NL-15-183, Watts Bar Nuclear Plant, Unit 2, Amendment 114 to Final Safety Analysis Report, Section 9.0 - Auxiliary Systems, Pages 9.4-1 - 9.5-66
NL-15-183, Watts Bar Nuclear Plant, Unit 2, Amendment 114 to Final Safety Analysis Report, Section 8.0 - Electric Power
NL-15-183, Watts Bar Nuclear Plant, Unit 2, Amendment 114 to Final Safety Analysis Report, Section 3.0 - Design of Structures, Components, Equipment, and Systems, Pages 3-i - 3.5A-4
NL-15-183, Watts Bar Nuclear Plant, Unit 2, Amendment 114 to Final Safety Analysis Report, Section 1.0 - Introduction and General Description of Plant
NL-15-156, Sequoyah Nuclear Plants, Units 1 and 2 - Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) - Supplement 3. Part 7 of 9
NL-15-128, Sequoyah Nuclear Plants, Units 1 and 2 Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) - Supplement 2. Part 7 of 8
CNL-18-130, Revised Application to Modify the Technical Specifications for Unbalanced Voltage Relays
CNL-19-014, Application to Modify Watts Bar Nuclear Plant Unit 2 Technical Specifications 3.7.8 to Extend the Completion Time for an Inoperable Essential Raw Cooling Water Train on a One-Time Basis (WBN-TS-18-07)
CNL-19-033, Revised Response to Request for Additional Information Regarding Application to Modify Technical Specifications 3.8.9 Regarding Alternating Current (AC) Vital Buses (WBN-TS-17-19)
CNL-19-110, Application to Revise Technical Specifications 3.8.1, AC Sources - Operating (WBN-TS-18-10)
CNL-21-062, Application to Modify Watts Bar Nuclear Plant Units 1 and 2 Technical Specification 3.7.8 to Support Shutdown Board Cleaning (WBN-TS-19-019)
05000327/LER-1998-001-04, :on 980519,automatic Reactor Trip Occurred. Caused by Failure of Alternate Feedwater to 1A1-A 480-volt Shutdown Board.Normal Feedwater Breaker Placed in Svc & 480- Volt Shutdown Board Returned to Operation
05000327/LER-1986-019, :on 860505,auxiliary Bldg Ventilation Isolation Occurred While Mod to 400-volt Shutdown Board 1A1-A Performed.Caused by Personnel Error Causing Loss of Power to Radiation Monitor & Subsequent Spike
05000327/LER-1982-102-03, /03L-0:on 820727,1A1-A Control & Auxiliary Vent Board Tripped,Resulting in Loss of Power to Ventilation Equipment & Radiation Monitors.Caused by burned-out Phase Bus Link Due to Loose Connection.Phase Link Replaced
NL-21-0019, Response to Request for Additional Information Regarding Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors