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MONTHYEARML0717905142007-06-25025 June 2007 Unit 1, Exigent Technical Specifications (TS) Change TS-461 - Modification of Restart Large Transient Testing License Condition 2. (G) 2 Project stage: Request ML0718705152007-07-0909 July 2007 Individual Notice of Consideration of Issuance of Amendments Concerning Deletion of License Condition 2 (G)2 (TAC No. MD5871) (TS-461) Project stage: Other ML0719203402007-07-16016 July 2007 Request for Additional Information for Deletion of License Condition 2.G.(2) (TAC No. MD5871) (TS-461) Project stage: RAI ML0720706672007-07-26026 July 2007 Browns, Unit 1 - Technical Specifications (TS) Change TS-461S1 - Modification of Restart Large Transient Testing License Condition 2. (G)2 - Response to Request for Additional Information (RAI) Project stage: Response to RAI ML0722506192007-08-14014 August 2007 Issuance of Amendment Deletion of License Condition 2.G.(2) TAC MD5871 Project stage: Approval ML0722602322007-08-14014 August 2007 Issuance of Amendment Deletion of License Condition 2.G.(2) TAC MD5871 Project stage: Approval 2007-07-26
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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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July 9, 2007 Mr. William R. Campbell Chief Nuclear Officer and Executive Vice President Tennessee Valley Authority 6A Lookout Place 1101 Market Street Chattanooga, TN 37402-2801
SUBJECT:
BROWNS FERRY, UNIT 1 - INDIVIDUAL NOTICE OF CONSIDERATION OF ISSUANCE OF AMENDMENT CONCERNING DELETION OF LICENSE CONDITION 2.G.(2) (TAC NO. MD5871)(TS-461)
Dear Mr. Campbell:
The Nuclear Regulatory Commission (NRC) has forwarded the enclosed Notice of Consideration of Issuance of Amendment to Facility Operating License, Proposed No Significant Hazards Consideration Determination, and Opportunity for a Hearing, to the Office of the Federal Register for publication.
The proposed amendment would allow deletion of License Condition 2.G.(2) regarding the performance of power uprate large transient testing. In addition, it was requested that this proposed amendment be handled as an exigent request consistent with Title 10 to the Code of Federal Regulations Section 50.91(a)(6). The NRC has reviewed this request and determined that the circumstances presented by the licensee do not support an exigent review and abbreviated public comment period.
If you have any questions, please contact me at 301-415-2315.
Sincerely,
/RA/
Eva A. Brown, 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
July 9, 2007 Mr. William R. Campbell Chief Nuclear Officer and Executive Vice President Tennessee Valley Authority 6A Lookout Place 1101 Market Street Chattanooga, TN 37402-2801
SUBJECT:
BROWNS FERRY, UNIT 1 - INDIVIDUAL NOTICE OF CONSIDERATION OF ISSUANCE OF AMENDMENT CONCERNING DELETION OF LICENSE CONDITION 2.G.(2) (TAC NO. MD5871)(TS-461)
Dear Mr. Campbell:
The Nuclear Regulatory Commission (NRC) has forwarded the enclosed Notice of Consideration of Issuance of Amendment to Facility Operating License, Proposed No Significant Hazards Consideration Determination, and Opportunity for a Hearing, to the Office of the Federal Register for publication.
The proposed amendment would allow deletion of License Condition 2.G.(2) regarding the performance of power uprate large transient testing. In addition, it was requested that this proposed amendment be handled as an exigent request consistent with Title 10 to the Code of Federal Regulations Section 50.91(a)(6). The NRC has reviewed this request and determined that the circumstances presented by the licensee do not support an exigent review and abbreviated public comment period.
If you have any questions, please contact me at 301-415-2315.
Sincerely,
/RA/
Eva A. Brown, Project Manager Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-259
Enclosure:
Notice of Cnsideration cc w/encl: See next page DISTRIBUTION:
PUBLIC LPL2-2 R/F RidsNrrPMEBrown RidsOgcRp RidsNrrLABClayton (Hard Copy) RidsNrrDorlLpl2-2 RidsAcrsAcnwMailCenter RidsRgn2MailCenter RidsNrrDorlDpr ADAMS ACCESSION NO: ML071870515 NRR-106 OFFICE LPL2-2/PM LPL2-2/LA LPL2-2/BC NAME EBrown BClayton TBoyce DATE 7/9/07 7/9/07 7/9/07 OFFICIAL RECORD COPY
7590-01-P UNITED STATES NUCLEAR REGULATORY COMMISSION TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT, UNIT 1 DOCKET NO. 50-259 NOTICE OF CONSIDERATION OF ISSUANCE OF AMENDMENT TO RENEWED FACILITY OPERATING LICENSE, PROPOSED NO SIGNIFICANT HAZARDS CONSIDERATION DETERMINATION, AND OPPORTUNITY FOR A HEARING The U.S. Nuclear Regulatory Commission (the Commission or NRC) is considering issuance of an amendment to Renewed Facility Operating License No. DPR-33 issued to the Tennessee Valley Authority (the licensee) for operation of the Browns Ferry Nuclear Plant, Unit 1, located in Limestone County, Alabama.
