ML20059G000
| ML20059G000 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 12/31/1993 |
| From: | Cialkowski M, Ray D COMMONWEALTH EDISON CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9401210041 | |
| Download: ML20059G000 (21) | |
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Commonw:alth Edison taSaile County Nuclear Station 2601 N. 21st. Rd.
Marseilles, Illinois 61341 Telephone 815/357-6761 January 10,1994 U.S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555 Enclosed for your information is the monthly performance report covering LaSalle County Nuclear Power Station for December 1993.
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Donald J. Ray
- Station Manager LaSalle County Station I
DJR/tmb Enclosure cc: Regional Administrator - Region Ill NRC Senior Resident inspector - LaSalle IL Department of Nuclear Safety - LaSalle NRR Project Manager - LaSalle GE Representative - LaSalle Regulatory Assurance Supervisor - LaSalle Manager of Nuclear Licensing - Downers Grove Nuclear Fuel Services Manager - General Office QA/NS Off-Site Review - General Office INPO Records Center Station File 9401210041 931231 [
PDR -ADOCK 050003 3 f 6 2 t/-
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LASAT.fR NUCLEAR POWER STATION UNIT 1 MONTHLY PERFORMANCE REPORT DECEMBER 1993 i f COMMONWEALTH EDISON COMPANY .1 I
i NRC DOCKET NO. 050-373
-i LICENSE NO. NPF-11 l i
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I TABLE OF CONTENTS (UNIT 1)
I. INTRODUCTION l II. REPORT A.
SUMMARY
OF OPERATING EXPERIENCE B. AMENDMENTS TO FACILITY LICENSE OR TECHNICAL SPECIFICATIONS .
C. MAJOR CORRECTIVE MAINTENANCE TO SAFETY-RELATED: EQUIPMENT D. LICENSEE EVENT REPORTS j 1
E. DATA TABULATIONS '
- l. Operating Data Report
- 2. Average Daily Unit Power Level
- 3. Unit Shutdowns and Power Reductions F. UNIQUE REPORTING REQUIREMENTS
- 1. Main Steam Safety Relief Valve Operations
- 2. ECCS System Outages
- 3. Off-Site Dose Calculation Manual Changes '
- 4. Major Changes to Radioactive Waste Treatment System
- 5. Indications of Failed Fuel Elements i
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.l I. 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 Water Reactor with a designed net electrical
. output of 1078 Megawatts. Waste 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 contractor was i Commonwealth Edison Company.
Unit one was issued operating license number NPF-11 on April 17, .l 1982. Initial criticality was achieved on June 21, 1982 and !
commercial power operation was commenced on January 1, 1984. '
This report was compiled by Michael J. Cialkowski, telephone number i (815)357-6761, extension 2427. 4 l
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,II. MONTHLY REPORT A.
SUMMARY
OF OPERATING EXPERIENCE (Unit 1)
Ray Time Event 1 0000 Reactor critical, Generator on-line at 1135 Mwe.
2 0300 Reduced power level to 1030 Hwe due to system. load.
1000 Increased power level to 1135 Mwe.
7 0030 Reduced power level- to 1000 Mwe to perform a rod set.
0900 Increased power level to 1135 Hwe.
12 2200 Reduced power level to 675 Mwe due to 11C Feedwater heater valve failure.
14 0200 Increased power level to 800 Hwe.
1230 Reduced power to 510 Mwe, isolated the 'C' Feedwater heater for relief valve repair.
17 0430 Increased power level to 1080 Mwe. -
18 0300 Reduced power level to 680 Mwe to perform a rod set. ,
i 1000 Increased power level to 1075 Mwe.
19 1300 Increased power level to 1130 Mwe. ;
31 2400 Reactor critical, Generator on-line at 1123 Mwe. ;
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I B. AMENDMENTS TO THE FACILITY OR TECHNICAL SPECIFICATION (None)
C. MAJOR CORRECTIVE MAINTENANCE TO SAFETY-RELATED EQUIPMENT (including I SOR differential pressure switch failure reports ).
