05000457/LER-1993-006
| ML20056G008 | |
| Person / Time | |
|---|---|
| Site: | Braidwood  |
| Issue date: | 08/26/1993 |
| From: | Haeger A, Kofron K COMMONWEALTH EDISON CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| BW-93-0236, BW-93-236, LER-93-006-06, LER-93-6-6, NUDOCS 9309010147 | |
| Download: ML20056G008 (9) | |
| Event date: | |
|---|---|
| Report date: | |
| 4572093006R00 - NRC Website | |
text
i f'~N C ;m monwralth Edison l
/ rw Braidwood Nuclear Power Station i
. ~ " lZ'L y) Route *1 Box 84 V Braceville, lltinois 60407 Telephone 815/458-2801 August 26, 1993 1 BW/93-0236 l
.I l
U.S. Nuclear Regulatory Commission I Document Control Desk Washington, D.C. 20555
Dear Sir:
The enclosed Licensee Event Report from Braidwood Generating i Station is being transmitted to you with the requirement of l 10CER50.73 (a) (2) (i) (B) , which requires a 30-day written report.
This report is number 93-006-00, Docket No. 50-457. ;
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(. L._hhfron l Station Manager i Braidwood Power Station l l
Encl: Licensee Event Report !
No. 50-457/93-006-00 cc: NRC Region III Administrator NRC Resident Inspector INPO Record Center CECO Distribution List 310 ': :'.
f0fl r 9309010147 930826 E" I
)
WRC IORM 366 U.S. C3ACLE AR RECJL ATOY COMMISSIC APPff0tfED BY OMB MO. 3150-0104 l
-l (5 42) EXPIRES 5/31/95 l ESTIMATED BURDEN PER RESPONSE TO COMPLY WITH i CU LICENBEE EVENT REPORT (LER) $x,3"'$I3 3 "sg ggSEC RDlh BURDEN STIMATE b THE lhTORMAT10N AND RECORDS MAkACEMENT BRANCH (MNB9 7714), U.S. NUCLEAR REGULATORY COMMISSION, (See reverse for required rssuber of digits / characters for each block) WASHINGTON, DC 20555-0001, AND TO THE PAPERWORK ;
REDUCTION PROJECT (3150-0104), OFFICE OF MAkAGEMEhT AND BUDGET, WASHIN0 TON, DC 20503.
FACILITY KAME (1) DOCD.T WlMBER (2) PAGE (3)
Braidwood 2 05000457 1 OF 8 TITLE (4)
Operation of RH ptsap with inadequate oil supply due to clogged orifice IVE NT DATE (5) L E R WUMBE R (6) REPORT DATE (7) OTHER F ACILITIES INVOLVED (8)
SEQUENTIAL REVISION FACILITY NAME DOCKET NUMBER MONTH DAY YEAR YEAR MONTH DAY YEAR None NUMBER NUMBER 05000 FACI W NAM CKE 07 27 93 93 -- 006 -- 00 08 26 93 B 0
OPERATING y THIS REMRT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CTR i: (Check one or more) (11)
MODE (9) 20.402(b) 20.405(c) 50.73(a)(2 Hiv) 73.71(b)
POWER gg 2 MMO cW aMh) M c)
LEVEL (10) 20.405(a)(1)(ii) 50.36(c)(2) 50.73(a)(2)(vil) OTHER 20.405(eH1)(iii) X 50.73(e M2)(i) 50.73(a)(2)(vi ii)( A) (Specif y in 20.405(a)(1)(tv) 8' "
50.73(a)(2 H i i ) 50.73(a)(2)(viii)(B) 20.405(a)(1)(v) 50.73(a)(2)(ii O 50. 73(a)(2)(a ) NRC form 366A)
LICENSEE Cf*T ACT f 0R THIS LIR (12)
C1AME TELEPHONE NUMBER (Include Area Code)
A. Haeger, Regulatory Assurance (815)458-2801 x2702 COMPtFTE ONE IINE FOR EACH CfMP(WENT F AILURE DESCRISED IN THIS REPORT (13)
OR L CAUSE SYSTEM COMPONENT MANUFACTURER CAUSE SYSTEM COMPONENT MANUFACTURER X BP P W120 Yes SUPPtIMENTAt REPORT E XPECTED (14) EXPE CTED MONTH DAY VEAR YES SUBMIS$10N (if yes, conplete EXPECTED SUEMISSION DATE). DATE (15) l ABSTRACT (Limit to 1400 spaces, i.e., approximately 15 single-spaced typewritten lines) (16)
During an oil change on the 2A Residual Heat Removal (RH) pump motor, the bearing oil reservoir was unable to be drained. An investigation showed that the oil reservoir did not have an adequate amount of oil. The cause t of this event is attributed to an obstruction of the orifice separating the !
sightglass and the bearing reservoir. The cause of the obstruction is due to corrosion particles resulting from a previous seal leak. The 2A RH pump l motor was replaced. Subsequent corrective actions will include evaluating RH system seal leakage, enhancing lubrication processes, training, checki'.ig other systems with similar designs, and review of the bearing oil temperature probe. There have been no previous occurrences. I I
NRC FC?M 366 (5-92) 4 C FORM 3664 U.S. WJCLEAR RECULA ORY COWIISSION APPROVED BY CMB ho. 3150-0104 u-92) EXPIRES 5/31/95 ESTIMATED BURDEN PER RESPONSE TO COMPLY WITH l THIS INFORMATION COLLECTION REQUEST: 50.0 HRS.
i TORWARD COMMENTS REGARDING BURDEN ESTIMATE TO LICENSEE EVENT REPORT (LER) THE INFORMAT!ON AND RECORDS MANAGEMENT BRANCH TEXT CONTINUATION (MNes m 4), U.S. NUCLEAR REGULATORY COMMIS$10N, WASHINGTON, DC 20555-0001, AND TO THE PAPERWORK REDUCTION PROJECT (3150-0104), OFFICE OF MANAGEMENT AND BUDCET. WASHINGTON, DC 70503.
l FACILITY NAM (1) DOCKET WLMBER (2) LER NLMBER (6) PAGE (3)
Braidwood 2 YEAR SEQUENTIAL REVISION l 05000457 93 0
-- 0 0 6 --
1 TEXT (If more space is teouired. use additional copies of WRC Fonn >66A) (17) l A. PLANT CONDITIONS PRIOR TO EVENT:
Unit: Braidwood 2; Event Date: July 27, 1993; Event Time: 1300; j Mode: 1 - Power Operation; Rx Power:99%
RCS [AB] Temperature / Pressure: NOT/NOP B. DESCRIPTION OF EVENT:
There were no components inoperable at the beginning of the event which contributed to the severity of the avent.
During the third refueling outage on Unit 2, the mechanical seal was replaced on the 2A Residual Heat Removal J.H) punip because of a seal leak. Since the purp was due for an oil change and there appeared to be some water in the oil, the fuel handling department performed an !
oil change on April 21, 1993. During this oil change the sightglass appeared dirty so the fuel handlers cleaned the sightglass and i performed several oil flushes on the system. '
From April 23, 1993 through April 24, 1993, the 2A RH pump was run in the shutdown cooling mode of operation for 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br /> and 48 minutes.
After the outage, the system engineer contacted the unit operating engineer and requested the oil to be changed again as a precautionary measure to ensure that all the water was removed. This job was scheduled to be performed on June 28, 1993.
On June 28, 1993, prior to its regularly scheduled ASME surveillance run, the 2A RH pump was run during shift I for 30 minutes in attempts to homogenize the oil and any remaining water in support of the oil change, which was scheduled to be performed on shift 2. On shift 2 the fuel handlers began the oil change. When the oil drain plug was removed only drops of oil came out of the drain. The fuel handlers observed the sightglass and it contained the normal full level of oil.
The oil sightglass was drained and refilled with oil. The fuel handling foreman then contacted the shift engineer to inform him of the inability to drain the oil from the 2A RH pump. The operating engineer was informed and it was decided to perform the regularly scheduled ASME pump run, monitor bearing temperatures and vibrations.
The ASME pump run was conducted. The pump was run for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and 18 minutes. During this run all pump parameters were normal. The vendor was contacted and agreed on the
i NaC FORM 3en (5-92)
NRC TORM 366A U.S. WCLEAR REGULATORY COMISSION APPROVED BY OMB No. 3150-0104 )
(5-92) EXPIRES 5/31/95 l
ESTIMATED BURCEN PER RESP 0kSE TO COMPLY WITH THIS INFORMATION COLLECTION REQUEST: 50.0 HRS.
FORWARD COMMENTS REGARDlhG BURDEN ESTIMATE 10 LICENSEE EVENT REPORT (LER) THE INFORMATION AND RECORDS MANAGEMENT BRANCH TEXT CONTINUATION (MNSB 7714), U.S. NUCLEAR REGULATORY CCMMISSION, I WASHINGTON, DC 20555-0001, AND 10 THE PAPERWDRK REDUCTioW PROJECT (3150-0104), OFFICE OF MANAGEMENT AND BUDCET, WASHINGTON, DC 20503.
F ACit ITY kAE (1) DOCKET NUMBER (?) LER WLMBER (6) PAGE (3)
Braidwood 2 YEAR SEQUE NTI AL REVISION O' 300457 93 0 3 OF 8
- 006 -
TEXT (If more space is reavired, use siittional copies of NRC Form'3k (17) symptoms of a plugged oil drain. The vendor also agreed to send out a plant-specific drawing of the motor bearing and reservoir. Based on the ASME data, the correct oil level showing in the sightglass and the
. recommendation from the vendor, the decision was reached to declare l the pump operable and schedule a future oil change where the oil drain could be rodded out. This job was subsequently scheduled for July 26, 1993.
On July 26, 1993, the pump was taken out of service and the Technical Specification action statement was entered so that the fuel handlers l along with the mechanical maintenance department could change the oil and rod out the drain. The oil drain plug was removed and only several drops of oil were removed from the reservoir. An attempt was made to rod out the oil drain and to remove oil by other methods. l These were unsuccessful. Based on this and the vendor drawing that !
had been received, a question arose as to whether or not an obstruction existed in the orifice located upstream of the bearing reservoir. System engineering developed and performed a test which proved that the oil drain was not plugged and that an obstruction possibly existed within the system.
The maintenance department used air to attempt to clear the oil i system. In the process of doing this, a quantity of thick oily i material was removed from the reservoir, followed by a quantity of normal oil, followed by air. The oil system was flushed, filled and i vented. The ASME pump run was conducted again and all parameters were in the normal range. After the ASME pump run the oil was changed and it was found to be very black in color and it contained metallic material. Several oil flushes and refills were conducted with each drain containing a better looking sample of the oil. l On July 28, 1993, it was decided to send several of the oil samples offsite for analysis. In addition, a kerosene flush as recommended by the vendor manual was performed in attempts to flush any further substances from the oil reservoir. At this time it was postulated that the metallic material may not have come from the bearing but from other components in the reservoir. Oil sample results would be needed to confirm this.
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WRC FOR;I 366 (5-92)
U.S. NUCLEAR REGULATORY CupWISSION
( NRC FORM 366A APPROVED Bf OMB Wo. 3150-0104 EXPIRES 5/31/95 (5-92) i ESTIMATED BURDEN PER RESPONSE TO COMPLY WITH THIS INFORMATION COLLECTION REQUEST: 50.0 HRS.
FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO LICENSEE EVENT REPORT (LER) THE INFORMATION AND RECORDS MANAGEMENT BRANCH TEXT CONTINUATION (MNBB 7714), U.S. NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC 20555-0001, AND TO THE PAPERWORK l (3150-0104),
REDUCT ION PROJECT OFilCE OF MANAGEMEN T AND BUDGET. WASHINGTON, DC 20503.
FALILITY E M (1) DOCKET M.MnER (?) LER ItJMBER (6) FACE (3)
Braidwood 2 YEAR SEQUENTIAL REVISION 05000457 93 0 4 of 8
-- 0 0 6 --
TEXT (11 mnre space is reautred, use additional copies of NRC Form 366A) (17)
On July 29, 1993, it was decided to conservatively proceed with the i change out of the motor based on the visual condition of the oil samples.
The 2A RH pump motor was successfully replaced and tested. The action statement was exited at 0450 on August 1, 1993. i On August 5, 1993, the 2A RH pump motor was disassembled to assess the condition of the motor bearings and perform visual inspections on the !
bearing oil reservoir. Upon initial visual inspection the motor bearings appeared to be in relatively good condition, with only a :
slight discoloration of the bronze retainer ring. The bearing oil l reservoir vent pipe contained an unusual amount of rust and corrosion. !
On August 11, 1993, the bearing vendor (SKF), and Commonwealth Edison OAD personnel reported that their evaluation of the bearing showed no excessive wear. The bronze retainer ring and rollers showed discoloration due to overheating.
This event is being reported pursuant to 10CFR50.73 (a) (2) (i) (B) , any operation or condition prohibited by the plant's Technical Specifications. The 2A RH pump parameters were normal and the removed bearing showed no abnormal wear. Based on this, the pump would likely have been able to perform its injection functions as described above.
However, given the condition of the oil in the reservoir it is not certain that the RH pump could have fulfilled its design requirement of long term cooling. Thus, the pump was declared to have been inoperable since April 21, 1993, when the oil was last changed.
C. CAUSE OF THE EVENT:
The direct cause of the inadequate lubrication was the obstruction of the orifice separating the sightglass and the bearing reservoir. This obstruction prevented oil from flowing to the bearing reservoir while indicating adequate oil level.
The cause of the obstruction is corrosion due to water intrusion.
Water is known to have been present in the oil of the pump. The standpipe in the bearing reservoir was found with a great deal of corrosion. Further, since water was observed in the sightglass region, this area was also subjected to possible corrosion.
i i
tRC rcx] 3M (5-92)
NRC FORM 3664 U.S. NUCLEAR REGULATORY Capt(ISSION APPRCNED BY OMB No. 3150-0104 (5-92) EXP!RES 5/31/95 EST! MATED BURDEN PER RESPONSE TO COMPLY WITH THIS INFORMATION COLLECTION REQUEST: 50.0 HRS.
FORWARD COMMENTS REGARDING BURDEN ESilMATE TO LICENSEE EVENT REPORT (LER) THE INFORMATION AND RECORDS MANAGEMENT BRANCH TEXT CONTINUATION (MNBB 7714), U.S. NUCLEAR REGULATORY COMMIS$10N, j WASHINGTON, DC 20555-0001, AND TO THE PAPERWORK REDUCTION PROJECT (3150-0104), OFFICE OF MANAGEMENT AND BUDGFT, WASHINGTON, DC 20503.
FACILITY EAME (1) DOCKET RD4BER (2) LER ED4BER (6) PAGE (3)
Braidwood 2 ygAn SEouENTIAL REVISION ppser p yper p 05000457 93 00 5 OF 8
-- 0 0 6 --
TEXT (11 more spece is rem: ired use sifitional copies of WC Form 3%A) (17)
An investigation into the time of occurrence of the obstruction focused on the following possibilities:
Circulation of the oil. The pump vendor has stated that circulation of the oil between the reservoir and sightglass area ,
is minimal. Further, no rise in sightglass level was observed which would indicate that oil was being circulated from the reservoir to the sightglass area and remaining there due to a plugged orifice. ;
Oil leakage. Plant housekeeping records were checked. These records, combined with the system engineer's awareness of system conditions ind:Leate that no significant oil leakage was present after April 21, 1993.
4 Blockage during drain and/or refill of the oil system. During the j flushing of the oil system on April 21, 1993, corrosion could have become dislodged and plugged the orifice, preventing the correct amount of oil from reaching the reservoir on the final fill. Accurate data concerning the actual capacity of lubrication systems had not been previously available. This was not realized prior to this event. The capacities of the sightglass region and the bearing reservoir were checked and found to be approximately equal, with the sightglass region !
containing slightly more capacity than the reservoir. The total i capacity is less than two quarts, so that it would be difficult to notice a difference in the amount of oil added. Since no previous experience has indicated that sightglass level was not reliable, fuel handling department work practices have not 4 required any other means to verify that the amount of oil added is correct.
The most likely time of occurrence of the blockage was during the oil drain and/or refill on April 21, 1993. There is no other credible mechanism by which the oil could have subsequently left the reservoir.
With the oil system partially refilled, the pump ran for approximately thirty two hours. Only a small film of oil is needed to prevent l catastrophic failure of the bearing. With minimal lubrication, the bearing and oil temperatures would increase, and cause the oil that i was present to break down, turning black and beginning to solidify.
Consultation with the motor and. bearing vendors supports this conclusion.
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t'RC 7006 366 (5-92)
NRC FOR.13664 U.S. NUCLEAR REGULATORT CO> MISSION APPROVED BY CMB NO. 3150-0104 (5-92) EXPIRES 5/31/95 ESTIMATED BURDEN PER RESPONSE TO COMPLY WITH THIS INFORMATION COLLECTION REQUEST: 50.0 HRS.
FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO LICENBEE EVENT REPORT (LER) THE INFORMATION AND RECORDS MANAcEMENT SRANCH TEXT CONTINUATION (MNEB 771'), U.S. NUCLEAR REGUL ATORT COMMIS$10N, WASHINGTON, DC 20555-0001, AND TO THE PAPERWORK REDUCTION FROJECT (3150-0104), OFFICE OF MANAGEMENT AND BUDCFT, WASHINCTON, DC 20503.
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F ACILITY KAME (1) DOCK!T MLMBER (2) LER NLMBER (61 PAGE (3)
Braidwood 2 3 Egg SEQUENTIAL REVISION wmr t w w rP 6 OF 8 05000457 93 --
006 -- 00 TEXT (If enore space is re<rJired. USP Bddition81 CODies Of ARC Forn 366A) (17)
A contributing cause is that, given the unusual circumstances with the loss of oil, the bearing oil temperature probe failed to indicate the overheating condition. The oil temperature being measured did not accurately reflect the temperature seen at the bearing. This probe was added as a modification after initial pump installation. Since the design was a backfit to an existing bearing design, direct measurement of bearing temperatures was difficult. It was assumed l
that bearing oil temperatures would be reflective of actual bearing temperatures. In fact, the temperature profiles experienced in actual pump runs show the probe to have been fairly responsive to temperature changes in the past. However, due to the lack of oil in the bearing reservoir, there was minimal heat transfer to the probe, and therefore the probe failed to indicate the inadequate lubrication condition.
D. SAFETY ANALYSIS Per Technical Specifications 3.5.2 and 3.5.3 the residual heat removal system is required to be operable in modes 1 through 4. The ;
operability of two independent trains of Emergency Core Cooling (ECCS) ensures that sufficient cooling capacity is available in the event of a Loss of Coolant Accident {LOCA).
Each independent ECCS subsystem in conjunction with the safety injection accumulators ensures that fuel peak clad temperatures are within acceptable limits for all postulated LOCA's. Each ECCS subsystem also provides for long term cooling in the recovery phases of an v ident. !
1 Per UFSAR section 6.3.2 the ECCS components are designed such that a minimum of three accumulators, one charging pump, one safety injection pump, and one residual heat removal pump together with their associated piping and valves will ensure adequate core cooling in the event of a design basis accident.
Per UFSAR section 6.3.2.5 for the long term cooling function, adequate I core cooling capacity exists with one flow path removed from service.
Considering the 2A RH pump potentially inoperable and a single failure of the remaining train (2B) of residual heat removal during this period of time, there still exist other methods and proceduras to mitigate the consequences of an accident.
During a Loss of Coolant accident if the remaining train of RH was not available to perform its function as identified in BwEP-0, the operator would be directed to enter procedure BwCA 1.1, Loss of ;
Fmergency Coolant recirculation. In this nrocedure cool down of the '
NRC FORM 3h6 (5-92)
NRC f 0RM 366A U.S. NUCLEAR REGULATORY COMISSION APPROVED BY OMB NO. 3150-0104 (5-92) EXPIRES 5/31/95 ESTIMATED BURDEN PER RESPONSE TO COMPLY WITH THIS INFORMATION COLLECTION REQUEST: 50.0 HRS.
FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO LICENBEE EVENT REPORT (LER) inE throRMATioN AND RECORDS MANAGEMENT BRANCH TEXT CONTINUATION (MWBB 7714), u.S. NUCLEAR REGULATORY CUMMIS$10N, WASHlWGTON, DC 20555-0001, AND TO THE PAPERWORK REDUCTION PROJECT (3150-0104), OFFICE OF
_, MANAGEMENT AND BUDGET g WASHINGTON, DC 20503.
FACILITY MAME (1) DOCKET N(MBER (2) LER N M ER (6) PAGE (3)
Braidwood 2 TEAR SEQUENTIAL REVISION 05000457 93 --
006 -- Ob TEXT (if more sosce is reautred, use additional copies of WRC Form 366A) (17) reactor coolant system would be accomplished by use of dumping steam .
from either the condenser steam dumps or the steam generator PORV's.
Steps are taken to secure unnecessary containment spray and ECCS pumps based on determining the minimum required flow to remove decay heat, and refill of the RWST is directed. Depressurization of the reactor coolant system is performed to reduce the flow from the break.
During a steam generator tube rupture, cooldown of the reactor coolant system is accomplished by dumping steam through the condenser steam dumps or by use of the steam generator PORV's.
In the event the RH system was needed to perform its shutdown cooling i function, BwOA PRI-10, Loss of Shutdown Cooling procedure exists to provide alternate means of removing decay heat. l l
E. CORRECTIVE ACTIONS l The immediate corrective action was to replace the 2A RH pump motor.
The oil in other pumps with similar bearing oil reservoir design will be drained to check for sufficient oil in the reservoir. There is no evidence to indicate similar corrosion proolems with these other i pumps. The Unit 1 RH pumps have been checked and were found to have j adequate oil. The other pumps have been placed on the station work '
schedule. This will be tracked to completion by NTS item 457-180 00601.
The System Engineering department, with assistance from Station Support Engineering, will evaluate methods to reduce the effects of RH pump seal leakage on motor bearings. This will be tracked to completion by NTS item 457-180-93-00602.
The Fuel Handling department will update the lubrication program LUBQ for equipment with similar oil reservoir designs to ensure it contains the correct data for oil changes. This will be tracked to completion by NTS item 457-180-93-00603.
Fuel Handling department work practices will be enhanced to include a method of checking that oil reservoirs of this type are full after completing an oil change. This will be tracked to completion by NTS item 457-180-93-00604.
The Station Support Engineering department will review potential improvements to the design of the bearing temperature probe for-the RH pumps. This will be tracked to completion by NTS item 457-180 00605.
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1 NRC FORM 366 ($-92)
NRC FORM 366A U.S.IOCLEARREGULATORYCOMMISSE APPROVED BY DMB No. 3150-0104 (5-92) EXPIRES 5/31/95 ESilMATED BUROEN PER RESPONSE TO COMPLY WITH THis INFORMATION COLLECTION REQUEST: 50.0 HRS.
FORWARD COMMENTS REGARDING BURDEN ESTIMATE 10 i LICENBEE EVENT REPORT (LER) THE INFORMATION AND RECORDS MANAGEMENT BRANCH l TEXT CONTINUATION (MNBB 7714), U.S. NUCLEAR REGULATORY COMMISSION, j WASHINGTON, DC 20555-0001, AND TO THE PAPERWORK REDUCTION PROJECT (3150-0104), OFFICE OF MANAGEMENT AND BUDGET, WASHINGTON, DC 20503.
FACILITY NAE (1) DOCKET N'MLIR (?) LER NUMBER (6) PAE (3) i Braidwood 2 yggg SEQUENTI AL REVISION W"MEFp wwcrp 05000457 93 05 8 OF S
- 006 -
TEXT (11 more space is reavired, use additional copies of NRC Form 3664) (17)
A Site Lessons Learned briefing on this event for operations, i maintenance, fuel handling, and system and station engineering '
personnel will be conducted for this event. This will include a discussion on the need to preserve evidence that may help in !
determining the causes of equipment problems. This will be tracked to :
completion by NTS item 457-180-93-00606. '
A review of the design, operation, and maintenance of oil systems for i safety related and other important pumps was in progress at the time I of this event. This review will continue and will be tracked to .
completion by NTS item 457-180-93-00607. I F. PREVIOUS OCCURRENCES !
l None G. COMPONENT FAILURE DATA Westinghouse, 400 HP, Life-line D, LAC Motor, 5010 Frame Series i
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