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{
    "query_string": "[[Topic::Reactor Vessel Water Level]] [[Site::Sequoyah]]",
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	Issue date	Title
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.

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