(See Table 1)
D. LICENSEE EVENT REPORTS (Unit 1)
LER Number Date Description ,93-018 12/05/93 Reactor Protection System channel 'A' lost ,
power which caused a 1/2. scram, a group isolation and a ESF actuation. ;93-019 12/04/93 Two Safety Relief Valves were not tested as required by the Technical Specifications. l 93-020* 11/29/93 Alternate feed to the Reactor Protection System tripped while starting the Reactor Recirculation system.
- LER 93-020 was reported as LER 93-009 in the Unit 2 section of the November Monthly Report. ;
E. DATA TABULATIONS (Unit 1) i
- 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) !
F. UNIQUE REPORTING REQUIREMENTS (UNIT 1) {
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- 1. Safety Relief Valve Operations (None) ;
- 2. ECCS System Outages (None) .;
- 3. Changes to the Off-Site Dose Calculation Manual ;
(None) .
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- 4. Major Changes to Radioactive Waste Treatment Systems (None)
- 5. Indications of Failed Fuel Elements (None)
C. TABLE 1 (Unit 1) ,
MAJOR CORRECTIVE MAINTENANCE TO SAFETY-RELATED EQUIPMENT WORK RESULTS AND EFFECTS -
REQUEST COMPONENT CAUSE OF MALFUNCTION ON SAFE PLANT OPERATION CORRECTIVE ACTION L31938 High Pressure Core Damper actuator Damper failed to open Replaced actuator.
Spray pump room supply fan inlet damper IVD018Y L35909 Reactor Protection Logic card Breaker tripping Replaced logic card.
System channel 'A' elect. protection assembly breakers IC71-5003A L26000 Reactor Vessel low Control relay Erratic relay ' Replaced relay.
level 1 and 2 1B21-K100CI performance isolation logic L26114 Leakage Detection Differential Spurious alarms Replaced module.
system differential temperature module temperature switch 1E31-N603B (No SOR failures this month.)
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a TABLE 2 E.1 OPERATING DATA REPORT DOCKET No. 050-373 UNIT LASALLE ONE DATE January 10, 1994 COMPLETED BY M.J. CIALK0WSKl ,
TELEPHONE (815) 357-6761 f
OPERATING STATUS j
- 1. OEPORTING PERIOD: Decenter 1993 GROSS HOURS IN REPORTING PERIOD 744
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- 2. CURRENTLY AUTHORIZED POWER LEVEL (MWt): 3,323 MAX DEPEND CAPACITY (MWe-Net): 1,036 ;
DESIGN ELECTRICAL RATING (MWe N 1,078 !
- 3. POWER LEVEL TO WHICH RESTRICTED (If ANY) (MWe-Net): N/A
- 4. OEASONS FOR RESTRICTION (IF ANY): [
REPORTING PERIOD DATA THIS MONTH YEAR-TO DATE CUMULATIVE ,
- 5. REACTOR CRITICAL TIME (HOURS) 744.0 7,402.2- 61,326.9
- 6. REACTOR RESERVE SHUTDOWN TIME (HOURS) 0.0 0.0 1,641.2 !
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- 7. GENERATOR ON LINE TIME (HOURS) 744.0 7,106.1 60,013.7 !
- 9. UNIT RESERVE SHUTDOWN TIME (HOURS) 0.0 0.0 1.0 [
- 9. THERMAL ENERGY GENERATED (MWHt) 2,304,304 22,265,479 177,325,637 l
- 10. ELECTRICAL ENERGY GENERATED (MWHe-Gross) 783,454 7,462,022 59,254,371 l
- 11. ELECTRICAL ENERGY GENERATED (MWHe-Net) 757,114 7,200,664 56,848,754 '!
