Letter Sequence Other |
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Results
Other: BSEP 07-0053, Areva Np, Inc., Topical Report, ANP-2637, Revision 1, Boiling Water Reactor Licensing Methodology Compendium., BSEP 07-0067, BSEP 07-0067 Enclosure 9; Areva Report ANP-2624(NP), Revision 0, Brunswick, Units 1 and 2 LOCA-ECCS Analysis MAPLHGR Limit for ATRIUM-1O Fuel, Dated June 2007, BSEP 07-0075, Areva Report ANP-2638NP, Revision 0, Applicability of Areva Np BWR Methods to Extended Power Uprate Conditions, Enclosure 6, BSEP 07-0102, ANP-2661 (Np), Revision 0, Brunswick Nuclear Plant New Fuel Storage Vault Criticality Safety Analysis for ATRIUM-10 Fuel., ML072070311, ML072070318, ML072180372, ML072340562, ML072570210, ML072840219
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MONTHYEARBSEP 06-0128, Request for License Amendments Regarding Fuel Design and Storage Requirements for Areva Np Fuel2007-01-22022 January 2007 Request for License Amendments Regarding Fuel Design and Storage Requirements for Areva Np Fuel Project stage: Request ML0718402152007-06-21021 June 2007 Additional Information in Support of Request for License Amendment Regarding Linear Heat Generation Rate and Core Operating Limits Report References for Areva Np Fuel Project stage: Request BSEP 07-0053, Areva Np, Inc., Topical Report, ANP-2637, Revision 1, Boiling Water Reactor Licensing Methodology Compendium.2007-06-30030 June 2007 Areva Np, Inc., Topical Report, ANP-2637, Revision 1, Boiling Water Reactor Licensing Methodology Compendium. Project stage: Other ML0720703112007-06-30030 June 2007 BSEP 07-0067 Enclosure 3; Areva Report ANP-2646(NP), Revision 0, Brunswick, Unit 1, Thermal-Hydraulic Design Report for ATRIUM-10 Fuel Assemblies, Dated June 2007 Project stage: Other ML0720703182007-06-30030 June 2007 BSEP 07-0067 Enclosure 6; Areva Report ANP-2625(NP), Revision 0, Brunswick, Units 1 and 2 LOCA Break Spectrum Analysis for ATRIUM-10 Fuel, Dated June 2007 Project stage: Other BSEP 07-0067, BSEP 07-0067 Enclosure 9; Areva Report ANP-2624(NP), Revision 0, Brunswick, Units 1 and 2 LOCA-ECCS Analysis MAPLHGR Limit for ATRIUM-1O Fuel, Dated June 20072007-06-30030 June 2007 BSEP 07-0067 Enclosure 9; Areva Report ANP-2624(NP), Revision 0, Brunswick, Units 1 and 2 LOCA-ECCS Analysis MAPLHGR Limit for ATRIUM-1O Fuel, Dated June 2007 Project stage: Other ML0720703052007-07-18018 July 2007 Additional Information in Support of Request for License Amendment Regarding Linear Heat Generation Rate and Core Operating Limits Report References for Areva Np Fuel Project stage: Request BSEP 07-0075, Areva Report ANP-2638NP, Revision 0, Applicability of Areva Np BWR Methods to Extended Power Uprate Conditions, Enclosure 62007-07-31031 July 2007 Areva Report ANP-2638NP, Revision 0, Applicability of Areva Np BWR Methods to Extended Power Uprate Conditions, Enclosure 6 Project stage: Other ML0721803722007-07-31031 July 2007 Areva Report ANP-2658(NP), Revision 0, Brunswick Unit 1 Cycle 17 Fuel Cycle Design, Enclosure 3 Project stage: Other ML0721803702007-07-31031 July 2007 Additional Information in Support of Request for License Amendment Regarding Linear Heat Generation Rate and Core Operating Limits Report References for Areva Np Fuel Project stage: Request ML0723405622007-08-22022 August 2007 Notice of Consideration of Issuance of Amendment to Facility Operating License, Proposed No Significant Hazards Consideration Determination, and Opportunity for a Hearing Project stage: Other ML0728402172007-09-28028 September 2007 Additional Information in Support of Request for License Amendments Regarding Fuel Design and Storage Requirements for Areva Np Fuel Project stage: Request BSEP 07-0102, ANP-2661 (Np), Revision 0, Brunswick Nuclear Plant New Fuel Storage Vault Criticality Safety Analysis for ATRIUM-10 Fuel.2007-09-30030 September 2007 ANP-2661 (Np), Revision 0, Brunswick Nuclear Plant New Fuel Storage Vault Criticality Safety Analysis for ATRIUM-10 Fuel. Project stage: Other ML0728402192007-09-30030 September 2007 ANP-2642(NP), Revision 0, Brunswick Nuclear Plant Spent Fuel Storage Pool Criticality Safety Analysis for ATRIUM-10 Fuel. Project stage: Other ML0725701472007-11-0909 November 2007 Progress Energy Carolinas, Inc. - Request for Withholding of Proprietary Information from Public Disclosure for Brunswick Steam Electric Plant, Unit Nos. 1 and 2 Project stage: Withholding Request Acceptance ML0725701702007-11-0909 November 2007 Progress Energy