staff Supervisor

. Station File 150064

,1oj,3an,,30131 PDR ADOCK 05000373 a

R PDR JZCADTS/5-

'If

i LASALLE NUCLEAR POWER STATION

'JNIT 1 MONTHLY PERFORMANCE REPORT JANUARY 1991 COMMONWEALTH EDISON COMPANY NRC DOCKET NO. 050-373 LICENSE NO. NPF-11 i

ZCADTS/5 I

1

s 4.

TABLE OF CONTENTS (UNIT 1) 1.

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.

Main Steam Relief Valve Operations 2.

ECCS System Outages 3.

Off-Site Dose Calculation Manual Chang >s 4.

Major Changes to Radioactive Haste Treatment System 5.

Indications of failed fuel Elements 1

I, L

l ZCA3TS/5

I.

INTRODUCTION (Unit 1)

The LaSalle County Nucler, Power Station is a two-unit facility owned by Commonwealth Edison Cot,pany and located near Marsellies, Illinois.

Each unit is a Boiling W:.ter Reactor with a designed net electrical output of

'4aste heat is rejected to a man-ma6t cooling pond using 1078 Megawatts.

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 One was issued operating license number NPF-11 on April 17, 1982.

Initial criticality was achieved on June 21, 1982 and commercial power operation was commenced on January 1, 1984.

This report was complied by Michael J.

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

ZCADTS/5

II. HONTHLY REPORT A.

SUMMARY

Of OPERATING EXPERIENCE (Unit 1)

DM lin 11ent 1

0000 Reactor critical, generator on-line at 1130 MWE 0215 Recuted power to 1050 MHE for CRD exercising.

1600 Increased power to 1130 MWE.

8 0200 Reduced power to 850 MHE for CR0 exercising, enrterly surveillances and to perform rod set.

1800 Increased power to 1135 MWE.

11 2345 Reduced power to 890 MHE for system load.

12 0800 Increased power to 1075 MWE.

2330 Feduced power to 745 MWE for heater drain work.

14 0300 Iricreased power to 1135 MH.

15 0100 Reduced power to 950 MWE for CRD exercising and for rod withdrawal.

1300 Incteased power to 1138 MWE.

22 0100 Redeced power to 750 MWE for rod set.

1900 Increased power to 1136 HWE.

28 0030 Reduced power to 1000 MHE for feedwater pump testing.

0600 Increased power to 1128 MWE.

29 0030 Reduced power to 970 MWE for feedwater check valve testing and rod set.

1400 Increased power to 1136 MHE.

31 2400 Reactor critical, generator on line at 1135 MWE.

ZCADTS/5

i B.

AMENDMENTS TO Tile FACILITY LICENSE OR TECliNICAL SPECIFICATION (None)

C.

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

(See Table 1)

D.

LICENSEE TVENT REPORTS (Unit 1)

LER Number-Date Digniption 90-001-00 01/23/91 rallure of relay in the Reactor Building ventilation system causes Engineered Safety Teature isolation.

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) t P

ZCADTS/5

.C-TABLE 1.(Unit.1)

~

' MAJOR CORRECTIVE MAINTENANCE W.

.SAFETT-RELATED EQUIPMENT RESULTS AND EFFECTS WOff REQUEST NUMBER' COMPONEN>

CAUSE Or. MALFUNCTION ON SAFE PLANT OPERATION CORRECTIVE ACTICE i

LO2189-1E51-COO 3

. Pump casing leaking oil None Replaced pump RCIC Water Leg. Pump LO3899 1E31-N614A-Differential temperature None Replaced switch-RER EQ Area Ventilation switch LO3386 Hydraulle Control' Bent valve stem Degraded control rod operation Replaced valve-Unit 30-59 Rebuilt unit lot 836

.OKY-VC165B

Worn cassette carrier None Ammonia Detector' guide posts

~

Rebuilt unit LO4838 OKY-VC125B Worn cassette carrier None Amunonia Detector guide posts LO5043 IVROSTA Favity relay None Replaced relay Reactor Building -

Isolation Damper

-(See attached SOR railure Report)

ZCADTS/5+

a

/

L L

SQR de Swit.ch_.EAilurg _patgLShggt Equipment Piece 11 umber: 1E31-N007AA Model Number: 103AS-E203-NX-JJTTX6 Serial Number:

86-6-2517 Application RCIC liigh Steam Line Flow Isolation Switch Date and Time of Discovery:

01/15/.21 1345 hours0.0156 days <br />0.374 hours <br />0.00222 weeks <br />5.117725e-4 months <br /> Reactor Mode 1 (Runi Power Level 100%

Calibration Tolerance:

110.4 - 112.4 "WC Nominal Setpoints 123.0 "WC Action Limits:

<1D6 Q. or >116.8 "WC Reject Limits:

<102.8 or >12.0 A "WC Technical Specification Limit 12fLD "WC As Found Setpoints "WC Date and Time of Return to Service:

01/19/9.1 0335 hours0.00388 days <br />0.0931 hours <br />5.539021e-4 weeks <br />1.274675e-4 months <br /> Model 11 umber of R. placement Switch:

1Q2hs-D203-NX-JJTTX6 Serial Number of Replacement Switch:

90-8-6256 DVR Humber:

1-1-91-002 Cause Switch would not hold pressuro durino fungtional tanting.

During inspection the switch was found to have a hole in the diaphrggm.

ThD fAuae of the_.h01tLCQuld_nQt DD 310tRImined4 Corrective Action:

Replaced switch.

Ingpggted failed switch.

c.

1.-

1,,

'- F t

. E.1 0PERA11NG DATA PI KA1 KCtEl NO. 0504373 LNIT LA3ALLE C#E

-IATE ffffuARY 10, 1971 COMPLITED Pf Haf CIALKDal TELEPHDtE (815)*357-6761 C OfTRAIDG STATUS (

Lt. kEPORt!NG PERIODi JMRARY 1901 GRDSS KtRS IN RU $ 11NG PERIOD.

-744-

4. ; CtflREWTLY #JiMRI2rD FtWJi LEVEL- (%

3,323 MX KPl.ND CthClif (MWe-Net):

-.1,036.

- K SIGN ELECTRitAt RATI E ( w e Net):

t,078

~

y

-3.

FtYJER LEVEL 10 alICH RESTRICTED (IF Nff) (PWNet):

N/A 4.L REASONS FIR RESTRICTION (if Mn:

REFSTUC FERIOD DATA THIS OfiH YEAR-10-DATE C1MJLA11VE-

,..m u s. 5. REACTOR CRITICAL TIMC ( M S)

Mt.0 744.0-41,353.4-

'6.I RE/4 TOR PistRVE !HIIKLH TIME (HluiS)-

0.0 0.0 1,641.2-

/

7.[CDDATOR OrH.IE TDi-(MyJRS)-

.744.0 744.0

-40,472.0

0.'. [ NIT RE10NE SHJ1DOW Tire (HOLRS)-

0.0 -

0.0 t,0 9 THlWK ENERGY COGATED (Mit)-1 2,404,488' 2,404,4% -

116,608,009

i:

1,0. ELECTRICet DER;Y COERATID_(Mie-Gross)'

020,925

-02S,925

.30,832,213 (iiijELECTRICtl ENEMGY GENERATED (MlHa-Net)'

B02,633' 002.633 37,172,717

.12. REACTOR SERV 1CE FACTOR ft) 100.0 100.0 44.6

13. REACitR AVAILABILITY FAC10R G)'

100.0=

100.0 47.2 114L LHIT SERVICE FACTORMX) 100.0 100.0 :

65.2 15; tiili AVAb IBILITY?FACIOR (b 100.0 100.0

65.2 i

L16', LNIT CAPACITY FACTOR-(OSIC MDC).m 104.1 104.1 57.7 017. LHli CAPACITY FACTOR (LSIK MSICN MWe)im

-100.1-100.1 55.5 m

?:18.-lHIT ffRCED OUTAGE FACTOR *(%)

0.0.-

0.0'

- 8.3

- 19i 9UittVC SCEDJLED DAR TIE NEXT 6 M0HitG (TYPE, tete, #3 ftFATION LT EACH):

--Refueling (L1R04) 02/16/91,10 WEEKS l-20. -IF Sl!Uit04N AT DtD Or FHLET PERICO, ESTIMIED DATE OF STARilF:

N/A 1

b'-

n -

n.

-r; -).

IKKCT NO. OM-373 -

/

TARE 3 __

LHITLASALLEONE_.

