Semantic search

Jump to navigation Jump to search
 Issue dateTitle
CNL-14-154, Status of Regulatory Framework for the Completion of Construction and Licensing for Unit 2 - Revision 12 (TAC No. MD6311), and Status of Generic Communications for Unit 2 - Revision 122 September 2014Status of Regulatory Framework for the Completion of Construction and Licensing for Unit 2 - Revision 12 (TAC No. MD6311), and Status of Generic Communications for Unit 2 - Revision 12
CNL-15-104, Submittal of Revision 106, Appendix C to Central Emergency Control Center, Radiological Emergency Plan15 June 2015Submittal of Revision 106, Appendix C to Central Emergency Control Center, Radiological Emergency Plan
CNL-15-137, Status of Regulatory Framework for the Completion of Construction and Licensing for Unit 2 - Revision 13 (TAC No. MD6311) and Status of Generic Communications for Unit 2 - Revision 1327 July 2015Status of Regulatory Framework for the Completion of Construction and Licensing for Unit 2 - Revision 13 (TAC No. MD6311) and Status of Generic Communications for Unit 2 - Revision 13
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 Syste17 November 2017Application 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 Levels7 July 2017Response 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 Levels27 July 2017Revised 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-18-067, Application for Technical Specifications Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (WBN-TS-18-14)12 October 2018Application for Technical Specifications Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (WBN-TS-18-14)
CNL-19-051, Application to Implement the Full Spectrum LOCA (Fsloca) Methodology for Loss-of-Coolant Accident (LOCA) Analysis and New LOCA-specific Tritium Producing Burnable Absorber Rod Stress Analysis Methodology17 January 2020Application to Implement the Full Spectrum LOCA (Fsloca) Methodology for Loss-of-Coolant Accident (LOCA) Analysis and New LOCA-specific Tritium Producing Burnable Absorber Rod Stress Analysis Methodology
CNL-20-016, Application to Modify Watts Bar Nuclear Plant Unit 1 Technical Specifications 3.3.3, Post Accident Monitoring Instrumentation, (WBN-TS-19-23)22 June 2020Application to Modify Watts Bar Nuclear Plant Unit 1 Technical Specifications 3.3.3, Post Accident Monitoring Instrumentation, (WBN-TS-19-23)
CNL-21-010, Correction of Application to Implement the Full Spectrum LOCA (Fsloca) Methodology for Loss-of-Coolant Accident (LOCA) Analysis and New LOCA-specific Tritium Producing Burnable Absorber Rod Stress Analysis Methodology (WBN-TS-19-04) (EPID26 January 2021Correction of Application to Implement the Full Spectrum LOCA (Fsloca) Methodology for Loss-of-Coolant Accident (LOCA) Analysis and New LOCA-specific Tritium Producing Burnable Absorber Rod Stress Analysis Methodology (WBN-TS-19-04) (EPID L
Information Notice 1990-22, Unanticipated Equipment Actuations Following Restoration of Power to Rosemount Transmitter Trip Units23 March 1990Unanticipated 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 Draindown25 February 1992Loss of Flow from the Residual Heat Removal Pump During Refueling Cavity Draindown
Information Notice 1993-27, Level Instrumentation Inaccuracies Observed During Normal Plant Depressurization8 April 1993Level Instrumentation Inaccuracies Observed During Normal Plant Depressurization
Information Notice 1993-62, Thermal Stratification of Water in BWR Reactor Vessels10 August 1993Thermal Stratification of Water in BWR Reactor Vessels
Information Notice 1993-89, Potential Problems with BWR Level Instrumentation Backfill Modifications26 November 1993Potential Problems with BWR Level Instrumentation Backfill Modifications
Information Notice 1994-36, Undetected Accumulation of Gas in Reactor Coolant System24 May 1994Undetected Accumulation of Gas in Reactor Coolant System
Information Notice 1994-52, Inadvertent Containment Spray and Reactor Vessel Draindown at Millstone Unit 115 July 1994Inadvertent Containment Spray and Reactor Vessel Draindown at Millstone Unit 1
