Letter Sequence Other |
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MONTHYEARML0631800372006-11-14014 November 2006 Individual Notice, Low Pressure Coolant Injection Loop Crosstie Valve Position Verification Project stage: Other ML0703004272007-02-0606 February 2007 Amendment, Low Pressure Coolant Injection Crosstie Valve Surveillance Requirement (TAC No. MD3544) (TS-458) Project stage: Other 2006-11-14
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Category:Code Relief or Alternative
MONTHYEARML23159A2552023-07-20020 July 2023 Proposed Alternative to the Requirements of the ASME Code Regarding Volumetric Inspection of Standby Liquid Control Nozzles ML23054A2902023-03-13013 March 2023 Request for Relief from the Requirements of the ASME Boiler and Pressure Vessel Code Regarding Weld Examination Coverage ML23048A3042023-03-0808 March 2023 Tennessee 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) ML22329A0762022-12-0101 December 2022 Correction of Error in Authorization of Alternative Request BFN-21-ISI-02 ML22298A2852022-11-14014 November 2022 Request for Alternative to American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI, Paragraph IWB-2420(B) and Use of Code Case N-526 ML22010A1952022-01-12012 January 2022 Request to Use Later Edition of the American Society of Mechanical Engineers Code for Operation and Maintenance of Nuclear Power Plants ML18323A1722018-12-31031 December 2018 Relief Request No. 1 ISI 29 Regarding Second 10-Year Inservice Inspection Interval Regarding Examination Coverage for Certain Pressure Retaining Welds ML18323A0262018-12-0404 December 2018 Relief Request No. 1-ISI-28 Regarding Third 10-Year Inservice Inspection Interval Regarding Examination Coverage for Certain Pressure Retaining Reactor Vessel Welds ML17261A0362017-10-0606 October 2017 Request for Request 3-ISI-28 Regarding Third 10-Year Inservice Inspection Interval Examination Coverage of Inside Radius and Nozzle-to-Vessel Welds ML17135A1462017-08-18018 August 2017 Browns Ferry Nuclear Plant, Unit 3 - Relief Request No. 3 ISI 29 Regarding Third 10-Year Inservice Inspection Interval Regarding Examination Coverage for Certain Pressure Retaining Piping Welds (CAC No. MF9258) ML17145A5522017-08-11011 August 2017 Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Alternative Request IST-RR-1 for the Fourth 10-Year Inservice Testing Interval (CAC Nos. MF9087, MF9088, and MF9089) ML17045A7722017-03-14014 March 2017 Browns Ferry Nuclear Plant, Units 2 and 3 - Relief Request 2-ISI-30 and 3-ISI-27 - Relief from ASME Code, Section XI Requirements for Periods of Extended Operation for RPV Circumferential Shell Weld Examinations (CAC Nos. MF7795 and MF7796) ML16225A6332016-09-0202 September 2016 Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Sequoyah Nuclear Plant, Units 1 and 2; Watts Bar Nuclear Plant, Unit 1 and 2 - Relief Request for Use of Alternate Calibration Block Reflector Requirements 16-PDI-5 (TAC Nos. MF7754-MF7760) ML16020A1152016-02-17017 February 2016 Alternative Relief Request 1-ISI-27 for Relief from the Reactor Vessel Circumferential Weld Examination Requirements of the ASME Code ML12003A0812012-01-20020 January 2012 Safety Evaluation for Relief Request 3-ISI-25, for the Third 10-Year Inservice Inspection Interval ML0921809542009-08-24024 August 2009 Relief, the Second Ten-Year Interval Inservice Inspection Program Relate to ASME Code Case N-504-3, Alternative Rules for Repair of Classes 1, 2, and 3 Austenitic Stainless Steel Piping ME0155 ML0916703582009-07-0101 July 2009 Withdrawal of Relief Request (2-ISI-22) for Repair of Classes 1, 2, and 3 Austenitic Stainless Steel Piping ML0912000402009-06-16016 June 2009 Safety Evaluation for Relief Request 2-ISI-18R1 Associated with Inservice Inspection Examination Coverage ML0916104992009-06-12012 June 2009 Verbal Relief Related to Instrument Line Weld Overlay (TAC No. ME1319) (2-ISI-21) ML0913906422009-05-18018 May 2009 American Society of Mechanical Engineers Section XI, Inservice Inspection Program - Request for Relief 2-ISI-21, Revision 1 - Examination of Piping Weld Overlays ML0907110772009-04-0202 April 2009 Safety Evaluation for Relief Request 1-ISI-18 Associated with Inspection and Testing of Snubbers ML0833802012008-11-25025 November 2008 American Society of Mechanical Engineers (ASME) Section XI, Inservice Inspection Program for the Second Ten-year Inspection Interval - Relief Request for 1-ISI-22 ML0821704212008-07-29029 July 2008 American Society of Mechanical Engineers (ASME) Section XI, Inservice Inspection (ISI) Program, Third Ten-Year Inspection Interval- Request for Relief 2-ISI-18, Revision 1 ML0800805242008-05-20020 May 2008 Safety Evaluation for Relief Request 3-ISI-22 Limited Examination Coverage for Valve to Pipe Weld GR-3-63 Tac No. MD6748) ML0725600472007-08-24024 August 2007 American Society of Mechanical Engineers (ASME) Section XI, Inservice Inspection (ISI) Program, Third Ten-Year Inspection Interval Requests for Relief 3-ISI-22 & 3-ISI-23 ML0706504752007-02-21021 February 2007 American Society of Mechanical Engineers (ASME) Section XI, Inservice Inspection (ISI) Program, Second Ten-Year Inspection Interval - Request for Relief 3-ISI-7, Revision 2 ML0700903492007-02-12012 February 2007 Relief Request, Risk-Informed Inservice