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- E.2 ~ ' MERCE MILY Ufli K4R LEVEL (%944el)

' MTE TURWJiY 10,1991 00hitETED PY M.J. CIALK M KI TELETHONE (8151-337-6761 PDTRT KR100:

SMJARY 1991 TN

'F%TR DM F%th

.i' 1,089 '

17 1,107 2'

i,107 18 1,iO1 3.

1,t05 19 1.,103

'4 1,100 20 1,101 15-1,i004 21 t,087 6:

1.098 -

22 981

- 7

,1,099 ---

' 23 i,11i B

t.021-

-24 i,107 N

t 19J

1,193_-

25 1,100 ~

_10 l

- 1,107

. 26 1,103 11 -

l 1,093 --

- 27L L1,076

.;12 '

977 20 1,084 1134-

-b20

,29 1,057

-- t 4

'1,078.

-30 i,iO3 f-15

.l,065 -

- 31

--1,112

)

-1,105

_-16 r

W_

___1_.1.

O ITABt.E 4

~

E.3 UNIT SHUTDOWNS AND POWER REDUCTIONS > 20%

(Unit 1)

METHOD F CORRF,CTIVE YEARLY

. TYPE SHUTTI's. DOWN

. ACTIONS / COMMENTS SEQUENTIAL DATE F: FORCED

-DURATION THE REACTOR OR (LER/DVR I if NUMBER (YYMMDD) 'S: SCHEDULED (HOURS)

REASON REDUCING POWER applicable)~

i (None)

.)

SUMMARY

OF OPERATION:

The Unit remained on line at high power throughout the month.

Several minor power reductions were required due to low grid demand, routine surveillances, and feedwater system testing ZCADTS/5

. _..__ a

~- -.. -

~.,..

~. - - - -.. - - -. - - - - -

Oiz..

~ UNIQUE REPORTING REQUIREMENTS (Unit-1)

F =. -

1.

-Safety / Relief-valve operations VALVES NO & TYPE PLANT-'

DESCRIPTION

~

QME.

ACTUATED- = ACTUATION-CONDITION OF EVENT

'(None) 2.

ECCS System Outages I

-(See Table 5).

3.

' Changes-lto the Off-Site Dose Calculation Hanual

'(None) 4.

. Major-changes-to Radioactive Haste-Treatment Systems.-

.(None)~

.5.

-Indications of Failed Fuel Elements.

.(None) 4

-5 4

. i.

+

b a

'I' e

' bif',

s

-- i a

- ZCADTS/S-

. ~

(Unitil)

Table 5.

j 4

F.2. ECCS System Outages Note:;LThe year and unit data-has been removed from the outage' number..

l

-t OUTAGE:NO.

EOUIPMENT PURPOSE

S 1DG011

Administrative control.

12 1E12-F052A-Perform surveillance LES-EQ-012.

148-1E51-C003-Rebuild water leg ' pump.1 a

61-1E51-C003 Change water leg pump minimum flow-orifice.-

77L

~1D002P-Lubricated coupling;-

79 1E22-S001 Replaced air start solenoids,

- 84'

-1E22-S001 Change, soak back oil pump filter.

97-1E12-F052

-Remove spring pack for test.

.105

.1DG01 K -

Replaced solenoids 1061 1DG01P Breaker inspection.

109~

1E12-C300D Repair cable jacket-at switchgear breaker.

113'

'1E12-F336B:

Valve maintenance.

1181 1E22-C001 Perform LES-GH-129.

?!

y 01 4

7

f. ~

t t

~

d

ZCADTS/5+1

u.- _..

m 9

l LASALLE NUCLEAR P0HER STATION UNIT 2 i

MONTHLY PERFORMANCE REPORT q

JANUARY 1991 COHHONWEALTH EDISON COMPANY NRC DOCKET NO. 050-374 LICENSE NO. NPF-18 ZCADTS/7

-.m

~

i n.

. TABLE OF CONTENTS (Unit 2)

.i I

I.

INTRODUCTION =

II. -REPORT l

A.

SUMMARY

OF OPERATING EXPERIENCE 4

B.

EAMENDHENTS T0 FACILITY LICENSE'OR TECHNICAL SPECIFICATIONS j

C.

MAJOR-CORRECTIVE MAINTENANCE.TO SAFETY-RELATED EQUIPMENT -

10.

