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| Issue date | Title | |
|---|---|---|
| IR 05000327/2023002 | 31 July 2023 | Integrated Inspection Report 05000327/2023002 and 05000328/2023002 |
| ML21245A267 | 27 October 2021 | NON-PROPRIETARY - Sequoyah Nuclear Plant, Units 1 and 2 - Issuance of Amendment Nos. 356 and 349 Regarding the Transition to Westinghouse Robust Fuel Assembly-2 (RFA-2) Fuel |
| CNL-21-039, Response to Request for Additional Information Re Application to Modify Technical Specification to Allow for Transition to Westinghouse RFA-2 Fuel (SQN-TS-20-09) | 5 May 2021 | Response to Request for Additional Information Re Application to Modify Technical Specification to Allow for Transition to Westinghouse RFA-2 Fuel (SQN-TS-20-09) |
| ML19197A021 | 16 July 2019 | NRR E-mail Capture - Accepted for Review - Exigent License Amendment Request for Reactor Vessel Level Instrument |
| NL-17-034, Application to Modify the Technical Specifications for Browns Ferry (TS-512), Sequoyah (TS-17-03), and Watts Bar (TS-17-20) to Resolve the Open Phase Issue Identified in NRC Bulletin 2012-01, Design Vulnerability in Electrical Power System | 17 November 2017 | Application to Modify the Technical Specifications for Browns Ferry (TS-512), Sequoyah (TS-17-03), and Watts Bar (TS-17-20) to Resolve the Open Phase Issue Identified in NRC Bulletin 2012-01, Design Vulnerability in Electrical Power System. |
| CNL-17-034, Application to Modify the Technical Specifications for Browns Ferry (TS-512), Sequoyah (TS-17-03), and Watts Bar (TS-17-20) to Resolve the Open Phase Issue Identified in NRC Bulletin 2012-01, Design Vulnerability in Electrical Power Syste | 17 November 2017 | Application to Modify the Technical Specifications for Browns Ferry (TS-512), Sequoyah (TS-17-03), and Watts Bar (TS-17-20) to Resolve the Open Phase Issue Identified in NRC Bulletin 2012-01, Design Vulnerability in Electrical Power System. |
| CNL-17-098, Revised Response to NRC Request for Additional Information Related to TVA Fleet License Amendment Request to Adopt NEI 99-01 Revision 6 Emergency Action Levels | 27 July 2017 | Revised Response to NRC Request for Additional Information Related to TVA Fleet License Amendment Request to Adopt NEI 99-01 Revision 6 Emergency Action Levels |
| CNL-17-085, Response to NRC Request for Additional Information Related to TVA Fleet License Amendment Request to Adopt NEI 99-01 Revision 6 Emergency Action Levels | 7 July 2017 | Response to NRC Request for Additional Information Related to TVA Fleet License Amendment Request to Adopt NEI 99-01 Revision 6 Emergency Action Levels |
| ML16340A009 | 9 March 2017 | Safety Evaluation Regarding Implementation of Mitigation Strategies and Reliable Spent Fuel Pool Instrumentation Related to Orders EA-12-049 and EA-12-051 |
| ML15100A046 | 28 September 2015 | SQN U1 Renewed License v2 |
| ML15100A049 | 28 September 2015 | SQN U2 Renewed License v2 |
| 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 | 24 July 2015 | 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 |
| ML15205A414 | 24 July 2015 | Plants, Units 1 and 2 - Technical Specifications Conversion to NUREG-1431, Rev. 4.0 (SQN-TS-11-10) - Supplement 3. Part 9 of 9 |
| ML15205A406 | 24 July 2015 | 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-15-128, 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 | 19 June 2015 | 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 |
| ML15176A682 | 19 June 2015 | 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 |
| ML15092A854 | 2 April 2015 | Initial Exam 2015-301 Final SRO Written Exam |
| ML14283A513 | 17 November 2014 | NRC Staff Review Documentation Provided by TVA for the Sequoyah Nuclear Plant, Units 1 and 2 Concerning Resolution of GL2004-02 Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurizer-Wate |
| ML14071A152 | 13 March 2014 | Slide, ITS Project Electrical Systems Presentation March 13, 2014 |
| ML13275A059 | 27 September 2013 | Initial Exam 2012-302 Final Administrative JPMs |
| ML120720077 | 21 February 2012 | Initial Exam 2012-301 Draft Administrative Job Performance Measure |
| ML120720356 | 21 February 2012 | Initial Exam 2012-301 Final Administrative JPMs |
| ML110350603 | 4 February 2011 | Initial Exam 2010-302 Draft SRO Written Exam |
