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 Issue dateTitle
ML23283A27910 October 2023Revisions to the Sequoyah Nuclear Plant Units 1 and 2 Technical Requirements Manual
CNL-22-023, Supplement to License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - Ritstf28 April 2022Supplement to License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - Ritstf
ML20304A40328 October 2020Revisions to the Sequoyah Nuclear Plant Units 1 and 2 Technical Requirements Manual
ML19296B78631 October 2019NUREG/CR-7245 State-of-the-Art Reactor Consequence Analyses (Soarca) Project Sequoyah Integrated Deterministic and Uncertainty Analyses
ML17340B20930 November 2017NUREG/CR-7245 State-of-the-Art Reactor Consequence Analyses (Soarca) Project.
CNL-16-011, Proposed Technical Specification Change to Extend the Allowed Completion Time to Restore Essential Raw Cooling Water System Train to Operable Status from 72 Hours to 7 Days (TS-SQN-16-01)11 March 2016Proposed Technical Specification Change to Extend the Allowed Completion Time to Restore Essential Raw Cooling Water System Train to Operable Status from 72 Hours to 7 Days (TS-SQN-16-01)
CNL-15-067, Completion of Required Action by NRC Order EA-12-051, Reliable Spent Fuel Pool Instrumentation15 July 2015Completion of Required Action by NRC Order EA-12-051, Reliable Spent Fuel Pool Instrumentation
CNL-15-020, Supplement to the Application to Modify Ice Condenser Technical Specifications to Address Revisions in Westinghouse Mass and Energy Release Calculation (SQN-TS-12-04) and Response to NRC Requests for Additional Information10 April 2015Supplement to the Application to Modify Ice Condenser Technical Specifications to Address Revisions in Westinghouse Mass and Energy Release Calculation (SQN-TS-12-04) and Response to NRC Requests for Additional Information
CNL-14-211, Expedited Seismic Evaluation Process Report (CEUS Sites) Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima.22 December 2014Expedited Seismic Evaluation Process Report (CEUS Sites) Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima.
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
NRC-2014-0037, FRN: Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations: Publication Date: March 4, 20144 March 2014FRN: Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations: Publication Date: March 4, 2014
ML14051A6714 March 2014FRN: Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations: Publication Date: March 4, 2014
CNL-13-139, Response to Request for Additional Information Regarding Sequoyah Nuclear Plant, Units 1 and 2, Ultimate Heat Sink License Amendment Request (TS-SQN-13-01 and 13-02)11 December 2013Response to Request for Additional Information Regarding Sequoyah Nuclear Plant, Units 1 and 2, Ultimate Heat Sink License Amendment Request (TS-SQN-13-01 and 13-02)
ML13280A2672 October 2013Proposed Technical Specification Change, Ultimate Heat Sink Temperature Limitations Supporting Alternate Essential Raw Cooling Water Loop Alignments (TS-SQN-13-01 and 13-02)
ML13294A43026 September 2013Fukushima Near-Term Task Force Recommendation 2.3: Seismic Response Report, Revision 1
ML13282A23326 September 2013Fukushima Near-Term Task Force Recommendation 2.3: Seismic Response Report
ML13199A2813 July 2013Application to Modify Ice Condenser Technical Specifications to Address Revisions in Westinghouse Mass and Energy Release Calculation (SQN-TS-12-04)
ML13031A50031 January 2013NUREG/CR-7154 Vol 1 Risk Informing Emergency Preparedness Oversight: Evaluation of Emergency Action Levels - a Pilot Study of Peach Bottom, Surry and Sequoyah (Main Report, Appendices a and B)
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
ML12342A13312 November 2012Fukushima Near-Term Task Force Recommendation 2.3: Seismic Response Report
ML12342A13412 November 2012Fukushima Near-Term Task Force Recommendation 2.3: Seismic Response Report
ML12114A0615 April 2012Technical Report, SQN2-SGR-TRI, Revision 3, Sequoyah Unit 2 Steam Generator Replacement Rigging and Heavy Load Handling.
