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 Issue dateTitle
IR 05000259/202300313 November 2023Integrated Inspection Report 05000259/2023003, 05000260/2023003 and 05000296/2023003
ML23159A25520 July 2023Proposed Alternative to the Requirements of the ASME Code Regarding Volumetric Inspection of Standby Liquid Control Nozzles
IR 05000259/20230013 May 2023Integrated Inspection Report 05000259/2023001, 05000260/2023001 and 05000296/2023001
ML23054A29013 March 2023Request for Relief from the Requirements of the ASME Boiler and Pressure Vessel Code Regarding Weld Examination Coverage
CNL-23-019, Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3, American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI, Request for Alternative BFN-0-ISI-3211 March 2023Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3, American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI, Request for Alternative BFN-0-ISI-32
ML23048A3048 March 2023Tennessee Valley Authority - Request for Relief from Requirements of ASME Boiler and Pressure Vessel Code Regarding Weld Examination Coverage (EPID L-2022-LLR-0045,-0046,-0047)
ML22348A00525 January 2023Issuance of Amendment Nos. 326, 349, and 309; 363 and 35; 159 and 67 Regarding Adoption of TSTF-554, Revise Reactor Coolant Leakage Requirements
ML23013A03612 January 2023NRR E-mail Capture - (External_Sender) State Consultation for Alabama - Browns Ferry, Units 1, 2 and 3; Sequoyah, Units 1 and 2; and Watts Bar, Units 1 and 2, License Amendment Request to Adopt TSTF-554-A, Revision 1 (L-2022-LLA-0100)
ML22348A04413 December 2022NRR E-mail Capture - State Consultation - Browns Ferry, Units 1, 2 and 3; Sequoyah, Units 1 and 2; and Watts Bar, Units 1 and 2, License Amendment Request to Adopt TSTF-554-A, Revision 1 (L-2022-LLA-0100)
IR 05000259/202201220 September 2022Biennial Problem Identification and Resolution Inspection Report 05000259 2022012, 05000260 2022012 and 05000296 2022012
ML22215A2753 August 2022NRR E-mail Capture - Acceptance Review Results for TVA Fleet License Amendment Request to Adopt TSTF-554
CNL-22-039, Application to Revise Technical Specifications to Adopt TSTF-554-A, Revision 1, Revise Reactor Coolant Leakage Requirements (BFN TS-537) (SQN-21-05) (WBN-TS-21-04)13 July 2022Application to Revise Technical Specifications to Adopt TSTF-554-A, Revision 1, Revise Reactor Coolant Leakage Requirements (BFN TS-537) (SQN-21-05) (WBN-TS-21-04)
CNL-22-002, Request for Relief from American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI, in Accordance with 10 CFR 50.55a(g)(5)(iii) and 50.55a(g)(6) (BFN-2-ISI-003)24 May 2022Request for Relief from American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI, in Accordance with 10 CFR 50.55a(g)(5)(iii) and 50.55a(g)(6) (BFN-2-ISI-003)
CNL-22-009, Request for Relief from American Society of Mechanical Engineers Boiler & Pressure Vessel Code, Section XI, In.25 April 2022Request for Relief from American Society of Mechanical Engineers Boiler & Pressure Vessel Code, Section XI, In.
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-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
ML14154A3732 June 2014Initial Exam 2014-301 Draft SRO Written Exam
ML14142A16121 May 201405202014 Final Browns Ferry 2014-301 SRO Written Exam
ML1127900894 October 2011Initial Exam 2011-302 Draft SRO Written Exam
ML11237011124 August 2011Initial Exam 2011-302 Final SRO Written Exam
ML10062140422 March 2010Issuance of Amendments Regarding Deletion of Containment Isolation Valve Local Leak Rate Testing
ML0813702308 April 2008Feb-Mar 05000259/2008301 Exam Draft RO Written Exam (Part 3 of 4)
IR 05000259/200700430 October 2007IR 05000259-07-004, 05000260-07-004 & 05000296-07-004; on 07/01/2007 - 09/30/2007; Browns Ferry Nuclear Plants, Units 1, 2, & 3; Event Followup Integrated Inspection Report
PNO-II-07-011, A - Update, Browns Ferry, Unit 3, Pressure Boundary Leakage Discovered During Drywell Inspection1 October 2007PNO-II-07-011A - Update, Browns Ferry, Unit 3, Pressure Boundary Leakage Discovered During Drywell Inspection
ML07267051124 September 2007PNO-II-07-011: Browns Ferry Unit 3, Pressure Boundary Leakage Discovered During Drywell Inspection
ML0611402094 May 2006Improved Technical Specifications for Browns Ferry Nuclear Plant, Unit 2
ML0611401824 May 2006Improved Technical Specifications for Browns Ferry Nuclear Plant, Unit 3
ML0611403524 May 2006Improved Technical Specifications for Browns Ferry Nuclear Plant, Unit 1
ML14357A31926 April 2004TVA Nuclear Radiological Emergency Plan (Rep), Revision 73
ML0406200481 March 2004Brown Ferry, Unit 1, Ltr, Relief, Containment Inservice Inspection
ML03247134029 August 2003American Society of Mechanical Engineers (ASME) Section XI, Subsection IWE, Requirements for Class Mc and Metallic Liners of Class CC Components of Light-Water Cooled Plants, Requests for Relief
ML03111027725 July 2002E-mail from J. Starefos to A. Howell, Regarding DB LLRT List
ML03111026925 July 2002E-mail from J. Starefos to H. Hackett, Regarding DB LLRT List
ML02102047326 April 2002Uit 1 - Reuests for Code Relief GISI-1, GISI-2, and GISPT-1
ML18039A5048 September 1998Proposed Tech Specs Providing TS for Operation of Oscillation Power Range Monitor Upscale Trip Function in Aprm,Which Is Part of Power Range Neutron Monitoring Sys
ML18039A40219 June 1998Proposed Tech Specs (TS) Converting from Existing Custom TS to Improved TS
Information Notice 1998-13, Post-Refueling Outage Reactor Pressure Vessel Leak Testing Before Core Criticality20 April 1998Post-Refueling Outage Reactor Pressure Vessel Leak Testing Before Core Criticality
ML20199E13614 November 1997Proposed Tech Specs Section 3.4 Re Reactor Coolant Sys
ML18038B7546 September 1996Proposed Conversion from Current TSs to Improved STS Consistent w/NUREG-1433,rev 1
NRC Generic Letter 1995-1015 December 1995NRC Generic Letter 1995-010: Relocation of Selected Technical Specifications Requirements Related to Instrumentation
ML18038B30220 June 1995Forwards Response to NRC 950301 RAI Re TVA 941019 Submittal of Rev to App a of Radiological Emergency Plan,Replacing Current EALs W/Eals Developed from NUMARC Methodology. Revised App a of Radiological Emergency Plan Encl
ML0311405497 November 1991Withdrawn NRC Generic Letter 1991-018: Information to Licensees Regarding Two NRC Inspection Manual Sections on Resolution of Degraded and Nonconforming Conditions and on Operability
NRC Generic Letter 1990-0625 June 1990NRC Generic Letter 1990-006: Resolution of Generic Issue, Power-Operated Relief Valve and Block Valve Reliability, and Generic Issue 94, Additional Low-Temp. Overpressure Protection for Light-Water Reactors, Pursuant to 10 CFR 50354 (F)
ML18094A07830 August 1983Rev 1 to Technical Evaluation of Integrity of Browns Ferry 1,2 & 3 Reactor Coolant Boundary Piping Sys.