Turbine Driven Main Feed Pump
type: Ontology
creation date: 2025-12-06T23:17:31-05:00
imports: http://semantic-mediawiki.org/swivt/1.0

Turbine Driven Main Feed Pump
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wiki page modification date: 2017-11-19T02:47:09Z
modification date#aux: 2458076.6160764
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05000391/LER-1917-003, Regarding Automatic Start of Auxiliary Feedwater System Due to Main Condenser Failure
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NL-15-183, Watts Bar Nuclear Plant, Unit 2, Amendment 114 to Final Safety Analysis Report, Section 10.0 - Main Steam and Power Conversion System
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CNL-20-058, Tennessee Valley Authority, Application to Modify the Watts Bar Nuclear Plant Unit 1 and Unit 2 Technical Specifications for Function 6.e of Table 3.3.2-1, Engineered Safety Feature Actuation System Instrumentation (WBN-TS-19-27)
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page: https://kanterella.com/CNL-2D20-2D058-2C_Tennessee_Valley_Authority-2C_Application_to_Modify_the_Watts_Bar_Nuclear_Plant_Unit_1_and_Unit_2_Technical_Specifications_for_Function_6.e_of_Table_3.3.2-2D1-…
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IR 05000456/1998012
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IR 05000309/1986005
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AEP-NRC-2021-19, 0 to Updated Final Safety Analysis Report, Chapter 1, Introduction and Summary
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PMNS20211575, Pre-Submittal Meeting with Tennessee Valley Authority Regarding Watts Bar Nuclear Plant, Unit 1, Proposed License Amendment Request
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ST-HL-AE-2704, Forwards Evaluation of Adequacy of Plant Hardware & Operating Staff Performance to Determine Plant Readiness to Continue Power in Excess of 50- of Rated Power.Facility Has Been Operated,Tested & Maintained in Acceptable Manner
type: Subject
label: ST-HL-AE-2704, Forwards Evaluation of Adequacy of Plant Hardware & Operating Staff Performance to Determine Plant Readiness to Continue Power in Excess of 50% of Rated Power.Facility Has Been Operated,Tested & Maintained in Acceptable Manner
page: https://kanterella.com/ST-2DHL-2DAE-2D2704-2C_Forwards_Evaluation_of_Adequacy_of_Plant_Hardware_-26_Operating_Staff_Performance_to_Determine_Plant_Readiness_to_Continue_Power_in_Excess_of_50-_of_Rated…
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CNL-23-036, Application to Revise Function 5 of Technical Specification Table 3.3.2-1, Engineered Safety Feature Actuation System Instrumentation, for the Sequoyah Nuclear Plant and Watts Bar Nuclear Plant (SQN-TS-23-02 and WBN-TS-23-08)
type: Subject
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ENS 52630
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LER-1986-002, :on 851106 & 860417,automatic Reactor Trip on Loss of Load Occurred Due to Main Turbine Trip on High Steam Generator Level.Caused by Controller Malfunction & Faulty Potentiometer.Controller Replaced
type: Subject
label: 05000309/LER-1986-002, :on 851106 & 860417,automatic Reactor Trip on Loss of Load Occurred Due to Main Turbine Trip on High Steam Generator Level.Caused by Controller Malfunction & Faulty Potentiometer.Controller Replaced
page: https://kanterella.com/05000309/LER-2D1986-2D002-2C_-3Aon_851106_-26_860417-2Cautomatic_Reactor_Trip_on_Loss_of_Load_Occurred_Due_to_Main_Turbine_Trip_on_High_Steam_Generator_Level.Caused_by_Controlle…
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system: Turbine Driven Main Feed Pump
wiki page sort key: 05000309/LER-1986-002, :on 851106 & 860417,automatic Reactor Trip on Loss of Load Occurred Due to Main Turbine Trip on High Steam Generator Level.Caused by Controller Malfunction & Faulty Potentiometer.Controller Replaced