Inspection of Piping ML0633306482006-12-22022 December 2006 Relief Request, Request for Relief from American Society of Mechanical Engineers, Section XI Requirements for the Third Inservice Inspection Interval - Snubbers ML0631800372006-11-14014 November 2006 Individual Notice, Low Pressure Coolant Injection Loop Crosstie Valve Position Verification ML0615600902006-08-0303 August 2006 Relief Requests, Revision 3-ISI-12 and 3-ISI-19, Associated with Weld Examination Coverage ML0615902822006-07-0303 July 2006 Letter Withdrawal of Relief Requests Regarding Third Interval Inservice Inspection Requirements of the ASME Code ML0613903032006-06-30030 June 2006 Relief, Relief Request 3-ISI-20 Associated with the Use of ASME Code Case- 700 for the Third Inservice Inspection Interval ML0535403782005-12-20020 December 2005 American Society of Mechanical Engineers (ASME) Section XI, Inservice Inspection (ISI) Program - Request to Use Subsequent Edition and Addenda of ASME Section XI Code for Repair and Replacement Activities ML0523101262005-08-18018 August 2005 American Society of Mechanical Engineers RPV Welds Withdrawal of Requests ML0517304872005-08-0202 August 2005 Relief, Inservice Inspection Program Relief Request PDI-4 ML0518106792005-07-18018 July 2005 Safety Evaluation for Request for Relief Regarding the Use of ASME Code Case 700 (TACs MC6437, MC6438) ML0506305582005-03-0404 March 2005 American Society of Mechanical Engineers Section XI, Inservice Inspection Program, Second Ten-Year Inspection Interval - Requests for Relief 3-ISI-7, Revision 1, 3-ISI-12, and 3-ISI-19 ML0502504152005-02-15015 February 2005 Relief, Use of ASME and Pressure Vessel (PV) Code for VT-2 ML0433803212004-11-15015 November 2004 American Society of Mechanical Engineers Section XI, in Service Inspection Program ML0432206272004-11-15015 November 2004 American Society of Mechanical Engineers Section XI, Inservice Inspection Program - Requests for Relief 2-ISI-22, and 3-ISI-18 for Examination of Reactor Pressure Vessel Nozzle-To-Vessel Shell Welds and Nozze Blend. ML0421504382004-10-0606 October 2004 Relief, Relief Request Re. Maximum Allowable Flaw Width When Planar Flaw Evaluation Rules May Be Applied ML0410403752004-04-12012 April 2004 Requests for Relief Nos. 2-ISI-18 and 2-ISI-19 for Third 10-Year Interval Inservice Inspection ML0406200482004-03-0101 March 2004 Brown Ferry, Unit 1, Ltr, Relief, Containment Inservice Inspection ML0404203552004-02-11011 February 2004 Relief, Second 10-Year Interval Inservice Inspection Programs ML0335303822003-12-19019 December 2003 Brown Ferry Nuclear Plant, Units 2 and 3, Relief Request, 2-ISI-21 and 3-ISI-17 to Inservice Inspection Program ML0325909292003-09-12012 September 2003 (BFN) - Unit 1 - American Society of Mechanical Engineers (ASME) Section XI, Inservice Inspection (ISI) Program - Request for Relief PDI-2 - Clarification and Additional Information ML0316714662003-06-0202 June 2003 Relief, American Society of Mechanical Engineers (ASME) Section XI, Inservice Inspection (ISI) Program, Third Ten-Year Inspection Interval - Requests for Relief 2-ISI-18, and 2-ISI-19 ML0314107352003-05-0909 May 2003 American Society of Mechanical Engineers (ASME) Section XI, Inservice Inspection (ISI) Program - Requests for Relief 3-ISI-13, 3 -ISI-14, & 3-ISI-15 ML0313500882003-05-0909 May 2003 (Bfn), Unit 3, American Society of Mechanical Engineers (ASME) Section XI, Inservice Inspection (ISI) Program - Requests for Relief 3-ISI-13, 3-ISI-14 & 3-ISI-15 ML0230202092002-10-25025 October 2002 (Bfn), Unit 2, American Society of Mechanical Engineers (ASME) Section XI, Inservice Inspection (ISI) Program, Request for Relief 2-ISI-13, Examination & Testing of Snubbers 2023-07-20
[Table view] Category:Federal Register Notice
MONTHYEARML24022A1742024-02-0505 February 2024 Subsequent License Renewal Application - Receipt and Availability - FRN ML19238A3692019-09-0303 September 2019 Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: 09/10/2019 ML19186A0012019-07-0808 July 2019 Letter, Individual Notice of Consideration of Issuance of Amendment, Extend Implementation Dates for Modifications 102 and 106 Listed in Transition License Condition 2 ML19186A0022019-07-0808 July 2019 FRN, Individual Notice of Consideration of Issuance of Amendment, Extend Implementation Dates for Modifications 102 and 106 Listed in Transition License Condition 2 ML18295A7442018-10-25025 October 2018 Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: 11/06/18 ML18278A2802018-10-10010 October 2018 Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: 10/23/2018 ML18200A1922018-08-21021 August 2018 Withdrawal of Amd Request to Change Implementation Date for Emergency Action Level Scheme ML18200A2142018-08-21021 August 2018 FRN; Tennessee Valley Authority, Browns Ferry Nuclear Plant Units 1, 2 and 3, Sequoyah Nuclear Plant, Units 1 and 2, Watts Bar Nuclear Plant, Units 1 and 2 NRC-2014-0045, FRN; Tennessee Valley Authority, Browns Ferry Nuclear Plant Units 1, 2 and 3, Sequoyah Nuclear Plant, Units 1 and 2, Watts Bar Nuclear Plant, Units 1 and 22018-08-21021 August 2018 FRN; Tennessee Valley Authority, Browns Ferry Nuclear Plant Units 1, 2 and 3, Sequoyah Nuclear Plant, Units 1 and 2, Watts Bar Nuclear Plant, Units 1 and 2 ML18180A2182018-07-0505 July 