| ML110350624 | 4 February 2011 | Initial Exam 2010-302 Draft Administrative JPMs |
| ML080720525 | 29 February 2008 | Feb Exam 05000327-08-301, 05000328-08-301 Final Administrative JPMs |
| ML080640205 | 29 February 2008 | Supplemental Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accident at Pressurized-Water Reactors (PWR) - Notice of Completion |
| ML071570437 | 9 May 2007 | April/May 2007 Exam Nos. 05000327-07-301, 05000328-07-301 - Draft RO Written Exam (Part 1 of 2) |
| ML072980432 | 9 May 2007 | April/May 2007 Exam Nos. 05000327-07-301, 05000328-07-301 - Draft JPMs and Outlines (Part 1 of 3) (Section 3 of 3) |
| ML14357A319 | 26 April 2004 | TVA Nuclear Radiological Emergency Plan (Rep), Revision 73 |
| ML040420372 | 27 January 2004 | Emergency Plan Implementing Procedure (EPIP) Revision 35 for EPIP-1 and Revision 4 for EPIP-12 |
| ML031990400 | 10 July 2003 | Emergency Response Data System Data Point Library Update |
| ML023250196 | 8 November 2002 | Emergency Plan Implementing Procedure (EPIP) Revision 34 |
| ML030430608 | 5 August 2002 | December 2002-301 Exam Draft Ro/Sro Written Exam |
| ML011790073 | 22 June 2001 | Emergency Plan Implementing Procedure (EPIP) Revisions |
| Information Notice 1999-14, Unanticipated Reactor Water Draindown at Quad Cities Unit 2, Arkansas Nuclear One Unit 2, & FitzPatrick | 5 May 1999 | Unanticipated Reactor Water Draindown at Quad Cities Unit 2, Arkansas Nuclear One Unit 2, & FitzPatrick |
| NRC Generic Letter 1998-02 | 28 May 1998 | NRC Generic Letter 1998-002: Loss of Reactor Coolant Inventory and Associated Potential for Loss of Emergency Mitigation Functions While in a Shutdown Condition |
| Information Notice 1997-83, Recent Events Involving Reactor Coolant System Inventory Control During Shutdown | 5 December 1997 | Recent Events Involving Reactor Coolant System Inventory Control During Shutdown |
| ML20212B760 | 21 October 1997 | Requests for Technical Review of Encl Draft in 97-076 Re Inadvertent Draindown at Plant,Unit 1 |
| ML20141H701 | 19 May 1997 | Provides ERDS Data Point Library Update for Unit 1.Encl Contains Revised Listing |
| Information Notice 1996-65, Undetected Accumulation of Gas in Reactor Coolant System and Inaccurate Reactor Water Level Indication During Shutdown | 11 December 1996 | Undetected Accumulation of Gas in Reactor Coolant System and Inaccurate Reactor Water Level Indication During Shutdown |
| Information Notice 1996-56, Problems Associated with Testing, Tuning, or Resetting of Digital Control Systems While at Power | 22 October 1996 | Problems Associated with Testing, Tuning, or Resetting of Digital Control Systems While at Power |
| Information Notice 1996-42, Unexpected Opening of Multiple Safety Relief Valves | 5 August 1996 | Unexpected Opening of Multiple Safety Relief Valves |
| Information Notice 1996-37, Inaccurate Reactor Water Level Indication and Inadvertent Draindown During Shutdown | 18 June 1996 | Inaccurate Reactor Water Level Indication and Inadvertent Draindown During Shutdown |
| Information Notice 1996-05, Partial Bypass of Shutdown Cooling Flow from Reactor Vessel | 18 January 1996 | Partial Bypass of Shutdown Cooling Flow from Reactor Vessel |
| ML20084R130 | 2 June 1995 | Forwards Response to NRC 950315 RAI Re Emergency Action Plan Conversion to NUMARC Eals.Revised EALs Which Occurred as Result of 950322 Meeting Between NRC & TVA & Rev 16 to EPIP-1, Emergency Plan Classification Matrix Also Encl |
| ML20082E466 | 6 April 1995 | Proposed Tech Specs,Deleting License Condition 2.c |
| Information Notice 1994-52, Inadvertent Containment Spray and Reactor Vessel Draindown at Millstone Unit 1 | 15 July 1994 | Inadvertent Containment Spray and Reactor Vessel Draindown at Millstone Unit 1 |
| Information Notice 1994-36, Undetected Accumulation of Gas in Reactor Coolant System | 24 May 1994 | Undetected Accumulation of Gas in Reactor Coolant System |
| ML20069B539 | 20 May 1994 | Responds to NRC Re Violations Noted in Insp Repts 50-327/94-04 & 50-328/94-04.Corrective Actions:Vct Temp Raised,Reactor Head Vented & Appropriated Plant Procedure Revised to Address Operation RCS at Atmospheric Pressure |
| ML071040017 | 28 April 1994 | 59 FRN 12990, Biweekly Notice; Applications and Amendments to Facility Operating Licenses Involving No Significant Hazards Considerations |