LER-1980-036, /03L-0:on 800717,w/unit in Mode 2 & During Special NRC Test,Turbine Driven Auxiliary Feedwater Pump Was Connected to Header Common to Three Steam Generators.Vol in Emergency Condensate Storage Tank Below 100,000 Gallons |
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LICENSEE CODE LICENSE NUMBER LICENSE TYPE CAT
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On July 17, 1980, with the unit in Mode 2, to facilitate a special test re-
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quired by the NRC 'the turbine driven auxiliary feedwater pump was connected to /
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a header common to al1~three steam generat.- s contrary to T.S. 3.7.1.2.
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'the volume in the'Emersency Condensate Storage Tank (ECST) dropped below 110,
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000 sal. contrary to TS 3.7.1.3.
Since a safety evaluation had been performed /
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on the valve lineup'and the 300,000 gal, condensate tank was available, the
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SEQUENTIAL OCCURRENCE REPORT REVISION
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ACTION FUTURE EFFECT SHUTDOWN ATTACHMENT NPRD-4 PRIME COMP. COMPONENT TAKEN
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The Turbine Driven Auxiliary Feedwater Pump Endurance (48 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />) Test was
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required to be performed via NRC letter from Eisenhut dated 9-28-79.
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adequate cooling water was not available due to high outside air temperatures, /
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the test was modified to allow the turbine driven auxiliary feed pump to feed /
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FACILITY-METHOD OF
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ACTIVITY
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LOCATION OF RELEASE (36)
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Virginia Electric and Power Company North Anna Power Station,' Unit #2 Attachment: Page 1 of 2 Docket No. 50-339 Report No. LER-80-036/03L-0 Description of Event -
On July 17, 1980, with the unit in Mode 2, the turbine driven
- - auxiliary feedwater pump (2-FW-P-2) was lined up to a header common to all three steam generators. This was contrary to T.S. 3.7.1.2 since three independent flow paths were not lined up to the steam generators.
In addition, the water volume in the Emergency Condensate Stroage Tank i
(ECST) dropped below 100,000 gal (91.4%) contrary te T.S. 3.7.1.3.
Probable Consequences of Occurrence The consequences were minimized because of the following reasons:
1.
Prior to the implementation of the endurance test, the test and required deviations on the test were approved by the station safety committee.
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A safety analysis was performed on a deviation that required that the steam driven auxiliary feed pump supply the generators instead of discharging to the Emergency Condensate Storage Tank via temporary piping. This safety analysis determined that there were no unreviewed safety questions as defined by 10 CFR50.59.
3.
During the operation of the test, an operator was stationed in the Auxiliary Feedwater Pump House for the purpose of realigning the auxiliary feedwater system, if required.
4.
The auxiliary feedwater system was returned to the normal lineup within the required 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> action statement period.
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Makeup water was provided continuously to the ECST during the performance of the endurance test.
Due to the above reasons the health and safety of the general public.were not affected.
Cause of Event
The lineup for the~ endurance test had to.be altered since adequate
- - cooling was not_ available to prevent the Emergency ~ Condensate Storage
. Tank from exceeding maximum temperature of 120'F. 'Due to the high heat j
loads of the plant caused by. unusually high outside temperatures, cooling water was not available. An alternate method to perform the required
- - test was to feed the steam generators taking suction on the Emergency Condensate Storage Tank. This method was contrary to T.S. 3.7.1.2 since three independent flow paths were not available to-feed the steam generators.
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l Attachment: Page 2 of 2 Cause of Event (cont.)
The level in the ECST dropped below 91.4% during the performance of the spectial test. Due to high heat loads on the chilled water system caused by abnormally high outside temperatures, chilled water was not available for cooling of the discharge on its recire. path back to the ECST via temporary piping.
Instead, the pump was lined up to discharge to all three steam generators as designed. -The level of the tank stabilized to approximately 80% while being gravity fed continuously from the 300,000 gallon' condensate storage tank. This test demonstrated that the steam driven auxiliary feed pump can feed all three steam generators and the ECST can maintain adequate level (80%) while being gravity fed from the 300,000 gallon storage tank for 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, as designed.
Immediate Corrective Action
An operator was stationed in the Auxiliary Feedwater Pump House to realign the system, if required.
The ECST was filled above the required level upon completion of the test.
Scheduled Corrective Action No scheduled corrective action is required.