- 12. REACTOR SERVICE FACTOR (%) 100.0 84.5 69.9 I
- 13. REACTOR AVAILABILITY FACTOR (%) 100.0 84.5 71.8
- 14. UNIT SERVICE FACTOR (%) 100.0 81.1 '68.4 :
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- 15. UNIT AVAILIBILITY FACTOR (%) 100.0 81.1 68.4
- 16. UNIT CAPACITY FACTOR (USING MDC) (%) 98.2 79.3 62.6 f
- 17. UNIT CAPACITY FACTOR (USING DESIGN MWe) (%) 94.4 76.3 60.1 i
- 18. UNIT FORCED OUTAGE FACTOR (%) 0.0 11.7 7.5
- 19. SHUTDOWNS SCHEDULED DVER THE NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH):
Refuel, 03/18/94, 11 Weeks
- 20. IF SHUTDOWN AT END OF REPORT PERIOD, EST! MATED DATE OF STARTUP:
9 DOCKET NO. 050-373 TABLE 3 UNIT LASALLE ONE E.2 AVERAGE DAILY UNIT POWER LEVEL (MWe-Net) DATE January 10, 1994 COMPLETED BY M.J. CIALK0WSKI TELEPHONE (815)-357 6761 REPORT PERICO: Decenber 1993 DAY POWER DAY POWER '
1 1,098 17 974 !
2 1,086 18 972 3 1,098 19 1,067 4 1,096 20 1,093 l
5 1,093 21 1,094 6 1,091 22 1,092 i
7 1,090 23 1,093 l 8 1,098 24 1,090 e 9 1,099 25 1,088 10 1,098 26 1,085 x
11 1,097 27 1,091 0
12 1,054 28 1,089 ,
13 699 29 1,088 14 631 30 1,086 '
- 15 511 31 1,080 i
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E.3 UNIT SHUTDOWNS AND POWER REDUCTIONS > 20%
(UNIT 1)
METHOD OF CORRECTIVE YEARLY TYPE SHUTTING DOWN ACTIONS / COMMENTS i SEQUENTIAL DATE F ?ORCED DURATION THE~ REACTOR OR (I.ER/DVR # if NUMBER (YYFMDD) $t SCHEDULED (HOURS) REASON REDUCING POWER applicable) 11 931212 P 0.0 A 4 Power level reduced due to 11C Feedwater heater valve failure.
SUMMARY
.OF OPERATION:
The unit remained on-line at high power tnrous. <t the month. Several minor power reductions were required during the month due to maintenance and. routine surveillance activities.
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UNIT 2 l HONTHLY PERFORMANCE REPORT I
DECEMBER 1993 i
COMMONWEALTH EDISON COMPANY ,
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NRC DOCKET NO. 050-374 LICENSE NO. NPF-18 I
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B TABLE OF CONTENTS *
(UNIT 2) {
i I. INTRODUCTION II. REPORT !
A.
SUMMARY
OF OPERATING EXPERIENCE l B. AMENDMENTS TO FACILITY LICENSE OR TECHNICAL SPECIFICATIONS l C. HAJOR CORRECTIVE MAINTENANCE TO LAFETY-RELATED EQUIPMENT l
D. LICENSEE EVENT REPORTS ;
E. DATA TABULATIONS
- 1. Operating Data Report . <
- 2. Average Daily Unit Power Level !
- 3. Unit Shutdowns and Power Reductions l l
F. UNIQUE REPORTING REQUIREMENTS l
- 1. Main Steam Safety Relief Valve Operations ,
- 2. ECCS System Outages
- 3. Off-Site Dose Calculation Manual Changes j
- 4. Major Changes to Radioactive Waste Treatment System j
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- 5. Indications of Failed Fuel Elements I
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I. INTRODUCTION (UNIT 2)
The LaSalle County Nuclear Power Station is 4 two-Unit facility owned by Commonwealth Edison company aud located near Marseilles, Illinois. Each unit is a Boiling Water Reactor with a designed net electrical output of 1078 Megawatts. Waste 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 i contractor was commonwealth Edison company. ;
b 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 compiled by Michael J. cialkowski, telephone number- .!'
(815)357-6761, extension 2427.
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I'I . MONTHLY REPORT.
i A.
SUMMARY
OF. OPERATING EXPERIENCE (Unit 2)
DAE Time Event i 1 '0000 Reactor sub-critical, Generator off-line, rufuel outage ,
in progress. .
23 2342 Reactor critical. i 26 1426 Generator on-line at 60 Mwe. ,
1700 Power level at 165 Mwe.
2120 Main Turbine trip for overspeed testing, f
2220 Generator on-line at 164 Mwe.
t) 1315 Power level at 323 Mwe. -
30 1730 Upshifted Reactor Recirculation Pumps, power level at 475 Mwe. ;
1900 Power level at 560 Mwe.
2215 Power level at 850 Mwe, level held to perform a tip set.
31 2400 Reactor critical, Generator on-line at 840 Mwe.