2018 Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: 7/17/2018 NRC-2018-0140, Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: 7/17/20182018-07-0505 July 2018 Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: 7/17/2018 ML18172A3042018-06-22022 June 2018 Tennessee Valley Authority - License Amendment Application; Opportunity to Comment, Request a Hearing, and Petition for Leave to Intervene ML18173A0532018-06-22022 June 2018 Ind. Notice of Consideration of Issuance of Amendments to Facility Operating Licenses, Proposed No Sig. Hazards ... ML18124A0632018-05-17017 May 2018 Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving Proposed No Significant Hazards Considerations and Containing Sensitive Unclassified Non-Safeguards Information and Order for 6/5/18 Publication NRC-2018-0102, Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving Proposed No Significant Hazards Considerations and Containing Sensitive Unclassified Non-Safeguards Information and Order for 6/5/18 Publication2018-05-17017 May 2018 Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving Proposed No Significant Hazards Considerations and Containing Sensitive Unclassified Non-Safeguards Information and Order for 6/5/18 Publication ML17139D3982017-06-0707 June 2017 Browns Ferry Nuclear Plant, Units 1, 2, and 3 - FR Notice of Withdrawal of an Amendment Request (CAC Nos. MF6738, MF3739, and MF3740) ML17062A3902017-05-22022 May 2017 Cover Letter; Final Environmental Assessment and Finding of No Significant Impact Related to the Proposed Extended Power Uprate ML17062A4032017-05-22022 May 2017 Final Environmental Assessment and Finding of No Significant Impact Related to the Proposed Extended Power Uprate NRC-2016-0244, Final Environmental Assessment and Finding of No Significant Impact Related to the Proposed Extended Power Uprate (CAC Nos. MF6741, MF6742, and MF6743)2017-05-22022 May 2017 Final Environmental Assessment and Finding of No Significant Impact Related to the Proposed Extended Power Uprate (CAC Nos. MF6741, MF6742, and MF6743) ML16287A5702016-11-21021 November 2016 EPU Draft Environmental Assessment ML16271A0922016-09-28028 September 2016 Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: October 11, 2016 NRC-2016-0100, Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: May 24, 20162016-05-13013 May 2016 Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: May 24, 2016 ML16131A7952016-05-13013 May 2016 Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: May 24, 2016 ML15356A5992015-12-29029 December 2015 Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: January 5, 2016 ML15148A3762015-06-0101 June 2015 Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Published June 9, 2015 ML13018A2392015-04-0808 April 2015 G20110171 - Letter to Petitioner Saporito on Proposed Director'S Decision Regarding 2.206 Petition Dated: March 12, 2011 ML15007A2932015-01-21021 January 2015 Federal Register Notice on Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving Proposed No Significant Hazards Considerations and Containing SUNSI and Order Imposing Procedures for Access to SUNSI - Fe NRC-2015-0009, G20110262 - FRN - Paul Gunter and Kevin Kamps Letter 2.206 - Immediately Suspend the Operating License of General Electric Boiling Water Reactors Mark I Units2015-01-15015 January 2015 G20110262 - FRN - Paul Gunter and Kevin Kamps Letter 2.206 - Immediately Suspend the Operating License of General Electric Boiling Water Reactors Mark I Units ML14335A6302015-01-15015 January 2015 G20110262 - Final Response to Paul Gunter and Kevin Kamps Letter 2.206 - Immediately Suspend the Operating License of General Electric Boiling Water Reactors Mark I Units ML14335A6482015-01-15015 January 2015 G20110262 - FRN - Paul Gunter and Kevin Kamps Letter 2.206 - Immediately Suspend the Operating License of General Electric Boiling Water Reactors Mark I Units ML14121A5912014-05-0101 May 2014 FRN - Browns Ferry, Units 1, 2, and 3, Confirmatory Order NRC-2014-0107, FRN - Browns Ferry, Units 1, 2, and 3, Confirmatory Order2014-05-0101 May 2014 FRN - Browns Ferry, Units 1, 2, and 3, Confirmatory Order ML14099A2172014-04-28028 April 2014 FRN on Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving Proposed No Significant Hazards Considerations and Containing SUNSI and Order Imposing Procedures for Access to SUNSI NRC-2013-0198, Individual Fr Notice of Appliaction and Amendment to Facility Operating License2013-08-16016 August 2013 Individual Fr Notice of Appliaction and Amendment to Facility Operating License ML13227A2552013-08-16016 August 2013 Individual Fr Notice of Appliaction and Amendment to Facility Operating License ML13227A2532013-08-16016 August 2013 Individual Notice of Consideration of Issuance of Amendment to Facility Operating License and Opportunity of a Hearing ML13228A3992013-08-12012 August 2013 Letter to Holders of Independent Spent Fuel Storage Installation (ISFSI) Licenses Re Rescission of Certain Security Orders Concerning Spent Nuclear Fuel in Transit - Rin 3150-AI64 (NRC-2009-0163) EA-02-109 ML13225A5572013-08-12012 August 2013 Rescission of Certain Security Orders Concerning Spent Nuclear Fuel in Transit ML12053A1902012-05-18018 May 2012 Federal Register Notice - Confirmatory Order Modifying License (Effective