Steam Generator

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The steam generator is the component between the high pressure primary loop and secondary loop of a PWR.

There are two, three, or four loop steam generators reactor models. Each steam generator can measure up to 70 feet (21 m) in height and weigh as much as 800 tons. Each steam generator can contain anywhere from 3,000 to 16,000 tubes, each about .75 inches (19 mm) in diameter. The coolant (treated water), which is maintained at high pressure to prevent boiling, is pumped through the nuclear reactor core. Heat transfer takes place between the reactor core and the circulating water and the coolant is then pumped through the primary tube side of the steam generator by coolant pumps before returning to the reactor core. This is referred to as the primary loop.

That water flowing through the steam generator boils water on the shell side (which is kept at a lower pressure than the primary side) to produce steam. This is referred to as the secondary loop. The secondary-side steam is delivered to the turbines to make electricity. The steam is subsequently condensed via cooled water from a tertiary loop and returned to the steam generator to be heated once again. The tertiary cooling water may be recirculated to cooling towers where it sheds waste heat before returning to condense more steam. Once-through tertiary cooling may otherwise be provided by a river, lake, or ocean. This primary, secondary, tertiary cooling scheme is the basis of the pressurized water reactor.

Reactor Scrams

Feedwater supplies the water to the secondary loop and if it stops supplying water, the water level decreases. If the steam generators can't extract heat from the reactor then pressure and temperature would increase; therefore, a manual Scram may be initiated.

 TitleSiteReactor type
05000029/LER-1988-003, :on 880326,reactor Scrammed & Turbine Tripped on Low Steam Generator Level at 85% Power.Caused by Failure of Power Supply for Steam Generator Level Control Channels on Steam Generators.Feedwater Pumps Restarted
on 880326,reactor Scrammed & Turbine Tripped on Low Steam Generator Level at 85% Power.Caused by Failure of Power Supply for Steam Generator Level Control Channels on Steam Generators.Feedwater Pumps Restarted
Yankee RoweWestinghouse PWR 4-Loop
05000206/LER-1979-002, Forwards LER 79-002/03L-0Forwards LER 79-002/03L-0San OnofreCE
Westinghouse PWR 3-Loop
05000206/LER-1989-012, :on 890525,auxiliary Feedwater Sys Train a Actuation Occurred When wide-range Steam Generator Level Signals Decreased Below Actuation Setpoint.Caused by Effects of Internal Circulation Flow
on 890525,auxiliary Feedwater Sys Train a Actuation Occurred When wide-range Steam Generator Level Signals Decreased Below Actuation Setpoint.Caused by Effects of Internal Circulation Flow
San OnofreCE
Westinghouse PWR 3-Loop
05000206/LER-1989-019, :on 890724,unit Manually Tripped Due to Loss of Feedwater Flow to Steam Generator a & Hi Hi Level & Steam/ Feed Mismatch Alarm Received.Caused by Error in Incorporating Design Change Info
on 890724,unit Manually Tripped Due to Loss of Feedwater Flow to Steam Generator a & Hi Hi Level & Steam/ Feed Mismatch Alarm Received.Caused by Error in Incorporating Design Change Info
San OnofreCE
Westinghouse PWR 3-Loop
05000206/LER-1989-023, :on 890918,four Control Rods from Shutdown Bank 2 Dropped Into Core & Approx 23 Later,Remaining 12 Shutdown Bank Control Rods Dropped Into Core.Caused by Failure of Contactor Coil 2MS1.Coil Replaced
on 890918,four Control Rods from Shutdown Bank 2 Dropped Into Core & Approx 23 Later,Remaining 12 Shutdown Bank Control Rods Dropped Into Core.Caused by Failure of Contactor Coil 2MS1.Coil Replaced
San OnofreCE
Westinghouse PWR 3-Loop
05000206/LER-1989-023-02, :on 890918,manual Reactor Trip Occurred Following Dropped Shutdown Bank Rods.Caused by Failed Contactor Coil & Blown Fuse.Contactor Coil & Fuse Replaced w/in-kind Parts
on 890918,manual Reactor Trip Occurred Following Dropped Shutdown Bank Rods.Caused by Failed Contactor Coil & Blown Fuse.Contactor Coil & Fuse Replaced w/in-kind Parts
San OnofreCE
Westinghouse PWR 3-Loop
05000206/LER-1990-011, :on 900515,manual Reactor Trip Occurred Due to Low & Decreasing Level in Steam Generator Resulting from Loss of Feedwater Flow.Caused by Short to Ground in Valve Control Cable.Investigation Continuing
on 900515,manual Reactor Trip Occurred Due to Low & Decreasing Level in Steam Generator Resulting from Loss of Feedwater Flow.Caused by Short to Ground in Valve Control Cable.Investigation Continuing
San OnofreCE
Westinghouse PWR 3-Loop
05000206/LER-1990-019, :on 901016,nuclear Overpower Low Trip Setpoint Was Determined to Be Greater than Allowed by Tech Specs Due to Inadequate Review of Design Change Documents
on 901016,nuclear Overpower Low Trip Setpoint Was Determined to Be Greater than Allowed by Tech Specs Due to Inadequate Review of Design Change Documents
San OnofreCE
Westinghouse PWR 3-Loop
05000206/LER-1991-010, :on 910528,2 of 12 Control Bank 1 Control Alarms Dropped Into Core & Reactor Manually Tripped.Caused by Open Connection in half-voltage Resistor Network.Jumper & Lugs Replaced w/in-kind Parts
on 910528,2 of 12 Control Bank 1 Control Alarms Dropped Into Core & Reactor Manually Tripped.Caused by Open Connection in half-voltage Resistor Network.Jumper & Lugs Replaced w/in-kind Parts
San OnofreCE
Westinghouse PWR 3-Loop
05000213/LER-1986-020, :on 860508,automatic Reactor & Turbine Trip Occurred During Turbine Vibration Tests.Caused by Operator Accelerating Turbine at Too High Rate.Shift Supervisor & Operators Counseled
on 860508,automatic Reactor & Turbine Trip Occurred During Turbine Vibration Tests.Caused by Operator Accelerating Turbine at Too High Rate.Shift Supervisor & Operators Counseled
Haddam NeckWestinghouse PWR 4-Loop
05000213/LER-1986-027, :on 860606 & 17,two Unit Trips from 100% Power Manually Initiated on Low Suction Pressure to Steam Generator Feedwater Pumps.Caused by Failure of Stem/Actuator Coupling on Heater Drain Tank Control Valve
on 860606 & 17,two Unit Trips from 100% Power Manually Initiated on Low Suction Pressure to Steam Generator Feedwater Pumps.Caused by Failure of Stem/Actuator Coupling on Heater Drain Tank Control Valve
Haddam NeckWestinghouse PWR 4-Loop
05000213/LER-1986-041, :on 860830,feedwater Regulating Valve FW-FCV-1301-1 to Steam Generator 1 Became Stuck Open,Causing Manual Reactor Trip.Caused by Failure of Weld Between Stem & Plug.Failed Part of Weld Sent to Mfg
on 860830,feedwater Regulating Valve FW-FCV-1301-1 to Steam Generator 1 Became Stuck Open,Causing Manual Reactor Trip.Caused by Failure of Weld Between Stem & Plug.Failed Part of Weld Sent to Mfg
Haddam NeckWestinghouse PWR 4-Loop
05000213/LER-1986-044, :on 861130,feedwater Control Valve for Loop 3 Failed in Closed Position,Resulting in Automatic Reactor Trip.Caused by Inadequate Control Over Repair Activities. Improved Job Planning Initiated
on 861130,feedwater Control Valve for Loop 3 Failed in Closed Position,Resulting in Automatic Reactor Trip.Caused by Inadequate Control Over Repair Activities. Improved Job Planning Initiated
Haddam NeckWestinghouse PWR 4-Loop
05000213/LER-1990-010, :on 900727,actuation of Reactor Protection Sys Occurred Due to Test Procedure Used at Inappropriate Time. Caused by Failure to Identify Test Procedure Incompatibility W/New Tech Spec Requirements.Procedure Revised
on 900727,actuation of Reactor Protection Sys Occurred Due to Test Procedure Used at Inappropriate Time. Caused by Failure to Identify Test Procedure Incompatibility W/New Tech Spec Requirements.Procedure Revised