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B. AMENDMENTS TO THE FACILITY OR TECHNICAL SPECIFICATION Addition of check valves for containment isolation of instrument reference leg backfill lines to Technical Specification 3.6.3-1.
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 Rate Description 93-009* 12/24/93 Reactor Water Cleanup system isolation when placing the 2B filter on-line with the reactor temperature at 317 degrees fahrenheit.93-010 12/25/93 While attempting to start the Reactor Core' Isolation Cooling system the RCIC Turbine achieved 600 RPM due to the 2E51-F045 and 2E51-F013 valves being open.
- LER 93-009 as previously reported in the November Monthly Report was renumbered to LER 93-020 and a summary is included in the Unit I section of this report. LER number 93-009 was reissued for Unit 2.
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)
F. UNIQUE REPORTINO REQUIREMENTS (UNIT 2)
- 1. Safety Relief Valve Operations (None)
- 2. ECCS System Outages (See Table 5)
- 3. Changes to the Off-Site Dose calculation Manual (None)
- 4. Major Changes to Radioactive Naste Treatment Systems (None)
- 5. Indications of Failed Fuel Elements (None)
4 C. TABLE 1 (Unit 2)
MAJOR CORRECTIVE MAINTENANCE TO SAFETY-RELATED EQUIPMENT ,
WORK RESULTS AND EFFECTS REOl'EST COMPONENT CAUSE OF MALFUNCTION - ON SAFE PLANT OPERATION , CORRECTIVE ACTION L12477 Reactor Recirc. Breaker needle bearing Breaker failed response Replaced needle bearing arc suppression time testing and cotter pins in breaker 3A operating mechanism.
Ll7850 Primary Cont. Regulator leaking None Replaced regulator.
Instrument Nitrogen system drywell suction isolation line L18937 Reactor Recire. Hydraulic actuator None Replaced actuator.
flow control leaking oil valve 2B33-F060A L24003 Reactor Recire. Stem to disc separation None Replaced drain valves.
flow control valve drains 2B33-F065A 2B33-F066A L24570 Reactor Core Leakage past seat Failed local leak rate Lapped disc.
Isolation Cooling testing steam line drain valve 2E51-F357 L24744 Reactor Recirc. Leakage past seat Failed local leak rate Lapped disc.
seal injection testing check valve 2B33-FOl7A L24797 Drywell floor Leakage past seat Failed local leak rate Rebuilt valve, drain' sump test ,
isolation valve 1 2RF012 L24814 Reactor inst. Valve leakage None Replaced valve.
reference leg isolation valve 2B21-F568
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C. TABLE 1 (Unit 2)
MAJOR CORRECTIVE MAINTENANCE TO SAFETY-RELATED EQUIPMENT WORK RESULTS AND EFFECTS REOUEST COMPONENT CAUSE OF MALFUNCTION ON SAFE PLANT OPERATION CORRECTIVE ACTION L34820 Control Rad Drive Directional control Rod drifting Replaced valve.
Hydraulic Control valve Unit 34-11 L25320 Control Rod Drive Drain valve leaking None Replaced valve.
Hydraulic Control Unit 34-35 L35327 Control Rod Drive Directional control Control valve sticking Replaced valve.
Hydraulic Control valve Unit 26-11 L35S59 Safety Relief Actuator leakage Valve failed testing Replaced actuator.
Valve 2B21-FOl3A L35560 Safety Relief Actuator leakage Valve failed testing Replaced actuator.
Valve 2B21-FOl3K L25565 Safety Relief Actuator leakage Valve failed testing Replaced actuator.
Valve 2B21-F013J L35568 Safety Relief Actuator leakage Valve failed testing Replaced actuator.
Valve 2B21-F013D L25569 Safety Relief Air valve assembly Valve failed testing Replaced air valve Valve 2B21-FOl3C leaking assembly.
L35570 Safety Relief Air actuator Valve failed testing Replaced actuator.
Valve 2B21-FOl3S L35571 Safety Relief Air actuator -Valve failed testing Replaced actuator.
Valve-2B21-F913R
'L35573 Safety Relief Air actuator Valve failed testing Replaced actuator.
Valve 2B21-F013N L35575 Safety Relief Air actuator Valve failed testing Replaced actuator.
Valve 2B21-F013V 4'
C. TABLE 1-(Unit 2)
MAJOR CORRECTIVE MAINTENANCE TO SAFETY-RELATED EQUIPMENT 1
WORK RESULTS AND EFFECTS i REQUEST COMPONENT CAUSE OF MALFUNCTION ON SAFE PLANT OPERATION CORRECTIVE ACTION L25585 Control Rod Drive Directional control Valve sticking on open Replaced valve.
Hydraulic Control valve signal Unit 06-31 L35589 -Primary Cont. Valve leaking Nous Lapped valve seat.
Instrument-Nitrogen system vent valve 2IN098M L25590 Primary cont. Valve leaking None Lapped valve seat.
Instrument
. Nitrogen system vent valve 2Ir098F L25595 Safety Relief Air actuator Velve failed testing Replaced actuator.
Valve 2B21-F013F L25702 Low Pressure Core Valve gearing. Valve failed to operate Replaced gears.
Injection manual injection valve 2E12-F092C L25756 Alternate Rod Annunciator input Trouble Alarm gave no Replaced input card.
Insertion system card indication with ARI trauble a ura system inoperable L26031 Main Steam Line Thermal overload Overload trips early Replaced overload.
drain valve 2B21-F020' L26043 Auxiliary Power Auxiliary switch . Breaker failed to R.eplaced switch main feed breaker assembly close in assembly.
to 2351 L26046 Switchgear Heat Breaker contact Supply fan failed to Replaced contactor.
Removal system start supply fan 2VIO4C
C. TABLE 1 (Unit 2)
MAJOR CORRECTIVE MAINTENANCE TO SAFETY-RELATED EQUIPMENT WORK RESULTS AND EFFECTS REQUEST COMPONENT CAUSE OF MALFUNCTION ON SAFE PLANT OPERATION CORRECTIVE ACTION L26111 Control Rod Drive Pressure switch Accumulator alarm Replace - , witch. -
Hydraulic Control failed to reset Unit 26-27 L36152 Residual Heat Limit switch No closed indication Replaced limit Removal system when valve was closed switch. ;
testable check valve 2E12-F041B
! L36208 Reactor Prot. Logic card Trip indication would Replaced logic System Elec. not clear card.
protection assembly L36235 Residual Heat Amplifier Unable to calibrate Replaced amplifier.
Removal system recorder heat exchanger '
temperature recorder 2E12-R601 L26305 Control Rod Drive Pressure switch Accumulator alarm up Replaced switch.
Hydraulic Control '
Unit 34-27 L36369 Hydrogen Recomb. Torque switch Valve-failed to open Replaced switch, isolation valve 2HG002B L85153 Main Steam Iso. Steam cute on valve None Replaced valve.
Leakage control seat Valve 2E32-F009 i
L99665 Main Steam Iso. Valve leaking None Replaced valve.