Information Notice 1996-05, Partial Bypass of Shutdown Cooling Flow from Reactor Vessel18 January 1996Partial Bypass of Shutdown Cooling Flow from Reactor Vessel
Information Notice 1996-37, Inaccurate Reactor Water Level Indication and Inadvertent Draindown During Shutdown18 June 1996Inaccurate Reactor Water Level Indication and Inadvertent Draindown During Shutdown
Information Notice 1996-42, Unexpected Opening of Multiple Safety Relief Valves5 August 1996Unexpected Opening of Multiple Safety Relief Valves
Information Notice 1996-56, Problems Associated with Testing, Tuning, or Resetting of Digital Control Systems While at Power22 October 1996Problems 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 Shutdown11 December 1996Undetected 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 Shutdown5 December 1997Recent 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, & FitzPatrick5 May 1999Unanticipated Reactor Water Draindown at Quad Cities Unit 2, Arkansas Nuclear One Unit 2, & FitzPatrick
ML02081042912 March 2002Emergency Plan Implementing Procedure EPIP-1, Revision 18
ML0222004912 August 2002Plan (WBN) - Revisions to Emergency Plan Implementing Procedures, Including Revision 20 to EPIP-1, Revision 19 to EPIP-2, Revision 22 to EPIP-3 & Revision 23 to EPIP-4
ML03086035524 March 2003Emergency Plan Implementing Procedure Revision
ML03115058529 January 1985Withdrawn NRC Generic Letter 1985-004: Operator Licensing Examinations
ML03156070815 May 2003May 2003 Exam 50-390/03-301 Final SRO Written Exam References
ML03156076415 May 2003May 2003 Exam 50-390/03-301 Draft Written Exam with References
ML04113029219 April 2004EPIP-1, Emergency Plan Classification Flowchart, Revision 22
ML0721900473 August 2007Unit 2 - Reactivation of Construction Activities
ML0725706787 September 2007Generic Communications Issued Prior to 1995
ML08039041515 October 1979Proposed Revision 2 to Regulatory Guide 1.97, Instrumentation for Light-Water-Cooled Nuclear Power Plants to Assess Plant and Environs Conditions During and Following an Accident, Draft 1
ML0806704197 March 2008CDBI Findings
ML08085025320 March 2008Unit 2 - Generic Communications Status for Unit 2 - Restructured Tables
ML08149011828 May 2008NRC Review: Generic Communications Status for TVA Watts Bar Unit 2
ML08266014717 September 2008Transmittal of Emergency Response Data System (ERDS) Data Point Library (Dpl), Revision 2
ML0826801844 September 2008Unit 1 - Technical Specifications (TS) Change 08-03, Request for Technical Specification Improvement to Eliminate Requirements for Hydrogen Recombiners and Hydrogen Monitors Using the Consolidated Line Item Improvement Process.
ML0834601779 December 2008Unit 2 - Licensing Basis Preservation and Construction Refurbishment Program for Structures, Systems and Components (Sscs)
ML09034072618 December 2008Final Safety Analysis Report, Amendment 92, Section 5.0 Reactor Coolant System - 5.6 Instrumentation Application
ML09140065230 April 2009Final Safety Analysis Report (Fsar), Amendment 93, Section 5, Reactor Coolant System Through Page 5.6-7
ML09247030627 August 2009Final Safety Analysis Report, Amendment 94, Section 5, Reactor Coolant System
ML09337034624 November 2009Final Safety Analysis Report, Amendment 95, Chapter 5, Sections 5.0 Through 5.6-7
ML09357049614 December 2009Final Safety Analysis Report, Amendment 96, Table of Contents - Section 5 - Table of Contents, Reactor Coolant System Page 5-i Through 5.6-7
ML10019167511 January 2010Final Safety Analysis Report, Amendment 97, Section 5 - Reactor Coolant Systems Through Page 5.6-7
ML1005504512 February 2010Developmental Revision B - Technical Specifications 3.3 - Instrumentation
ML1005505012 February 2010Developmental Revision B - Technical Specifications Bases B 3.3 - Instrumentation
ML10083009511 February 2010Initial Exam 2009-302 Draft Administrative JPMs
ML10117014820 April 2010Changes Made to the Technical Specification Bases
Retrieved from "https://kanterella.com/Special:Ask"