Carolinas, Inc. - Request for Withholding of Proprietary Information from Public Disclosure for Brunswick Steam Electric Plant, Unit Nos. 1 and 2 Project stage: Withholding Request Acceptance ML0725702102007-11-0909 November 2007 Withholding from Public Disclosure, Areva Report ANP-2638(P): Applicability of Areva Np BWR Methods to Extended Power Uprate Conditions, Dated July 2007 (Tac. MD4061 and MD4062) Project stage: Other ML0725702512007-11-0909 November 2007 Progress Energy Carolinas, Inc. - Request for Withholding of Proprietary Information from Public Disclosure for Brunswick Steam Electric Plant, Unit Nos. 1 and 2 Project stage: Withholding Request Acceptance ML0725702842007-11-0909 November 2007 Progress Energy Carolinas, Inc. - Request for Withholding of Proprietary Information from Public Disclosure for Brunswick Steam Electric Plant, Unit Nos. 1 and 2 Project stage: Withholding Request Acceptance ML0733203672007-11-27027 November 2007 Technical Specifications, Issuance of Amendment Storage of Areva Np Fuel Project stage: Approval ML0733105522007-11-27027 November 2007 License Amendment, Issuance of Amendment Storage of Areva Np Fuel Project stage: Approval 2007-06-30
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Category:Federal Register Notice
MONTHYEARML24102A2572024-04-25025 April 2024 Federal Register Notice - Issuance of Multiple Exemptions Regarding 10 CFR Part 73 - March 2024 ML21322A2872021-11-23023 November 2021 Approval of Exemption from 10 CFR 55.47 - Waiver of Examination and Test Requirements ML20035C4082020-02-18018 February 2020 Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: 02/25/2020 ML19337A0312019-12-11011 December 2019 Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: 12/17/2019 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 ML19140A4562019-05-28028 May 2019 Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: 06/04/2019 ML19042A3062019-02-15015 February 2019 Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: 2/26/2019 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 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 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 ML18172A3042018-06-22022 June 2018 Tennessee Valley Authority - License Amendment Application; Opportunity to Comment, Request a Hearing, and Petition for Leave to Intervene ML18127B7232018-05-14014 May 2018 Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: May 22, 2018 NRC-2018-0096, Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: May 22, 20182018-05-14014 May 2018 Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: May 22, 2018 ML18127B0322018-05-0707 May 2018 ACRS Subcommittee Meeting on T-H Phenomena-Brunswick Mellla+Atws, May 15, 2018 ML18127B1672018-05-0707 May 2018 ACRS Subcommittee Meeting on Power Uprates, May 16, 2018 ML16355A2612016-12-21021 December 2016 Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations; Publication Date: January 3, 2017 NRC-2016-0273, Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations; Publication Date: January 3, 20172016-12-21021 December 2016 Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations; Publication Date: January 3, 2017 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 ML16215A2272016-08-0303 August 2016 Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: August 16, 2016 NRC-2016-0161, Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: August 16, 20162016-08-0303 August 2016 Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: August 16, 2016 ML16145A2252016-06-0707 June 2016 Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: June 7, 2016 NRC-2016-0107, Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: June 7, 20162016-06-0707 June 2016 Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: June 7, 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 ML16061A3012016-03-0202 March 2016 Biweekly Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: March 15, 2016 ML15218A6252015-08-14014 August 2015 Biweekly FRN - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: August 14, 2015 ML15159A6322015-07-0606 July 2015 Letter Approving Direct Transfer of Control of Licenses and Conforming Amendments NRC-2015-0100, FRN, Direct Transfer of Licenses; Order; Issuance2015-07-0606 July 2015 FRN, Direct Transfer of Licenses; Order; Issuance ML15159A6772015-07-0606 July 2015 FRN, Direct Transfer of Licenses; Order; Issuance NRC-2015-0104, Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication in April 28, 2015, Federal Register2015-04-20020 April 2015 Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication in April 28, 2015, Federal Register ML15106A9162015-04-20020 April 2015 Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication in April 28, 2015, Federal Register ML15042A2322015-04-13013 April 2015 Notice of Consideration of Approval of Transfer of Facility Operating License and Conforming Amendment, Opportunity for Hearing 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 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 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 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 ML13339A5882013-12-30030 December 2013 G20120489/OEDO-2012-0421 - Response LTR to Petitioner 2.206 - Redress Technical Specifications Deficiencies Regarding Irradiated Fuel at the Brunswick Steam Electric Plant 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 ML13164A2012013-06-13013 June 2013 Correction to Bi-weekly Notice NRC-2012-0269, G20120489/EDATS: OEDO-2012-0421 - Federal Register Notice - Request for Action2012-10-31031 October 2012 G20120489/EDATS: OEDO-2012-0421 - Federal Register Notice - Request for Action ML12261A3442012-10-31031 October 2012 G20120489/EDATS: OEDO-2012-0421 - Federal Register Notice - Request for Action 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-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 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 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 NRC-2011-0284, Brunswick Steam Electric Plant, Units 1 and 2 and Brunswick Independent Spent Fuel Storage Installation - Federal Register Notice - Order Approving Indirect License Transfer2011-12-0202 December 2011 Brunswick Steam Electric Plant, Units 1 and 2 and Brunswick Independent Spent Fuel Storage Installation - Federal Register Notice - Order Approving Indirect License Transfer ML11255A0562011-12-0202 December 2011 Independent Spent Fuel Storage Installation - Federal Register Notice - Order Approving Indirect License Transfer ML11251A0092011-09-0808 September 2011 September 20, 2011 Applications and Amendments to Facility Operating License Involving No Significant Hazards Considerations 2024-04-25
[Table view] Category:Letter
MONTHYEARIR 05000324/20253012024-10-17017 October 2024 Notification of Licensed Operator Initial Examination 05000325/2025301 and 05000324/2025301 IR 05000324/20244012024-10-15015 October 2024 Security Baseline Inspection Report 05000324/2024401 and 05000325/2024401 ML24297A6262024-10-11011 October 2024 PCA Letter to NRC Brunswick Potential Tropical Storm Eight IR 05000324/20240102024-09-10010 September 2024 Focused Engineering Inspection Commercial Grade Dedication Report 05000324-2024010 and 05000325-2024010 ML24249A1362024-09-0404 September 2024 EN 57304 - Westinghouse Electric Company, LLC, Final Report - No Embedded Files. Notification of the Potential Existence of Defects Pursuant to 10 CFR Part 21 IR 05000324/20240052024-08-23023 August 2024 Updated Inspection Plan for Brunswick Steam Electric Plant, Units 1 and 2 (Report 05000324/2024005 and 05000325/2024005) IR 05000324/20240022024-08-0505 August 2024 Integrated Inspection Report 05000324/2024002 and 05000325/2024002 and 07200006/2024001 ML24206A1062024-07-30030 July 2024 2024 Brunswick Requal Inspection Corporate Notification Letter ML24183A0972024-07-12012 July 2024 ISFSI; Catawba 1, 2 & ISFSI; McGuire 1, 2 & ISFSI; Oconee 1, 2, 3 & ISFSI; Shearon Harris 1; H. B. Robinson 2 & ISFSI; and Radioactive Package Shipping Under 10 CFR 71 (71-266 & 71-345) – Review of QA Program Changes EPID L-2024-LLQ-0002 IR 05000324/20244202024-07-0202 July 2024 – Security Baseline Inspection Report 05000324/2024420 and 05000325/2024420 ML24108A0702024-06-0505 June 2024 – Issuance of License Amendments to Revise the 10 CFR 50.69 Categorization Process to Reflect an Alternative Seismic Approach IR 05000324/20244022024-05-17017 May 2024 Plan Material Control and Accounting Program Inspection Report 05000324/2024402 and 05000325/2024402 - Cover Letter IR 05000324/20240012024-05-0909 May 2024 Integrated Inspection Report 05000324/2024001 and 05000325/2024001 05000325/LER-2024-002, Re Automatic Start of Emergency Diesel Generator Due to Emergency Bus De-energization2024-04-10010 April 2024 Re Automatic Start of Emergency Diesel Generator Due to Emergency Bus De-energization 05000325/LER-2024-001, Primary Containment Penetration Local Leak Rate Testing