ML20127E261
| ML20127E261 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 12/31/1992 |
| From: | Cialkowski M, Spedl G COMMONWEALTH EDISON CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 9301190228 | |
| Download: ML20127E261 (26) | |
Text
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, Commonw alth Ediso 1
. LaSailo County Nuclear Station 2601 N. 215t. Ad.
fAarsoilles, Ilknots 61341 Telephone 815/357 6'761 January 11, 1993 l
Director of Nuclear Reactor Regulation United States Nuclear Regulatory Commission Hall Station PI-137 Hashington, D.C. 20555 ATIN: Document Control Desk Gentlemen:
Enclosed for your information is the monthly performance report covering LaSalle County Nuclear Power Station for December 1992.
Very truly yours,
,, s lj r Gary F. Spedi qv Station Hanager LaSalle County Station GFS/HJC/djf Enclosure xt: A. B. Davis, NRC, Region III D. E. 11111s, NRC Resident Inspector LaSalle J. L. Roman, IL Dept. of Nuclear Safety B. Stransky, NRR Project Manager H. J. Hallace, CECO D. L. Farrar, CECO INP0 Records-Center D. R. Eggett, NED P. D. Doverspike, GE Resident T. K. Schuster, Manager of Nuclear Licensing T. A. Rieck, Nuclear fuel Services Manager J. E. Lockwood, Regulatory Assurance Supervisor H. P. Pietryga, QA/NS Off Site Review c.
40uStationFile u _t c 930)190228 921231 PDR ADOCK 05000373 R PDR
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LASALLE NUCLEAR P0HER STATION UNIT 1 e
HONTilLY PERFORMANCE REPORT DECEMBER 1992 COMMONHEALTH EDISON COMPANY NRC DOCKET NO. 050-373 LICENSE NO. NPF-11 l
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TABLE Of CONTENTS (UNIT 1)
- 1. INTRODUCTION II. REPORT A.
SUMMARY
Of OPERATING EXPERIENCE D. AMENDHENTS 10 FACILITY LICENSE OR TECHNICAL SPE(,IFICATIONS C. HAJOR CORRECTIVE HAINTENANCE 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. 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
- 5. Indications of failed fuel Elements j
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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 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 One was issued operating license number NPT-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.
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II. MONTHLY REPORT
- k. SU W RY OF OPERATING EXPERIENCE (Unit 1) liEft fJtnt Day 1 0000 Reactor sub-critical, Generator off-line, refuel outage (LIR05) in progress.
31 2400 Reactor sub-critical, Generator off-line, refuel outage (L1R05) in progress.
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l 0. AMENDHENTS TO THE FACILITY LICENSE OR TEGINICAL SPECIFICATION Technical Specification Amendment to remove the rod sequence control system and lower the rod worth minimizer setpoint to 101.
C. MAJOR CORRECTIVE HAINTENANCE 10 SAFETY-RELATED EQUIPHENT (including SC,R differential pressure switch failure reports).
(See Table 1)
D. LICENSEE EVENT REIVRIS (Unit 1)
LflLliumbfr DAin Description 92-015-00 12/01/92 Loss of Bus 141Y due to personnel error.
92-016-00 12/03/92 Unplanned ESF actuation during reactor protection system bus transfer due to personnel error.
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) 2CADTS/5
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C. TABLE 1 (Unit 1)
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MAJOR CORRECTIVE MAINTENANCE TO SAFETY-RELATED EQUIPMENT ,
HORK REQUEST RESULTS AND EFFECTS NUMBER COMPONENT CAUSE OF MALFUNCTION ON SAFE PLANT OPERATION CORRECTIVE ACTION LOl685 Low Pressure Core Valve packing leakage. None. Adjusted valve actuator
< Spray Testable Check packing.
Valve IE21-F006
Ventilation Isola- '
tion Check Damper IVR010Y LO7282 250 VDC Battery Battery cell #61. Cell failed individual cell Replaced cell.