Immediately) NRC-2012-0069, Order Modifying Licenses with Regard to Reliable Hardened Containment Vents - to All Operating Boiling Water Reactor Licensees with Mark I and Mark Ii Containments2012-03-12012 March 2012 Order Modifying Licenses with Regard to Reliable Hardened Containment Vents - to All Operating Boiling Water Reactor Licensees with Mark I and Mark Ii Containments ML12056A0442012-03-12012 March 2012 Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Effective Immediately) - to All Power Reactor Licensees and Holders of Construction Permits in Active or Deferred Status ML12056A0432012-03-12012 March 2012 Order Modifying Licenses with Regard to Reliable Hardened Containment Vents - to All Operating Boiling Water Reactor Licensees with Mark I and Mark II Containments NRC-2012-0067, Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Effective Immediately) - to All Power Reactor Licensees and Holders of Construction Permits in Active or Deferred Status2012-03-12012 March 2012 Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Effective Immediately) - to All Power Reactor Licensees and Holders of Construction Permits in Active or Deferred Status NRC-2011-0187, Biweekly Sholly Report - Applications and Amendments to Facility Operating Licenses Involving No Significant Hazards Considerations; Fr Publication Date: 8/23/20112011-08-11011 August 2011 Biweekly Sholly Report - Applications and Amendments to Facility Operating Licenses Involving No Significant Hazards Considerations; Fr Publication Date: 8/23/2011 ML1122302752011-08-11011 August 2011 Biweekly Sholly Report - Applications and Amendments to Facility Operating Licenses Involving No Significant Hazards Considerations; Fr Publication Date: 8/23/2011 NRC-2010-0030, FRN: General Notice. Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Federal Register Notice - Exemption from the Requirements of 10 CFR Part 73, Section 73.55 (TAC Nos. ME2595, ME2596, and ME2597)2010-03-11011 March 2010 FRN: General Notice. Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Federal Register Notice - Exemption from the Requirements of 10 CFR Part 73, Section 73.55 (TAC Nos. ME2595, ME2596, and ME2597) ML1000507372010-03-11011 March 2010 FRN: General Notice. Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Federal Register Notice - Exemption from the Requirements of 10 CFR Part 73, Section 73.55 ML0936502022010-01-26026 January 2010 Environmental Assessment and Finding of No Significant Impact ML0936501992010-01-26026 January 2010 Environmental Assessment and Finding of No Significant Impact NRC-2009-0553, Biweekly Sholly Report for Federal Register Publication on December 15, 20092009-12-15015 December 2009 Biweekly Sholly Report for Federal Register Publication on December 15, 2009 2024-02-05
[Table view] Category:Letter
MONTHYEARML24032A4762024-02-0101 February 2024 Final Report of a Part 21 Evaluation Associated with Starter Contactors for the BFN Unit 1 High Pressure Coolant Injection Suppression Pool Inboard Suction Valve ML24023A2802024-01-23023 January 2024 Final Report of a Deviation or Failure to Comply Associated with a Relay in the Reactor Core Isolation Cooling Condensate Pump CNL-24-017, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure and Emergency Preparedness Department Procedure Revisions2024-01-17017 January 2024 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure and Emergency Preparedness Department Procedure Revisions ML24016A3042024-01-16016 January 2024 Final Report of a Part 21 Evaluation Associated with Check Valve 0-CKV-023-0565 for D1 Residual Heat Removal Service Water Pump CNL-23-071, Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3, Inservice Inspection and Augmented Program Interval Revised Request for Alternative 0-ISI-472024-01-11011 January 2024 Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3, Inservice Inspection and Augmented Program Interval Revised Request for Alternative 0-ISI-47 ML24022A1732024-01-0303 January 2024 Receipt and Availability of the Subsequent License Renewal Application ML23319A1992024-01-0303 January 2024 Issuance of Amendment Nos. 333, 356, and 316 Regarding the Technical Specification Surveillance Requirements 3.4.3.2 and 3.5.1.11 Regarding Safety Relief Valves ML23355A2062023-12-21021 December 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23348A3942023-12-14014 December 2023 Interim Part 21 Report of a Potential Deviation or Failure to Comply Associated with Starter Contactors for the High Pressure Coolant Injection Suppression Pool Inboard Suction Valve IR 05000259/20230102023-12-11011 December 2023 Commercial Grade Dedication Inspection Report 05000259/2023010 and 05000260/2023010 and 05000296/2023010 ML23335A0722023-12-0101 December 2023 Interim Report of a Deviation or Failure to Comply Associated with a Relay in the Unit 2 Reactor Core Isolation Cooling Condensate Pump ML23334A2492023-11-30030 November 2023 Site Emergency Plan Implementing Procedure Revision CNL-23-070, Submittal of Fifth 10-Year Interval Inservice Testing Program Plan2023-11-29029 November 2023 Submittal of Fifth 10-Year Interval Inservice Testing Program Plan ML23331A2532023-11-27027 November 2023 Summary Report for 10 CFR 50.9 Evaluations, Technical Specifications Bases Changes, Technical Requirement Manual Changes, and