Actions Taken to Prevent Recurrence No actions taken to prevent recurrence are required.
Generic Implication There are no generic implications.
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| 05000338/LER-1980-001-01, /01T-0:on 800118,during Review for IE Bulletin 79-14,letdown Lines 3/4-CH-275-1502Q1 & 3/4-CH-123-1502-Q2 Reported Overstressed.Caused by Incorrect Valve Weights Used in Pipe Stress Calculations | /01T-0:on 800118,during Review for IE Bulletin 79-14,letdown Lines 3/4-CH-275-1502Q1 & 3/4-CH-123-1502-Q2 Reported Overstressed.Caused by Incorrect Valve Weights Used in Pipe Stress Calculations | | | 05000338/LER-1980-001, Forwards LER 80-001/01T-0 | Forwards LER 80-001/01T-0 | | | 05000339/LER-1980-001, Forwards LER 80-001/03L-0 | Forwards LER 80-001/03L-0 | | | 05000339/LER-1980-001-03, /03L-0:on 800423,w/unit in Mode 6 Following Fuel Loading,Rhr Sys Inlet Valve MOV-2700 Ran Closed,Causing Loss of Operable RHR Loop.Caused by Blown Signal Comparator Card Power Supply Fuse in Process Control Sys.Card Replaced | /03L-0:on 800423,w/unit in Mode 6 Following Fuel Loading,Rhr Sys Inlet Valve MOV-2700 Ran Closed,Causing Loss of Operable RHR Loop.Caused by Blown Signal Comparator Card Power Supply Fuse in Process Control Sys.Card Replaced | | | 05000338/LER-1980-002, Forwards LER 80-002/01T-0 | Forwards LER 80-002/01T-0 | | | 05000338/LER-1980-002-01, /01T-0:on 800107,S&W Informed Util That Stress on Vertical Supports RH-R-19 & WS-R-316 & Snubbers SI-HSS-101B,101C & 107A Exceeded Allowable Design Values. Caused by Wrong Valve Weights Used in Design Calculations | /01T-0:on 800107,S&W Informed Util That Stress on Vertical Supports RH-R-19 & WS-R-316 & Snubbers SI-HSS-101B,101C & 107A Exceeded Allowable Design Values. Caused by Wrong Valve Weights Used in Design Calculations | | | 05000339/LER-1980-002-01, /01T-0:on 800429,during Structural Review for IE Bulletin 79-14,S&W Discovered Overstressed Pipe Hangers in Svc Bldg.Caused by Error in Stress Analysis Used to Design Pipe Hanger Supports.Mods Will Be Implemented | /01T-0:on 800429,during Structural Review for IE Bulletin 79-14,S&W Discovered Overstressed Pipe Hangers in Svc Bldg.Caused by Error in Stress Analysis Used to Design Pipe Hanger Supports.Mods Will Be Implemented | | | 05000339/LER-1980-002, Forwards LER 80-002/01T-0 | Forwards LER 80-002/01T-0 | | | 05000339/LER-1980-003, Forwards LER 80-003/03L-0 | Forwards LER 80-003/03L-0 | | | 05000339/LER-1980-003-03, /03L-0:on 800528,2H Diesel Generator Frequency & Voltage Response Was Not Verified Every 8-h,contrary to Tech Spec.Caused by Faulty Lead on Monitoring Instrumentation. Offsite Power Sources Verified & Found Acceptable | /03L-0:on 800528,2H Diesel Generator Frequency & Voltage Response Was Not Verified Every 8-h,contrary to Tech Spec.Caused by Faulty Lead on Monitoring Instrumentation. Offsite Power Sources Verified & Found Acceptable | | | 05000338/LER-1980-003-03, /03L-0:on 800121,nuclear Instrumentation Sys Power Range Channel 4 Declared Inoperable Due to Erratic Power Bistable Operation.Caused by Failed Ion Chamber Detector.Ion Chamber Detector Replaced | /03L-0:on 800121,nuclear Instrumentation Sys Power Range Channel 4 Declared Inoperable Due to Erratic Power Bistable Operation.Caused by Failed Ion Chamber Detector.Ion Chamber Detector Replaced | | | 05000338/LER-1980-003, Forwards LER 80-003/03L-0 | Forwards LER 80-003/03L-0 | | | 05000339/LER-1980-004, Forwards LER 80-004/03L-0 | Forwards LER 80-004/03L-0 | | | 05000339/LER-1980-004-03, /03L-0:on 800519,during Mode 3 Operation,Steam Generator Level Channel LT-2475 Indicated Level 9% Lower than Two Redundant Channels.Caused by Voltage Drift.Channel Was Placed in Trip Mode | /03L-0:on 800519,during Mode 3 Operation,Steam Generator Level Channel LT-2475 Indicated Level 9% Lower than Two Redundant Channels.Caused by Voltage Drift.Channel Was Placed in Trip Mode | | | 05000338/LER-1980-004-03, /03L-0:on 800109,during Test of Equipment Hatch Emergency Escape Lock,Inner Door Seal Found Leaking When Door Opened & Lock Found to Be Under Slight Vacuum.Caused by Frequent Door Operation.Seals Replaced | /03L-0:on 800109,during Test of Equipment Hatch Emergency Escape Lock,Inner Door Seal Found Leaking When Door Opened & Lock Found to Be Under Slight Vacuum.Caused by Frequent Door Operation.Seals Replaced | | | 05000338/LER-1980-004, Forwards LER 80-004/03L-0 | Forwards LER 80-004/03L-0 | | | 05000338/LER-1980-005-03, /03L-0:on 800110,w/unit in Mode 4,main Steam Isolation Trip Valve TV-MS101C Would Not Close Using Train a Push Button.Caused by Open Auxiliary Relay in Circuit. Relay Replaced from Stock & Tested Satisfactorily | /03L-0:on 800110,w/unit in Mode 4,main Steam Isolation Trip Valve TV-MS101C Would Not Close Using Train a Push Button.Caused by Open Auxiliary Relay in Circuit. Relay Replaced from Stock & Tested Satisfactorily | | | 05000338/LER-1980-005, Forwards LER 80-005/03L-0 | Forwards LER 80-005/03L-0 | | | 05000339/LER-1980-005-03, /03L-0:on 800517,2J Emergency Diesel Generator Tripped After Starting & Operability of 2H Diesel Generator Was Not Verified within 1-h.Caused by Existing Procedures Not Specifying Test Connections Required to Test Diesel | /03L-0:on 800517,2J Emergency Diesel Generator Tripped After Starting & Operability of 2H Diesel Generator Was Not Verified within 1-h.Caused by Existing Procedures Not Specifying Test Connections Required to Test Diesel | | | 05000339/LER-1980-005, Forwards LER 80-005/03L-0 | Forwards LER 80-005/03L-0 | | | 05000339/LER-1980-006, Forwards LER 80-006/03L-0 | Forwards LER 80-006/03L-0 | | | 05000339/LER-1980-006-03, /03L-0:on 800520,during Startup Testing in Mode 3, B Steam Generator Narrow Range Level Channel III Was Observed Reading Below Redundant Level Channels & Drifting Low.Caused by Air Pocket in Steam Generator Sensing Line | /03L-0:on 800520,during Startup Testing in Mode 3, B Steam Generator Narrow Range Level Channel III Was Observed Reading Below Redundant Level Channels & Drifting Low.Caused by Air Pocket in Steam Generator Sensing Line | | | 05000338/LER-1980-006, Forwards LER 80-006/03L-0 | Forwards LER 80-006/03L-0 | | | 05000338/LER-1980-006-03, /03L-01:on 800111,w/unit in Mode 3,casing Coolant Pump Discharge Valve MOV-RS-100A Was Discovered to Be Inoperable.Caused by Removal of Casing Cooling Tank Level Transmitter LT-RS103A During Execution of Design Change | /03L-01:on 800111,w/unit in Mode 3,casing Coolant Pump Discharge Valve MOV-RS-100A Was Discovered to Be Inoperable.Caused by Removal of Casing Cooling Tank Level Transmitter LT-RS103A During Execution of Design Change | | | 05000338/LER-1980-007-03, /03L-0:on 800111,during Mode 3 Reactor Heating Containment Average Temp Decreased to 85 F,Less than Tech Specs.Caused by Insufficient Procedural Precautions. Removed Chiller from Svc.Monitored Temp | /03L-0:on 800111,during Mode 3 Reactor Heating Containment Average Temp Decreased to 85 F,Less than Tech Specs.Caused by Insufficient Procedural Precautions. Removed Chiller from Svc.Monitored Temp | | | 05000339/LER-1980-007, Forwards LER 80-007/03L-0 | Forwards LER 80-007/03L-0 | | | 05000339/LER-1980-007-03, /03L-0:on 800521,during Mode 3 Operation,Channel in Tave Protection Loop 2 Failed in High Direction.Cause Is Unknown.Failed Channel Was Removed from Svc & Replaced by Spare | /03L-0:on 800521,during Mode 3 Operation,Channel in Tave Protection Loop 2 Failed in High Direction.Cause Is Unknown.Failed Channel Was Removed from Svc & Replaced by Spare | | | 05000339/LER-1980-008, Forwards LER 80-008/03L-0 | Forwards LER 80-008/03L-0 | | | 05000338/LER-1980-008-01, /01T-0:on 800111,during Review for IE Circular 78-08,S&W Found Control Room Air Conditioning Chiller Units Control Panel Not Qualified to Seismic Category I Requirements.Cause Unknown.Vendor Reviewing Components | /01T-0:on 800111,during Review for IE Circular 78-08,S&W Found Control Room Air Conditioning Chiller Units Control Panel Not Qualified to Seismic Category I Requirements.Cause Unknown.Vendor Reviewing Components | | | 05000339/LER-1980-008-03, /03L-0:on 800521,during Mode 3 Operation,Redundant Channel Protection Was Lost.Caused by Personnel Not Placing Tave Protection Loop Failed Channel in Trip Mode within Required Time.Failed Channel Placed in Trip Mode | /03L-0:on 800521,during Mode 3 Operation,Redundant Channel Protection Was Lost.Caused by Personnel Not Placing Tave Protection Loop Failed Channel in Trip Mode within Required Time.Failed Channel Placed in Trip Mode | | | 05000338/LER-1980-009-03, /03L-0:on 800111,while Performing Periodic Test on Main Steam Safety Valves,Found Valves SV-MS-101-A & C, SV-MS-102-A & B & SV-MS-105-A & C Did Not Lift at Pressure Setpoints Per Tech Specs.Caused by Setpoint Drift | /03L-0:on 800111,while Performing Periodic Test on Main Steam Safety Valves,Found Valves SV-MS-101-A & C, SV-MS-102-A & B & SV-MS-105-A & C Did Not Lift at Pressure Setpoints Per Tech Specs.Caused by Setpoint Drift | | | 05000339/LER-1980-009, Forwards LER 80-009/03L-0 | Forwards LER 80-009/03L-0 | | | 05000339/LER-1980-009-03, /03L-0:on 800522,power Supply for Main Steam Pressure Protection Channel III Failed High,Causing Steam Line Pressure Mismatch.Caused by Failed Card in Power Supply.Card Was Replaced & Calibr | /03L-0:on 800522,power Supply for Main Steam Pressure Protection Channel III Failed High,Causing Steam Line Pressure Mismatch.Caused by Failed Card in Power Supply.Card Was Replaced & Calibr | | | 05000338/LER-1980-010-01, /01T-0:on 800111,during Review for IE Bulletin 79-14,S&W Found Stress on Vertical Rod Hangers SW-H-162A & SW-H-160A to Be Over Design Allowable.Caused by Incorrect Valve Weights Used in Pipe Support Design Calculations | /01T-0:on 800111,during Review for IE Bulletin 79-14,S&W Found Stress on Vertical Rod Hangers SW-H-162A & SW-H-160A to Be Over Design Allowable.Caused by Incorrect Valve Weights Used in Pipe Support Design Calculations | | | 05000339/LER-1980-010, Forwards LER 80-010/01T-0 | Forwards LER 80-010/01T-0 | | | 05000339/LER-1980-010-01, /01T-0:on 800523,during Review of ECCS Piping for Fluid Temp Below 70 F,Determined That Loadings on Both Low Head Safety Injection Pump Nozzles Exceeded Design Stress Allowables.Caused by Deficiency in Sys Stress Analysis | /01T-0:on 800523,during Review of ECCS Piping for Fluid Temp Below 70 F,Determined That Loadings on Both Low Head Safety Injection Pump Nozzles Exceeded Design Stress Allowables.Caused by Deficiency in Sys Stress Analysis | | | 05000339/LER-1980-011-03, /03L-0:on 800520,personnel Air Lock Doors Would Not Seal Completely,Causing Air Leakage While Performing Surveillance Test 2-PT-62.4.Caused by Leakage Past Seals on Inner & Outer Doors.New Seals Were Installed | /03L-0:on 800520,personnel Air Lock Doors Would Not Seal Completely,Causing Air Leakage While Performing Surveillance Test 2-PT-62.4.Caused by Leakage Past Seals on Inner & Outer Doors.New Seals Were Installed | | | 05000339/LER-1980-011, Forwards LER 80-011/03L-0 | Forwards LER 80-011/03L-0 | | | 05000338/LER-1980-011, Forwards LER 80-011/03L-0 | Forwards LER 80-011/03L-0 | | | 05000338/LER-1980-011-03, /03L-0:on 800115,when Sys Sample Monitoring Pumps Were Removed from Svc,Ventilation Vent Stack B Particulate & Gas Radiation Monitors RM-VG112 & 113 Were Rendered Inoperable.Design Changes Will Add High Range Monitor | /03L-0:on 800115,when Sys Sample Monitoring Pumps Were Removed from Svc,Ventilation Vent Stack B Particulate & Gas Radiation Monitors RM-VG112 & 113 Were Rendered Inoperable.Design Changes Will Add High Range Monitor | | | 05000339/LER-1980-012, Forwards LER 80-012/03L-0 | Forwards LER 80-012/03L-0 | | | 05000339/LER-1980-012-03, /03L-0:on 800618 While in Mode 2,control Rod Demand Position Indication Noted 19 Steps Higher than Associated Rod Position Indication.Caused by Drift of Rod Position Indicator Channel.Channel Recalibr | /03L-0:on 800618 While in Mode 2,control Rod Demand Position Indication Noted 19 Steps Higher than Associated Rod Position Indication.Caused by Drift of Rod Position Indicator Channel.Channel Recalibr | | | 05000338/LER-1980-012, Forwards LER 80-012/03L-0 | Forwards LER 80-012/03L-0 | | | 05000338/LER-1980-012-03, /03L-0:on 800111,during Testing in Mode 3 to Verify Main Steam Trip Valve Closure Time,Trip Valve Failed to Close Fully within Required Five Seconds.Cause Unknown. Valve Was Retested.Closure Time within Acceptable Limits | /03L-0:on 800111,during Testing in Mode 3 to Verify Main Steam Trip Valve Closure Time,Trip Valve Failed to Close Fully within Required Five Seconds.Cause Unknown. Valve Was Retested.Closure Time within Acceptable Limits | | | 05000338/LER-1980-013, Forwards LER 80-013/03L-0 | Forwards LER 80-013/03L-0 | | | 05000338/LER-1980-013-03, /03L-0:on 800114,while Using Steam Driven Feedwater Pump 1-FW-P-2 to Add Feedwater to Steam Generator A,Water Leaked from Pump Oil Cooler Gasket.Caused by Blown Gasket.Gasket Replaced | /03L-0:on 800114,while Using Steam Driven Feedwater Pump 1-FW-P-2 to Add Feedwater to Steam Generator A,Water Leaked from Pump Oil Cooler Gasket.Caused by Blown Gasket.Gasket Replaced | | | 05000339/LER-1980-013-03, /03L-0:on 800520 & 27,w/unit in Hot Standby, Samples of Boron Injection Tank & C Boric Acid Storage Found to Contain Less than 20,000 Ppm Boron.Caused by Leaks Past Inlet Valves MOV-2867 a & B.Switch Settings Increased | /03L-0:on 800520 & 27,w/unit in Hot Standby, Samples of Boron Injection Tank & C Boric Acid Storage Found to Contain Less than 20,000 Ppm Boron.Caused by Leaks Past Inlet Valves MOV-2867 a & B.Switch Settings Increased | | | 05000339/LER-1980-013, Forwards LER 80-013/03L-0 | Forwards LER 80-013/03L-0 | | | 05000338/LER-1980-014, Forwards LER 80-014/03L-0 | Forwards LER 80-014/03L-0 | | | 05000338/LER-1980-014-03, /03L-0:on 800113,during Insp of Auxiliary Feedwater Pump 1-FW-P-2 Outboard Bearing,Discovered Inboard Side of Thrust Bearing Had Been Wiped.Caused by Lack of Oil. Bearing Replaced & Pump Returned to Svc | /03L-0:on 800113,during Insp of Auxiliary Feedwater Pump 1-FW-P-2 Outboard Bearing,Discovered Inboard Side of Thrust Bearing Had Been Wiped.Caused by Lack of Oil. Bearing Replaced & Pump Returned to Svc | |
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