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WBL-23-013, 10 CFR 50.46 Annual Report for 202229 March 202310 CFR 50.46 Annual Report for 2022
WBL-22-034, Update to Fire Protection Report Figures Redacted1 August 2022Update to Fire Protection Report Figures Redacted
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)27 August 2020Tennessee 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)Anticipated operational occurrence
Surveillance Frequency Control Program
ML18022A36419 January 2018Survey Codes_Twra
CNL-17-141, Tennessee Valley Authority - Anchor Darling Double Disc Gate Valve Information and Status28 December 2017Tennessee Valley Authority - Anchor Darling Double Disc Gate Valve Information and StatusAnchor Darling
ML16056A13911 March 2016Correction to the U.S. Nuclear Regulatory Commission Analysis of Licensees' Decommissioning Funding Status Reports
CNL-15-213, Compliance with Three Mile Island (TMI) Action Plan Requirements for an Operating License7 October 2015Compliance with Three Mile Island (TMI) Action Plan Requirements for an Operating License
ML15238B6673 September 2015MSFHI Public Table
ML14307B70710 December 2014Supplemental Information Related to Development of Seismic Risk Evaluations for Information Request Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Seismic Hazard Reevaluations for Recommendation 2.1 of the Near-TProbabilistic Risk Assessment
Fukushima Dai-Ichi
ML13255A31514 August 2013Final Safety Analysis Report (Fsar), Amendment 110, Table 6.2.4-1 Containment Penetrations and Barriers - Page 1 of 64 - Page 64 of 64
ML13175A1355 March 20132-PTI-092-03, Revision 0, Nuclear Instrumentation Source Range Noise Checks During Hot Functional Testing.Temporary Modification
ML13175A1368 November 20122-PTI-099-06, Revision 0, Reactor Protection Setpoint Verification.
ML13175A1341 November 20122-PTI-082-02, Revision 0, Rod Control - Non Hft.
ML13175A13322 October 20122-PTI-085-01, Revision 0, Rod Control Functional Test.
ML12157A30424 July 2012SECY-12-0103 - Enclosure 1 - Statistical Status Report - Sixth Report on the Status of Reactivation of Construction and Licensing for Watts Bar Nuclear Plant, Unit 2Cyber Security
ML12157A46124 July 2012SECY-12-0103 - Enclosure 2 - Future Activities for Watts Bar Unit 2, Reactivation Project PlanCyber Security
ML11203A00521 July 2011SECY-11-0102 - Enclosure 2 - Chart of Future Activities - Fourth Report on Status of Reactivation of Construction and Licensing for Watts Bar Nuclear Plant Unit 2Cyber Security
ML11178A1853 June 2011Final Safety Analysis Report (Fsar), Amendment 104, Table of Contents, Section 15.0, Accident Analyses, Through Table 15A-2 Accident Atmospheric Dilution Factors (sec/m3)Safe Shutdown
Boric Acid
Shutdown Margin
Loop seal
Post Accident Monitoring
Emergency Lighting
Earthquake
Fuel cladding
Coast down
ML11178A1823 June 2011Final Safety Analysis Report (Fsar), Amendment 104, Table of Content, Section 12.0, Radiation Protection, Through Appendix 12A - Radiation Protection Features for the Tritium Production ProgramBoric Acid
High Radiation Area
Grab sample
Offsite Dose Calculation Manual
Anticipated operational occurrence
Locked High Radiation Area
Deep Dose Equivalent
ML11178A1843 June 2011Final Safety Analysis Report (Fsar), Amendment 104, Table of Contents, Section 14.0, Initial Test Program Through Figures 14.2-2 Power Ascension Test ScheduleSafe Shutdown
Boric Acid
Shutdown Margin
Grab sample
Stroke time
Post Accident Monitoring
Hydrostatic
Emergency Lighting
Fuel cladding
Pressure Boundary Leakage
Power change
ML11178A1813 June 2011Final Safety Analysis Report (Fsar), Amendment 104, Table of Contents, Section 11.0, Through Table 11A-2 Tritium Release for 1972 from Westinghouse Designed Operating ReactorsBoric Acid
Grab sample
Offsite Dose Calculation Manual
Anticipated operational occurrence
Process Control Program
Chernobyl
Fuel cladding
ML11178A1793 June 2011Final Safety Analysis Report (Fsar), Amendment 104, Section 9.4 Air Conditioning, Heating, Cooling and Ventilation Systems Through Figure 9.5-30 Diesel Exhaust System Piping SchematicHot Short
Safe Shutdown
Boric Acid
Health Physics Network
Fire Barrier
Tornado Missile
Safe Shutdown Earthquake
Emergency Lighting
Tornado-Generated Missile
Tornado Generated Missile
Offsite Circuit
Fire Protection Program
ML11178A1783 June 2011Final Safety Analysis Report (Fsar), Amendment 104, Table of Contents, Section 9.0 Auxiliary Systems, Through Figure 9.3-21 Watts Bar Nuclear Plant Boric Acid Tank LimitsSafe Shutdown
Boric Acid
High winds
Loop seal
Ultimate heat sink
Grab sample
Tornado Missile
Safe Shutdown Earthquake
Hydrostatic
VT-2
Design basis earthquake
Earthquake
Fuel cladding
ML11178A1753 June 2011Final Safety Analysis Report (Fsar), Amendment 104, Section 6.3 Emergency Core Cooling System Through 6.9 Motor-Operated Valve (MOV) ProgramsHot Short
Safe Shutdown
Boric Acid
Packing leak
Stroke time
Safe Shutdown Earthquake
Post Accident Monitoring
Coatings
Operating Basis Earthquake
Incorporated by reference
Earthquake
Liquid penetrant
ML11178A1773 June 2011Final Safety Analysis Report (Fsar), Amendment 104, Table of Contents, Section 8.0 Electric Power, Through Page 8E-11Safe Shutdown
Mission time
Fire Barrier
Anticipated operational occurrence
Tornado Missile
Safe Shutdown Earthquake
Post Accident Monitoring
Operating Basis Earthquake
Emergency Lighting
Offsite Circuit
ML11178A1723 June 2011Final Safety Analysis Report (Fsar), Amendment 104, Table of Contents, Section 4.0 Reactor, Through Figure 4.4-6, Location of Incore Instrumentation System Fixed Incore Detector Core Exit Thermocouples and Iitas (Unit 2)Boric Acid
Shutdown Margin
Non-Destructive Examination
Safe Shutdown Earthquake
Hydrostatic
Design basis earthquake
Earthquake
Fuel cladding
Power change
Flow Induced Vibration
ML11178A1733 June 2011Final Safety Analysis Report (Fsar), Amendment 104, Table of Contents, Section 5.0, Reactor Coolant System, Through Instrumentation Application 5.6-7Hot Short
Safe Shutdown
Boric Acid
Shutdown Margin
Reactor Vessel Water Level
Loop seal
Non-Destructive Examination
Offsite Dose Calculation Manual
Safe Shutdown Earthquake
Weld Overlay
Post Accident Monitoring
Hydrostatic
Operating Basis Earthquake
Nondestructive Examination
Pressure and Temperature Limits Report
Design basis earthquake
Earthquake
Liquid penetrant
Pressure Boundary Leakage
Power change
Flow Induced Vibration
Unidentified leakage
ML11132A1185 May 2011Bellefonte, Units 1 and 2 - Proposed Regulatory Framework for the Possible Completion of Construction ActivitiesSafe Shutdown
Boric Acid
Fitness for Duty