NRC Commitment Revisions CNL-23-067, Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2023-11-27027 November 2023 Central Emergency Control Center Emergency Plan Implementing Procedure Revisions ML23325A1102023-11-21021 November 2023 Anchor Darling Double Disc Gate Valve Commitment Revision ML23320A2542023-11-16016 November 2023 Interim Part 21 Report of a Deviation or Failure to Comply Associated with Check Valve 0-CKV-023-0565 for D1 Residual Heat Removal Service Water Pump IR 05000259/20230032023-11-13013 November 2023 Integrated Inspection Report 05000259/2023003, 05000260/2023003 and 05000296/2023003 IR 05000259/20230402023-11-0202 November 2023 Supplemental Inspection Supplemental Report 05000259 2023040 and Follow-Up Assessment Letter ML23292A2532023-10-18018 October 2023 BFN 2024-301, Corporate Notification Letter (210-day Ltr) ML23282A0022023-10-0606 October 2023 Interim Part 21 Report of a Deviation or Failure to Comply Associated with Check Valve 0-CKV-023-0565 for D1 Residual Heat Removal Service Water Pump ML23278A0122023-10-0505 October 2023 Updated Final Safety Analysis Report, Amendment 30 ML23271A1702023-09-28028 September 2023 Site Emergency Plan Implementing Procedure Revision ML23270A0702023-09-26026 September 2023 SLRA Pre-Application Meeting Summary 09-13-2023 ML23257A1232023-09-22022 September 2023 Administrative Changes to Technical Specification Pages Issued for License Amendment Nos. 332, 355, and 315 CNL-23-061, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revision2023-09-20020 September 2023 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revision ML23263B1042023-09-20020 September 2023 Special Report 260/2023-001 for Inoperable Post Accident Monitoring (PAM) Instrumentation ML23205A2132023-09-0808 September 2023 Issuance of Amendment Nos. 332, 355, and 315 Regarding the Revision of Technical Specifications to Adopt TSTF-566-A and TSTF-580-A, Rev. 1 CNL-23-057, Central Emergency Control Center Emergency Plan Implementing Procedure Revisions. Includes CECC-EPIP-1, Revision 76 and CECC-EPIP-9, Revision 642023-09-0505 September 2023 Central Emergency Control Center Emergency Plan Implementing Procedure Revisions. Includes CECC-EPIP-1, Revision 76 and CECC-EPIP-9, Revision 64 IR 05000259/20230052023-08-29029 August 2023 Updated Inspection Plan for Browns Ferry Nuclear Plant, Units 1, 2 and 3 - Report 05000259/2023005, 05000260/2023005 and 05000296/2023005 ML23233A0432023-08-18018 August 2023 Enforcement Action EA-22-122 Inspection Readiness Notification ML23219A1542023-08-17017 August 2023 Request to Use Later Edition of ASME Code for Operation and Maintenance and Alternative Requests BFN-IST-01 Through 05 for the Fifth 10-Year Interval Inservice Testing Program ML23228A1642023-08-16016 August 2023 Site Emergency Plan Implementing Procedure Revision ML23228A0202023-08-15015 August 2023 (BFN) Unit 1 - Special Report 259/2023-001 for Inoperable Post Accident Monitoring (PAM) Instrumentation IR 05000259/20230022023-08-10010 August 2023 Integrated Inspection Report 05000259/2023002, 05000260/2023002, 05000296/2023002 and 07200052/2023001 ML23192A4472023-07-31031 July 2023 Staff Assessment of Updated Seismic Hazards at TVA Sites Following the NRC Process for the Ongoing Assessment of Natural Hazards Information CNL-23-055, Tennessee Valley Authority - Emergency Preparedness Department Procedure Revision. Includes EPDP-3, Revision 3, Emergency Plan Exercises and Preparedness Drills2023-07-25025 July 2023 Tennessee Valley Authority - Emergency Preparedness Department Procedure Revision. Includes EPDP-3, Revision 3, Emergency Plan Exercises and Preparedness Drills ML23171A8862023-07-24024 July 2023 Issuance of Amend. Nos. 331, 354, and 314; 365 and 359 Regarding Adoption of TSTF-541-A, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position ML23201A2182023-07-20020 July 2023 Registration of Use of Cask to Store Spent Fuel (MPC-298 and -299) ML23159A2552023-07-20020 July 2023 Proposed Alternative to the Requirements of the ASME Code Regarding Volumetric Inspection of Standby Liquid Control Nozzles ML23199A3072023-07-18018 July 2023 Site Emergency Plan Implementing Procedure Revision CNL-23-053, Tennessee Valley Authority - Radiological Emergency Plan Revisions2023-07-18018 July 2023 Tennessee Valley Authority - Radiological Emergency Plan Revisions IR 05000259/20233012023-07-18018 July 2023 NRC Operator License Examination Report Nos. 05000259/2023301, 05000260/2023301, and 05000296/2023301 2024-02-01
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Text
November 14, 2006 Mr. Karl W. Singer Chief Nuclear Officer and Executive Vice President Tennessee Valley Authority 6A Lookout Place 1101 Market Street Chattanooga, TN 37402-2801
SUBJECT:
NOTICE OF CONSIDERATION OF ISSUANCE OF AMENDMENT TO FACILITY OPERATING LICENSE, PROPOSED NO SIGNIFICANT HAZARDS CONSIDERATION DETERMINATION, AND OPPORTUNITY FOR A HEARING REGARDING LOW PRESSURE COOLANT INJECTION LOOP CROSSTIE VALVE POSITION VERIFICATION (TAC NO. MD3544)
Dear Mr. Singer:
The Commission has requested the Office of the Federal Register to publish the enclosed Notice of Consideration of Issuance of Amendment to Facility Operating License, Proposed No Significant Hazards Consideration Determination, and Opportunity for Hearing.