1DC01E charge.
LO9602 Main Steam Line High HFA relay. None. Replaced relay.
Radiation Scram And Isolation.
L13046 Main Steam Line Low Valve leakage. None. Replaced valve. l Pressure Switch Stop '
Valve i L13740 Low Power Range LPRM Card Spurious upscale alarms. Replaced card.
Monitor 24-09C .
L15254 Residual Heat Removal Valve packing leakage. None. Replaced packing.
Heat Exchanger Outlet Valve IE12-F068A ,
L15387 Low Pressure Core Valve packing leakage. None. Repacked valve.
Spray Full Flow Bypass Valve IE21-F012 (No SOR failures this month.)
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C. TABLE 1 (Unit 1) FAGE 2 MAJOR CORRECTIVE MAINTENANCE TO SAFETY-RELATED EQUIPMENT RESULTS AND EFFECTS .
HORK REQUEST CORRECTIVE ACTION COMPONENT C/,USE OF HALFUNCTION ON SAFE PLANT OPERATION NUMBER i
Unable to isolate seal cooler. Replace valve disc and L15826 Residual Heat Removal Valve leakage.
stem.
Pump Seal Cooler Inlet Valve IE12-F333C None. Replaced valve disc.
L18241 Main Steam Isolation Valve leakage.
Valve Air Accumulator Check Valve 1821-F0298 None. Replaced air control L18288 Main Steam Isolation Air leakage.
valves.
Valve Air Control Valves 1821-F0228 Valve leakage. Failed pressure drop test. Replaced valve o-ring.
L18329 Main Steam Isolation Valve Accumulator Check Valve 1821-F0240.
Valve Icakage. None. Replaced valve disc.
L18736 Control Rod Drive Hydraulic Control Unit 02-31 Isolation Valve Temperature controller. Low room temperature. Replaced controller.
L18928 Division III Switch-gear Room Ventilation Broken Yoke Bushing. Unable to close valve. Replaced bushing.
L18991 Low Pressure Core Spray Suction Drain Valve 1E21-F331 Relay. None. Replaced relay.
L19102 Reactor Protection Shutdo c Scram Reset Interlack.
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C. TABLE 1 (Unit 1) PAGE 3 MAJOR CORRECTIVE MAINTENANCE TO SAFETY-RELATED EQUIPMENT HORK REQUEST RESULTS AND EFFECTS NUMBER COMPONENT CAUSE OF MALFUNCTION ON SAFE PLANT OPERATION (DRRECTIVE ACTION L19107 Control Rod Drive Nitrogen charging valve Unable to charge accumulator. Replaced valve cartridge.
Hydraulic Control leakage.
Unit 18-47 L19171 Standby Gas Treatment Cooling fan breaker Cooling fan failed to auto Replaced breaker.
Systec Cooling Fan start.
L19220 Circuit Breaker 1412 Control switch. Circuit breaker failed to open Replaced control switch.
on under voltage condition.
- L19241 Auxillary Electric Temperature switch. Switch tripping below trip Replaced switch.
Equipe?nt Room setpoint.
Compressor OVE04CA L19244 Standby Liquid Control Pump packing. Packing wall temperatures Repacked pump.
Pump IC41-C001B exceeded limit of 130 degrees fahrenheit.
L19279 Control Rod Drive Accumulator level switch. None. Replaced level switch.
Hydraulic Control Unit 38-15 ZCADTS/5+
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i TABLE 2 )
. E.1 OPERATIl3G DATA REPORT i DOCKET 110. 050 373 !