Shutdown Margin
Reactor Vessel Water Level
Ultimate heat sink
Offsite Dose Calculation Manual
Fire Barrier
Stroke time
Commercial Grade Dedication
Probabilistic Risk Assessment
Coatings
Anchor Darling
VT-2
Cyber Security
Scram Discharge Volume
Process Control Program
Safeguards Contingency Plan
Hemyc
Control of Heavy Loads
Turbine Missile
Fuel cladding
Fire Protection Program
Brachytherapy
Uranium Hexafluoride
ML11087162815 March 2011Unit 2 - Final Safety Analysis Report (Fsar), Amendment 103, FSAR 2.5-596, Underground Barrier Trench a, STA 5 + 78
ML11087162915 March 2011Unit 2 - Final Safety Analysis Report (Fsar), Amendment 103, FSAR 2.5-597, Underground Barrier Trench a, STA 7 + 78
ML11087163015 March 2011Unit 2 - Final Safety Analysis Report (Fsar), Amendment 103, FSAR 2.5-602 RO, Underground Barrier Trench B, STA 1 + 00
ML11087163115 March 2011Unit 2 - Final Safety Analysis Report (Fsar), Amendment 103, FSAR 2.5-603, Underground Barrier Trench B, STA 2 + 50
ML11087163215 March 2011Unit 2 - Final Safety Analysis Report (Fsar), Amendment 103, FSAR 2.5-604, Underground Barrier Trench B, STA 3 + 00
ML11087166515 March 2011Unit 2 - Final Safety Analysis Report (Fsar), Amendment 103, FSAR 2.5-605, Underground Barrier Trench B, STA 4 + 50
ML12257A0681 January 2011Tennessee Valley Authority 2012 Watts Bar - Office of Environmental and Research Recreation Area Matrix
ML11221A32217 December 2010Amendment 102 to Final Safety Analysis Report (Fsar), Table 6.2.4-1, Page 1 of 69 - 64 of 69
ML10197031116 July 2010Request for Additional Information Regarding Fire Protection ProgramHot Short
Safe Shutdown
Boric Acid
Fire Barrier
Probabilistic Risk Assessment
Operator Manual Action
Multiple Spurious Operation
Fire Protection Program
ML1016005053 June 2010Chapter 14 - Question 4 - Supporting InformationHydrostatic
ML10161045627 May 2010Amendment 99 to Final Safety Analysis Report (Fsar), Containment Penetrations and Barriers-Table 6.2.4-1. Pages 1 Through 64
ML1013705387 May 2010Amendment 98 to Final Safety Analysis Report, Figure 2.5-549, ERCW Pipeline Section A-A, Sheet 1 of 4
ML1013705397 May 2010Amendment 98 to Final Safety Analysis Report, Figure 2.5-549, ERCW Pipeline Section A-A, Sheet 2 of 4
ML1013705377 May 2010Amendment 98 to Final Safety Analysis Report, Figure 2.5-281, Category 1 Conduit Banks Section F-F, Sheet 1
ML1013705347 May 2010Amendment 98 to Final Safety Analysis Report, Figure 2.5-71, Graphic Log & Elastic Moduli Sta. L-61+00
ML1013705317 May 2010Amendment 98 to Final Safety Analysis Report, Figure 2.5-281, Category I Conduit Banks Section F-F, Sheet 2
ML10063023525 February 2010Yard Holding Pond Wsel Graph Overflow for 2001
ML09357055514 December 2009Final Safety Analysis Report, Amendment 96, Figure 2.5-281, Category 1 Conduit Banks, Section F-F Sheet 1 of 2
ML09357055614 December 2009Final Safety Analysis Report, Amendment 96, Figure 2.5-281, Category 1 Conduit Banks, Section F-F, Sheet 1 of 2
ML09357055714 December 2009Final Safety Analysis Report, Amendment 96, Figure 2.5-549, ERCW Pipeline Section A-A, Sheet 1 of 4
ML09357056014 December 2009Final Safety Analysis Report, Amendment 96, Figure 2.5-71, Graphic Log and Elastic Moduli Sta. L-61+00
ML09357056114 December 2009Final Safety Analysis Report, Amendment 96, Figure 2.5-222, Borrow Investigation