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Issue date | Title | |
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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-17-085, 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 |
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-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) |
IR 05000327/1989005 | 13 March 1989 | Special Team Insp Repts 50-327/89-05 & 50-328/89-05 on 890131-0209.Violations Noted.Major Areas Inspected:Radwaste, Radiological Controls,Corporate QA Audits & Site Chemistry |
IR 05000327/2023002 | 31 July 2023 | Integrated Inspection Report 05000327/2023002 and 05000328/2023002 |
Information Notice 1990-22, Unanticipated Equipment Actuations Following Restoration of Power to Rosemount Transmitter Trip Units | 23 March 1990 | Unanticipated Equipment Actuations Following Restoration of Power to Rosemount Transmitter Trip Units |
Information Notice 1992-16, Loss of Flow from the Residual Heat Removal Pump During Refueling Cavity Draindown | 25 February 1992 | Loss of Flow from the Residual Heat Removal Pump During Refueling Cavity Draindown |
Information Notice 1993-27, Level Instrumentation Inaccuracies Observed During Normal Plant Depressurization | 8 April 1993 | Level Instrumentation Inaccuracies Observed During Normal Plant Depressurization |
Information Notice 1993-62, Thermal Stratification of Water in BWR Reactor Vessels | 10 August 1993 | Thermal Stratification of Water in BWR Reactor Vessels |
Information Notice 1993-89, Potential Problems with BWR Level Instrumentation Backfill Modifications | 26 November 1993 | Potential Problems with BWR Level Instrumentation Backfill Modifications |
Information Notice 1994-36, Undetected Accumulation of Gas in Reactor Coolant System | 24 May 1994 | Undetected Accumulation of Gas in Reactor Coolant System |
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 1996-05, Partial Bypass of Shutdown Cooling Flow from Reactor Vessel | 18 January 1996 | Partial Bypass of Shutdown Cooling Flow from Reactor Vessel |
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 1996-42, Unexpected Opening of Multiple Safety Relief Valves | 5 August 1996 | Unexpected Opening of Multiple Safety Relief Valves |
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 1996-65, 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 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 |
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 |
ML011790073 | 22 June 2001 | Emergency Plan Implementing Procedure (EPIP) Revisions |
ML023250196 | 8 November 2002 | Emergency Plan Implementing Procedure (EPIP) Revision 34 |
ML030430608 | 5 August 2002 | December 2002-301 Exam Draft Ro/Sro Written Exam |
ML031150585 | 29 January 1985 | Withdrawn NRC Generic Letter 1985-004: Operator Licensing Examinations |
ML031990400 | 10 July 2003 | Emergency Response Data System Data Point Library Update |
ML040420372 | 27 January 2004 | Emergency Plan Implementing Procedure (EPIP) Revision 35 for EPIP-1 and Revision 4 for EPIP-12 |
ML071040017 | 28 April 1994 | 59 FRN 12990, Biweekly Notice; Applications and Amendments to Facility Operating Licenses Involving No Significant Hazards Considerations |
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) |
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 |
ML080720525 | 29 February 2008 | Feb Exam 05000327-08-301, 05000328-08-301 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 |
ML120720077 | 21 February 2012 | Initial Exam 2012-301 Draft Administrative Job Performance Measure |
ML120720356 | 21 February 2012 | Initial Exam 2012-301 Final Administrative JPMs |
ML13275A059 | 27 September 2013 | Initial Exam 2012-302 Final Administrative JPMs |
ML14071A152 | 13 March 2014 | Slide, ITS Project Electrical Systems Presentation March 13, 2014 |
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 |
ML14357A319 | 26 April 2004 | TVA Nuclear Radiological Emergency Plan (Rep), Revision 73 |
ML15092A854 | 2 April 2015 | Initial Exam 2015-301 Final SRO Written Exam |
ML15100A046 | 28 September 2015 | SQN U1 Renewed License v2 |
ML15100A049 | 28 September 2015 | SQN U2 Renewed License v2 |
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 |
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 |
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 |
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 |
ML19197A021 | 16 July 2019 | NRR E-mail Capture - Accepted for Review - Exigent License Amendment Request for Reactor Vessel Level Instrument |
ML19211D138 | 11 January 1980 | Forwards Revisions Re Relief & Safety Valve Testing Program, to Revised Response to NUREG-0578.Info Includes Core Cooling Detection Instrumentation & Containment Isolation |
ML19257C211 | 30 November 1979 | TVA Nuclear Program Review:Rept of President'S Commission on Accident at Tmi. |
ML19260A244 | 31 October 1979 | Forwards Revised Responses to NUREG-0578, Lessons Learned Requirements. |