This notice relates to your application for amendment dated November 9, 2006, which requests deletion of Technical Specification Surveillance Requirement 3.5.1.4 Low Pressure Coolant Injection (LPCI) Loop Crosstie Valve Position Verification, which requires the monthly verification that the LPCI loop discharge crosstie valve is in the closed position with its motive power removed.
Sincerely,
/RA/
Margaret H. Chernoff, Project Manager Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-259
Enclosure:
Notice of Consideration cc w/encl: See next page
November 14, 2006 Mr. Karl W. Singer Chief Nuclear Officer and Executive Vice President Tennessee Valley Authority 6A Lookout Place 1101 Market Street Chattanooga, TN 37402-2801
SUBJECT:
NOTICE OF CONSIDERATION OF ISSUANCE OF AMENDMENT TO FACILITY OPERATING LICENSE, PROPOSED NO SIGNIFICANT HAZARDS CONSIDERATION DETERMINATION, AND OPPORTUNITY FOR A HEARING REGARDING SECONDARY CONTAINMENT ACCESS DOORS (TAC NO.
MD3544)
Dear Mr. Singer:
The Commission has requested the Office of the Federal Register to publish the enclosed Notice of Consideration of Issuance of Amendment to Facility Operating License, Proposed No Significant Hazards Consideration Determination, and Opportunity for Hearing.
This notice relates to your application for amendment dated November 9, 2006, which requests deletion of Technical Specification Surveillance Requirement 3.5.1.4 Low Pressure Coolant Injection (LPCI) Loop Crosstie Valve Position Verification, which requires the monthly verification that the LPCI loop discharge crosstie valve is in the closed position with its motive power removed.
Sincerely,
/RA/
Margaret H. Chernoff, Project Manager Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-259
Enclosure:
Notice of Consideration cc w/encl: See next page DISTRIBUTION:
Non-Public RidsNrrLABClayton RidsRgn2MailCenter LPL2-2 R/F RidsNrrLACGoldstein RidsNrrDorlDpr RidsNrrDorl RidsOgcRp RidsNrrPMMChernoff RidsAcrsAcnwMailCenter Accession No.: ML063180037 NRR-041 OFFICE LPL2-2/PM LPL2-2/LA LPL2-2/BC NAME MChernoff BClayton LRaghavan DATE 11/14/06 11/14/06 11/14/06 OFFICIAL RECORD COPY
7590-01-P UNITED STATES NUCLEAR REGULATORY COMMISSION TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-259 NOTICE OF CONSIDERATION OF ISSUANCE OF AMENDMENT TO FACILITY OPERATING LICENSE, PROPOSED NO SIGNIFICANT HAZARDS CONSIDERATION DETERMINATION, AND OPPORTUNITY FOR A HEARING The U.S. Nuclear Regulatory Commission (the Commission) is considering issuance of an amendment to Facility Operating License No. DPR-33 issued to the Tennessee Valley Authority (TVA) for operation of the Browns Ferry Nuclear Plant (BFN), Unit 1 located in Limestone County, Alabama.
The proposed amendment would delete the Technical Specification (TS) Surveillance Requirement (SR) to verify the position of a low pressure coolant injection (LPCI) crosstie valve.
Before issuance of the proposed license amendment, the Commission will have made findings required by the Atomic Energy Act of 1954, as amended (the Act), and the Commission's regulations.
The Commission has made a proposed determination that the amendment request involves no significant hazards consideration. Under the Commission's regulations in Title 10 of the CODE OF FEDERAL REGULATIONS (10 CFR), Section 50.92, this means that operation of the facility in accordance with the proposed amendment would not (1) involve a significant increase in the probability or consequences of an accident previously evaluated; or (2) create the possibility of a new or different kind of accident from any accident previously evaluated; or (3) involve a significant reduction in a margin of safety. As required by 10 CFR 50.91(a), the
licensee has provided its analysis of the issue of no significant hazards consideration, which is presented below:
- 1. Does the proposed Technical Specification change involve a significant increase in the probability or consequences of an accident previously evaluated?
Response: No. This TS change is administrative in nature, since it deletes the surveillance requirement (SR 3.5.1.4) to periodically verify the position of a valve which has now been physically removed from Unit 1. Originally, BFNs LPCI design included the capability for the redundant LPCI loop discharge piping to be cross-tied; however, subsequent analysis determined that the crosstie capability, under certain accident and single-failure scenarios, could result in the loss of injection from both LPCI loops. This analysis also determined that the crosstie capability was not required for the mitigation of any design basis events.
Accordingly, since certain crosstie failure modes could prevent mitigation of these or other events, TVA modified the plant design to eliminate the crosstie capability. This was accomplished by closing and deenergizing the motor-operated isolation valve that existed in the crosstie flow path and adding an SR to require periodic verification that the valve was closed and deenergized.
The modified Unit 1 configuration [i.e., LPCI loop discharge crosstie valve removed and the associated remaining piping capped or closed with a blind flange] eliminates the possibility of an undesired flow path. Additionally, the Seismic Class I qualification and the ASME Section XI classification of the remaining piping in the new plant configuration are equivalent to the replaced line configuration. Accordingly, the TS change does not involve a significant increase in the probability or consequences of an accident previously evaluated.