LICENSEE EVENT REPORTS' E.

DATA TABULATIONS:

r 1

1.-

Operating Data Report 12. <. Average Daily Unit Power Level ions

-3.'

Unit Shutdowns-and-PoWor Reduct F.;

UNIQUE-REPORTING REQUIREMENTS

l.

, Safety / Relief. Valve Operations

2.

ECCS System Outages L

"3.-

Off-Site Dose Calculation Manual Changes i

4.:

Major Changes to Radioactive Haste Treatment System

~

5.-

Indications of: Failed Fuel Elements.

=;

y

- -.i i

1 L

=i 11 JZCADTS/ ^/

.=

i 4

t

-I.

INTRODUCTION (Unit 2)'

The LaSalle County Nuclear Power Station is a two-unit facility owned _by Connonwealth: 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..

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 June 19. 1984.

This report.was complied by Michael _J.

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

L

^

_j.

A

)

1 I

[

h L

L ZCADTS/7 S,

I 4

p' 111..;HONTHLY REPORT A.

SUMMARY

OF-.0PERATING EXPERIENCE (Unit 2) 1 DH lime

-Event

'l 0000 Reactor critica1, generator on line at 1130 MWE.

2300-Reduced power to-1070 MHE for CRD exercising.

f-2

1000-Increased power to 1132 HHE.

l 9i 0130 Reduced power to 1045 MWE for CRD exercising.

0730 Increased power to 1130 MHE.

l'S 2340 Reduced power to 1060 flHE_for CRD exercising, s

.16-1100

_ Increased _ power to 1133 MHE.

23-0200

. Reduced power to 1070 MHE for CRD exercising.

0930' Increased power to 1130 MWE.

26-0400 Reduced power to 750 MHE to' perform monthly / quarterly surveillances and for rod set.

1200.

Increased power to-1100 MHE.

.27 L1200 Increased power to 1132 MWE.

~

~ 30 --

l 0030 '

Reduced' power to 1064 HWE for CRD exercising.,

+

'l400' Increased _ power to_1130 MHE.

31 2400-

. Reactor-critical, generator on line at 1130 MHE.

i

'i l-4

~ZCADTS/7

t p.

~ B.'

AMENDMENTS TO TIIE TACILYTY LICENSE OR TECIINICAL SPECITICATION (None)-

C.

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

(See Table 1) 7.

LICENSEE EVENT REPORTS (Unit 2)

LER Numb 1I Data-DAActiplian 91-001-00 01/10/91 rire rated assemblies found inoperable during inspection.

E.

DATA TADULATIONS (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) i 1

e l

ZCADTS/7'

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a Eit OffRATING DATA REPORT 1 m ET NO. 050-374-Wii LASALLE TWO

~

DATE E MUtRY 10,1991 COTtETED l<Y M.J. 01/LK0WK!

TELEMDE (815)-357 6761 IFERATIE STATV5 ;

11. ? REP 0nflW FDIGD:

-JANUARY 1971

- GROSS HOURS IN REPORTIC KR!DD:

744

-2. " CURRENTLY. Al1 TWEED P0liR LEWL (st):

3,323 MX DEPEND CtPACITY-(MWe-Net) t 1,036 DESIfA ELEC1RICol RATING (NeNet):

1,0W v

3. g POWER LEWL 10 tiHICF RESTRICTED (IF ANY) OW-Net):

WA-3

-E REAC&G FOR RESTRICTION (If Avf):

i

.REPORTINGPERIODDATA

]

THIS HONTH' YEtA-TO-DATE CtN1ATIWf l5.[ REACTOR CRii!CtLl TIE THOURS)'

-744,6 744.0 137,234.2;

4XREtCTOR RESEME SWIDCW TIME (HOURS) 0.0 0.0 i~716.9, I -f GENERATOR Cte LI E T % NOURS).

744.0 744,0-

_36,591.2.

! 02 : WIT RESERVE SRfibouN IlliE (HOURS).

- 0.0

- 0.0 0.0 -

9/ TFE!LWENERGY GErDATED (MlJit)

-2,450,520

=2,450,520 107,889,693 (10. ELECTRIC /L DERGY LENERATED (MLHe-Gross) 832,572 832,572 35,7?6,404 3 U ELECTRICAL EEF3Y GENERATED:(MWe-MM

" 004,342._

006,342 34,225,432' 1

+

12hREACTOR SERVICE FACTCR (%)

100.0-100.0 :

67.5-d6 REACTOR AVAINSILITY FtCTOR (I) 100.0--

100.0:

170.7 il4;j WII SERVICE FETUR '(%)

100.0 --

109.0

'66.4 15.ilNii AVAIL 18ILITY F/CTOR (%)--

100.0 10050.

64'4.

1

16; WIT C#'/ CITY FAC10ft (USING htC) (%)-

164.6

104.6 59.9 :

f7; WIT C#'rCITY FACTCn (U$1NG IESIGN Mue) 1%)-

100.5

-100.5-57.6 = *

^ 18.: (NIT FORCED CUTACF FACTOR '(%)'

O9-0.0 14.6=

-.19. $FIUTDCt'l3 SCWDLLED OVER THE }DT 6 rDm!S (TYPE, DATE, NID DURATION OF EACH' j

(NGO i s20.IIF SK!!DOWN AT FJtD OF REPORT PERIOD, ESTimTED DATE OF Sit # TUP:

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. DOCKET to. 050 374-TABLE'3-tJHIT LA%ut. ik0 L2 - AWFEE DAILY UNIT TOER LEVEL OW-tJet)

' DATE QC1W,Y t o,1991 :

C0titETED BY NJ. CItLKOV3K!

)

TELHtDE (915)-357-6761

' I REFtRT PERIOD:

JNL%R) 1971 i

s i4 MY,-

KRR.

14Y FSER 4

t 1,090 17 i,092

- 2 1,077 -

18 1 994 4

t 3

1,093 19 1,094 4

i M2 20 1,0?3 5.

1,092' 21 1,092

6 -_

1,093 22' 1,092 T

i,093 23 1,005-8-

.1,091 24 -

1,091_

9..

1,082

25 I,089 o

~ '26 923

, 10 1,092

_ 1.1 :

.i,093 27 1,085--

. nt,0?0 -

28.

.1,006 4 i,070-,

29 _

i,057 s

v.

4

-14+

1,094 -

30 -

3,074 15

.1,0'72 ;

- 31 1,092

. (

+

1-

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. 16 j

'i,073

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N ij o

i 3

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.i-'W.+ 4 y --rt g,v r e -+*..-,yy g y -.g.

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.-g-ww, vewg e, g -w w.g m y.. s w y--,w h e, m

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

_(UNIT 2)

METHOD OF CORRECTIVE YEARLY TYPE SHUTTING DOWN ACTIONS / COMMENTS SEQUENTIAL DATE F: FORCED DURATION THE REACTOR OR (LER/DVR I if 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.

ZCADTS/7

.s, T.

UN10VE REPORTING RE001REMENTS.(Unit 2) 1.-

Safety / Relief Valve Operations VALVES.

NO t. TYPE PLANT DESCRIPTICH 4

DATI

- ACil!ATED ACIVATIONS CONDlIluti OL IYRII_

-(None) 2.

ECCS. System Octages (See Table 5) 3.-

Changes to the Off-Site Dose Calculat. ion Manual.

(None) 4.

Major changes to Radioactive Waste Treatment Systems.

(Hone) 5.

Indications of Talled fuel Elements.

(None) r l

ZCADTS/7 i

y 2

(Unit 2)

Table 5 F.2 ECCS System Outages-

=

' Note:

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

OUTAGE NO.

LQUIPMENT PURPOSE 1

2DG08CA Lubrication' maintenance.

2 2E51-F360 Replaced motor.

9 2E12-C300A -

Coupling lubrication, 2E12-C300B 12 2E12-F087A Administrative control.

15 2E21-C001 Pump lubrication.

26 2E12-C003 Pump lubrication.

30-i-

2E12-C300C Coupling lubrication.

2E12-C3000 35 2E22-S001 Soak'back oil pump maintenance, p

38 2E22-C003?

Coupling lubrication.

39 2E22-F349 Reroute piping.-

2E22-F350-

~

40 2E22-S001-Replace' circuit breaker.

-t 41:

2E22-S001 Lubrication.

c46 2E22-F349-Held repair.

-2E22-F350 50 2E51-C003 Replace orifice plate.

52-2E51-F054 Replace cable.

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- ZCADTS/7 I

L L

L 1

1-

~ ~.

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