The proposed amendment would allow deletion of License Condition 2.G.(2) regarding the performance of power uprate large transient testing. In addition, it was requested that this proposed amendment be handled as an exigent request consistent with Title 10 to the Code of Federal Regulations (10 CFR), Section 50.91(a)(6). The Commission has reviewed this request and determined that the circumstances presented by the licensee do not support an exigent review and abbreviated public comment period.
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 10 CFR 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 change involve a significant increase in the probability or consequences of an accident previously evaluated?
Response: No The requested licensing action would eliminate the current license condition schedule requirement to perform a full power turbine generator load reject transient test. No other changes are proposed. This proposed licensing action will not affect any system, structure, or component designed for the mitigation of previously analyzed events. Therefore, the proposed change does not involve an increase in the probability or consequences of an accident previously evaluated.
- 2. Does the proposed change create the possibility of a new or different kind of accident from any accident previously evaluated?
Response: No The requested licensing action would eliminate the current schedule requirement to perform a full power turbine generator load reject transient test. No other changes are proposed. Therefore, the proposed TS change does not create the possibility of a new or different kind of accident from any accident previously evaluated.
- 3. Does the proposed change involve a significant reduction in a margin of safety?
Response: No Performance of the full power load reject transient test is not necessary to ensure acceptable plant operation at the high thermal power level. Simple, integrated system tests have been performed, and a turbine trip from a high power and a main steam isolation valve transient test from full power have been experienced. In addition, other testing has been performed which demonstrated the satisfactory performance of individual components and subsytems. Thus, the proposed elimination of the load reject transient test will not significantly reduce any margin of safety.
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.
For further details with respect to this action, see the application for amendment dated June 25, 2007, and supplemental letter dated July 3, 2007, which are 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 9th day of July 2007.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA/
Eva A. Brown, Project Manager Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
William R. Campbell, Jr. BROWNS FERRY NUCLEAR PLANT Tennessee Valley Authority cc:
Mr. Ashok S. Bhatnagar Mr. Robert G. Jones, General Manager Senior Vice President Browns Ferry Site Operations Nuclear Generation Development Browns Ferry Nuclear Plant and Construction Tennessee Valley Authority Tennessee Valley Authority P.O. Box 2000 6A Lookout Place Decatur, AL 35609 1101 Market Street Chattanooga, TN 37402-2801 Mr. Larry S. Mellen Browns Ferry Unit 1 Project Engineer Mr. Preston D. Swafford Division of Reactor Projects, Branch 6 Senior Vice President U.S. Nuclear Regulatory Commission Nuclear Support 61 Forsyth Street, SW.
Tennessee Valley Authority Suite 23T85 6A Lookout Place Atlanta, GA 30303-8931 1101 Market Street Chattanooga, TN 37402-2801 Ms. Beth A. Wetzel, Manager Corporate Nuclear Licensing Mr. Walter M. Justice II and Industry Affairs Interim Vice President Tennessee Valley Authority Nuclear Engineering & Technical Services 4X Blue Ridge Tennessee Valley Authority 1101 Market Street 6A Lookout Place Chattanooga, TN 37402-2801 1101 Market Street Chattanooga, TN 37402-2801 Mr. William D. Crouch, Manager Licensing and Industry Affairs Brian OGrady, Site Vice President Browns Ferry Nuclear Plant Browns Ferry Nuclear Plant Tennessee Valley Authority Tennessee Valley Authority P.O. Box 2000 P.O. Box 2000 Decatur, AL 35609 Decatur, AL 35609 Senior Resident Inspector General Counsel U.S. Nuclear Regulatory Commission Tennessee Valley Authority Browns Ferry Nuclear Plant ET 11A 10833 Shaw Road 400 West Summit Hill Drive Athens, AL 35611-6970 Knoxville, TN 37902 State Health Officer Mr. John C. Fornicola, General Manager Alabama Dept. of Public Health Nuclear Assurance RSA Tower - Administration Tennessee Valley Authority Suite 1552 6A Lookout Place P.O. Box 303017 1101 Market Street Montgomery, AL 36130-3017 Chattanooga, TN 37402-2801 Chairman Mr. Bruce Aukland, Plant Manager Limestone County Commission Browns Ferry Nuclear Plant 310 West Washington Street Tennessee Valley Authority Athens, AL 35611 P.O. Box 2000 Decatur, AL 35609 Mr. Robert H. Bryan, Jr., General Manager Licensing and Industry Affairs Mr. Masoud Bajestani, Vice President Tennessee Valley Authority Browns Ferry Unit 1 Restart 4X Blue Ridge Browns Ferry Nuclear Plant 1101 Market Street Tennessee Valley Authority Chattanooga, TN 37402-2801 P.O. Box 2000 Decatur, AL 35609