Failure2024-04-10010 April 2024 Primary Containment Penetration Local Leak Rate Testing Failure ML24066A0132024-03-0505 March 2024 Bru 2024-002 Radiation Safety Baseline Inspection Information Request ML24026A0982024-03-0101 March 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0057 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) IR 05000324/20230062024-02-28028 February 2024 Annual Assessment Letter for Brunswick Steam Electric Plant, Units 1 and 2 – NRC Inspection Reports 05000324/2023006 and 05000325/2023006 IR 05000324/20244032024-02-14014 February 2024 Information Request for the Cybersecurity Baseline Inspection, Notification to Perm Inspection 05000325/2024403; 05000324/2024403 ML24032A1392024-02-12012 February 2024 Correction of Errors within Authorized Alternative Request RA-22-0308 IR 05000324/20230042024-02-0606 February 2024 Integrated Inspection Report 05000324/2023004 and 05000325/2023004 IR 05000324/20230112023-12-26026 December 2023 NRC Fire Protection Team Inspection - FPTI Report 05000324/2023011 and 05000325/2023011 IR 05000324/20234022023-12-14014 December 2023 Security Baseline Inspection Report 05000324-2023402 and 05000325-2023402 ML23297A0262023-11-27027 November 2023 – Proposed Alternatives to ASME Code Section XI Subsection IWE Requirements for Torus Metallic Liner Inspections ML23317A3462023-11-14014 November 2023 Duke Fleet - Correction Letter to License Amendment Nos. 312 & 340 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-554, Revision 1 IR 05000324/20230032023-11-0101 November 2023 Integrated Inspection Report 05000324/2023003 and 05000325/2023003 IR 05000324/20230102023-10-17017 October 2023 Biennial Problem Identification and Resolution Inspection Report 05000324/2023010 and 05000325/2023010 IR 05000325/20234012023-10-16016 October 2023 Security Baseline Inspection Report 05000324 and 05000325 2023401 ML23346A1322023-10-0606 October 2023 Communication from C-10 Research & Education Foundation Regarding NextEra Common Emergency Fleet Plan License Amendment Request and Related Documents Subsequently Published ML23256A0882023-09-25025 September 2023 Issuance of Alternative to Steam Generator Welds ML23195A0782023-08-29029 August 2023 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-554, Revision 1 IR 05000324/20230052023-08-23023 August 2023 Updated Inspection Plan for Brunswick Steam Electric Plant, Units 1 and 2 (Report 05000324/2023005 and 05000325/2023005) IR 05000324/20230022023-08-0404 August 2023 Integrated Inspection Report 05000324/2023002 and 05000325/2023002 ML23201A2042023-07-28028 July 2023 Summary of Regulatory Audit in Support of Alternative Request RA-22-0308 for Inservice Inspection of the Torus Metallic Liner IR 05000324/20243012023-07-25025 July 2023 – Notification of Licensed Operator Initial Examination 05000325/2024301 and 05000324/2024301 05000324/LER-2023-001, Two Main Steam Line Safety Relief Valves Inoperable2023-07-17017 July 2023 Two Main Steam Line Safety Relief Valves Inoperable 05000325/LER-2023-001, Loss of Redundant Power Supply Operation Causes Turbine Trip and Subsequent Reactor Scram2023-06-15015 June 2023 Loss of Redundant Power Supply Operation Causes Turbine Trip and Subsequent Reactor Scram ML23146A0012023-05-24024 May 2023 EN 56538 - Engine Systems Inc and Brunswick ML23212A9502023-05-24024 May 2023 Engine Systems, Inc., Part 21 Report Re Woodward EGB-35P Governor/Actuator with Foreign Material ML23130A3902023-05-12012 May 2023 – Regulatory Audit Plan in Support of Alternative Request RA 22-0308 for Inservice Inspection of the Torus Metallic Liner IR 05000324/20230012023-05-10010 May 2023 – Integrated Inspection Report 05000324 2023001 and 05000325 2023001 ML23118A0762023-05-0101 May 2023 Approval for Use of Specific Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI IR 05000324/20220042023-04-0404 April 2023 Reissue - Brunswick Steam Electric Plant - Integrated Inspection Report 05000324/2022004 and 05000325/022004 ML22332A4932023-03-10010 March 2023 William States Lee III 1 and 2 - Issuance of Amendments Regarding the Relocation of the Emergency Operations Facility IR 05000324/20220062023-03-0101 March 2023 Annual Assessment Letter for Brunswick Steam Electric Plant, Units 1 and 2 – NRC Inspection Reports 05000324/2022006 and 05000325/2022006 ML23033A5252023-02-0808 February 2023 Integrated Inspection Report 05000324/2022004 and 05000325/2022004 IR 05000324/20223012023-02-0303 February 2023 NRC Operator License Examination Report 05000325/2022301 and 05000324/2022301 IR 05000324/20224022022-11-23023 November 2022 Security Baseline Inspection Report 05000324 2022402 and 05000325 2022402 ML22332A0132022-11-23023 November 2022 Operator Licensing Written Examination Approval 05000325/2022301 and 05000324/2022301 ML22096A0032022-11-18018 November 2022 McGuire Nuclear Station and Shearon Harris Nuclear Power Plant Authorization of RA-19-0352 Regarding Use of Alternative for RPV Head Closure Stud Examinations 2024-09-04