ML11273A16929 September 2011Application to Revise Sequoyah Nuclear Plant, Unit 1, Operating License and Technical Specification 3.7.5, Ultimate Heat Sink, to Support Steam Generator Replacement Project (TS-SQN-2011-05)
ML08273068426 September 2008Request for Enforcement Discretion for Technical Specification Limiting Condition for Operation 3.0.5, Inoperability Due to Loss of a Main Control Room Air Handling Unit in Conjunction with an Emergency Power Source Out-of-Service
ML0532503504 November 2005Revisions to the Technical Requirements Manual (TRM) (Revisions 28, 29, 30, 31, 32, 33, 34, and 35) and Technical Specification (TS) Bases (Unit 1 Revisions 25, 26, 27, and 28; Unit 2 Revisions 24, 25, 26, and 27)
ML14357A31926 April 2004TVA Nuclear Radiological Emergency Plan (Rep), Revision 73
ML03163082419 May 2003Accepted Version of Topical Report No. 24370-TR-C-003-A, Steam Generator Compartment Roof Modification.
ML03071035528 February 2003License Amendment (SQN-TS-03-03) to Utilize Methodology Described in Topical Report No. 24370-TR-C-003, Revision 1, for Modification of Steam Generator Roof Compartment
ML03059031825 February 2003Attachments to 02/12/2003 Meeting Summary - Design Summary of the Steam Generator Enclosure Roof Support Frames
ML03051023414 February 2003Steam Generator Replacement Project - Topical Report No. 24370-TR-C-003, Steam Generator Compartment Roof Modification, Revision 1.
ML0304204824 February 2003Generator Replacement Project - Topical Report No. 24370-TR-C-002, Rigging & Heavy Load Handling Topical Report, Additional Information
ML03016024015 January 2003Steam Generator Replacement Project - Topical Report No. 24370-TR-C-002, Rigging and Heavy Load Handling Topical Report, Response to NRC Request for Additional Information
ML03161090824 December 2002Rev 3 to 24370-TR-C-002-A, Sequoyah Unit 1 Steam Generator Replacement Rigging and Heavy Load Handling Topical Report, Attachment 1 Through Figure 3
ML03161089924 December 2002Rev 3 to 24370-TR-C-002-A, Sequoyah Unit 1 Steam Generator Replacement Rigging and Heavy Load Handling Topical Report, Table of Contents Through Figure 1
ML0233807034 December 2002RAI, Unit 1 Steam Generator Replacement Topical Reports and Associated TS Amendment
ML02346049224 October 2002Meeting Agenda & Slides from Tva/Nrc Sequoyah Steam Generator Replacement Project Topical Meeting
ML0225502799 September 2002Memo, Draft Questions for the Unit 1 Steam Generator Replacement Topical Reports & Associated Technical Specification Amendment
ML02106058115 April 2002Steam Generator Replacement Project - Topical Report No. 24370-TR-C-002, Rigging & Heavy Load Handling.
ML02091079228 March 2002Steam Generator Replacement Project - Topical Report No. 24370-TR-C-003, Steam Generator Compartment Roof Modification.
IR 05000327/199700822 September 1997Insp Repts 50-327/97-08 & 50-328/97-08 on 970706-0823. Violations Noted.Major Areas Inspected:Licensee Operations, Maint,Engineering,Plant Support & Effectiveness of Licensee Controls in Identifying,Resolving & Preventing Problems
ML20141M13427 March 1992Spent Fuel Pool Mod for Increased Storage Capacity
ML20236A36710 March 1989Responds to Unresolved Item 88-12-08 Re Component Damping Values Noted in Insp Repts 50-327/88-12 & 50-328/88-12. Corrective Actions:Fsar Currently Being Revised to Incorporate 2% & 3% Values for Mechanical Equipment
ML20148C10520 January 1988Forwards Summary of Microbiologically Induced Corrosion (MIC) Program & Technical Basis for Structural Integrity Evaluations,Per NRC Request Made at 871215 Meeting.Plant Acceptable for Restart
ML20215L8426 May 1987Rev 1 to TVA Employee Concerns Special Program Element Rept 223.2(B), Instrument Support Design
ML20235G8156 March 1987Revised Nuclear Safety-Related Moderate Energy Line Break Flooding Evaluation Rept Sequoyah Nuclear Plant Units 1 & 2
ML20207H3312 January 1987Forwards Addl Info Re Containment Isolation Design/Chemical & Vol Control Sys,Per NRC 861016,1105 & 10 Requests & Unresolved Items Noted in Insp Repts 50-327/86-20 & 50-328/86-20
ML20207L22230 December 1986Rev 0 to Sequoyah Element Rept, Instrument Support Design, Instrument Mounting Brackets
ML19345B10731 October 1980Application for Amend to License DPR-77,authorizing Storage of Low Level Radwaste Generated by Onsite Plant Operation
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