Haddam NeckWestinghouse PWR 4-Loop
05000213/LER-1990-020, :on 901019,manual Trip Occurred Due to Condensate Pump Degradation & Procedural Noncompliance
on 901019,manual Trip Occurred Due to Condensate Pump Degradation & Procedural Noncompliance
Haddam NeckWestinghouse PWR 4-Loop
05000213/LER-1992-020, :on 920727,wide Range SG Level Channel Declared Inoperable.Caused by Implementation of Std Instrumentation Action Statement W/O Associated Hardware. Channel Restored to Operability
on 920727,wide Range SG Level Channel Declared Inoperable.Caused by Implementation of Std Instrumentation Action Statement W/O Associated Hardware. Channel Restored to Operability
Haddam NeckWestinghouse PWR 4-Loop
05000213/LER-1993-012, :on 930714,high Steam Flow Transmitters Inadvertently Isolated Due to Inadequate Administrative Controls.Preventive Matl Procedure PMP 9.2-29 Revised.W/
on 930714,high Steam Flow Transmitters Inadvertently Isolated Due to Inadequate Administrative Controls.Preventive Matl Procedure PMP 9.2-29 Revised.W/
Haddam NeckWestinghouse PWR 4-Loop
05000213/LER-1996-022, :on 960901,RCS Loop Stop Valves Were Opened Without Timely Boron Sample.Caused by Personnel Error. Operations Dept Formed New Procedure Group to Upgrade Operations Procedures
on 960901,RCS Loop Stop Valves Were Opened Without Timely Boron Sample.Caused by Personnel Error. Operations Dept Formed New Procedure Group to Upgrade Operations Procedures
Haddam NeckWestinghouse PWR 4-Loop
05000213/LER-1997-015, :on 970813,functional Testing of Radiation Monitoring Sys Was Not Performed as Defined in Ts.Caused by Lack of Understanding of Definition of Acot.Revised Appropriate RMS Surveillance Procedure
on 970813,functional Testing of Radiation Monitoring Sys Was Not Performed as Defined in Ts.Caused by Lack of Understanding of Definition of Acot.Revised Appropriate RMS Surveillance Procedure
Haddam NeckWestinghouse PWR 4-Loop
05000244/LER-1985-014, :on 850606,automatic Reactor & Turbine Trips Occurred When Overpower Delta Temp Reactor Trip Actuated. Reactor Stabilized at Hot Shutdown Conditions.Caused by Grounding of Wire During Repairs
on 850606,automatic Reactor & Turbine Trips Occurred When Overpower Delta Temp Reactor Trip Actuated. Reactor Stabilized at Hot Shutdown Conditions.Caused by Grounding of Wire During Repairs
GinnaWestinghouse PWR 2-Loop
05000244/LER-1985-019, :on 851125,condenser Circulating Water Pump 1B Tripped,Resulting in Reactor Trip.Caused by Power Factor Relay Trip Setpoint Drift.Trip Setpoint Readjusted & Relay Tested Satisfactorily
on 851125,condenser Circulating Water Pump 1B Tripped,Resulting in Reactor Trip.Caused by Power Factor Relay Trip Setpoint Drift.Trip Setpoint Readjusted & Relay Tested Satisfactorily
GinnaWestinghouse PWR 2-Loop
05000244/LER-1986-004, :on 860729,reactor Tripped Manually When Large Steam Leak Discovered in Turbine Bldg.Caused by Leak in Pipe Elbow on Moisture Separator Reheater Drain Line 2A.Elbow Replaced & Tested Satisfactorily
on 860729,reactor Tripped Manually When Large Steam Leak Discovered in Turbine Bldg.Caused by Leak in Pipe Elbow on Moisture Separator Reheater Drain Line 2A.Elbow Replaced & Tested Satisfactorily
GinnaWestinghouse PWR 2-Loop
05000244/LER-1986-008, :on 861023,automatic Reactor Trip Occurred from Pressurizer High Pressure Due to Turbine Load Runback.Caused by Personnel Error.Module Replacement Procedure Written & Control & Protective Devices Checked & Tested
on 861023,automatic Reactor Trip Occurred from Pressurizer High Pressure Due to Turbine Load Runback.Caused by Personnel Error.Module Replacement Procedure Written & Control & Protective Devices Checked & Tested
GinnaWestinghouse PWR 2-Loop
05000244/LER-1986-011, :on 861128,MSIV Inadvertently Closed,Causing Pressurizer High Pressure Reactor Trip.Caused by Personnel Error.Event Discussed W/Personnel
on 861128,MSIV Inadvertently Closed,Causing Pressurizer High Pressure Reactor Trip.Caused by Personnel Error.Event Discussed W/Personnel
GinnaWestinghouse PWR 2-Loop
05000244/LER-1995-008, :on 950825,secondary Transient Occurred.Caused by Loss of B Condenser Circulating Water Pump That Resulted in Manual Rt.Returned S/G Levels to Normal Operating Levels
on 950825,secondary Transient Occurred.Caused by Loss of B Condenser Circulating Water Pump That Resulted in Manual Rt.Returned S/G Levels to Normal Operating Levels
GinnaWestinghouse PWR 2-Loop
05000244/LER-1996-002, :on 960307,secondary Transient Occurred.Caused by Loss of B Condenser Circulating Water Pump.C/As: Thermography Performed
on 960307,secondary Transient Occurred.Caused by Loss of B Condenser Circulating Water Pump.C/As: Thermography Performed
GinnaWestinghouse PWR 2-Loop
05000244/LER-1996-012, :on 960820,feedwater Transient Occurred,Due to Closure of Feedwater Regulating Valve,Causing Lo Lo Steam Generator Level Reactor Trip.Sgs Were Restored & Missing Screw in 1/P-476 Was Replaced
on 960820,feedwater Transient Occurred,Due to Closure of Feedwater Regulating Valve,Causing Lo Lo Steam Generator Level Reactor Trip.Sgs Were Restored & Missing Screw in 1/P-476 Was Replaced
GinnaWestinghouse PWR 2-Loop
05000244/LER-2002-0010 LER 2002-001, Loss of "A" Condenser Circulating Water Pump Results inR.E. Ginna Nuclear Power Plant0 Page: 1 Of 8
05000244/LER-2003-002, Major Power Grid Disturbance Causes Loss of Electrical Load and Reactor TripMajor Power Grid Disturbance Causes Loss of Electrical Load and Reactor TripGinna
05000244/LER-2009-002, Regarding Plant Trip Due to Loss of Electro-Hydraulic Control System PressureRegarding Plant Trip Due to Loss of Electro-Hydraulic Control System PressureGinna
05000244/LER-2011-003, Regarding Reactor Trip Due to Failure of Tubine Lube Oil PipingRegarding Reactor Trip Due to Failure of Tubine Lube Oil PipingGinna
05000244/LER-2023-003, Manual Reactor Trip Due to Degraded Condenser Vacuum from Lowering Main Steam to Air Ejectors and Auxiliary Feedwater Actuation Due to Low Steam Generator LevelManual Reactor Trip Due to Degraded Condenser Vacuum from Lowering Main Steam to Air Ejectors and Auxiliary Feedwater Actuation Due to Low Steam Generator LevelGinna
05000244/LER-2023-003-01, Re. Ginna Nuclear Power Plant, Manual Reactor Trip Due to Degraded Condenser Vacuum from Lowering Main Steam to Air Ejectors and Auxiliary Feedwater Actuation Due to Low SteamRe. Ginna Nuclear Power Plant, Manual Reactor Trip Due to Degraded Condenser Vacuum from Lowering Main Steam to Air Ejectors and Auxiliary Feedwater Actuation Due to Low SteamGinna
05000247/FIN-2013002-01Inadequate Maintenance Procedure Results in a Reactor TripIndian PointWestinghouse PWR 4-Loop
05000247/FIN-2018003-04Inadequate Procedure for Turbine Startup Caused a Reactor TripIndian PointWestinghouse PWR 4-Loop
05000247/LER-1917-001, Regarding Manual Reactor Trip Due to Decreasing Steam Generator Levels Caused by Main Boiler Feedwater Pump Turbine Low Pressure Governor Valves Failed ClosedRegarding Manual Reactor Trip Due to Decreasing Steam Generator Levels Caused by Main Boiler Feedwater Pump Turbine Low Pressure Governor Valves Failed ClosedIndian PointWestinghouse PWR 4-Loop
05000247/LER-1917-002, Regarding Auxiliary Feedwater Flow Indication Inoperable for Longer than the Allowed Technical Specification Completion Time Due to Failure of Complete Restoration Following CalibrationRegarding Auxiliary Feedwater Flow Indication Inoperable for Longer than the Allowed Technical Specification Completion Time Due to Failure of Complete Restoration Following CalibrationIndian PointWestinghouse PWR 4-Loop
05000247/LER-1986-031, :on 860916,during Preparation for Biweekly Rod Exercise Test,Reactor Manually Tripped Following Drop of Three Control Rods.Caused by Inadequate Electrical Jumper. Jumper Replaced
on 860916,during Preparation for Biweekly Rod Exercise Test,Reactor Manually Tripped Following Drop of Three Control Rods.Caused by Inadequate Electrical Jumper. Jumper Replaced
Indian PointWestinghouse PWR 4-Loop
05000247/LER-1986-036, :on 861023,reactor Tripped Manually Following Automatic Trip of Main Boiler Feed Pump on High Discharge Pressure Due to Excess Flow.Caused by Problems W/Main Feedwater Discharge Valves
on 861023,reactor Tripped Manually Following Automatic Trip of Main Boiler Feed Pump on High Discharge Pressure Due to Excess Flow.Caused by Problems W/Main Feedwater Discharge Valves
Indian PointWestinghouse PWR 4-Loop
05000247/LER-2000-001, Unit, 2 - Manual Reactor Trip Following Steam Generator Tube Rupture Dtd 03/17/2000Unit, 2 - Manual Reactor Trip Following Steam Generator Tube Rupture Dtd 03/17/2000Indian PointWestinghouse PWR 4-Loop
05000247/LER-2001-001
05000247/LER-2001-007, Re Automatic Reactor Trip Initiated by Main Turbine Trip on Auto Stop OilRe Automatic Reactor Trip Initiated by Main Turbine Trip on Auto Stop OilIndian PointWestinghouse PWR 4-Loop
05000247/LER-2002-003, Loss of 138 Kv Offsite Power Source Due to Ground Protection Trip Results in Auto Start of Emergency Diesel GeneratorsLoss of 138 Kv Offsite Power Source Due to Ground Protection Trip Results in Auto Start of Emergency Diesel GeneratorsIndian PointWestinghouse PWR 4-Loop
05000247/LER-2003-003, From Indian Point, Unit 2 Regarding Automatic Reactor Trip Initiated by a Main Turbine Trip on Auto Stop OilFrom Indian Point, Unit 2 Regarding Automatic Reactor Trip Initiated by a Main Turbine Trip on Auto Stop OilIndian PointWestinghouse PWR 4-Loop
05000247/LER-2003-004, Re Automatic Turbine Trip/Reactor Trip Due to 345kV Grid DisturbanceRe Automatic Turbine Trip/Reactor Trip Due to 345kV Grid DisturbanceIndian PointWestinghouse PWR 4-Loop
05000247/LER-2004-001, Re Manual Reactor Trip Due to Oscillating Feedwater Flow and Steam Generator Level with Flow Perturbations Caused by a Degraded Feed Water Regulating ValveRe Manual Reactor Trip Due to Oscillating Feedwater Flow and Steam Generator Level with Flow Perturbations Caused by a Degraded Feed Water Regulating ValveIndian PointWestinghouse PWR 4-Loop
05000247/LER-2004-002, Re Regulating Valve Closure Due to a De-energized Solenoid Operated Valve from Wiring FailureRe Regulating Valve Closure Due to a De-energized Solenoid Operated Valve from Wiring FailureIndian PointWestinghouse PWR 4-Loop
05000247/LER-2004-005, Regarding Automatic Reactor Trip Due to Turbine Generator Trip Caused by Low Stator Cooling Water PressureRegarding Automatic Reactor Trip Due to Turbine Generator Trip Caused by Low Stator Cooling Water PressureIndian PointWestinghouse PWR 4-Loop
05000247/LER-2006-003, Regarding Manual Reactor Trip Due to a Mismatch Between Reactor Power and Turbine Load Caused by Cycling of Steam Dump Valves After a Power Reduction for Loss of Heater Drain Tank PumpsRegarding Manual Reactor Trip Due to a Mismatch Between Reactor Power and Turbine Load Caused by Cycling of Steam Dump Valves After a Power Reduction for Loss of Heater Drain Tank PumpsIndian PointWestinghouse PWR 4-Loop
05000247/LER-2006-005, Re Automatic Reactor Trip Due to a Turbine Trip as a Result of a Main Generator Exciter Protective Trip Caused by a Generrex Power Supply Loss of Electrical GroundRe Automatic Reactor Trip Due to a Turbine Trip as a Result of a Main Generator Exciter Protective Trip Caused by a Generrex Power Supply Loss of Electrical GroundIndian PointWestinghouse PWR 4-Loop
... further results

See also