Leakage Control Valve,2E32-F008 (No SOR failures this month)
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- E .1 OPERATING DATA REPORT DOCKET NO. 050-374 UNIT LASALLE TWO ,
DATE January 10, 1994 l COMPLETED BY M.J. CIALK0WSKI TELEPHONE (815) 357-6761 i
1 OPERATING STATUS
- 1. REPORTING PERIOD: December 1993 GROSS HOURS IN REPORTING PERIOD: 744
- 2. CURRENTLY AUTHORI2ED POWER LEVEL (MWt): 3,323 MAX DEPEND CAPACITY (MWe Net): 1,036 DESIGN ELECTRICAL RATING (kwe-Net): :-1,078 i
- 3. POWER LEVEL TO WHICH RESTRICTED (IF ANY) (MWe Net): N/A 4, REASONS FOR RESTRICTION (IF ANY):
i REPORTING PERIOD DATA THl$ MONTH YEAR 10-DATE CUMULATIVE
- 5. DEACTOR CRITICAL TIME (HOURS) 192.3 5,912.1 .56,925.'6
- 6. 0.0 0.0 1,716.9J
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REACTOR RESERVE SHUTDOWN TIME (HOURS)
- 7. GENERATOR DN-LINE TIME (HOURS) 128.6 5,826.0 55,882.4
- 8. UNIT RESERVE SHUTDOWN TIME (HOURS) 0.0 0.0 0.0
- 9. THERMAL ENERGY GENERATED (MWHt) 175,035 18,085,566' :168,100,453
- 10. ELECTRICAL ENERGY GENERP.TED (MWHe-Cross) 52,702 6,083.331 55,984,640-
- 11. ELECTRICAL ENERGY GENERATED (MWHe Net) 42,576 5,842,958 53,755,891 12,' REACTOR SERVICE FACTOR (%) 25.8 67.5 70.6 i
- 13. REACTDR AVAILABILITY Fr.CTOR (%) 25.8 67.5 72.7
- 14. UDIT SERVICE FACTOR (%) 17.3 66.5 69.3 ~
- 15. UNIT AVAILIBILITY FACTOR (%) 17.3 66.5 69.3
- 16. UNIT CAPACITY FACTOR (USING MDC) (%) 5.5 64.4 64.3 t
- 17. UNIT CAPACITY FACTOR (USING DESIGN MWe) (%) 5.3 61.9 61.8 l
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- 10. UNIT FORCED suTAGE FACTOR (%) 0.0 0.0 11.4 19 - SHUTDOWNS SCHEDULED DVER THE NEXT 6 MONTHS (TYPE, DATE, AMD DURATION OF EACH)2 ,
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- 20. IF SHUTDOWN AT END OF REPORT PERIOD, EsilMATED DATE OF STARTUP:
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DOCKE1.0. 050-374 TABLE 3 UNIT LASALLE TWO E.2 AVERACE DAILY UNif POWER LEVEL (MWe Net) DATE January 10, 1994 l COMPLETED BY M.J. CIALK0WSKI-TELEPHONE (815)-357-6761 j
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REPORT PERIOD: December 1993 - -i i
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1 11 17 -12 2 -12 18 12 3 -12 19 -12 r
4 12 20 -12 ',
.+
5 -12 21 -12 6 -12 22 -12 ,
7 12 23 -12 8 -12 24 -12 ,
9 12 25 -12 10 -12 26 43 11 27 216 12 -12 28 305 13 -12 29 308 j 14 -12 30 404 15 -12 31 797 l
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TABLE 4 E.3 UNIT SHUTDOWNS AND POWER REDUCTIONS > 20% ,
(UNIT 2)
METHOD OF CORRECTIVE YEARLY TYPE SHUTTING DOWN ACTIONS /COBOENTS SEQUENTIAL DATE F FORCED DURATION THE REACTOR OR (LER/DVR # if NUMBER (YYMMDD) St SCHEDULED (HOURS) REASON REDUCING POWER applicable) 3 930904 S 614.4 C 2 Refueling Outnge (L2R05) 3 931226 S 1.0 B 4 Turbine trip for overspeed testing.
The Reactor remained critical.
1 M -RY OF OPERATION The unit entered =a scheduled refueling outage on 09/04/93. The unit was returned to service on' 12/26/93.
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Table 5 F.2 ECCS System Outages Note: The year and unit data has been removed from the outage number.
OUTAGE NO. EQUIPMENT PURPOSE 0911 2E51-C001 Repair valve and pump leakage, replace 2E51-C002 oil filter drain plugs. l 2E51-F026 2E51-F038 2E51-F039 l 2E51-F045 ;
2E51-F064 2E51-F357 i
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0929 2E51-F045 Repair valve leakage. l
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0957 2E51-C005 Repair pump shaft seal leak.
1025 2E51-C001 Repair pump seal leak.
t 1480 2E51-F022 Repair oil leak.
1629 2E12-F402 Valve repair. ,
1709 2E51-C003 Replace orifice gaskets. [
1778 2E51-C002 covernor valve inspection.
1798 2E51-C002 Repair relief valve.
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