[Table view] |
Text
August 22, 2007 Mr. James Scarola, Vice President Brunswick Steam Electric Plant Carolina Power & Light Company Post Office Box 10429 Southport, North Carolina 28461
SUBJECT:
BRUNSWICK STEAM ELECTRIC PLANT, UNITS 1 AND 2 - NOTICE OF CONSIDERATION OF ISSUANCE OF AMENDMENT TO FACILITY OPERATING LICENSE, PROPOSED NO SIGNIFICANT HAZARDS CONSIDERATION DETERMINATION, AND OPPORTUNITY FOR A HEARING (TAC NOS. MD4061 AND MD4062)
Dear Mr. Scarola:
Enclosed is a copy of a Notice of Consideration of Issuance of Amendment to Facility Operating License, Proposed No Significant Hazards Consideration Determination, and Opportunity For a Hearing related to the application for an amendment dated January 22, 2007, for the Brunswick Steam Electric Plant, Unit Nos. 1 and 2. The application proposes to change the Technical Specifications related to the fuel design description and the fuel criticality methods to accommodate the transition to AREVA fuel.
The notice has been forwarded to the Office of the Federal Register for publication.
Sincerely,
/RA/
Stewart N. Bailey, Senior Project Manager Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-325 and 50-324
Enclosure:
As stated cc w/encl: See next page
Carolina Power & Light Company Brunswick Steam Electric Plant Units 1 and 2 cc:
David T. Conley Ms. Margaret A. Force Associate General Counsel II - Assistant Attorney General Legal Department State of North Carolina Progress Energy Service Company, LLC Post Office Box 629 Post Office Box 1551 Raleigh, North Carolina 27602 Raleigh, North Carolina 27602-1551 Mr. Robert P. Gruber Mr. David R. Sandifer, Chairperson Executive Director Brunswick County Board of Commissioners Public Staff - NCUC Post Office Box 249 4326 Mail Service Center Bolivia, North Carolina 28422 Raleigh, North Carolina 27699-4326 Resident Inspector Ben Waldrep U. S. Nuclear Regulatory Commission Director, Site Operations 8470 River Road Brunswick Steam Electric Plant Southport, North Carolina 28461 Carolina Power & Light Company Post Office Box 10429 Mr. John H. ONeill, Jr. Southport, North Carolina 28461-0429 Pillsbury Winthrop Shaw Pittman, LLP 2300 N Street NW. Mr. Norman R. Holden, Mayor Washington, DC 20037-1128 City of Southport 201 East Moore Street Ms. Beverly Hall, Section Chief Southport, North Carolina 28461 Division of Radiation Protection N.C. Department of Environment Mr. Warren Lee and Natural Resources Emergency Management Director 3825 Barrett Dr. New Hanover County Department of Raleigh, North Carolina 27609-7721 Emergency Management Post Office Box 1525 Mr. Terry D. Hobbs Wilmington, North Carolina 28402-1525 Plant General Manager Brunswick Steam Electric Plant Mr. J. Paul Fulford Carolina Power & Light Company Manager, Performance Evaluation and Post Office Box 10429 Regulatory Affairs PEB5 Southport, North Carolina 28461-0429 Carolina Power & Light Company Post Office Box 1551 Public Service Commission Raleigh, North Carolina 27602-1551 State of South Carolina Post Office Drawer 11649 Columbia, South Carolina 29211
August 22, 2007 Mr. James Scarola, Vice President Brunswick Steam Electric Plant Carolina Power & Light Company Post Office Box 10429 Southport, North Carolina 28461
SUBJECT:
BRUNSWICK STEAM ELECTRIC PLANT, UNITS 1 AND 2 - NOTICE OF CONSIDERATION OF ISSUANCE OF AMENDMENT TO FACILITY OPERATING LICENSE, PROPOSED NO SIGNIFICANT HAZARDS CONSIDERATION DETERMINATION, AND OPPORTUNITY FOR A HEARING (TAC NOS. MD4061 AND MD4062)
Dear Mr. Scarola:
Enclosed is a copy of a Notice of Consideration of Issuance of Amendment to Facility Operating License, Proposed No Significant Hazards Consideration Determination, and Opportunity For a Hearing related to the application for an amendment dated January 22, 2007, for the Brunswick Steam Electric Plant, Unit Nos. 1 and 2. The application proposes to change the Technical Specifications related to the fuel design description and the fuel criticality methods to accommodate the transition to AREVA fuel.
