Turbine Driven Main Feed Pump# QUERYc6b85d30dd72fb2ef4cda49a405a9cf4
Turbine Driven Main Feed Pump
Turbine Driven Main Feed Pump# QUERY485b659d9f6731b39119711ebb253eb1
Turbine Driven Main Feed Pump# QUERYf864c597bb97d3515758921de5d5679f
Turbine Driven Main Feed Pump# QUERY03460c58efcc75e88ad90faab05ad9f4
Turbine Driven Main Feed Pump# QUERYdef7518cd85b0fe80ca2f5b9893c2aed
05000391/LER-1917-003, Regarding Automatic Start of Auxiliary Feedwater System Due to Main Condenser Failure
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
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)
AEP-NRC-2021-19, 0 to Updated Final Safety Analysis Report, Chapter 1, Introduction and Summary
PMNS20211575, Pre-Submittal Meeting with Tennessee Valley Authority Regarding Watts Bar Nuclear Plant, Unit 1, Proposed License Amendment Request
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
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)
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
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
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
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
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
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