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 Issue dateTitle
ML20323A31129 October 2020Amendment 3 to Updated Final Safety Analysis Report, Chapter 4, Reactor
ML19039A0498 February 2019Amd 1 to USAR Chapter 9 Auxiliary System NRC Additional Redactions
ML17334A1702 November 2017Amendment 1 to Updated Safety Analysis Report, Chapter 5, Reactor Coolant System
ML17334A1692 November 2017Amendment 1 to Updated Safety Analysis Report, Chapter 4, Reactor
ML15111A3775 October 2015Seismic Hazard Re-Evaluations Relating to Recommendation 2.1 of the Near-Term Task Force Review of Insight from the Fukushima Dai-Chi Accident
ML15055A5435 October 2015Staff Assessment of Information Provided Pursuant to Title 10 of the Code of Federal Regulations Part 50, Section 50.54(f), Seismic Hazard Reevaluations Relating to Recommendation 2.1 of the NTTF Review of Insights
ML15279A27711 September 2015Amendment 114 to Final Safety Analysis Report, Section 9.0 - Auxiliary Systems, Pages 9-i - 9.3-158
ML15279A27311 September 2015Amendment 114 to Final Safety Analysis Report, Section 6.0 - Engineered Safety Features, Pages 6-iv - 6.2.6-30
ML15279A27211 September 2015Amendment 114 to Final Safety Analysis Report, Section 5.0 - Reactor Coolant System
ML15279A27011 September 2015Amendment 114 to Final Safety Analysis Report, Section 4.0 - Reactor, Pages 4-i - 4.4-52
ML15279A26911 September 2015Amendment 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 9.0 - Auxiliary Systems, Pages 9-i - 9.3-15811 September 2015Watts 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 4.0 - Reactor, Pages 4-i - 4.4-5211 September 2015Watts Bar Nuclear Plant, Unit 2, Amendment 114 to Final Safety Analysis Report, Section 4.0 - Reactor, Pages 4-i - 4.4-52
NL-15-183, Watts Bar Nuclear Plant, Unit 2, Amendment 114 to Final Safety Analysis Report, Section 5.0 - Reactor Coolant System11 September 2015Watts Bar Nuclear Plant, Unit 2, Amendment 114 to Final Safety Analysis Report, Section 5.0 - Reactor Coolant System
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 - 6.2.6-3011 September 2015Watts 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 - 3.12-611 September 2015Watts 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
CNL-15-168, Notification of Construction Substantially Complete and Request for Operating License12 August 2015Notification of Construction Substantially Complete and Request for Operating License
CNL-14-072, Follow-up Response to NRC Request for Additional Information Related to Overall Integrated Plan in Response to the Commission Order Modifying Licenses with Regard to Requirements for Reliable Spent Fuel Pool Instrumentation (Order EA-12-025 June 2014Follow-up Response to NRC Request for Additional Information Related to Overall Integrated Plan in Response to the Commission Order Modifying Licenses with Regard to Requirements for Reliable Spent Fuel Pool Instrumentation (Order EA-12-051
ML14170A04316 June 2014Attachment 4 - TRM Bases Developmental Revision D Changes (Mark-Up) for WBN Unit 2
ML14160B10630 May 2014Final Safety Analysis Report, Amendment 112, Section 6.0, Engineered Safety Features
ML14160B10230 May 2014Final Safety Analysis Report, Amendment 112, Section 3.8.5, Foundations and Concrete Supports
ML14160B10430 May 2014Final Safety Analysis Report, Amendment 112, Section 4.0, Reactor
ML14160B10530 May 2014Final Safety Analysis Report, Amendment 112, Section 5.0, Reactor Coolant System
ML14160B11030 May 2014Final Safety Analysis Report, Amendment 112, Section 9.0, Auxiliary Systems
ML14128A12915 May 2014Report for the Audit Regarding Implementation of Mitigating Strategies and Reliable Spent Fuel Instrumentation Related to Orders EA-12-049 and EA-12-051
CNL-14-038, Tennessee Valley Authority'S Seismic Hazard & Screening Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Recommendation 2.1 of Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Acc31 March 2014Tennessee Valley Authority'S Seismic Hazard & Screening Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Recommendation 2.1 of Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accid
CNL-13-124, Tennessee Valley Authority - Response to NRC Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding the Watts Bar Nuclear Plant Seismic Walkdown Results of Recommendation 2.3 of the Near-Term Ta2 December 2013Tennessee Valley Authority - Response to NRC Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding the Watts Bar Nuclear Plant Seismic Walkdown Results of Recommendation 2.3 of the Near-Term Task
CNL-13-125, Response to NRC Request for Additional Information Related to Overall Integrated Plan in Response to the Commission Order Modifying Licenses with Regard to Requirements for Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051)22 November 2013Response to NRC Request for Additional Information Related to Overall Integrated Plan in Response to the Commission Order Modifying Licenses with Regard to Requirements for Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051) (
IR 05000390/201360730 September 2013IR 05000391-13-607, 8/17/2013, Watts Bar Nuclear Plant Unit 2 Construction - NRC Integrated
IR 05000391/201360730 September 2013IR 05000391-13-607, 8/17/2013, Watts Bar Nuclear Plant Unit 2 Construction - NRC Integrated
ML13255A27014 August 2013Final Safety Analysis Report (Fsar), Amendment 110, Section 6, Engineered Safety Features
ML13255A28014 August 2013Final Safety Analysis Report (Fsar), Amendment 110, Section 9, Auxiliary Systems
ML13255A27914 August 2013Final Safety Analysis Report (Fsar), Amendment 110, Section 5, Reactor Coolant System
ML13255A27814 August 2013Final Safety Analysis Report (Fsar), Amendment 110, Section 4, Rector
ML13255A27714 August 2013Final Safety Analysis Report (Fsar), Amendment 110, Section 3.8.5, Foundations and Concrete Supports
ML12335A34027 November 2012Tennessee Valley Authority - Fleet Response to NRC Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding the Flooding Walkdown Results of Recommendation 2.3 of the Near-Term Task Force Review of
ML12244A07123 August 2012Final Safety Analysis Report (Fsar), Amendment 109 - Section 6, Engineered Safety Features - Page 6-I Through 6.2.6-30
ML12244A07023 August 2012Final Safety Analysis Report (Fsar), Amendment 109 - Section 5, Reactor Coolant System - Page 5-I Through 5.6-8
ML12244A06923 August 2012Final Safety Analysis Report (Fsar), Amendment 109 - Section 4, Reactor - Page 4-I Through 4.4-52
ML12244A06823 August 2012Final Safety Analysis Report (Fsar), Amendment 109 - Section 3, Design of Structures, Components, Equipment, and Systems - Page 3.8.5-1 Through 3.12-6
ML12244A08123 August 2012Final Safety Analysis Report (Fsar), Amendment 109 - Section 9, Auxiliary Systems, Page 9-I Through 9.3-160
ML12073A3938 March 2012TVA White Paper Common Q Pams Design Basis Conformance to the Requirements of IEEE 603-1991, Dated March 8, 2012 (Letter Items 1 and 3, Sser 23 Appendix Hh Item Numbers 94 and 105). Attachment 4
ML12083A1715 March 2012Final Safety Analysis Report, Amendment 108. Chapter 9 - 9.0 Through 9.3-160
ML12083A1695 March 2012Final Safety Analysis Report, Amendment 108. Chapter 3 - 3.8.5 Through 3.12-6
ML12083A1705 March 2012Final Safety Analysis Report, Amendment 108. Chapter 4 - 4.0 Through 4.4-52
ML12083A1635 March 2012Final Safety Analysis Report, Amendment 108. Chapter 5 - 5.0 Through 5.6-8
ML12083A1645 March 2012Final Safety Analysis Report, Amendment 108. Chapter 6 - 6.0 Through 6.2.6-30
ML12178A18417 November 2011Final Safety Analysis Report, Amendment 107 - Section 3.8.5 - Foundations and Concrete Supports Through Section 3.12.5 - Safety Evaluation
ML12178A18517 November 2011Final Safety Analysis Report, Amendment 107 - Section 4 - Reactor
ML12178A18617 November 2011Final Safety Analysis Report, Amendment 107 - Section 5 - Reactor Coolant System
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