UNIT LASALLE OllE DATE January. 11, 1993-COMPLETED BY M.J.CIALKO4 SKI i OPERATI!1G STAnJS TELEPHONE (815) 357 6761 l 1
- 1. REPORTIllG PERIOD: December 1992 l GROSS 1100RS IN REPDRTIllG PERIOD: 744 i
- 2. CURREllTLY AUT!!ORIZED POWER LEVEI. (MWL): 3,323 MAX DEPENDAltLE CAPACITY (MWe-Het): 1,036 ,
DESIGlJ ELECTRICAL RATING (MWe-Het): 1,078
- 3. NMER LEVEL TO WHICil RES rRICTED (IF ANY) (MWe-Net): N/A i
4 REASoli FOR RESTRICTIOli (IF ANY):
T1115 MONTil YEAR TO DATE CUMULATIVE +
5 REACTOlt CRITICAL TIME (llOURS) 0.0 6,568.3 53,924.8
- 6. REACTOR RESERVE S11UTDGiN TIME (llOURS) 0.0 0.0 1,641.2
- 7. GENERATOR OH-LINE TIME (1100RS) 0.0 6,529.3 52,907.6 8.. UtilT RESERVE SIIUTDOWN TIME (llOURS) 0.0 0.0 -1.0
- 9. Ti!ERMAL ENERGY GENERATED (MWilt) 0 19,903,179 155,060,158
- 10. ELECTRICAL ENERGY GENERATED (MWile-Gross) 0 6,702,577 51,792,"49' ,
II. ELECTRICAL ENERGY GENERATED (MWile-Net) 8,307 6,452,945 49,648,090
- 12. REACTOR SERVICE FACTOR (%) 0.0 74.8 68.3
- 13. REACTOR AVAILADILITY-FACTOR (%) 0.0 -74.8 70.4 14.. UNIT SERVICE FACTOR (%) 0.0 74.3 67.0 ,
- 15. UNIT AVAILIBILITY FACTOR (%) 0.0 74.3 67.0
-16. UNIT CAPACITY FACTOR (USING MDC).(%) -1,1 70.9 60.7
- 17. UNIT CAPACITY FACTOR (USING DESIGN If.4e) 1.0 68.1 58.3'
.18. UNIT FORCED OUTAGE. FACTOR (%) 0.0 1.4 6.9 19 = SilUTDOWNS SCI!EDULED OVER Tile NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH):
No Outages Scheduled =
- 20. IF SilUTDOWN AT END OF REPORT PERIOD, ESTIMATED DATE'OF STARTUP: 01/22/93'
- - __- __=_ .. _. . . . _ _ . . ._ _. . . _ _ - _. _ _
TADLE 3 -
E.2 AVERAGE DAILY U1117 POWER LEVEL (MWe Ilet)
DOCKET 110 050-373 Url!T LASALLE OliE DATE January 11, 1993 COMPLETED BY M.J. CIALKOWSK1 TELEPHONE (815)-357-6761 REPORT PERIOD: December 1992 DAY POWER DAY POWER 1 -11 17 -11 2 -11 10 -11 3 -11 19 -11 4 -11 20 -11 5 -11 21 -11 6 -11 22 -11 2 7 -11 23 -11 8 -11 24 -12 9 -11 25 -12 10 -11 26 -11 11 -11 27 -12 -
12 -11 28 -11 13 -11 29 -11
-14 -11 30 -11 15 -11 31 -12.
16 -11 l
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', i E.3 UNIT SHUTDOHNS AND POWER P. EDUCTIONS > 201 (Unit 1) , I q j
, HETH00 OF CORRECTIVE d'
YEARLY TYPE SHUTTING DCHN ACTIONS /COPMENTS SEQUENTIAL DATE F: FORCED DURATION THE REACTOR OR (LER/DVR # 1f ,
NUMBER .(N) S: SCHEDULED (HOURS) REASON REDUCING POWER app 11 cable) 1 l
4 921003 S 744.0 C 1 Refcel outage (LIR05)
SutMARY OF OPERATION:
The unit entered a scheduled refueling outage on 10/03/92. Scheduled return to service is 01/22/93.