The notice has been forwarded to the Office of the Federal Register for publication.
Sincerely,
/RA/
Stewart N. Bailey, Senior Project Manager Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-325 and 50-324
Enclosure:
As stated cc w/encl: See next page DISTRIBUTION:
PUBLIC RidsOgcRp LPL2-2 R/F RidsAcrsAcnwMailCenter RidsNrrDorlLpl2-2 RidsRgn2MailCenter RidsNrrPMSBailey RidsNrrDorlDpr RidsNrrLABClayton ADAMS ACCESSION NO: ML072340562 OFFICE LPL2-2/PM LPL2-2/LA LPL2-2/BC NAME SBailey BClayton BMoroney for TBoyce DATE 08/22/07 08/21/07 08/22/07 OFFICIAL RECORD COPY
7590-01-P UNITED STATES NUCLEAR REGULATORY COMMISSION CAROLINA POWER & LIGHT COMPANY DOCKET NOS. 50-324 AND 50-325 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 Nos. DPR-71 and DPR-62 issued to the Carolina Power & Light Company (the licensee) for operation of the Brunswick Steam Electric Plant, Unit Nos. 1 and 2, located in Brunswick County, North Carolina.
The proposed amendment would change the Technical Specifications related to the fuel design description and the fuel criticality methods to accommodate the transition to AREVA fuel.
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 change involve a significant increase in the probability or consequences of an accident previously evaluated?
Response: No The proposed amendments revise the fuel bundle description contained in Technical Specification 4.2.1, "Fuel Assemblies," to reflect both the existing fuel designs in use and the new AREVA NP fuel design. The change to the fuel assembly description involves a minor revision to reflect that AREVA fuel assemblies have a water channel.
The proposed amendments also revise Technical Specification 4.3, "Fuel Storage," to remove criteria specific to GNF-A fuel storage criticality methods.
The criticality analysis criteria being retained in Technical Specifications 4.3.1.1 and 4.3.1.2 will continue to ensure that adequate criticality margins are maintained for new and spent fuel storage.
These changes do not involve any plant modifications or operational changes that could affect system reliability, performance, or possibility of an operator error. These requested changes do not affect any postulated accident precursors, do not affect the performance of any accident mitigation systems, and do not introduce any new accident initiation mechanisms.
Based on the above, the proposed amendments do 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 As previously stated, the proposed amendments revise Technical Specification fuel bundle description and fuel storage rack criticality requirements to support receipt and storage of a new fuel bundle manufactured by a different vendor.
Analytic methods will continue to be used to demonstrate the criticality acceptability of fuel being stored in the new and spent fuel storage racks. As such, the proposed amendments do 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
The proposed amendments incorporate an administrative revision to the Technical Specification fuel bundle description and modify the fuel storage Technical Specification requirements to remove vendor-specific nomenclature for criticality analysis criteria. Criticality analyses for new and spent fuel storage will continue to ensure compliance with fuel storage and criticality criteria described in the Updated Final Safety Analysis Report.
Therefore, the proposed amendments do not involve a significant reduction in a 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 David T. Conley,
Associate General Counsel II - Legal Department, Progress Energy Service Company, LLC, Post Office Box 1551, Raleigh, North Carolina 27602, attorney for the licensee.
For further details with respect to this action, see the application for amendment dated January 22, 2007, 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 22nd day of August 2007.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA/
Stewart N. Bailey, Senior Project Manager Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation