Auxiliary Building Gas Treatment System# QUERYc6b85d30dd72fb2ef4cda49a405a9cf4
Auxiliary Building Gas Treatment System
Auxiliary Building Gas Treatment System# QUERYfd6da94bb856b4a2364be69be79fcc77
Auxiliary Building Gas Treatment System# QUERY96145afdbd7c3a78890f6f244ebbba6c
Auxiliary Building Gas Treatment System# QUERY8744e2f957650ca67025ee09217d6d14
Auxiliary Building Gas Treatment System# QUERY83feb1e1fdbcfeea6f0510886c8e1605
05000390/LER-2013-002, Regarding Two Trains of Emergency Gas Treatment System Inoperable
05000327/LER-2009-006, Units 1 and 2 Inoperability of Auxiliary Building Gas Treatment System Because of Inadequate Surveillance
CNL-16-147, Non-Voluntary License Amendment Request to Modify and Clarify Technical Specification 3.6.15, Shield Building, Condition B Note
CNL-17-014, Application to Revise Technical Specifications to Adopt Technical Specification Task Force (TSTF)-522, Revise Ventilation System Surveillance Requirements to Operate for 10 Hours Per Month, Using the Consolidated Line Item Improvement Pro
CNL-17-066, Response to Request for Additional Information Regarding License Amendment Request for One-Time Extension of Technical Specification Surveillance Requirements Group 2 (LAR Encl. 1 Attachments 5, 6, 7, 9, 12, 13, 14, 15, 16, and 17)
CNL-17-093, Revised Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specification 3.7.12, Auxiliary Building Gas Treatment System (ABGTS)
CNL-16-031, Application to Modify Technical Specifications Regarding Discrepancies in Control Room Ventilation and Other Administrative Changes to the Technical Specifications (WBN-TS-16-03)
CNL-15-094, Responses to Requests for Additional Information - Developmental Revision I Technical Specification Section 3.8
CNL-14-234, Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) - Supplement 1
CNL-17-119, Application to Modify Watts Bar Nuclear Plant, Units 1 and 2 Technical Specifications 3.8.9 Regarding Alternating Current (AC) Vital Buses (WBN-TS-17-19)
NL-16-031, Watts Bar, Units 1 and 2 - Application to Modify Technical Specifications Regarding Discrepancies in Control Room Ventilation and Other Administrative Changes to the Technical Specifications (WBN-TS-16-03)
NL-15-183, Watts Bar Nuclear Plant, Unit 2, Amendment 114 to Final Safety Analysis Report, Section 15.0 - Accident Analyses, Pages 15.4-1 - 15A-6
NL-15-183, Watts Bar Nuclear Plant, Unit 2, Amendment 114 to Final Safety Analysis Report, Section 13.0 - Conduct of Operations
NL-15-183, Watts Bar Nuclear Plant, Unit 2, Amendment 114 to Final Safety Analysis Report, Section 11.0 - Radioactive Waste Management
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 9.0 - Auxiliary Systems, Pages 9-i - 9.3-158
NL-15-183, Watts Bar Nuclear Plant, Unit 2, Amendment 114 to Final Safety Analysis Report, Section 7.0 - Instrumentation and Controls
NL-15-183, Watts Bar Nuclear Plant, Unit 2, Amendment 114 to Final Safety Analysis Report, Section 6.0 - Engineered Safety Features, Pages 6.3-1 - 6.9-2
NL-15-183, Watts Bar Nuclear Plant, Unit 2, Amendment 114 to Final Safety Analysis Report, Section 6.0 - Engineered Safety Features, Pages 6-iv - 6.2.6-30
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 3.8.5-1 - 3.12-6
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 8 of 9
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 6 of 9
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 5 of 9
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 4 of 9
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 3 of 9
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 2 of 9
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 1 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
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 5 of 8
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 4 of 8
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 3 of 8
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 2 of 8
NL-16-141, Watts Bar, Units 1 & 2, Application to Modify Technical Specifications Regarding Intermittent Opening of the Auxiliary Building Secondary Containment Closure Technical Specification 3.7.12, Auxiliary Building Gas Treatment System.
CNL-19-084, Second Supplement to Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program.
CNL-18-121, Response to Request for Additional Information Regarding Application to Modify Watts Bar Nuclear Plant, Units 1 and 2 Technical Specifications 3.8.9 Regarding Alternating Current (AC) Vital Buses (WBN-TS-17-19)
Information Notice 2019-01, Inadequate Evaluation of Temporary Alterations
WBL-19-023, Periodic Submission for Changes Made to the WBN Technical Specification Bases and Technical Requirements Manual
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-19-038, License Amendment Request to Make Miscellaneous Administrative Changes (WBN-TS-19-02)
CNL-19-086, Supplement to Application for License Amendment Request to Make Miscellaneous Administrative Changes (WBN-TS-19-02)
CNL-19-077, Application to Modify Watts Bar Nuclear Plant (WBN) Unit 1 and Unit 2 Technical Specifications 3.6.15, Shield Building, (WBN-TS-19-10)
CNL-17-044, Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specification 3.7.12, Auxiliary Building Gas Treatment System (Abgts), for Watts Bar Nuclear Plant, Units 1 and 2
CNL-20-005, License Amendment Request to Adopt TSTF-541, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position, (WBN-TS-20-02)
CNL-20-041, License Amendment Request to Remove Licensee Control (BFN TS-527, SQN-TS-20-08, and WBN-TS-20-016)
CNL-21-015, Expedited Application to Modify Watts Bar Nuclear Plant, Unit 1 Technical Specification 3.7.12, Auxiliary Building Gas Treatment System, for One-Time Exception to Permit Opening of the Auxiliary Building Secondary Containment Enclosure as
IA-97-261, Amend 220 to License DPR-77,authorizing Operation at Reactor Core Power Levels Not in Excess of 3,411 Megawatts Thermal
CNL-21-075, Response to Request for Additional Information Regarding Expedited Application to Modify Technical Specification 3.7.12, Auxiliary Building Gas Treatment System, for One-Time Exception to Permit Opening
CNL-24-004, Application to Modify the Watts Bar Nuclear Plant, Unit 1 and Unit 2 Technical Specifications for Main Control Room Chiller Completion Time Extension (WBN-TS-23-13)
CNL-22-037, Application to Revise Technical Specifications to Adopt TSTF-541-A, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position (BFN TS-533)
05000327/LER-1989-014, :on 890506,limiting Condition for Operation Entered When Both Trains of Auxiliary Bldg Gas Treatment Sys Inoperable.Caused by Opening Control Power Fuse During Replacement of Indicating Lamp.Fuse Replaced.W/Undated Ltr
05000327/LER-1988-028, :on 880723,hourly Fire Watch Patrol Through 734 Ft Elevation of Auxiliary Bldg Suspended.Caused by Valve Leaks in Safety Injection Sys.Auxiliary Bldg Gas Treatment Sys Manually Initiated
05000327/LER-1989-006-02, :on 890216,auxiliary Bldg Waste Packaging Area Door A111 Breached W/O Issuance of Breaching Permit.Caused by Incomplete Door Identification,Inadequate Programmatic Control & Personnel Oversight.Door A111 Closed
05000327/LER-1989-018-01, :on 890619,discovered That Both Trains of Auxiliary Bldg Gas Treatment Sys (ABGTS) Automatic Actuation Could Have Been Rendered Inoperable.Caused by Removal of Radiation Monitor During Testing
05000327/LER-1989-018, :on 890619,0726 & 1010 & 890628,four Events Occurred Re Auxiliary Bldg Gas Treatment Sys During Periods When Radiation Monitor Was Removed from Sys.Caused by Inappropriate Inclusion of Monitor
05000327/LER-1989-006, :on 890216,discovered That Auxiliary Bldg Waste Packaging Area Door Breached W/O Issuance of Breaching Permit.Caused by Inadequate Training & Programmatic controls.Plant-wide Dispatch Issued on 890223
05000327/LER-1987-028, :on 870611,determined That Both Control Air Trains Could Be Lost in Event of Offsite Power Loss.Caused by Design Deficiency.Jumpers Installed Around sealed-in Contacts to Provide Automatic Reset
05000327/LER-1987-004, :on 870113,discovered That Determination of Charcoal Adsorber Bank Efficiency by Technical Instruction TI-9 Performed Improperly.Caused by Personnel error.TI-9 Revised to Ensure Accurate Adsorber Efficiency
05000327/LER-1986-055, :on 861201,during Cold Shutdown,Auxiliary Bldg Isolation (Abi) Occurred W/O Associated Relays Sealed In. Cause Probably Due to Spike on Radiation Monitor 0-RM-90-102.Change Notice Issued
05000327/LER-1986-033, :on 860717,seismic Qualification of Charcoal Filter Trays Not Verified in Listed Sys.Caused by Untraceability of Trays.Qualified Trays Will Be Installed Prior to Start Up
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-1988-035-01, :on 880927,auxiliary Bldg Isolation Occurred When Operator Inadvertently Tripped Circuit Breaker A. Cause Not Determined.Training Ltr Issued to All Licensed Operators Detailing Event
05000327/LER-1988-046, :on 881110,Unit 1 Containment Ventilation Isolation Occurred Due to Inadequate Test Recorder Ground Strap Configuration.Containment Ventilation Isolation Reset
05000327/LER-1988-032-01, :on 880903,during Calibr of Auxiliary Bldg Vent Radiation Monitor,Auxiliary Bldg Isolation Occurred.Caused by Procedure Inadequacy & Design of Control Circuitry. Handswitch Placed in Correct Position
05000327/LER-1988-027, :on 880714,discovered Incorrect Source Strength Evaluation Date on Surveillance Instructions for Channels. Caused by Inadequate Checklist in App F of Surveillance Instruction SI-1.Instruction Will Be Revised
05000327/LER-1988-001, :on 880111,four Emergency Diesel Generators Declared Inoperable Due to Interval for Tech Spec Surveillance Requirement 4.8.1.2 Exceeded.Caused by Oversight During Rev of Computer Program.W/Undated Ltr
05000327/LER-1985-045-01, :on 851031,diesel Generator Start & Train B Auxiliary Bldg Isolation Occurred.Caused by Bent Racking Lever in Start Bus 1B Alternate Feeder Breaker Racking Mechanism.Lever Straightened
05000327/LER-1985-031-01, :on 850729,auxiliary Bldg Isolation Occurred Due to High Radiation Indicated by Stack Ventilation Monitor.Caused by Leaking Weld at Sample Line Connection Upstream of Valve 62-674.Lines Replaced
05000327/LER-1984-045, :on 840625,auxiliary Control Air Compressor A-A Taken Out of Svc.On 840709,compressor B-B Removed from Svc. Power Reduction to Mode 3 Initiated But Stopped When Compressor B-B Returned to Svc
05000327/LER-1985-038, :on 850908,auxiliary Bldg Ventilation Isolation Occurred Due to Spike on Spent Fuel Pool (SFP) Radiation Monitor.Caused by Increase in Radiation Level Due to Removal of SFP Filter from Svc
05000327/LER-1985-017, :on 850422 & 0506,inadvertent Auxiliary Bldg Isolations (Abis) Occurred.Caused by electro-magnetic Frequency Feedback from Welding Activities.Abi in Both Events Reset
05000327/LER-1996-009-01, :on 960718,auxiliary Building Secondary Containment Boundary/Fire Barrier Not Maintained as Required by Design.Caused by Failure to Follow Design Control Process
05000327/LER-1984-055, :on 840817 & 20,during Work on Storage Facility for Plant Maint Insulators,Doors A028 & A029 Left Open. Caused by Personnel Failure to Realize Outer Door Part of Vital Area Boundary.Procedure Revised
05000327/LER-1984-053, :on 840905,both Trains of Auxiliary Bldg Gas Treatment Sys Declared Inoperable Due to Uncontrolled Breach of Auxiliary Bldg Secondary Containment Encl.Caused by Opened Inner & Outer Door.Outer Door Closed
05000328/LER-1991-007-03, :on 911110,discovered That Three one-half Inch Essential Raw Cooling Water Test Connection Valves Partially Opened.Cause Not Determined.Valves Closed & Locking Devices Securely Reinstalled
05000328/LER-1995-004-02, :on 950525,observed That Containment Purge Air Inboard Isolation Valve May Not Have Sufficient Clearance for Actuator Proper Function During Loca.Caused by Personnel Error.Clearance Deficiency Corrected
05000327/LER-1983-123-03, /03L-0:on 830926,train a of Auxiliary Bldg Gas Treatment Sys Declared Inoperable Due to Control Damper 1-FCV-30-149 Failing to Operate.Cause Unknown.Controller Replaced
05000327/LER-1984-008, :on 840124,high Radiation Alarm Actuated, Causing Auxiliary Bldg Isolation to Occur.Caused by Pressure in Vol Control Tank & Overflowing of Condensate Demineralizer Waste Evaporator.Bldg Cleaned
05000327/LER-1983-115-03, /03L-0:on 830827,while in Mode 1,operator for Auxiliary Bldg Gas Treatment Sys Damper 1-FCV-30-146A Disconnected.Caused by Loose Locking Nuts.Linkage Reconnected.Nuts Tightened
05000327/LER-1991-014, :on 910610,fire Watches Required by Tech Spec LCOs 3.3.3.8 & 3.7.12 Were Not Performed.Caused by Airborne Radiological Conditions.Airborne & Contamination Conditions Corrected
05000327/LER-1994-017, :on 941222,B-train Abi & Start of B-train Abgst Occurred as Result of High Radiation in Spent Fuel Area.Personnel Involved W/Spent Fuel Pool Rack Replacement Briefed on Event
05000328/LER-1994-005-02, :on 940419,determined Containment Leak Rate TS Limits Exceeded.Caused by Failure of Relief Valve Bellows & Check Value Leaking Through Seat.Failed Valve Replaced.W/
05000327/LER-1990-017, :on 900708,auxiliary Bldg Isolation Initiated. Caused by Random Drift of Setpoint for Switch 1-TS-30-103A. Temp Switch Calibr,Returned to Svc & Recovered from Auxiliary Bldg Isolation
05000327/LER-1993-020, :on 930719,Train B of Auxiliary Bldg Gas Treatment Sys Manually Initiated as Result of Fire in General Supply Fan Room.Sg Wet Layup Recirculation Pump Bearing & Motor Replaced
05000327/LER-1981-059-01, /01T-0:on 810428,auxiliary Bldg Gas Treatment Sys Inoperable.Caused by Railroad Door to Cask Loading Area Being Open W/O Personnel Present,Due to Misinterpretation of Procedural Control.Door Closed.Personnel Reinstructed
05000327/LER-1980-184-01, /01T-0:on 801120,in Mode 1,at 94% Power,Auxiliary Bldg Gas Treatment Sys Was Declared Inoperable.Caused by Nitrogen Supply Line Being Run Under Railroad Door to Cask Loading Area,Preventing Door from Completely Closing
05000327/LER-1989-028, :on 891115,penetration Room Developed Noble Gas High Airborne Radioactivity Excursion of 86.1 Max Permissible Concentration Fraction.Caused by Inadequate Latching Mechanism on Access Door
05000327/LER-2018-002, Exceeded Breach Margin Renders Both Trains of the Auxiliary Building Gas Treatment System Inoperable
05000390/LER-1917-013, Regarding Incorrectly Adjusted Auxiliary Building Gas Treatment System Damper Leads to a Condition Prohibited by Technical Specifications
05000390/LER-1917-008, Regarding Shield Building Inoperability and Potential Loss of Safety Function Resulting from Spurious Equipment Operation
05000390/LER-1917-007, Regarding Multiple Unreported Potential Loss of Safety Function Events Associated with Inoperable Single Train Systems Due to Misinterpretation of Reporting Guidance
CNL-16-141, Application to Modify Technical Specifications Regarding Intermittent Opening of the Auxiliary Building Secondary Containment Closure Technical Specification 3.7.12, Auxiliary Building Gas Treatment System
05000327/LER-2013-004, Regarding Failure to Comply with Technical Specifications for Containment Penetrations During Fuel Movement Resulting from Ineffective Procedures
05000390/LER-2009-001, For Watts Bar Regarding Inoperability of Aux Bldg Gas Treatment System Due to Inadequate Surveillance and Breach of ABSCE Boundary
05000390/LER-2006-010, Re Both Trains of Auxiliary Building Gas Treatment System (ABGTS) Inoperable Due to Boundary Breach
05000390/LER-2005-001, Regarding Two Trains of ABGTS Inoperable
05000390/LER-2003-005, Regarding Accident Mitigation System Degraded Due to Both Trains of ABGTS Inoperable
05000327/LER-2021-003, Exceeded Breach Margin Renders Both Trains of the Auxiliary Building Gas Treatment System Inoperable
05000327/LER-1917-001, Regarding Breached Door Renders Both Trains of the Auxiliary Building Gas Treatment System Inoperable
05000327/LER-1988-028-01, :on 880723,hourly Fire Watch Patrol Through 734 Ft Elevation of Auxiliary Bldg Could Not Be Completed. Caused by High Level Airborne Radioactivity on Bldg.Plant Operators Manually Initiated Treatment Sys
WBL-25-026, Periodic Submission for Changes Made to the Technical Specification Bases and Technical Requirements Manual