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/ T. UNIOUE R PORTING REQUIREMENTS (Unit 1) ,
1.- Safety / Relief valve operations (None.)
- 2. ECCS System Outages (See Table 5)
- 3. Changes to the Off-Site Dose Calculation Manual (None.)
- 4. Hajor changes to Radioactive Haste Treatment Systems.
(None.)
- 5. Indications of failed fuel Elements.
(None.) ,.
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(Unit 1) l l Table 5 f.2 ECCS System Outages Note: The year and unit data has been removed from the outage number.
QUIAGERQ. EOUIIHENT J3[R.[QSE 1062 1E22-f031 Remove flushing spool.
1503 IE51-f064 Administrative control.
1691 1E51-f031 Replaced seal on limitorque.
1716 IE51-f04S Install spring pack.
1878 IE12-f017A Replaced motor.
1879 IE22-f004 Administrative control.
1890 1E51-f063 Replaced seal on actuator.
1898 1012-f0908 Replaced damaged condult.
1902 IE12-f063A fill and vent the RHR system.
1905 IE12-F068A Replaced motor.
1912 IDG0lK Replace air start regulator pressure gauge.
1921 lE51-F360 Inspection and votes testing.
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LASALLE NUCLEAR P0HER STATION UNIT 2 HONillLY PERf0RMANCE REPORT DECEMBER 1992 COMMONHEALTH EDISON COMPANY NRC DOCKET NO. 050-374 LICENSE NO. NPF-18 3-ZCADTS!?
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e TABLE Of CONTENTS (Unit 2)
I. INTRODUCTION II. REPORT A.
SUMMARY
Of OPERATING EXPERIENCE B. AMENDHENTS TO FACILITY LICENSE OR TECilNICAL 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
- 5. Indications of failed fuel-Elements ZCADTS/7 i
1 I. INTRODUCTION (Unit 2)
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 Hater Reactor with a designed not 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 October 19, 1984.
This report was complied by Hichael J. Cialkowski, telephone number (815)357-6761 extension 2427.
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II. MONTHLY REPORT l A. SlM4ARY OF OPERATING EXPERIENCE (Unit 2)
Day 11m3 Event 1 0000 Reactor critical, Generator on-line at 1140 Mwe.
023ri Reduced power level to 895 Mwe due to system load.
10)0 Increased power level to 1135 Mwe.
2 0100 Reduced power level to 850 Mwe due to system load. j 1400 Increased power level to 1135 Mwe.
3 0300 Reduced power level to 1080 Mwe due to system load.
1000 Increased power level to 1135 Mwe.
4 0100 Reduced power level to 930 Mwe due to system load. ;
1030 Increased power level to 1135 Mwe.
7 0200 Reduced power level to 945 Mwe due tc ystem load.-
1200 Increased power level to 1138 Hve.
9 0230 Reduced power level to 1030 Mwe due to system load.
1100 Increased power level to 1140.Hwe. .;
10 0300 Reduced power level to 900 Mwe due to system load. i 1100 Increased power IcVel'to 1138 Mwe.
11 0100 Reduced power level to 835 Mwe due to system load.
1100 Increased power level to 1135 Mwe.
I 16 0100 Reduced power level to 995 Mwe due to system load. -
1130 Increased power level to.1138 Hve.
20 0100 Reduced power level to 990 Mwe due to system load. l 1000 Increased power level to 1138 Mwe.
21 0030 Reduced power level to 995 Mwe due:to system load.
0900 Increased power level to 1135 Mwe.
22 0300 Reduced power level to 890 Mwe due to system load.
1100 Increased power level to 1135 Mwe.
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II. HONTHLY REPORT
. A:
SUMMARY
Of OPERATING EXPERIENCE (Unit 2) (CONTINUED) day limi Event 23 0200 Reduced power level to 1025 Hve due to system load.
0930 Increased power levc! to 1135 Hve.
25 0100 Reduced power level to 850 Hve due to system load.
1500 Increased power level to 1135 Hwe.
27 0130 Reduced power level to 850 Hwe due to system load.
1100 Increased power level to 990 Hwe.
1400 Reduced power level to 950 Hvo due to system load. '
1700 Increased power level to 1075 Hwe.
28 0100 Reduced power level to 965 Hwe due to system load.
1000 Increased power level to 10J5 Hve.
2100 Increased power level to 1135 Hwe.
29 0130 Reduced power level to 850 Hwe due to system load.
1030 Increased power level to 1132 Hve.
30 0100 Reduced power level to 850 Hwe due to system load.
1200 Increased power level to 1132 Hwe.
31 0030 Reduced power level to 950 Hwe due to system load.
0300 Reduced power level to 850 Hwe due to system load.
1230 Increased power level to 1133 Hve.
2400 Reactor critical, Generator on-line at 1133 Hwo.
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.B. AMENDHENTS TO THE FACILITY LICENSE OR TEOINICAL SPECIFICATION Technical Specification Amendment to remove the rod sequence control system and lower the Rod Morth Minimizer Setpoint to 101.
C. MAJOR CORRECTIVE MAINTENANCE TO SAFETY RELATED EQUIPHENT (including SOR differential pressure switch failure reports).
(See Table 1)
D. LICENSEE EVENT REPORTS (Unit 2) l LDL&LmAff DAlf EQicr1otion (None.)
l l
E. DATA TABULATIONS (Unit 2)
- 1. Operating Data Report.
(See Table 2) s
- 2. Average Daily Unii Power Level.
(See Table 3)
- 3. Unit Shutdowns and Significant Power Reductions.
(See Table 4)
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C. TABLE 1 (Unit 2)
MAJOR TRRECTIVE MAINTENANCE TO SAFETY-RELATED EQUIPMENT .
HORK REQUEST RESULTS AND EFFECTS .
NUMBER COMPONENT CAUSE OF MALFUNCTION ON SAFE PLANT OPERATION CORRECTIVE ACTION i
L15638 Auxiliary Electric Compressor OVE04CB. None. Replaced compressor.
Equipment Room Ventilation j L19178 Residual Heat Removal Va' ave motor. Motor thermals tripped during Replaced motor and ;
Full Flow Test Valve testing. actuator. '
2E12-F024A (No SOR Failures this month.) [
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. TABLE 2 i
, E.1 OPERATI!10 DATA REPORT *
?
4 DOCKET !!O. 050 373 f UNIT LASALLE *IMO L DATE January 11, 1993 L COMPLETED BY M.J.CIALKOWSKI OPERATIllG STATUS TELErilONE (815) 357 6761 !
- 1. REPORTING PERIOD: December 1992 GROSS IlOUPS It2 REPORTING PERIOD: 744
- 2. CURitEllTLY AUTl!ORIZED POWER LEVEL (MWL): 3,323 MAX DEPEllDABLE CAPACITY (MWn. Net): 1,036 i DESIG!l ELECTRICAL HATIllG (MWe-Het ): 1,078 3 l'OWER LEVEL TO WilICil RESTRICTED (ir ANY) (MWe-Net): N/A 4
4 REASOli FOR ltESTI(ICTION (IT A!1Y):
TilIS MONTil YEAR TO DATE CUMULATIVE !