LER-1986-015, :on 860212,plant Received Reactor Trip from Low Steam Generator Level.Caused by Error in Procedure Covering Operation of Main Feedwater Pumps.All Safety Sys Actuated Properly.Procedure Revised
type: Subject
label: 05000423/LER-1986-015, :on 860212,plant Received Reactor Trip from Low Steam Generator Level.Caused by Error in Procedure Covering Operation of Main Feedwater Pumps.All Safety Sys Actuated Properly.Procedure Revised
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wiki page sort key: 05000423/LER-1986-015, :on 860212,plant Received Reactor Trip from Low Steam Generator Level.Caused by Error in Procedure Covering Operation of Main Feedwater Pumps.All Safety Sys Actuated Properly.Procedure Revised

LER-1985-018, :on 851106,reactor Trip on Loss of Load Occurred Due to Main Turbine Trip.Caused by Tripped Turbine Driven Main Feed Pump on Low Suction Pressing Due to Failure of Feed Pump Recirculation Valve Controller
type: Subject
label: 05000309/LER-1985-018, :on 851106,reactor Trip on Loss of Load Occurred Due to Main Turbine Trip.Caused by Tripped Turbine Driven Main Feed Pump on Low Suction Pressing Due to Failure of Feed Pump Recirculation Valve Controller
page: https://kanterella.com/05000309/LER-2D1985-2D018-2C_-3Aon_851106-2Creactor_Trip_on_Loss_of_Load_Occurred_Due_to_Main_Turbine_Trip.Caused_by_Tripped_Turbine_Driven_Main_Feed_Pump_on_Low_Suction_Pressin…
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system: Turbine Driven Main Feed Pump
wiki page sort key: 05000309/LER-1985-018, :on 851106,reactor Trip on Loss of Load Occurred Due to Main Turbine Trip.Caused by Tripped Turbine Driven Main Feed Pump on Low Suction Pressing Due to Failure of Feed Pump Recirculation Valve Controller

LER-1985-003, :on 850430,automatic Reactor Trip on Loss of Load Occurred Due to Main Turbine Trip.Caused by Technician Incorrectly Verifying Protective Circuiting Contact Positions.Technician Counseled
type: Subject
label: 05000309/LER-1985-003, :on 850430,automatic Reactor Trip on Loss of Load Occurred Due to Main Turbine Trip.Caused by Technician Incorrectly Verifying Protective Circuiting Contact Positions.Technician Counseled
page: https://kanterella.com/05000309/LER-2D1985-2D003-2C_-3Aon_850430-2Cautomatic_Reactor_Trip_on_Loss_of_Load_Occurred_Due_to_Main_Turbine_Trip.Caused_by_Technician_Incorrectly_Verifying_Protective_Circui…
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wiki page sort key: 05000309/LER-1985-003, :on 850430,automatic Reactor Trip on Loss of Load Occurred Due to Main Turbine Trip.Caused by Technician Incorrectly Verifying Protective Circuiting Contact Positions.Technician Counseled

Appropriate Personnel
type: Subject
label: 05000316/LER-1984-025, :on 840912,hi-hi Level in Steam Generator 2 Caused Operating Turbine Driven Main Feed Pump & Turbine to Trip.Caused by Operator Error & Level Control Problems.Event Discussed W/Appropriate Personnel
page: https://kanterella.com/05000316/LER-2D1984-2D025-2C_-3Aon_840912-2Chi-2Dhi_Level_in_Steam_Generator_2_Caused_Operating_Turbine_Driven_Main_Feed_Pump_-26_Turbine_to_Trip.Caused_by_Operator_Error_-26_Le…
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system: Turbine Driven Main Feed Pump
wiki page sort key: 05000316/LER-1984-025, :on 840912,hi-hi Level in Steam Generator 2 Caused Operating Turbine Driven Main Feed Pump & Turbine to Trip.Caused by Operator Error & Level Control Problems.Event Discussed W/Appropriate Personnel

IR 05000245/1993019
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ML19322B185
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ML19254D505
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ML18270A171
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ML16011A519
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ML18270A209
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CNL-25-028, Supplement to Application to Revise Function 5 of Technical Specification Table 3.3.2-1, Engineered Safety Feature Actuation System Instrumentation, for (SQN-TS-23-02 & WBN-TS-23-08) (EPID L-2023-LLA-0175
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ML25051A210
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IR 05000390/2020004
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ML21158A284
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IR 05000309/1986016
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ML20059L380
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