- 2. Does the proposed Technical Specification change create the possibility of a new or different kind of accident from any accident previously evaluated?
Response: No. The physical modification eliminating the LPCI loop discharge crosstie capability does not require revision of the safety analyses. In addition, since the LPCI loop crosstie valve has been physically removed from the system and the associated lines capped or closed via blind flange, the possibility for inadvertent flow between the LPCI loops has been eliminated. Removing the valve and capping/flanging the remaining piping is an improvement over the old configuration. The LPCI function will be accomplished in the same way as before the modification, and no new failure modes have been introduced.
- 3. Does the proposed Technical Specification change involve a significant reduction in a margin of safety?
Response: No. This TS changes does not involve a reduction in the margin of safety since removal of the LPCI loop cross tie valve eliminates the possibility of flow between the two LPCI loops, and it obviates the need for valve position verification contained in the SR. In addition, since removing the valve and capping/flanging the residual piping meets the intent of the SR, the safety analysis remains unchanged.
The NRC staff has reviewed the licensee's analysis and, based on this review, it appears that the three standards of 10 CFR 50.92(c) are satisfied. Therefore, the NRC staff proposes to determine that the amendment request involves no significant hazards consideration.
The Commission is seeking public comments on this proposed determination. Any comments received within 30 days after the date of publication of this notice will be considered in making any final determination.
Normally, the Commission will not issue the amendment until the expiration of 60 days after the date of publication of this notice. The Commission may issue the license amendment before expiration of the 60-day period provided that its final determination is that the amendment involves no significant hazards consideration. In addition, the Commission may issue the amendment prior to the expiration of the 30-day comment period should circumstances change during the 30-day comment period such that failure to act in a timely way would result, for example, in derating or shutdown of the facility. Should the Commission take action prior to the expiration of either the comment period or the notice period, it will publish in the Federal Register a notice of issuance. Should the Commission make a final No Significant Hazards Consideration Determination, any hearing will take place after issuance. The Commission expects that the need to take this action will occur very infrequently.
Written comments may be submitted by mail to the Chief, Rulemaking, Directives and Editing Branch, Division of Administrative Services, Office of Administration, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, and should cite the publication date and page number of this Federal Register notice. Written comments may also be delivered to Room 6D59, Two White Flint North, 11545 Rockville Pike, Rockville, Maryland, from 7:30 a.m.
to 4:15 p.m. Federal workdays. Documents may be examined, and/or copied for a fee, at the NRCs Public Document Room (PDR), located at One White Flint North, Public File Area O1 F21, 11555 Rockville Pike (first floor), Rockville, Maryland.
The filing of requests for hearing and petitions for leave to intervene is discussed below.
Within 60 days after the date of publication of this notice, the licensee may file a request for a hearing with respect to issuance of the amendment to the subject facility operating license and any person whose interest may be affected by this proceeding and who wishes to participate as a party in the proceeding must file a written request for a hearing and a petition for leave to intervene. Requests for a hearing and a petition for leave to intervene shall be filed in accordance with the Commissions Rules of Practice for Domestic Licensing Proceedings in 10 CFR Part 2. Interested persons should consult a current copy of 10 CFR 2.309, which is available at the Commissions PDR, located at One White Flint North, Public File Area O1F21, 11555 Rockville Pike (first floor), Rockville, Maryland. Publicly available records will be accessible from the Agencywide Documents Access and Management Systems (ADAMS)
Public Electronic Reading Room on the Internet at the NRC Web site, http://www.nrc.gov/reading-rm/doc-collections/cfr/. If a request for a hearing or petition for leave to intervene is filed by the above date, the Commission or a presiding officer designated by the Commission or by the Chief Administrative Judge of the Atomic Safety and Licensing Board Panel, will rule on the request and/or petition; and the Secretary or the Chief Administrative Judge of the Atomic Safety and Licensing Board will issue a notice of a hearing or an appropriate order.
As required by 10 CFR 2.309, a petition for leave to intervene shall set forth with particularity the interest of the petitioner in the proceeding, and how that interest may be affected by the results of the proceeding. The petition should specifically explain the reasons why intervention should be permitted with particular reference to the following general
requirements: 1) the name, address and telephone number of the requestor or petitioner; 2) the nature of the requestors/petitioners right under the Act to be made a party to the proceeding;
- 3) the nature and extent of the requestors/petitioners property, financial, or other interest in the proceeding; and 4) the possible effect of any decision or order which may be entered in the proceeding on the requestors/petitioners interest. The petition must also identify the specific contentions which the petitioner/requestor seeks to have litigated at the proceeding.
Each contention must consist of a specific statement of the issue of law or fact to be raised or controverted. In addition, the petitioner/requestor shall provide a brief explanation of the bases for the contention and a concise statement of the alleged facts or expert opinion which support the contention and on which the petitioner intends to rely in proving the contention at the hearing. The petitioner/requestor must also provide references to those specific sources and documents of which the petitioner is aware and on which the petitioner intends to rely to establish those facts or expert opinion. The petition must include sufficient information to show that a genuine dispute exists with the applicant on a material issue of law or fact. Contentions shall be limited to matters within the scope of the amendment under consideration. The contention must be one which, if proven, would entitle the petitioner to relief. A petitioner/requestor who fails to satisfy these requirements with respect to at least one contention will not be permitted to participate as a party.
Those permitted to intervene become parties to the proceeding, subject to any limitations in the order granting leave to intervene, and have the opportunity to participate fully in the conduct of the hearing.
If a hearing is requested, the Commission will make a final determination on the issue of no significant hazards consideration. The final determination will serve to decide when the hearing is held. If the final determination is that the amendment request involves no significant hazards consideration, the Commission may issue the amendment and make it immediately
effective, notwithstanding the request for a hearing. Any hearing held would take place after issuance of the amendment. If the final determination is that the amendment request involves a significant hazards consideration, any hearing held would take place before the issuance of any amendment.
Nontimely requests and/or petitions and contentions will not be entertained absent a determination by the Commission or the presiding officer of the Atomic Safety and Licensing Board that the petition, request and/or the contentions should be granted based on a balancing of the factors specified in 10 CFR 2.309(c)(1)(i)-(viii).
A request for a hearing or a petition for leave to intervene must be filed by: 1) first class mail addressed to the Office of the Secretary of the Commission, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, Attention: Rulemaking and Adjudications Staff; 2) courier, express mail, and expedited delivery services: Office of the Secretary, Sixteenth Floor, One White Flint North, 11555 Rockville Pike, Rockville, Maryland, 20852, Attention: Rulemaking and Adjudications Staff; 3) E-mail addressed to the Office of the Secretary, U.S. Nuclear Regulatory Commission, HEARINGDOCKET@NRC.GOV; or 4) facsimile transmission addressed to the Office of the Secretary, U.S. Nuclear Regulatory Commission, Washington, DC, Attention: Rulemakings and Adjudications Staff at (301) 415-1101, verification number is (301) 415-1966. A copy of the request for hearing and petition for leave to intervene should also be sent to the Office of the General Counsel, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, and it is requested that copies be transmitted either by means of facsimile transmission to 301-415-3725 or by email to OGCMailCenter@nrc.gov. A copy of the request for hearing and petition for leave to intervene should also be sent to the General Counsel, Tennessee Valley Authority, 400 West Summit Hill Drive, ET 11A, Knoxville, Tennessee 37902, attorney for the licensee.
For further details with respect to this action, see the application for amendment dated November 9, 2006, which is available for public inspection at the Commission's PDR, located at One White Flint North, File Public Area O1 F21, 11555 Rockville Pike (first floor), Rockville, Maryland. Publicly available records will be accessible from the Agencywide Documents Access and Management System's (ADAMS) Public Electronic Reading Room on the Internet at the NRC Web site, http://www.nrc.gov/reading-rm/adams.html. Persons who do not have access to ADAMS or who encounter problems in accessing the documents located in ADAMS, should contact the NRC PDR Reference staff by telephone at 1-800-397-4209, 301-415-4737, or by e-mail to pdr@nrc.gov.
Dated at Rockville, Maryland, this 14th day of November 2006.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA/
Margaret H. Chernoff, Project Manager Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Mr. Karl W. Singer BROWNS FERRY NUCLEAR PLANT Tennessee Valley Authority cc:
Mr. Ashok S. Bhatnagar, Senior Vice President Mr. Robert G. Jones, General Manager Nuclear Operations Browns Ferry Site Operations Tennessee Valley Authority Browns Ferry Nuclear Plant 6A Lookout Place Tennessee Valley Authority 1101 Market Street P.O. Box 2000 Chattanooga, TN 37402-2801 Decatur, AL 35609 Mr. Larry S. Bryant, Vice President Mr. Larry S. Mellen Nuclear Engineering & Technical Services Browns Ferry Unit 1 Project Engineer Tennessee Valley Authority Division of Reactor Projects, Branch 6 6A Lookout Place U.S. Nuclear Regulatory Commission 1101 Market Street 61 Forsyth Street, SW.
Chattanooga, TN 37402-2801 Suite 23T85 Atlanta, GA 30303-8931 Brian OGrady, Site Vice President Browns Ferry Nuclear Plant Mr. Russell R. Thompson, Acting Manager Tennessee Valley Authority Corporate Nuclear Licensing P.O. Box 2000 and Industry Affairs Decatur, AL 35609 Tennessee Valley Authority 4X Blue Ridge Mr. Robert J. Beecken, Vice President 1101 Market Street Nuclear Support Chattanooga, TN 37402-2801 Tennessee Valley Authority 6A Lookout Place Mr. William D. Crouch, Manager 1101 Market Street Licensing and Industry Affairs Chattanooga, TN 37402-2801 Browns Ferry Nuclear Plant Tennessee Valley Authority General Counsel P.O. Box 2000 Tennessee Valley Authority Decatur, AL 35609 ET 11A 400 West Summit Hill Drive Senior Resident Inspector Knoxville, TN 37902 U.S. Nuclear Regulatory Commission Browns Ferry Nuclear Plant Mr. John C. Fornicola, Manager 10833 Shaw Road Nuclear Assurance and Licensing Athens, AL 35611-6970 Tennessee Valley Authority 6A Lookout Place State Health Officer 1101 Market Street Alabama Dept. of Public Health Chattanooga, TN 37402-2801 RSA Tower - Administration Suite 1552 Mr. Bruce Aukland, Plant Manager P.O. Box 303017 Browns Ferry Nuclear Plant Montgomery, AL 36130-3017 Tennessee Valley Authority P.O. Box 2000 Chairman Decatur, AL 35609 Limestone County Commission 310 West Washington Street Mr. Masoud Bajestani, Vice President Athens, AL 35611 Browns Ferry Unit 1 Restart Browns Ferry Nuclear Plant Tennessee Valley Authority P.O. Box 2000 Decatur, AL 35609