- 5. l(EACTOR CRITICAL TIME (1100RS) 744,0 6,077.7 51,013.5
- 6. REACTOR ltESEHVE S!!UTDOWN TIME (HOURS) 0.0 0.0 1,710.9 7 . -- GENERATOR ON-LINE TIME (liOURS) 744.0 5,851.8- 50,056.4
'04 UNIT RESERVE SliUTDOWN TIME (HOURS) 0.v 0.0 0.0
- 9. TilEPMAL EtlERGY GENERATTD (MWilt) 2,394,204 17,772,488 150,014,887- [
- 10. ELECThiCAL ENERGY GENERATED (MWHe-Gross) 816,874 6,011,559 49,901,309
- 11. ELECTRICAL ENERGY GENERATED (MWile-Net) 793,754 5,781,429 47,912,933
- 12. REACTOR SERVICE FACTOR (%) 100.0 69.2 70.9
- l 'l . REACTOR AVAILABILITY TACTOR (%) 100.0 69.2 73.3 i
- 14. UNIT SERVICE FACTOR (%) 100,0 66.6 69.6 ,
- 15. UNIT - AVAILIDILITY FACTOR (%) 100.0 66.6 69.6 i
- 16. UNIT CAPACITY FACTOR (USING MDC) -(%) 103.0 63.5 64.3
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- 17. UNIT CAPACITY FACTOR (USING DESIGN MWe). 99.0 61.1 61.8
- 18. UNIT FORCED OUTAGE FACTOR (%) 0.0 8.4 12.6-3
- 19. SIIUTDOWNS..SCIIEDULED OVER TIIE NEXT 6 MONTHS (TYPE, DATE, AND-DURATION Or - EACH) -
-No Outages Scheduled
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- 20. IF SIIUTDOWN AT END OF REPORT- PERIOD,. ESTIMATED DATE OF STARnJP
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. - - - , ,.r-nwm,,,-- --w. m4-.w,, ..,s,,,. .,,,uns-., ,, , , . , , ,, ,,,,
TABLE 3
. E.2 AVERAGE DAILY UNIT POWER LEVEL (MWe-Het) l DOCKET NO. 050 373 UNIT LASALLE TWO DATC January 11, 1993 t COMPLETED D't M.J. CI ALKOWSKI TELf0 HONE (815)-357-6761 REPORT PERIOD: December 1992 DAY POWER DAY IDWER e_.~ .... .... .._ ......... _.........
I 1,065 17 1,103 2 1,024 18 1,102 l
3 1,092 19 1,103 4 1,049 20 1,069 5 1,101 21 1,072 6 1,102 22 1,059 7 1,066 23 1,081 H 1,099 24 1,095 9' 1,087 25 ~ 1,019 10 1,050 26 1,097 11 1,023 27 941' 1,103 28 1,023 +
12_
13 1,102 29 1,031 14 1,102 30 1,019 15 1,102- 31 1,023 16 1,069
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TABLE 4 .
E.3 UNir SHUTDOWNS AND POWER REDUCTIONS >20% .
(UNIT 2)
METHOD OF CORRECTIVE YEARLY TYPE SHUTTING DOW ACTIONS / COMMENTS SEQUENTIAL DATE F: FORCED DURATION THE REACTOR OR (LER/DVR # if NUMBER (YYMMDD_1 S: SCHEDULED (HOURS) HFJU50N REDUCING 10(ER applicable)
None.
+
SUMMARY
OF OPERATION:
The unit remained On line at high pwer throughout the month. Several minor power reductions were required due to system load and maintenance activities.
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-. 4 F. . UNIQUE REPORTING REQUIREMENTS (Unit 2)
- 1. Safety / Relief Valve Operations (None.)
- 2. ECCS-System Outaces (See Tabic 5.)
- 3. Changes to the Off-Site Dose Calculation Manual.
(None.)
- 4. Major changes to Radioactive Haste Treatment Systems.
(None.)
- 5. Indications of failed fuel Elements.
(None.)
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(Unit 2)
Table 5 F.2 ECCS System Outages Note: The year and unit data has been removed from the outage number.
OUTAGE NO. EOUIPMENT PURPOSE.
i 2238 2E12-F024A Replace motor.
2239 .
I 2241 2E12-F003A Administrative control. l 2E12-F04BA i l
2264 2E22-S001 Calibrations. l 2265 2E22-S001 Replace oil line tubing.
2266 2E22-S001 HFA relay inspection.
t' ZCADTS/7